PAGE
1
Rocky
Flats
Environmental
Technology
Site
1­
MAN­
008­
WM­
001
VERSION
7
TRANSURANIC
(
TRU)
WASTE
MANAGEMENT
MANUAL
APPROVED
BY:
G.
A.
O'Leary
/
/
S/
2/
10/
04
Print
Name
Date
Responsible
Organization:
TRU
Waste
Programs
Effective
Date:
02/
12/
2004
Review/
concurrence
documentation
is
contained
in
the
Document
History
File.

ISR
review
not
required.
Exempt
from
Classification
Review
SES
review
not
required.
Exemption
Number:
CEX­
032­
00
This
manual
supersedes
1­
MAN­
008­
WM­
001,
Revision
6.

Periodic
review
frequency:
1
year
from
the
effective
date
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
2
APPROVALS
The
approvals
listed
below
apply
to
Version
7
of
this
document.

Approved
by:

D.
C.
Gadbury
for
Kerry
W.
Watson
/
S/
2/
10/
04
CBFO
Assistant
Manager,
Office
of
National
TRU
Program
Date
(
Kerry
W.
Watson)

Ava
L.
Holland
/
S/
2/
10/
04
CBFO
Quality
Assurance
Manager
Date
(
Ava
Holland)

Lam
Xuan
/
S/
1/
28/
04
DOE
Rocky
Flats
Field
Office
Date
(
Lam
Xuan)

G.
A.
O'Leary
/
S/
1/
28/
04
RFETS
TWCP
Site
Project
Manager
Date
(
G.
A.
O'Leary)

C.
L.
Ferrera
/
S/
1/
28/
04
RFETS
TWCP
Site
Project
Quality
Assurance
Officer
Date
(
C.
L.
Ferrera)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
3
TABLE
OF
CONTENTS
Section
Page
TITLE
PAGE
..................................................................................................................
1
APPROVALS
PAGE.......................................................................................................
2
TABLE
OF
CONTENTS.................................................................................................
3
VERSION
CHANGE
SUMMARY..................................................................................
9
1.
OVERVIEW
.................................................................................................................
13
1.1
Purpose..............................................................................................................
14
1.2
TRU
Waste
Programs
........................................................................................
14
2.
REQUIREMENTS
FOR
CH­
TRU
WASTE
CERTIFICATION
AND
TRANSPORTATION
TO
WIPP
...................................................................................
16
2.1
CBFO
Requirements
Documents
........................................................................
16
2.2
RFETS
Program
Documents
..............................................................................
16
2.2.1
Waste
Certification
Plan.......................................................................
16
2.2.2
Certification
QA
Plan...........................................................................
17
2.2.3
Quality
Assurance
Project
Plan
(
TWCP
QAPjP)...................................
17
2.2.4
Graded
Approach
Procedure................................................................
17
2.2.5
Sampling
Plan......................................................................................
18
2.2.6
TRAMPAC
and
Associated
QA
Plan
...................................................
18
2.2.7
Packaging
QA
Plan..............................................................................
18
3.0
CERTIFICATION
AND
TRAMPAC
QUALITY
ASSURANCE
PROGRAMS.............
24
3.1
Management
Requirements.................................................................................
24
3.1.1
Organization
&
QA
Program................................................................
24
3.1.2
Personnel
Training
&
Qualification.......................................................
49
3.1.3
Quality
Improvement
...........................................................................
50
3.1.4
Document
Control
...............................................................................
55
3.1.5
Records
...............................................................................................
56
3.2
Performance
Requirements
.................................................................................
58
3.2.1
Work
Processes
...................................................................................
58
3.2.2
Design
Control.....................................................................................
69
3.2.3
Procurement
........................................................................................
70
3.2.4
Inspection
&
Testing............................................................................
75
3.3
Assessment
Requirements...................................................................................
81
3.3.1
Management
Assessments....................................................................
81
3.3.2
Independent
Assessments.....................................................................
81
3.4
Sample
Control
Requirements
............................................................................
84
3.4.1
Sample
Control
Requirements..............................................................
84
3.4.2
Sample
Identification
...........................................................................
84
3.4.3
Handling,
Storage
And
Shipping
Samples.............................................
84
3.4.4
Disposition
Of
Sample
Nonconformance
..............................................
84
3.5
Scientific
Investigation
Requirements
.................................................................
84
3.6
Software
Requirements
......................................................................................
85
3.6.1
Software
Quality
Assurance
(
SQA)......................................................
85
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
4
TABLE
OF
CONTENTS
(
continued)
Section
Page
4.0
RFETS
TRU
WASTE
PACKAGING
&
CERTIFICATION..........................................
86
4.1
Characterization
Process
....................................................................................
86
4.2
TRU
Waste
Certification
Official
(
WCO)
...........................................................
88
4.3
Waste
Packaging
and
Documentation
Requirements
...........................................
89
4.3.1
Waste/
Residue
Traveler
.......................................................................
89
4.3.2
Waste
and
Environmental
Management
System
(
WEMS).....................
91
4.3.4
Backlog
Waste
Reassessment
Baseline
Book
(
BWRBB)
......................
93
4.4
Shipment
Certification
Statements
......................................................................
94
4.5
RFETS
IDCs
Certifiable
to
WIPP
Operations
and
Safety
Criteria
and
TRUPACT­
II
Payload
Control
Criteria
........................................................
94
4.6
Packaging
QA
Program
Plan
..............................................................................
96
4.6.1
Organization
........................................................................................
96
4.6.2
Quality
Assurance
Program..................................................................
97
4.6.3
Design
Control.....................................................................................
97
4.6.4
Procurement
Document
Control...........................................................
98
4.6.5
Instructions,
Procedures,
and
Drawings................................................
99
4.6.6
Document
Control
.............................................................................
101
4.6.7
Control
of
Purchased
Material,
Equipment,
and
Services....................
102
4.6.8
Identification
and
Control
of
Materials,
Parts,
and
Components..........
103
4.6.9
Control
of
Special
Processes
..............................................................
103
4.6.10
Inspection
Control
.............................................................................
104
4.6.11
Test
Control
......................................................................................
105
4.6.12
Control
of
Measuring
and
Test
Equipment
.........................................
105
4.6.13
Handling,
Storage,
and
Shipping
........................................................
106
4.6.14
Inspection,
Test,
and
Operating
Status
...............................................
106
4.6.15
Control
of
Nonconforming
Materials,
Parts,
or
Components
..............
107
4.6.16
Corrective
Action
..............................................................................
107
4.6.17
Quality
Assurance
Records
................................................................
108
4.6.18
Audits................................................................................................
109
5.0
RFETS
CERTIFICATION
TO
WIPP
WASTE
ACCEPTANCE
CRITERIA
...............
110
5.1
General
............................................................................................................
110
5.1.1
DOE
Operations
and
Safety
Requirements
.........................................
112
5.1.2
NRC
Transportation
Safety
Requirements
for
the
TRUPACT­
II
........
112
5.1.3
NMED
Hazardous
Waste
Facility
Permit
Requirements
.....................
113
5.1.4
EPA
Compliance
Certification
Decision
Requirements
.......................
113
5.1.5
Land
Withdrawal
Act
Requirements...................................................
114
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
5
TABLE
OF
CONTENTS
(
continued)
Section
Page
5.2
Container
Properties.........................................................................................
116
5.2.1
Description
........................................................................................
116
5.2.2
Weight
Limits
and
Center
of
Gravity..................................................
118
5.2.3
Assembly
Configurations....................................................................
119
5.2.4
Removable
Surface
Contamination.....................................................
119
5.2.5
Identification/
Labeling
.......................................................................
120
5.2.6
Dunnage
............................................................................................
121
5.2.7
Filter
Vents........................................................................................
121
5.3
Radiological
Properties.....................................................................................
122
5.3.1
Radionuclide
Composition
.................................................................
122
5.3.2
Pu­
239
Fissile
Gram
Equivalent
.........................................................
123
5.3.3
TRU
Alpha
Activity
Concentration
....................................................
124
5.3.4
Pu­
239
Equivalent
Activity
................................................................
125
5.3.5
Radiation
Dose
Rate
..........................................................................
126
5.3.6
Decay
Heat
........................................................................................
126
5.4
Physical
Properties
...........................................................................................
127
5.4.1
Residual
Liquids
................................................................................
127
5.4.2
Sealed
Containers
..............................................................................
127
5.5
Chemical
Properties..........................................................................................
128
5.5.1
Pyrophoric
Materials..........................................................................
128
5.5.2
Hazardous
Waste...............................................................................
129
5.5.3
Chemical
Compatibility
......................................................................
130
5.5.4
Explosives,
Corrosives,
and
Compressed
Gases..................................
130
5.5.5
Headspace
Gas
Concentrations
..........................................................
131
5.5.6
Polychlorinated
Biphenyls
..................................................................
132
5.6
Data
Package
Contents.....................................................................................
132
5.6.1
Characterization
and
Certification
Data
..............................................
132
5.6.2
Shipping
Data
....................................................................................
133
6.0
TRUPACT­
II
AUTHORIZED
METHODS
FOR
PAYLOAD
CONTROL
(
TRAMPAC)
COMPLIANCE
PLAN................................................................................................
138
6.1
Introduction
.....................................................................................................
138
6.1.1
Scope
................................................................................................
138
6.1.2
Purpose
.............................................................................................
138
6.1.3
Requirements.....................................................................................
139
6.1.4
Methods
of
Compliance
.....................................................................
139
6.1.5
TRUCON
Document
.........................................................................
141
6.1.6
Compliance
Program..........................................................................
144
6.1.7
Quality
Assurance
..............................................................................
144
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
6
TABLE
OF
CONTENTS
(
continued)
Section
Page
6.2
Container
and
Physical
Properties
Requirements...............................................
145
6.2.1
Container
Descriptions.......................................................................
145
6.2.2
Dunnage
............................................................................................
147
6.2.3
Container/
Assembly
Weight
and
Center
of
Gravity.............................
149
6.2.4
Container
Marking.............................................................................
152
6.2.5
Filter
Vents........................................................................................
153
6.2.6
Liquids...............................................................................................
155
6.2.7
Sharp
or
Heavy
Objects
.....................................................................
157
6.2.8
Sealed
Containers
..............................................................................
158
6.3
Nuclear
Properties
Requirements......................................................................
159
6.3.1
Nuclear
Criticality..............................................................................
161
6.3.2
Radiation
Dose
Rates.........................................................................
166
6.4
Chemical
Properties
Requirements....................................................................
168
6.4.1
Pyrophoric
Materials..........................................................................
168
6.4.2
Explosives,
Corrosives,
and
Compressed
Gases..................................
169
6.4.3
Chemical
Composition
.......................................................................
172
6.4.4
Chemical
Compatibility
......................................................................
174
6.5
Gas
Generation
Requirements...........................................................................
175
6.5.1
Payload
Shipping
Category
................................................................
175
6.5.2
Compliance
With
Flammable
(
Gas/
VOC)
Concentration
Limits..........
187
6.5.3
Venting
and
Aspiration
......................................................................
200
6.6
Payload
Assembly
Requirements.......................................................................
203
6.6.1
Requirements.....................................................................................
203
6.6.2
Methods
of
Compliance
and
Verification............................................
204
6.7
Quality
Assurance
............................................................................................
227
6.7.1
QA
Requirements
for
Payload
Compliance.........................................
227
6.7.2
QA
Compliance
and
Verification........................................................
227
7.
RECORDS
PROCESSING..........................................................................................
272
8.
REFERENCES............................................................................................................
274
8.1
External
References..........................................................................................
274
8.2
RFETS
References
...........................................................................................
281
9.
GLOSSARY................................................................................................................
294
9.1
Definitions........................................................................................................
294
9.2
Acronyms.........................................................................................................
305
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
7
APPENDICES
Appendix
1,
RFETS
Organizational
Charts...............................................................
307
Appendix
2,
Waste
Certification
Flow
Diagram........................................................
309
Appendix
3,
Payload
Package
Integrity
Checklist......................................................
312
Appendix
4,
Nondestructive
Assay
...........................................................................
317
Appendix
5,
Numeric
Payload
Shipping
Category
Worksheet
...................................
345
Appendix
6,
Payload
Assembly
Transportation
Certification
Document
(
PATCD)
....
349
Appendix
7,
Payload
Package
Transportation
Certification
Document
(
PPTCD)
(
Analytical
Payload
Shipping
Category)
................................................
351
Appendix
8,
Payload
Package
Transportation
Certification
Document
(
PPTCD)
(
Test
Payload
Shipping
Category).........................................................
352
Appendix
9,
Overpack
Payload
Container
Transportation
Certification
Document
(
OPCTCD)
...........................................................................................
353
Appendix
10,
TRUPACT­
II
Transportation
Requirements
Matrix
for
RFETS
............
355
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
8
TABLES
AND
FIGURES
Table
2­
1,
Summary
of
RFETS
Program
Documents
.....................................................
19
Figure
2­
1,
CBFO
Requirements
Flowdown
Characterization.........................................
20
Figure
2­
2,
CBFO
Requirements
Flowdown
Certification...............................................
21
Figure
2­
3,
CBFO
Requirements
Flowdown
Quality
Assurance......................................
22
Table
5­
1,
Payload
Package
Assembly
Configurations..................................................
134
Table
5­
2,
Weight
Limits..............................................................................................
134
Table
5­
3,
Pu­
239
FGE
Limits
.....................................................................................
135
Table
5­
4,
PE­
Ci
Limits
...............................................................................................
136
Table
6­
1,
Pu­
239
Fissile
Gram
Equivalent,
Decay
Heat,
and
Specific
Activity
of
Many
Radionuclides...................................................................................................
228
Table
6­
2,
Allowable
Materials
 
Greater
Than
1
Weight
Percent.................................
233
Table
6­
3,
Summary
of
Payload
Waste
Types...............................................................
238
Table
6­
4,
CH­
TRU
Waste
Material
Types
and
G
Values.............................................
239
Table
6­
5,
Alpha­
numeric
Shipping
Category
Notation
for
Payload
Package
Configurations..................................................................................................
240
Table
6­
6,
Alpha­
numeric
Shipping
Category
Notation
for
Layers
of
Confinement
in
Payload
Packages
.............................................................................................
240
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits............................................................................................
241
Table
6­
8,
Decay
Heat
Criteria
for
Drum
Selection
......................................................
265
Table
6­
9,
Maximum
Total
Gas
Release
Rates
for
Test
Categories...............................
265
Table
6­
10,
Flammable
Volatile
Organic
Compounds
...................................................
266
Figure
6­
1,
TRUPACT­
II
Gas
Generation
Requirements
 
RFETS
Compliance
Logic
Flow
Diagram
..................................................................................................
267
Figure
6­
2,
Payload
Selection.......................................................................................
268
Figure
6­
3,
TRUPACT­
II
Payload
Assembly
Criteria
...................................................
269
Figure
6­
4,
Assignment
of
Shipping
Categories
............................................................
270
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
9
VERSION
CHANGE
SUMMARY
The
following
changes
were
necessary
to
maintain
compliance
with
RFETS
procedure
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents.
This
procedure
requires
changes
to
contolled
documents
to
result
in
the
issue
of
new
version
of
the
document.

Page
Section
Description
of
Change
1
Cover
Page
Changed
"
Revision
6"
to
"
Version
7."
Replaced
list
of
required
concurrence
organizations
with
"
Review/
concurrence
documentation
is
contained
in
the
Document
History
File."
Revised
to
indicate
this
manual
supersedes
Revision
6.

2
Approvals
Added
following
sentence,
"
The
approvals
listed
below
apply
to
Version
7
of
this
document."

3
TOC
Deleted
List
of
Effective
Pages,
moved
up
and
updated
the
Table
of
Contents.

9
VCS
Added
Version
Change
Summary.

100
4.6.6
Added
"
version(
s)
or
"
to
1st
and
last
sentence.

Entire
Document
Revised
header
on
every
page
from
"
Revision
6"
to
"
Version
7"
and
updated
the
effective
date.

The
following
changes
were
made
as
part
of
document
maintanenance.

Page
Section
Description
of
Change
25
3.1.1.1.2
Replaced
"
of
data
approval"
with
"
for
sample
release"
in
2nd
sub­
bullet
of
7th
bullet.

31
Changed
Quality
Assurance
Manager
to
Quality
Program
Manager.

34
3.1.1.1.3
Replaced
"
Initiating"
with
"
Initiates"
in
4th
bullet.

45
3.1.1.1.4
Revised
1st
bullet
for
LPQAOs
since
position
no
longer
matrixed.
Deleted
6th
bullet
since
this
is
conducted
by
TWCP
Site
PQAO.

307
Changed
Quality
Assurance
to
Quality
Program.
Added
LPQAO
under
Remediation,
Industrial
D&
D,
and
Site
Services.
Deleted
Procurement
QA
under
Procurement
Systems.

308
Appendix
1
Revised
Material
Stewardship
organizational
chart
to
delete
the
LPQAO
from
under
Material
Stewardship
Quality
Assurance.

The
following
changes
were
made
as
part
of
document
maintanenance
and
consist
of
replacing,
or
footnoting
superseded
documents
referenced
throughout
this
TWMM.

Page
Description
of
Change
Replaced
or
deleted
reference
to
PRO­
T20­
Traffic­
505,
Certifying
Authorized
Payloads
for
TRUPACT­
II
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.

L­
4231,
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.
42,
66,
99,
103,
105,
150,
164,
188,
193,
195,
197,
209,
210,
217,
222,
224,
280,
284,
310­
311,
355,
357,
359­
361
PRO­
1205­
MLA­
008,
Metrology
Control
of
Measuring
and
Test
Equipment,
superseded
by
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
10
VERSION
CHANGE
SUMMARY
(
continued)

Page
Section
Description
of
Change
77
3.2.4.6
Modified
2nd
paragraph
to
demonstrate
that
calibrations
formerly
conducted
per
PRO­
1205­
MLA­
008,
Metrology
Control
of
Measuring
and
Test
Equipment,
are
now
conducted
under
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management.

84
3.6.1
Replaced
reference
to
PRO­
1327­
Services,
Requisitioning
Services
with
MAN­
134­
PPM,
Procurement
Program
Manual.

The
following
changes
were
made
as
part
of
document
maintanenance
and
consist
of
adding
notes
to
deactivated
documents
referenced
throughout
this
TWMM.

Page
Referenced
Documents
RS­
012­
005,
Cone
and
Quartering
Method
 
Solid
Sampling
and
Analysis
Plan.

L­
4031,
Software
Quality
Assurance.

PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR.

PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
371.

PRO­
717­
HDGAS­
371,
Headspace
Gas
Sampling,
Building
371.

00­
NDA­
TGS­
002,
Qualification
Plan
for
the
371TGS02
Tomographic
Gamma
Scanner
(
TGS)
Building
371.

00­
NDA­
TGS­
004,
Qualification
Plan
for
the
371TGS05
Tomographic
Gamma
Scanner
(
TGS)
Building
371.

CALG­
PD­
00005,
Calorimeter/
Gamma
Spec
Lower
Limit
of
Detection.

KH­
NDA2001­
CAL­
371TGS02,
Calibration
and
Qualification
Report
for
the
ANTECH
Tomographic
Gamma
Scanning
(
TGS)
Can
Counter
371TGS02
After
Installation
of
ANTECH
MasterScan
and
MasterAnalysis
Software.

KH­
NDA2001­
CAL­
371TGS05,
Calibration
and
Qualification
Report
for
the
ANTECH
Tomographic
Gamma
Scanning
(
TGS)
Can
Counter
371TGS05.

KH­
NDA2001­
RECAL­
371TGS03,
Calibration
and
Qualification
Report
for
the
Conversion
of
the
ANTECH
TGS
Can
Counter
371TGS03
from
DAC.
TGS
Data
Acquisition
to
MasterScan
Data
Collection
Software.

PRO­
1072­
NDA­
MSQ,
Matrix­
Specific
Qualification
for
NDA
Can
Counters.

PRO­
1290­
TRIFID­
371,
TRIFID
Gamma­
Ray
Isotopic
Analysis
System
Qualification.

PRO­
1297­
CLC&
RPT­
371,
Calorimetry/
Gamma­
Ray
Assay
Calculation
and
Reporting
of
Results.

PRO­
1298­
ISOAN­
371,
Gamma­
Ray
Isotopic
Analysis
of
Plutonium­
Bearing
Solids
in
Building
371
Cal/
Gamma
Laboratory.

PRO­
1299­
AIRBATH­
371,
Calorimetry
Using
the
ANTECH
Airbath
System
in
Building
371
Cal/
Gamma
Laboratory.

PRO­
1302­
WIPPDATA­
371,
Data
Review
and
Validation
for
Calorimetric
Assay
for
WIPP­
TRU
Waste
Characterization
Program
in
Building
371
Cal/
Gamma
Laboratory.

PRO­
1386­
TGS­
371,
Setup
and
Calibration
of
Building
371
Can
Tomographic
Gamma
Scanner
(
TGS).

PRO­
1392­
TGS­
371,
Operating
Building
371
Tomographic
Gamma
Scanning
(
TGS)
Can
Counters.
17,
84,
155­
156,
158,
170,
184,
201,
276,
278­
280,
282­
286,
322­
323,
327,
334,
356,
359
Determination
of
the
Total
Measurement
Uncertainty
for
the
RFETS
Skid
Mounted
TGS
and
Can
TGS.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
11
Rocky
Flats
Environmental
Technology
Site
Non­
Destructive
Assay
Calorimetry
and
Gamma
Spectrometry
Laboratories
Calorimeter
Qualification
Plan
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
12
VERSION
CHANGE
SUMMARY
(
continued)

The
following
changes
were
made
as
part
of
document
maintanenance
and
consist
of
revising
the
document
numbers
and
or
titles
of
documents
referenced
throughout
this
TWMM.

Page
Referenced
Documents
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management
Manual.

PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations
Flow.

Replaced
reference
to
4­
T30­
Traffic­
515,
Preparation
and
Retention
of
Shipping
Papers
with
PRO­
T30­
Traffic­
515,
Preparation
and
Retention
of
Hazardous
Materials
Shipping
Documents.

4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
for
and
Certification.

PRO­
1569­
SAP­
001,
Polymerized
Organic
and
Inorganic
Liquid
Process
 
Sampling
and
Analysis
Plan
17,
77­
78,
97,
99,
103­
105,
113,
150,
277,
281,
285­
286,
311,
355
PRO­
1668­
SQA,
TRU
Waste
Characterization
ProjectProgram
(
TWCP)
Software
Quality
Assurance.

The
following
changes
were
made
as
part
of
document
maintanenance
and
consist
of
documents
deleted
throughout
this
TWMM.

Page
Referenced
Documents
KH­
NDA2000­
QUAL­
371TGS01(
DRUM),
Qualification
Report
for
the
Determination
of
Plutonium­
239
Combustible
Waste
Packaged
in
55­
Gallon
Drums
Using
the
Reconfigured
Skid­
Mounted
TGS
Drum
Counter
371TGS01(
DRUM).

KH­
NDA2001­
QUAL­
569TGS04,
Calibration
and
Qualification
Report
for
the
Determination
of
Plutonium­
239
Combustible
Waste
Packaged
in
55­
Gallon
Drums
Using
the
ANTECH
TGS
Drum
Counter
569TGS04.

PRO­
1326­
Commodities,
Requisitioning
Commodities.

PRO­
1327­
Services,
Requisitioning
Services.

L­
4026,
Records
Handling,
Storage,
and
Retrieval
for
the
WIPP
Project
File.

L­
4048,
Radiological
Laboratories
Quality
Assurance
Plan.

PRO­
687­
TGS­
371,
Operating
the
Tomographic
Gamma
Scanner
(
TGS).

PRO­
701­
TGS­
371,
Setup
and
Calibration
for
the
Skid
Mounted
Tomographic
Gamma
Scanner
(
TGS)

PRO­
1006­
TGS­
569­
01,
Setup
and
Calibration
of
Building
569
Drum
Tomographic
Gamma
Scanner
(
TGS).

PRO­
1007­
TGS­
569­
02,
Operating
Building
569
Drum
Tomographic
Gamma
Scanner
(
TGS).
69­
71,
101,
278­
280,
282­
284,
286,
323,
334
PRO­
T20­
Traffic­
505,
Certifying
Authorized
Payloads
for
TRUPACT­
II.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
13
VERSION
CHANGE
SUMMARY
(
continued)

The
following
changes
were
made
as
part
of
document
maintanenance
and
consist
of
adding
references
to
the
following
documents
throughout
this
TWMM.

Page
Documents
Referenced
PRO­
1730­
903­
001,
903
Pad
Soil
Removal/
Repack
and
Characterization
Plan
KH­
NDA2003­
CALVER­
440PADC01,
Calibration
Verification
Plan
for
the
Newly
Relocated
Building
440
Imaging
Passive/
Active
Neutron
Drum
Counter
(
PADC),
Instrument
Control
Number
440PADC01.
17,
280,
286,
322,
333
KH­
NDA2003­
CALVER­
RPT­
440PADC01,
Calibration
Verification
Report
for
the
Newly
Relocated
Building
440
Imaging
Passive/
Active
Neutron
Drum
Counter
(
PADC),
Instrument
Control
Number
440PADC01.

The
following
change
was
made
to
update
KH­
Traffic
and
Transportation
organization
related
information,
and
active
NDA
system
information,
and
document
TRUCON
content
codes
for
new
IDCs.

Page
Section
Description
of
Change
41,
42
3.1.1.1.
4
Revised
Traffic
Management
Manager
and
Certification
Official
responsibilities
based
on
Traffic
and
Transportation
comments.
75
3.2.4.3
Replaced
reference
to
PRO­
T28­
Traffic­
513,
Waste
Package
Inspections
and
Shipments
with
PRO­
T95­
OSTP­
002,
Off­
Site
Transportation
Procedure.
99
4.6.5.4
Replaced
"
Traffic
Management"
with
"
Traffic
and
Transportation."
105
286
4.6.13.2
8.2
Deleted
reference
to
PRO­
T28­
Traffic­
513,
Waste
Package
Inspections
and
Shipments
169
6.4.2.2
Replaced
"
Transportation
Security
Officers"
with
"
Transportation
personnel"
and
added
"/
or"
following
"
move"
in
4th
paragraph.
243,
255­
258
Table
6­
7
Corrected
decay
heat
limit
for
numeric
shipping
category
30
0340
0034
to
0.4173
for
TRUCON
RF116F.
Added
new
IDCs
532A,
532B,
532C,
and
532D
to
TRUCON
content
code
RF130..
286
8.2
Added
reference
PRO­
T95­
OSTP­
002,
Off­
Site
Transportation
Procedure.
311
App.
2
Replaced
"
Trans.
Sec.
Off."
with
"
Trans.
Personnel."
319
320
A4.1
Revised
1st,
2nd,
3rd,
and
4th
paragraphs
to
demonstrate
additional
NDA
systems
now
inactive.
322
Table
A4.1­
1
Deleted
cal/
gamma
related
data
including
footnote
a.

325
A4.2.1
Revised
2nd
paragraph
and
deleted
last
paragraph
since
cal/
gamma
systems
are
inactive.
328
Table
A4.2­
1
Deleted
cal/
gamma
related
data.

330
A4.3
Deleted
last
sentence
from
the
3rd
paragraph.
Added
notes
to
Calorimeter
Specific
Qualification
Reports
and
Calorimetric
Assay
Total
Measurement
Uncertainty
and
Total
Bias
to
indicate
they
are
cancelled,
and
the
systems
are
no
longer
active.
333,
334
Table
A4.3­
2
Deleted
reference
to
Calibration
and
Qualification
Report
for
Tomographic
Gamma
Scanning
(
TGS)
Skid
Mounted
Can
Counter
371TGS01.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
14
1.
OVERVIEW
1.1
Purpose
The
purpose
of
the
Rocky
Flats
Environmental
Technology
Site
(
RFETS)
TRU
Waste
Management
Manual
(
TWMM)
is
to
describe
how
requirements
to
ship
waste
to
the
Waste
Isolation
Pilot
Plant
(
WIPP)
are
met
and
to
provide
some
of
the
sitespecific
program
documents.

Section
2.4
of
the
Contact­
Handled
Transuranic
Waste
Acceptance
Criteria
for
the
Waste
Isolation
Pilot
Plant
(
DOE/
WIPP­
02­
3122;
hereafter
referred
to
as
the
WIPPWAC
requires
that
each
participating
site
develop
and
implement
site­
specific
transuranic
(
TRU)
waste
program
documents
that
address
applicable
requirements
and
criteria
pertaining
to
packaging,
characterization,
and
certification
of
each
defense
TRU
waste
package
to
be
shipped
to
WIPP.
The
WIPP­
WAC
describes
the
site­
specific
program
documents
that
must
be
prepared
and
approved
in
response
to
Carlsbad
Field
Office
(
CBFO)
requirements.
Section
2
of
this
document
describes
the
site­
specific
program
documents
required
and
identifies
RFETS
documents
that
have
been
created
to
meet
the
requirements.

DOE
Order
435.1,
Radioactive
Waste
Management
(
U.
S.
DOE,
1999),
requires
that
a
TRU
waste
generator
and/
or
storage
site
prepare
certification
plan(
s)
identifying
how
the
site
will
ensure
compliance
with
the
waste
transportation
and
disposal
criteria/
requirements
applicable
to
the
WIPP
facility.
The
RFETS
certification
plan
is
the
same
as
the
Waste
Certification
Plan
required
by
CBFO.
Section
2
further
describes
compliance
with
this
requirement.

1.2
TRU
Waste
Programs
All
RFETS
processes
producing
transuranic
wastes
are
required
to
operate
in
accordance
with
the
requirements
and
implementing
procedures
provided
in
this
document
and
in
95­
QAPjP­
0050,
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
hereafter
referred
to
in
this
document
as
the
TWCP
QAPjP).
This
TWMM
addresses
overall
QA
activities
pertaining
to
the
TWCP,
WIPP­
WAC
requirements,
TRUPAC­
II
Authorized
Methods
for
Payload
Control
(
TRAMPAC),
and
TRUPACT­
II
Safety
Analysis
Report
(
SAR)
requirements
(
e.
g.,
waste
characterization
using
nondestructive
assay,
waste
certification
requirements,
and
shipping
requirements).
The
TWCP
QAPjP
addresses
the
requirements
of
the
WIPP
RCRA
Hazardous
Waste
Permit,
Attachment
B,
Waste
Analysis
Plan
(
WIPP­
WAP),
such
as
RCRA
waste
characterization
requirements,
acceptable
knowledge,
and
quality
assurance
records.
The
requirements
of
the
CBFO
Quality
Assurance
Program
Document
(
known
as
the
QAPD)
are
met
jointly
through
the
implementation
of
the
requirements
located
in
the
TWMM
and
in
the
TWCP
QAPjP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
15
1.2
TRU
Waste
Programs
(
continued)

Process­
specific
controls,
such
as
those
for
the
Residues
Projects,
are
referenced
in
applicable
Process
Control
Plans
(
PCPs)
and/
or
Process
Qualification
Plans
(
PQPs).
These
plans
are
prepared
in
accordance
with
1­
M60­
WPC­
001,
Waste
Process
Control,
and
are
referenced
as
applicable
requirements
documents
in
this
document
and
the
TWCP
QAPjP.

Procedure
1­
M60­
WPC­
001,
Waste
Process
Control,
directs
all
RFETS
management
responsible
for
the
development
of
new
TRU
waste
generation,
packaging,
or
characterization
operations
to
assess
these
operations
to
determine
if
additional
controls
are
required.
If
additional
controls
are
required,
responsible
management
is
required
to
characterize
process
attributes
in
order
to
define
and
document
process
parameter
values
that
produce
process
outcomes
in
compliance
with
WIPP
requirements.
Operations
are
then
required
to
comply
with
the
stated
process
parameter
settings
and
allowable
values
as
stated
in
the
PCP
and/
or
the
PQP
and
implemented
in
referenced
operational
procedures.
The
PCPs
are
typically
directed
at
waste
generation
operations,
while
the
PQPs
are
typically
directed
at
waste
characterization
and
waste
treatment
operations
that
produce
data
for
waste
certification.
Responsible
operations
management
may
elect
to
prepare
both
plans
if
they
deem
they
are
necessary.

The
PCPs/
PQPs
are
prepared
by
organizations
responsible
to
develop
new
processes
and
are
reviewed
and
approved
for
adequacy
and
completeness
against
WIPP
requirements
by
involved
management,
the
TWCP
Site
Project
Manager
(
TWCP
Site
PM),
the
TWCP
Site
Project
Quality
Assurance
Officer
(
TWCP
Site
PQAO),
and
the
TRU
Waste
Certification
Official
(
WCO).
The
following
PCPs
provide
controls
for
recently
developed
processes;
this
listing
will
be
updated
annually
to
indicate
the
new
operations
developed
or
in
development.
Refer
to
the
TWCP
QAPjP,
Section
A­
4,
Project
Description,
for
a
description
of
residue
activities.
Current
PCPs
include
the
following:

 
RS­
020­
021,
Salt
Residue
Repack,
Buildings
371
and
707
Process
Control
Plan
 
RS­
020­
006,
Salt
Residue
Stabilization,
Building
707
Process
Control/
Qualification
Plan1
 
RS­
020­
012,
Ash
Residue
Repack
Process
Control
Plan
 
RS­
020­
018,
Combustible
Residue
Repackaging
Process
Control
Plan
 
RS­
020­
013,
Dry
Residue
Repackaging
Process
Control
Plan
1
The
Salt
Residue
stabilization/
repack
activity
that
utilized
this
PCP
was
completed
in
June
2000.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
16
2.
REQUIREMENTS
FOR
CH­
TRU
WASTE
CERTIFICATION
AND
TRANSPORTATION
TO
WIPP
2.1
CBFO
Requirements
Documents
Criteria
and
requirements
that
must
be
complied
with
by
RFETS
before
TRU
waste
may
be
shipped
to
WIPP
are
derived
from
the
following
sources:

 
The
WIPP­
WAC
 
The
WIPP­
WAP
 
The
QAPD
 
The
TRAMPAC
 
The
WIPP
Transportation
Plan
(
DOE/
CAO
98­
3103)

 
Performance
Demonstration
Program
Plans
The
flowdown
of
regulatory
and
DOE
requirements
to
these
documents
and
to
sitespecific
program
documents
is
shown
in
Figures
2­
1,
2­
2,
and
2­
3.

2.2
RFETS
Program
Documents
RFETS
program
documents
have
been
developed
and
implemented
in
response
to
CBFO
program
requirements.
The
following
sections
(
2.2.1
through
2.2.7)
describe
the
documents
required
by
CBFO
and
identify
the
RFETS
document(
s)
that
provide
compliance.
A
summary
of
these
documents
and
approval
requirements
is
provided
in
Table
2­
1.

2.2.1
Waste
Certification
Plan
The
purpose
of
this
plan
is
to
identify
how
compliance
with
each
requirement
of
the
WIPP­
WAC
is
accomplished.
Section
5
of
the
TWMM
provides
the
site­
specific
Waste
Certification
Plan.
Section
5
identifies
the
implementing
procedures
that
provide
compliance
with
the
waste
acceptance
criteria
requirements
of
the
WIPPWAC
Appendix
4,
of
this
document,
addresses
the
procedures
implemented
to
the
Non­
Destructive
Assay
requirements
of
the
WIPP­
WAC,
Appendix
4.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
17
2.2.2
Certification
QA
Plan
The
purpose
of
the
Certification
QA
Plan
is
to
document
site
compliance
with
the
QAPD
requirements
for
the
site
certification
program.
Section
3
of
the
TWMM
documents
the
QA
program
that
has
been
implemented
at
RFETS
to
comply
with
certification
QA
requirements.

2.2.3
Quality
Assurance
Project
Plan
(
TWCP
QAPjP)

A
site­
specific
QAPjP
is
required
to
document
the
procedures
and
methods
that
are
used
for
waste
characterization.
The
RFETS
site­
specific
QAPjP
is
the
TWCP
QAPjP.
The
TWCP
QAPjP
uses
the
same
format
as
the
WIPP­
WAP
and
documents
how
RFETS
complies
with
WIPP­
WAP
requirements.
PCPs
and/
or
PQPs
implement
CBFO
requirements,
as
applicable,
at
the
process
level.

2.2.4
Graded
Approach
Procedure
The
QAPD
requires
that
each
site
prepare
a
Graded
Approach
Procedure.
The
procedure
is
to
be
used
to
determine
the
appropriate
controls
necessary
to
manage
the
items,
systems,
and
activities
under
the
cognizance
of
CBFO.
Procedure
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading,
has
been
developed
and
implemented
at
RFETS
to
comply
with
this
requirement.

The
steps
leading
to
identifying
realistic
process
controls
are
to:
(
1)
identify
the
RFETS
procedures
that
implement
WIPP
requirements,
(
2)
designate
each
WIPPrelated
procedure
as
Quality
Level
(
QL)­
Major
or
QL­
Minor,
and
3)
cross­
correlate
each
WIPP­
related
procedure
to
a
corresponding
QAPD
QA
element.
Procedure
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading,
contains
this
list
of
RFETS
WIPP­
related
procedures
that
implement
QAPD
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
18
2.2.5
Sampling
Plan
The
document
95­
WP/
SAP­
001,
Transuranic
(
TRU/
TRM)
Waste
Sampling
Plan,
supports
the
WIPP­
WAP
and
the
TRAMPAC
sampling
requirements.
It
outlines
the
strategy
to
be
used
by
the
site
in
the
sampling
of
TRU
waste
that
will
be
shipped
to
WIPP
for
disposal.
The
contents
of
95­
WP/
SAP­
001,
Transuranic
(
TRU/
TRM)
Waste
Sampling
Plan,
correspond
to
requirements
given
in
the
WIPP­
WAP.
Compliance
with
the
WIPP­
WAP
is
accomplished
through
the
use
of
the
TWCP
QAPjP
and
the
TWMM.

Individual
Sampling
Plans
that
support
various
processes
are:

 
RS­
012­
004,
Grid
Method
­
Solid
Sampling
and
Analysis
Plan;

 
RS­
012­
005,
Cone
and
Quartering
Method
­
Solid
Sampling
and
Analysis
Plan1;

 
PRO­
1569­
SAP­
001,
Polymerized
Organic
and
Inorganic
Liquid
Process
 
Sampling
and
Analysis
Plan;

 
PRO­
1730­
903­
001,
903
Pad
Soil
Removal/
Repack
and
Characterization
Plan.

2.2.6
TRAMPAC
and
Associated
QA
Plan
The
site­
specific
TRAMPAC
is
required
to
describe,
in
technical
detail,
how
compliance
with
requirements
of
the
TRAMPAC
and
Certificate
of
Compliance
will
be
met.
Section
6
of
the
TWMM
is
the
RFETS
TRAMPAC.
Section
6
references
RFETS
procedures
that
pertain
to
loading
and
unloading
the
TRUPACT­
II
and
that
provide
compliance
with
the
requirements
of
the
TRAMPAC.
Section
3
of
the
TWMM
provides
the
QA
Plan
that
is
associated
with
the
TRAMPAC.

2.2.7
Packaging
QA
Plan
The
Packaging
QA
Plan
describes
the
site
QA
program
for
TRU
Waste
Packaging.
The
requirements
for
packaging
are
contained
in
10
CFR
71,
Subpart
H.
Existing
QA
programs
may
be
used
if
they
meet
the
requirements
of
10
CFR
71
requirements.
Section
4.6
provides
the
Packaging
QA
Plan
for
the
TRU
Waste
Characterization
Project.

1
This
document
is
inactive
as
of
December
2003.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
19
Table
2­
1,
Summary
of
RFETS
Program
Documents
RFETS
PROGRAM
DOCUMENT
RFETS
DOCUMENT
PROVIDING
COMPLIANCE
DOCUMENT
REVIEW/
APPROVAL
Waste
Certification
Plan
TWMM,
Section
5.0
National
TRU
Waste
Program
Team
Leader
Approves
CBFO
QA
Manager
Approves
CBFO
Transportation
Package
Manager
Reviews
DOE
Rocky
Flats
Field
Office
(
RFFO)
Approves
RFETS
Contractor
Review
and
Approval
according
to
MAN­
001­
SDRM,
Site
Document
Requirements
Manual;
PRO­
1329­
DM­
03,
Site
Document
Control;
and
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
Certification
QA
Plan
TWMM,
Section
3.0
Same
review/
approval
as
listed
above
for
the
Waste
Certification
Plan
TWCP
Quality
Assurance
Project
Plan
(
TWCP
QAPjP)
TWCP
QAPjP
National
TRU
Waste
Program
Team
Leader
Approves
CBFO
QA
Manager
Approves
DOE
RFFO
Approves
RFETS
Contractor
Review
and
Approval
according
to
MAN­
001­
SDRM,
Site
Document
Requirements
Manual;
PRO­
1329­
DM­
03,
Site
Document
Control;
and
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
Graded
Approach
Procedure
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading
CBFO
QA
Manager
Approves
DOE
RFFO
Approves
RFETS
Contractor
Review
and
Approval
according
to
MAN­
001­
SDRM,
Site
Document
Requirements
Manual;
PRO­
1329­
DM­
03,
Site
Document
Control;
and
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
Sampling
Plan
(
no
longer
a
WIPP
requirement)
95­
WP/
SAP­
001,
Transuranic
(
TRU/
TRM)
Waste
Sampling
Plan
RFETS
Contractor
Review
and
Approval
according
to
MAN­
001­
SDRM,
Site
Document
Requirements
Manual;
PRO­
1329­
DM­
03,
Site
Document
Control;
and
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
TRAMPAC
&
Associated
QA
Plan
The
TRAMPAC
is
provided
in
the
TWMM,
Section
6;
and
the
associated
QA
Plan
is
provided
in
the
TWMM,
Section
3.0.
Same
review/
approval
as
listed
above
for
the
Waste
Certification
Plan
Packaging
QA
Plan
TWMM,
Section
4.6
Same
review/
approval
as
listed
above
for
the
Waste
Certification
Plan
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
20
Figure
2­
1,
CBFO
Requirements
Flowdown
Characterization
Site­
Specific
QAPjP
(
TWCP
QAPjP,
95­
QAPjP­
0050)

Site­
Specific
Sampling
Plan
Implementing
Procedures
WIPP
Hazardous
Waste
Facility
Permit
Waste
Analysis
Plan
(
WIPP­
WAP)
40
CFR
Parts
260­
266,
268,
&
270
RCRA
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
21
Figure
2­
2,
CBFO
Requirements
Flowdown
Certification
Implementing
Procedures
RFETS
DATA
INPUT
TO
WWIS
Site­
Specific
TRAMPAC
(
Section
6
of
TRU
Waste
Management
Manual)
Site­
Specific
Packaging
QA
Program
Plan
(
Section
4.6
of
TRU
Waste
Management
Manual)
10
CFR
Parts
70
and
71
Packaging
DOE/
WIPP­
02­
3122
CONTACT­
HANDLED
TRANSURANIC
WASTE
ACCEPTANCE
CRITERIA
(
WAC)
DOE
Order
5840.23
WIPP
Operations
WIPP
Safety
Analysis
Report
DOE
Order
6430.1A
WIPP
Design
49
CFR
Parts
107,
110,
and
171­
173
Transportation
TRAMPAC
Compliance
Certification
Application
40
CFR
Parts
191
&
194
Radiation
Standards
Site­
Specific
Waste
Certification
Plan
(
Section
5
of
TRU
Waste
Management
Manual)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
22
Figure
2­
3,
CBFO
Requirements
Flowdown
Quality
Assurance
DOE
Order
414.1a
NQA­
1
NQA­
2a
10­
CFR
830.

Site­
Specific
QAPjP
(
TWCP
QAPjP,
95­
QAPjP­
0050)
Graded
Approach
Procedure
(
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
Quality
Assurance
Grading)
TRAMPAC
Associated
QA
Plan
(
Section
3,
TWMM)
Site­
Specific
Certification
QA
Plan
(
Section
3,
TWMM)

Implementing
Procedures
DOE/
CBFO­
1012,
Quality
Assurance
Program
Document
(
QAPD)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
23
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
24
3.0
CERTIFICATION
AND
TRAMPAC
QUALITY
ASSURANCE
PROGRAMS
This
section
describes
the
TRU
Waste
Characterization
Project
QA
Program
that
provides
compliance
with
the
Quality
Assurance
requirements
defined
in
the
QAPD.
The
TRU
Waste
Characterization
Project
QA
Program
is
also
the
QA
Program
associated
with
the
TRAMPAC
for
the
use,
maintenance,
and
control
of
the
TRUPACT­
II.

The
RFETS
QA
requirements
are
identified
in
the
Kaiser­
Hill
Quality
Assurance
Program
Criteria.
The
QA
Program
implemented
by
the
TRU
Waste
Characterization
Project
is
directed
towards
CBFO
QA
requirements.

Any
payload
packages
with
unresolved
discrepancies
associated
with
hazardous
waste
characterization
will
not
be
shipped
to
WIPP
until
the
discrepancies
are
resolved.
Corrective
action
reports
applicable
to
WIPP­
WAP
requirements
shall
be
resolved
prior
to
waste
shipment.

3.1
Management
Requirements
3.1.1
Organization
&
QA
Program
This
section
describes
the
organizational,
managerial
and
quality
assurance
structure
and
responsibilities
for
the
RFET
TRU
Waste
Programs.
Generator
and
originator
are
titles
considered
synonymous
and
used
interchangeably
throughout
this
plan.

3.1.1.1
Organization
The
functional
organization
charts
in
Appendix
1,
Organizational
Charts
show
the
RFETS
TRU
Waste
Programs
organizational
breakdown
and
reporting
hierarchy,
which
is
updated
commensurate
with
changes
to
the
TWMM.
The
Kaiser­
Hill
(
KH)
Human
Resources
department
maintains
the
official
organizational
charts
for
RFETS.

3.1.1.1.1
Management
Responsibilities
The
responsibilities
listed
here
are
the
general
responsibilities
of
the
organizations.
The
specific
tasks
and
responsibilities
to
be
performed
by
these
organizations
are
defined
in
the
Rocky
Flats
Closure
Project
(
RFCP),
Project
Management
Plan
(
PMP),
work
packages,
and
in
specific
operating
procedures.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
25
3.1.1.1.1
Management
Responsibilities
(
continued)

Management
delegates
TWCP
authority
and
decision
making
to
the
organizations
described
in
Sections
3.1.1.1.1
through
3.1.1.1.4.
These
organizations
are
responsible
for
establishing,
planning,
accomplishing,
and
assessing
TRU
waste
activities
at
the
lowest
appropriate
level
in
the
organization.

Kaiser­
Hill
(
KH)
is
responsible
for
ensuring
the
development,
implementation,
and
maintenance
of
plans,
policies,
and
procedures
necessary
to
assure
compliance
with
all
applicable
regulations,
U.
S.
Department
of
Energy
(
DOE)
orders
and
requirements
applicable
to
activities
subject
to
the
QAPD.

Material
Stewardship,
TRU
Waste
Project,
provides
program
management
of
the
TWCP.
The
Vice
President,
Material
Stewardship,
designates
the
TRU
Waste
Project
Manager.
The
TRU
Waste
Project
Manager
fulfills
the
functional
role
of
TWCP
Site
PM.

The
TWCP
Site
PM
is
responsible
for
directing
the
TRU
waste
generation,
characterization,
certification
and
transportation
activities
across
all
organizations
supporting
the
program.
The
TWCP
Site
PQAO
identifies
and
achieves
all
management
QA
responsibilities
by
developing,
implementing
and
maintaining
the
quality
assurance
programs
and
mechanisms
to
ensure
compliance
to
specified
quality
assurance
requirements.
The
following
sections
of
this
document
describe
the
specific
responsibilities
of
the
Site
PM
and
the
Site
PQAO.

3.1.1.1.2
Employee
Responsibilities
The
TWCP
Site
PM
performs
the
following:

 
Provides
for
project
management
of
the
RFETS
TRU
Waste
Program.
Defines
project
activities,
authorizes
work,
and
manages
the
budget
for
the
project,
and
tracks
progress.

 
Performs
oversight
and/
or
management
of
TRU
Waste
Program
characterization
activities.

 
Interfaces
with
KH,
DOE,
WIPP
and
other
regulatory
agencies
on
projectspecific
matters,
and
serves
as
the
RFETS
Point­
of­
Contact
for
WIPP­
related
activities.

 
Manages
CBFO
and
New
Mexico
Environmental
Department
(
NMED)
audit
preparations
for
TRU
Waste
Program
characterization
and
Residues
processing.

 
Ensures
through
the
TWCP
Site
PQAO
that
surveillances
are
scheduled
and
performed.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
26
3.1.1.1.2
Employee
Responsibilities
(
continued)

The
TWCP
Site
PM
(
continued)

 
Ensures
development
and
maintenance
of
program
documents,
plans
and
procedures
necessary
to
implement
the
TRU
Waste
Program:

 
Ensures
preparation,
issuance,
control
and
maintenance
of,
and
approves
the
TWMM
and
the
TWCP
QAPjP;

 
Ensures
annual
review
of
the
TWCP
QAPjP
and
concurs
on
necessary
changes
or
revisions;

 
Reviews
and
concurs
on
TRU
Waste
Program
characterization
plans
and
procedures
[
e.
g.,
headspace
gas,
visual
examination
(
VE),
nondestructive
assay
(
NDA),
Real­
Time
Radiography
(
RTR)];

 
Ensures
distribution
of
CBFO
requirements
document
changes
to
affected
organizations
so
that
RFETS
implementing
procedures
can
be
modified
as
necessary.

 
Ensures
that
projects
that
support
TRU
Waste
Program
activities
utilize
processes
that
comply
with
TRU
Waste
Program
requirements.

 
Concurs
with
appointment
of
the
TWCP
Site
PQAO
and
the
Project
Data
Control
Officer
(
PDCO).

 
Designates
the
Project
Training
Officer.

 
Ensures
that
applicable
personnel
are
trained
and
qualified
to
TRU
Waste
Program
requirements.

 
Provides
for
waste
selection
and
tracking.

 
Provides
for
data
validation
and
verification:

 
Approves
Batch
Data
Reports;

 
Provides
notification
to
Headspace
Analytical
Services
and
the
Analytical
Laboratory
for
sample
release.

 
Provides
for
data
reconciliation
with
data
quality
objectives
(
DQOs):

 
Ensures
that,
as
applicable,
solid
sampling
and
analysis,
headspace
gas
sampling
and
analysis,
visual
examination,
NDA,
and
RTR
are
performed,
completed,
and
documented
in
accordance
with
TRU
Waste
Program
requirements;

 
Provides
direction
to
the
TWCP
Site
PQAO,
PDCO,
and
project
staff
regarding
analytical
data
validation
and
reconciliation
with
quality
assurance
objectives
(
QAOs)
as
necessary.
TRANSURANIC
(
TRU)
WASTE
1­
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WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
27
3.1.1.1.2
Employee
Responsibilities
(
continued)

The
TWCP
Site
PM
(
continued)

 
Provides
for
the
assignment
of
U.
S.
Environmental
Protection
Agency
(
EPA)
Hazardous
Waste
Codes:

 
Ensures
that
applicable
sampling
is
performed
(
e.
g.,
fingerprint
analysis,
headspace
sampling,
and
Resource
Conservation
and
Recovery
Act
(
RCRA)
solid
sampling).

 
Ensures
that
feedback
from
waste
characterization
activities
is
used
to
update
Acceptable
Knowledge
(
AK)
documentation.

 
Approves
Waste
Stream
Profile
Forms
(
WSPFs).

 
Provides
technical
guidance
for
treatment
and/
or
disposition
of
wastes.

 
Reviews
and
provides
for
the
transmission
of
QA/
QC
reports
to
the
DOE
Field
Office.

 
Provides
for
data
transmission
to
CBFO:

 
Signs
transmittal
of
the
final
Batch
Data
Reports;

 
Provides
for
submittal
of
the
required
Batch
Data
Reports
[
through
Waste
Environmental
Management
System
(
WEMS)]
to
the
WIPP
prior
to
each
TRU
waste
shipment
(
contains
complete
package
and
shipping
information).

 
Manages
facility
operational
aspects
of
the
TRU
Waste
Program
involving
headspace
gas
sampling
and
VE
for
use
in
verifying
RTR
as
follows:

 
Interfaces
with
Waste
Operations
and
the
TWCP
Site
PQAO
on
project
activities
affecting
cost,
schedule,
and
quality­
related
matters;

 
Ensures
that
operator
training
is
conducted
according
to
requirements;

 
Ensures
that
visual
waste
characterization
data
are
obtained
for
appropriate
waste
containers
used
in
the
TRU
Waste
Program;

 
For
VE
activities
used
to
verify
radiography,
ensures
that
activities
are
audio/
videotaped
and
that
audio/
videotape
equipment
is
checked
prior
to
each
day's
use,
to
including
recording
and
observation
of
test
patterns;

 
Ensures
that
VE
(
to
Confirm
RTR)
audio/
videotapes
are
transmitted
to
the
PDCO
within
30
days
of
completion;

 
Ensures
that
data
are
recorded
and
complete;

 
Ensures
that
waste­
characterization
data
forms
and
reports
are
transmitted
to
the
PDCO
as
soon
as
possible
after
data
generation;
and
 
Ensures
100%
validation
of
VE
raw
data.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
28
3.1.1.1.2
Employee
Responsibilities
(
continued)

The
PDCO
performs
the
following:

 
Manages
and
controls
the
TRU
Waste
Program
records
in
accordance
with
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing;
and
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center.

 
Supports
the
TWCP
Site
PQAO
in
project
quality
surveillance,
data
coordination,
and
data
acquisition
as
defined
in
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing.

 
Upon
completion
of
the
data
generation
level
data
validation
and
verification,
receives
the
Batch
Data
Reports
for
inclusion
in
the
project
records
management
system.

 
Upon
request,
transmits
data
generation
level
Batch
Data
Reports
to
the
TWCP
Site
PQAO
for
project
level
data
validation
and
verification.

 
Upon
completion
of
the
project
level
data
validation
and
verification,
receives
the
approved
Batch
Data
Reports
for
inclusion
in
the
project
records
management
system.

 
Provides
training
to
WIPP
records
custodians.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
29
3.1.1.1.2
Employee
Responsibilities
(
continued)

The
Headspace
Analytical
Services
Manager
performs
the
following:

 
Manages
the
Headspace
Analytical
Services
organization
which
conducts
headspace
gas
sampling
and
analysis
utilizing
on­
line
integrated
sampling
and
analysis
systems
in
support
of
TRU
waste
characterization.

 
Interfaces
with
the
TWCP
Site
PM
and
the
TWCP
Site
PQAO
on
TWCP
activities
affecting
cost,
schedule,
and
quality­
related
matters.

 
Ensures
that
headspace
personnel
are
trained
and
qualified.

 
Ensures
participation
in
the
PDPs
for
analytical
testing.

 
When
performing
the
functional
role
of
Technical
Supervisor,
reviews,
approves,
and
releases
the
Analytical
Batch
Data
Report.
Other
qualified
personnel
[
i.
e.,
qualified
as
specified
in
PLN­
97­
007,
TWCP
Training
Implementation
Plan
(
TWCP
TIP)]
may
perform
the
role
of
Technical
Supervisor.

 
Coordinates
and
schedules
analytical
work
to
support
the
TWCP.

 
Ensures
that
corrective
and
preventive
actions
have
been
completed.

 
Reviews
and
approves
all
Headspace
Analytical
Services
SOPs
and
reports.

 
Assigns
headspace
staff.

 
Manages
the
implementation
of
the
Headspace
Analytical
Services'
roles
and
responsibilities.

 
Verifies
that
analytical
requirements
of
the
WIPP­
WAP
and
QAPjP
have
been
met
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
30
3.1.1.1.2
Employee
Responsibilities
(
continued)

The
Measurements
Manager
is
responsible
for
delegating
the
following
technical,
operational,
data
management
and
planning,
and
quality
assurance
activities:

Technical
activities
include:

 
Establishing
and
maintaining
a
Measurement
Control
Program
in
accordance
to
the
WIPP­
WAC;

 
Selecting,
calibrating,
and
qualifying
RFETS
NDA
measurement
systems;

 
Coordinating
with
the
TWCP
Site
PM,
TWCP
Site
PQAO
and
Materials
Control
&
Accountability
on
NDA
activities
affecting
TRU
Waste
Programs;

 
Ensuring
that
Measurements
documents
are
compliant
with
TRU
Waste
Programs
requirements;

 
Providing
expert
review,
if
necessary,
of
NDA
Testing
Batch
Data
Reports;

 
Designating
and
providing
supervision
of
NDA
functions;

 
Providing
oversight
of
subcontracted
NDA
services
(
if
required);

 
Implementing
a
documented
program
for
a
measurement
facility
that
specifies
qualitative
and
quantitative
acceptance
criteria
and
corrective
action
processes;

 
Investigating
measurement
problems,
and
documenting
and
performing
corrective
actions;

 
Facilitating
the
implementation
of
quality
related
activities,
including
data
interpretation,
procedure
development
and
updates,
nonconformance
reports,
and
corrective
actions;
and
 
Supporting
quality
control
activities
of
measurement
operations
and
data
management.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
31
3.1.1.1.2
Employee
Responsibilities
(
continued)

The
Measurements
Manager
(
continued)

Operational
activities
include:

 
Supervising
the
installation
of
new
NDA
equipment
that
measure
radionuclides
for
Residues,
TRU
Waste,
and
low­
level
waste
(
LLW);

 
Performing
calibrations
and
calibration
verifications
of
NDA
equipment
to
applicable
requirements
and
at
specified
frequencies;

 
Maintaining
and
repairing
RFETS
NDA
counters
and
equipment;

 
Maintaining
configuration
control
of
RFETS
NDA
counters
to
meet
applicable
NDA
QC
requirements
and
frequencies;

 
Providing
subject
matter
expert
(
SME)
support
for
the
maintenance
and
operation
of
NDA
equipment;

 
Tracking
RFETS
NDA
standard
certification
status;

 
Establishing
and
maintaining
NDA
procedures;
and
 
Qualifying,
training
and
re­
qualifying
NDA
personnel
to
existing
industry
training
standards.

Data
management
activities
include:

 
Designating
and
providing
supervision
of
NDA
data
quality
functions
 
Establishing
and
maintaining
an
inventory
of
isotopic
ratios
of
prevalent
radionuclides
for
confirmation
of
AK;

 
Designating
and
providing
supervision
of
Data
Generation
Level
Data
Validation
and
Verification
(
V&
V)
as
follows:

 
Providing
NDA
Data
V&
V;

 
Monitoring
the
measurement
control
and
instrument
check
data
to
assure
that
RFETS
NDA
counters
perform
according
to
quality
requirements;
and
 
Resolving
Batch
Data
Report
issues
related
to
data
quality.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
32
3.1.1.1.3
Quality
Assurance
Management
&
Responsibilities
The
KH
Site
Quality
Program
Manager
performs
the
following:

 
Assures
QA
management
has
direct
access
to
responsible
management
at
a
level
where
appropriate
action
can
be
effected,
is
sufficiently
independent
from
cost
and
schedule
considerations,
has
the
organizational
freedom
to
communicate
with
management,
and,
has
no
other
assigned
responsibilities
unrelated
to
the
QA
program
that
would
prevent
full
attention
to
QA
matters.

 
Identifies
and
reports
quality
problems
to
the
TWCP
Site
PM
or
Site
PQAO.

 
Responsible
for
site
corrective
action
program
 
Initiates
stop
work
orders
according
to
1­
V10­
ADM­
15.02,
Stop
Work
Action,
when
appropriate.

 
Coordinates
the
identification,
evaluation,
and
resolution
of
site­
wide
quality
issues
or
quality
issues
that
cross
project
boundaries.

 
Provides
an
interface
between
senior
management
and
project
QA
functions
for
site­
wide
issues
or
issues
that
cross
project
boundaries.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
33
3.1.1.1.3
Quality
Assurance
Management
&
Responsibilities
(
continued)

The
Material
Stewardship
QA
Manager
performs
the
following:

 
Designates
and
provides
oversight
of
the
TWCP
Site
PQAO.

 
Assures
development
and
maintenance
of
the
TRU
Waste
Program
QA
program
in
conjunction
with
the
KH
Quality
Assurance
program.

 
Schedules
and
conducts
assessments
of
the
TRU
Waste
Program.

 
Provides
day­
to­
day
guidance
on
quality­
related
matters
to
TRU
Waste
Program
staff.

 
Ensures
that
an
independent
assessment
of
the
project
is
performed
annually
(
this
assessment
may
be
comprised
of
several
smaller
scope
assessments).

 
Ensures
that
Waste
Inspectors
are
trained
and
qualified
to
perform
waste
inspection.

 
Ensures
that
waste
inspection
procedures
and
work
instructions
are
developed
and
maintained.

 
Provides
for
technical
guidance
for
RFETS
Waste
Inspectors.

 
Ensures
that
Waste
Inspectors
meet
responsibilities
identified
in
waste
inspection
procedures.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
34
3.1.1.1.3
Quality
Assurance
Management
&
Responsibilities
(
continued)

The
TWCP
Site
Project
Quality
Assurance
Officer
(
TWCP
Site
PQAO)
performs
the
following:

 
Ensure
that
the
TRU
Waste
Program
QA
program
provides
RFETS
compliance
with
the
QAPD.

 
Schedules,
performs,
or
directs,
surveillance
of
TRU
waste
characterization,
generation,
packaging,
control,
and
acceptance
activities
including
assessments
of
labs
and
testing
facilities.

 
Tracks,
reviews
and
approves
the
disposition
of
TRU
Waste
Program
nonconformances

 
Assists
the
TWCP
Site
PM
in
responding
to
regulator
identified
deficiencies
and
non­
conformances.

 
Performs,
or
designates
individuals
to
perform,
data
validation
and
verification
activities
on
Batch
Data
Reports
as
defined
through
procedures
identified
in
the
TWCP
QAPjP.

 
Verifies
data
QA
documentation
through
the
data
validation
and
verification
of
Batch
Data
Reports
 
Tracks,
performs
trend
analysis,
and
reports
on
quality
problem
areas.

 
Identifies
and
reports
quality­
related
problems
to
the
TWCP
Site
PM,
initiates
documentation
to
track
the
quality­
related
problem,
reviews
corrective
actions,
and
tracks
corrective
actions
to
closure.

 
Performs
verification
of
corrective
actions
in
accordance
with
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems.

 
Provides
QA/
QC
reports
to
the
TWCP
Site
PM
for
review,
transmittal
to
CBFO,
and
distribution
to
the
RFFO.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
35
3.1.1.1.3
Quality
Assurance
Management
&
Responsibilities
(
continued)

The
TWCP
Site
PQAO
(
continued)

 
Ensures
conformance
to
QA
requirements
through:

 
Review
and
approval
of
procedures
that
implement
the
TRU
Waste
Program
QA
program;

 
Review
and
concurrence
on
the
TWCP
QAPjP,
the
Gas
Generation
Testing
Program
(
GGTP)
QAPjP,
the
TWMM
and
PRO­
486­
WIPP­
006;

 
Distribution,
to
affected
organizations,
of
changes
to
CBFO
requirement
documents
so
that
site
implementing
procedures
can
be
modified
as
necessary.

 
Provides
a
list
of
WIPP­
related
RFETS
documents
to
Site
Document
Control.

 
Provides
day­
to­
day
guidance
on
quality
assurance­
related
matters,
as
necessary,
to
TRU
Waste
Program
staff.

 
Initiates
a
stop
work
order
in
accordance
with
1­
V10­
ADM­
15.02,
Stop
Work
Action,
if
quality
work
is
not
assured.

 
Maintains
liaison
with
the
CBFO
QA
organization
and
sub­
tier
organizations.

 
Interfaces
with
generators
of
TRU
Waste
Program
data
and
quality­
related
records.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
36
3.1.1.1.3
Quality
Assurance
Management
&
Responsibilities
(
continued)

Headspace
Analytical
Services
Quality
Assurance
Officer
(
HASQAO)
performs
the
following:

 
Directs
all
of
the
Headspace
Analytical
Services'
WIPP­
related
QA
activities
and
is
matrixed
to
the
Headspace
Analytical
Services'
Manager
in
fulfilling
this
function.

 
Interfaces
directly
with
the
TWCP
Site
PQAO
on
headspace
specific
QA
matters
related
to
this
project.

 
Ensures
that
all
project
headspace
personnel
have
a
clear
understanding
of
the
special
QC
requirements
for
the
Project.

 
Develops,
reviews,
and
revises
headspace­
related
portions
of
the
TWCP
QAPjP.

 
Provides
quality
surveillance
of
headspace
TWCP­
related
activities.

 
Tracks
and
reports
headspace
nonconformances
for
management
reporting
to
the
TWCP
Site
PQAO.

 
Verifies
the
implementation
of
project
QA
requirements.

 
Identifies
and
reports
headspace
quality
deficiencies
to
the
appropriate
Project
personnel
and
the
TWCP
Site
PQAO.

 
Initiates,
recommends,
and
tracks
corrective
actions
to
closure.

 
Reviews
and
verifies
that
all
Headspace
Analytical
Services
SOPs
comply
with
QAPjP
and
WIPP­
WAP
requirements.

 
Reviews
and
approves
Batch
Data
Reports
prior
to
release
to
the
Waste
Records
Center
and
ensures
that
Batch
Data
Reports
are
transmitted
in
a
timely
manner.

 
Ensures
that
all
headspace
requirements
of
the
WIPP­
WAP
and
QAPjP
have
been
met.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
37
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
RFETS
TRU
Waste
Programs
has
communications
and
interface
responsibilities
with
Technical
Operations;
Waste
Certification
&
Oversight;
Traffic
&
Transportation;
and
other
supporting
groups.
The
following
paragraphs
discuss
the
general
responsibilities
of
each
of
these
groups.

Technical
Operations
The
Technical
Operations
organization
is
supported
by
Waste
Systems
and
the
Waste
Requirements
Group.

Waste
Systems
performs
the
following:

 
Maintains
the
content
and
accuracy
of
the
Waste
Stream
and
Residue
Identification
and
Characterization
(
WSRIC)
Building
Books
when
revision
requests
are
received
from
generator
organizations.

 
Maintains
the
Waste
and
Environmental
Management
System
(
WEMS)
computer
database.

 
Maintains
the
content
and
accuracy
of
the
Backlog
Waste
Reassessment
Baseline
Book
(
BWRBB)
and
coordinates
reassessment
of
characterization
information
for
packaged
waste.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
38
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Technical
Operations
(
continued)

Waste
Requirements
Group
performs
the
following:

 
Prepares,
issues,
controls,
and
maintains
waste
segregation
guidance
documents.

 
Provides
Independent
Technical
Reviewer,
Technical
Supervisor,
and
Quality
Assurance
Officer
reviews
of
visual
verification
data
generated
by
waste
generators.

 
Provides
waste
characterization,
generation,
and
packaging
assistance
to
waste
generators.

 
Prepares
Waste
Generating
Instructions
(
WGIs)
to
communicate
waste
characterization
and
packaging
requirements
to
waste
generators
at
the
floor
level.

 
Reviews
the
Waste/
Residue
Traveler
(
W/
RT)
for
conformance
to
the
Colorado
Department
of
Public
Health
&
Environment
(
CDPHE)
RCRA
Permit
and
onsite
procedural
requirements
before
the
waste
packages
are
sent
to
respective
storage
areas
to
ensure
compliance
with
all
applicable
requirements.

 
Prepares,
issues,
controls,
and
maintains
waste
packaging
procedures.

 
Specifies
labeling
and
marking
of
waste
packages
according
to
U.
S.
Department
of
Transportation
(
DOT)
and
treatment,
storage,
and
disposal
facility
(
TSDF)
requirements
in
accordance
with
the
appropriate
Labeling
and
Marking
Procedures
for
Radioactive
Waste
Material
Packages.

 
Reviews
requisitions
and
approves
for
WIPP­
related
commodities
to
ensure
project
requirements
are
included.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
39
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Waste
Operations
The
Waste
Operations
organization
performs
the
following:

 
Maintains
storage
area
for
off­
site
shipments.

 
Stores
RCRA
regulated
wastes
in
compliance
with
applicable
regulations.

 
Receives,
inspects,
logs,
serializes,
and
tracks
all
spare
parts
associated
with
the
TRUPACT­
II
package
(
PRO­
1418­
WO­
TRUOP,
TRUPACT­
II
Operations).

 
Prepares
waste
packages
and
TRUPACT­
II
packages
for
off­
site
shipment.

 
Labels
and
marks
packages
according
to
DOT
and
TSDF
requirements
(
refer
to
Labeling
and
Marking
Procedures
for
Radioactive
Waste
Material
Packages).

 
Performs
loading
operations
of
TRUPACT­
II
packages.

NDA
Operations
NDA
Operations
performs
the
following:

 
Operates
NDA
equipment
located
both
inside
and
just
outside
of
Buildings
440
and
664.

 
Participate
in
NDA
performance
demonstration
program
(
PDP).

Building
371
Nuclear
Operations
Building
371
Nuclear
Operations
performs
the
following:

 
Operates
NDA
equipment
located
in
Building
371.

 
Maintains
and
repairs
Building
371
cal/
gamma
counters.

Nondestructive
Testing
(
NDT)

NDT
performs
the
following:

 
Responsible
for
performing
helium
leak
test
on
the
TRUPACT­
II
Type
B
vessel.

 
Reviews
and
approves
the
TRUPACT­
II
leak
test
standard
operating
procedures
(
SOPs);

 
Maintain
and
qualify
TRUPACT­
II
leak
test
equipment
to
guidelines
of
ANSI,
N14.5­
1997,
Radioactive
Materials
 
Leakage
Tests
on
Packages
for
Shipment;

 
Responsible
for
performing
RTR
of
waste
packages.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
40
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

NDT
(
continued)

 
Responsible
for
the
oversight
of
mobile
RTR
vendors.

 
Manages
KH
operated
RTR
processes
of
waste
containers
involving
the
TWCP
as
follows:

 
Interfaces
with
the
TWCP
Site
PM
and
the
TWCP
Site
PQAO
on
TRU
Waste
Program
activities
affecting
cost,
schedule,
and
quality­
related
matters;

 
Reviews
and
approves
RTR
data
reports
and
forms;

 
Ensures
that
RTR
data
reports
and
forms
are
complete
and
receive
an
independent
technical
review;

 
Coordinates
and
schedules
NDT
work
to
support
the
TRU
Waste
Program;

 
Reviews
and
approves
the
NDT
SOPs
and
forms
and
reports;

 
Verifies
that
TWCP
QAPjP
requirements
are
met;

 
Reviews
and
concurs
with
the
TWCP
QAPjP;

 
Perform
QC
checks
of
NDT
equipment
to
applicable
requirements
and
at
specified
frequencies;

 
Periodically
reviews
audio/
videotape
of
accepted
waste
packages
by
personnel
other
than
the
operator
who
dispositioned
the
waste
package;

 
Ensures
that
the
RTR
audio/
videotapes
are
transmitted
to
the
PDCO
and
that
one
audio/
videotape
is
retained
in
the
NDT
files;

 
Assigns
NDT
personnel;

 
Ensures
that
RTR
operators
are
trained
and
certified
to
existing
industry
standards
and
comply
with
the
training
and
qualification
requirements
of
the
WIPP­
WAP
and
the
QAPD;

 
Ensures
the
preventive
and
routine
maintenance
is
conducted
in
accordance
with
the
requirements
of
this
document;
and
 
Ensures
that
nonconformances
are
reported
and
corrective
actions
have
been
completed.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
41
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Waste
Certification
&
Oversight
The
Waste
Certification
&
Oversight
(
WC&
O)
organization
performs
the
following
activities
through
the
Waste
Certification
Official
(
WCO):

 
Reports
to
the
Manager
of
WC&
O
who
reports
to
the
manager
of
Environmental
Compliance.

 
Maintains
independence
from
waste
generating
organizations.

 
Reviews
and
concurs
with
process
and
quality
controls.

 
Reviews
and
approves
NDA
Qualification
Reports.

 
Serves
as
a
point­
of­
contact
for
TRU
waste
NCRs.

 
Certifies
that
TRU
waste
is
properly
segregated
and
packaged,
including
designation
of
wastes
as
RCRA/
Toxic
Substances
Control
Act
(
TSCA)
hazardous
constituents
or
Land
Disposal
Restricted
materials,
as
applicable,
based
on
a
thorough
review
of
inspection,
test,
and
surveillance
information.

 
Certifies
that
TRU
waste
meets
all
applicable
WIPP­
WAC
based
requirements
on
the
waste
generator's
characterization,
RTR,
and
other
quality
controls.

 
Certifies
by
signature
that
the
TRU
waste
is
properly
classified,
packaged,
marked,
labeled,
and
loaded
in
the
TRUPACT­
II
package,
and
meets
WIPPWAC

 
Signs
the
TRU
waste
certification
checklist
attesting
that
the
TRU
waste
shipment
meets
WIPP­
WAC
requirements.

 
Assures
waste
certification
records
are
maintained
as
required
by
project
procedures.

 
Reviews
and
concurs
with
TRU
waste
management
procedures.

Document
Control
The
Document
Control
organization
conducts
information
resource
management
by
performing
the
following:

 
Ensures
controlled
distribution
of
specific
documents
related
to
the
TRU
Waste
Programs.

 
Maintains
document
history
files
as
specified
in
MAN­
001­
SDRM,
Site
Document
Requirements
Manual
(
SDRM).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
42
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Traffic
and
Transportation
The
Traffic
and
Transportation
organization
is
independent
from
waste
generation,
inspection,
test
and
certification
organizations.
The
Traffic
Management
group
supports
the
Traffic
and
Transportation
organization.
Traffic
and
Transportation
organization
is
responsible
for
the
following:

 
All
issues
concerning
on­
site
transfer
or
off­
site
shipments.

 
Compliance
to
DOT
requirements.

 
Appointing
the
Manager
of
Traffic
Management.

The
Manager
of
Traffic
Management
performs
or
designates
individuals
to
perform
the
following:

 
Reports
to
the
Manager
of
Traffic
and
Transportation.

 
Generates
and
maintains
site
procedures
providing
guidance
and
specifying
the
DOT
marking
and
labeling
requirements
for
waste
packages.

 
Prepares
shipping
papers
from
shipment
data
information.

 
Delivers
and
certifies
personnel
training
for
DOT
hazardous
materials
transportation,
as
required
in
49
CFR.

 
Notifies
the
TRU
waste
disposal
site
(
WIPP)
of
each
shipment
prior
to
departure.

 
Interfaces
with
WIPP,
oversight
groups,
the
WCO,
and
TRU
Waste
Programs
on
transportation
issues.

 
Maintains
a
records
system
pertaining
to
shipments.

 
Performs
pre­
loading
and
post­
loading
vehicle,
trailer,
and
load
inspections
per
Commercial
Vehicle
Safety
Alliance
(
CVSA)
requirements.

 
The
Manager
of
Traffic
Management
fulfills
the
Transportation
Certification
Official
(
TCO)
duties
by
appointing
the
Transportation
Certification
Official.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
43
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Traffic
and
Transportation
(
continued)

The
Transportation
Certification
Official
(
TCO)
performs
the
following:

 
Signs
the
Bill
of
Lading
and
the
Uniform
Hazardous
Waste
Manifest,
and
thereby
certifying
the
following:

 
Waste
package
contents
are
fully
and
accurately
described,
classified,
and
packaged;

 
Waste
packages
are
properly
marked
and
labeled;

 
Waste
shipments
are
,
in
all
respects,
in
proper
condition
for
transportation
according
to
the
applicable
regulations
of
the
Department
of
Transportation
and
meet
Title
40
and
Title
49
CFR
hazardous
waste
and
transportation
requirements;

 
A
waste
minimization
program
is
in
place;

 
Approval
of
payload
packages;

 
Compliance
with
packaging
and
records
requirements.

 
Verifies
the
Payload
Container
Transportation
Certification
Document
(
PCTCD),
Overpack
Payload
Container
Transportation
Certification
Document
(
OPCTCD),
and
the
Payload
Assembly
Transportation
Certification
Document
(
PATCD).
Each
item
on
these
documents
must
be
verified
per
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations,
and
this
procedure
is
consistent
with
the
TRAMPAC).

 
Ensures
compliance
to
all
requirements
before
releasing
the
truck
to
the
carrier.

Procurement
Engineering
&
Quality
Assurance
The
Procurement
Engineering
&
Quality
Assurance
organization
is
responsible
for
the
following:

 
Evaluates
suppliers.

 
Maintains
Site
Evaluated
Subcontractors
List.

 
Investigates
supplier
issues
leading
to
resolution.

 
Represents
the
Site
to
the
DOE
Contractor's
Supplier
Quality
Information
Group.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
44
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Procurement
Systems
Procurement
Systems
is
responsible
for
the
following:

 
Solicits
and
evaluates
offers
and
awards
purchase
orders.

 
Subcontracts
for
WIPP
packagings
and
supporting
items.

Procurement
Systems
performs
the
following:

 
Maintains
appropriate
stock
levels.

 
Pre­
assembles
the
Pipe
Overpack
Component
(
POC)
in
accordance
with
PRO­
284­
POC­
001,
Pipe
Overpack
Component
Initial
Assembly
Process.

 
Prepares
and
transfers
accepted
empty
waste
packaging,
including
hardware
and
associated
waste
packaging
items,
to
various
contractors
in
compliance
with
the
established
warehouse
transfer
operation
procedure,
PRO­
Q49­
PKG­
4040,
Warehouse
Waste
Packaging
Operations.

 
Conducts
essential
source
and
receipt
inspection
and
certification
processes
(
as
required)
on
new
waste
packagings,
drum
rings,
hardware,
and
associated
waste
packaging
materials,
to
verify
that
purchased
items
and
services
meet
all
applicable
requirements,
standards,
and
specifications
of
the
purchase
agreement,
prior
to
the
final
certification
and
release
to
the
RFETS
warehouse
storage
facility.

 
Records
and
controls
nonconforming
items
identified
by
certification
and
inspection
(
C&
I)
inspection
using
Receiving
Inspection
Deficiency
Reports,
implementing
the
nonconformance
process
described
in
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items.
This
prevents
inadvertent
or
unauthorized
use
while
a
technical
evaluation
of
the
item's
condition
is
being
conducted.

 
Maintains
inspection
records
to
substantiate
item
compliance
with
established
requirements,
standards
and
specifications
relevant
to
the
Purchase
Order
agreement.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
45
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Remediation,
Industrial
D&
D,
and
Site
Services
(
RISS)

The
RISS
organization
is
supported
by
the
Metrology,
Laboratory,
and
Analytical
Services
groups
The
Metrology
group
manages
the
subcontracted
calibration
of
measuring
and
test
equipment
used
in
the
packaging
and
processing
of
waste.

The
Laboratory
group
is
responsible
for
the
following:

 
Provides
analytical
chemistry
services
in
support
of
waste
characterization.

 
Performs
the
material
testing.

 
Performs
the
destructive
analysis
of
wastes
and
radioactive
materials.

 
Appointing
the
Analytical
Laboratories
Manager.

Analytical
Laboratories
Manager
performs,
or
delegates
to
subordinate
managers,
the
following
responsibilities:

 
Interfaces
with
the
TWCP
Site
PM
and
the
TWCP
Site
PQAO
on
TRU
Waste
Program
activities
affecting
cost,
schedule,
and
quality­
related
matters.

 
Ensures
that
analytical
personnel
are
trained
and
qualified.

 
Ensures
participation
in
the
PDPs
for
analytical
testing.

 
When
performing
the
functional
role
of
Technical
Supervisor,
reviews,
approves,
and
releases
the
Analytical
Batch
Data
Report.
Other
qualified
personnel
[
i.
e.,
qualified
as
specified
in
PLN­
97­
007,
TWCP
Training
Implementation
Plan
(
TWCP
TIP)]
may
perform
the
role
of
Technical
Supervisor.

 
Coordinates
and
schedules
analytical
work
to
support
the
TRU
Waste
Program.

 
Ensures
that
corrective
and
preventive
actions
have
been
completed.

 
Reviews
and
approves
all
Analytical
Laboratory
SOPs
and
reports.

 
Assigns
laboratory
staff.

 
Manages
the
implementation
of
the
Analytical
Laboratories'
roles
and
responsibilities.

 
Verifies
compliance
to
analytical
requirements
of
the
WIPP­
WAP
and
QAPjP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
46
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

RISS
(
continued)

The
Analytical
Services
group
is
responsible
for
the
following:

 
Performs
evaluations
of
requisitions
for
subcontracted
analytical
services.

 
Generates
Chain­
of­
Custody
and
unique
identification
and
control
numbers
for
sampling
activities.

 
Appointing
the
Analytical
Laboratories
Project
Quality
Assurance
Officer
(
LPQAO).

The
LPQAOs
perform
the
following:

 
Directs
all
of
the
Analytical
Laboratories'
WIPP­
related
QA
activities.

 
Interfaces
directly
with
the
TWCP
Site
PQAO
on
analytical
laboratory
specific
QA
matters
related
to
this
project.

 
Ensures
that
all
project
laboratory
personnel
have
a
clear
understanding
of
the
special
QC
requirements
for
the
Project.

 
Develops,
reviews,
and
revises
laboratory­
related
portions
of
the
TWCP
QAPjP.

 
Provides
quality
surveillance
of
analytical
laboratory
TRU
Waste
Program­
related
activities.

 
Verifies
the
implementation
of
project
QA
requirements.

 
Identifies
and
reports
laboratory
quality
deficiencies
to
the
appropriate
Project
personnel
and
the
TWCP
Site
PQAO.

 
Initiates,
recommends,
and
tracks
corrective
actions
to
closure.

 
Reviews
and
verifies
that
all
Analytical
Laboratory
SOPs
comply
with
QAPjP
and
WIPP­
WAP
requirements.

 
Reviews
and
approves
Batch
Data
Reports
prior
to
release
to
the
Waste
Records
Center
and
ensures
that
Batch
Data
Reports
are
transmitted
in
a
timely
manner.

 
Ensures
that
all
analytical
laboratory
requirements
of
the
WIPP­
WAP
and
QAPjP
have
been
met.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
47
3.1.1.1.4
Communication
and
Organizational
Interface
Responsibilities
(
continued)

Materials
Control
&
Accountability
(
MC&
A)

The
MC&
A
organization
performs
the
following:

 
Responsible
for
control
and
accountability
of
nuclear
material.
Controls
are
described
in
the
Safeguards
Accountability
Manual.

 
Maintains
program
for
the
application
of
tamper
indicating
devices
(
TIDs).

 
Generates
the
DOE/
Nuclear
Regulatory
Commission
(
NRC)
741
form
based
on
the
load
list
for
waste
shipments
to
WIPP.

 
Updates
the
RFETS
accountability
system
with
measurement
results.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
48
3.1.1.2
Implementation
of
the
QA
Program
The
documentation,
controls,
and
training
described
in
this
document
implement
the
TRU
Waste
Program
QA
program.
Section
3
of
this
document
provides
an
overall
description
of
project
activities
and
the
QA
Program.

3.1.1.2.1
Quality
Assurance
Program
Documents
The
TWMM
and
the
TWCP
QAPjP
document
the
plans
and
procedures
that
effectively
implement
the
requirements
of
the
QAPD,
the
WIPP­
WAP,
the
WIPPWAC
and
the
TRUPACT­
II
Authorized
Methods
for
Payload
Control
(
TRAMPAC).

3.1.1.2.2
Applicability
of
QAPD
Requirements
QAPD
requirements
apply
to
TRU
Waste
Program
items
or
activities
relative
to
compliance
application,
waste
characterization,
repository
performance
assessment,
waste
isolation,
waste
transportation,
nuclear
safety,
and
environmental
protection.

3.1.1.2.3
Grading
Items
and
Activities
&
Applying
Management
Controls
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading,
provides
instructions
for
implementing
the
graded
approach
utilized
in
implementing
the
QA
program.

3.1.1.2.4
Planning
Work
95­
QAPjP­
0050,
RFETS
QAPjP,
PRO­
486­
WIPP­
006
and
the
applicable
sections
of
this
document
are
used
in
the
planning
of
waste
management
activities
at
RFETS.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
49
3.1.2
Personnel
Training
&
Qualification
Training
development,
approval
and
delivery
complies
with
applicable
DOE
orders
and
the
WIPP­
WAP.
Personnel
associated
with
the
generation,
handling,
packaging,
inspection,
testing,
processing,
certification,
and
shipment
of
waste
shall
be
trained
and
qualified
to
applicable
criteria,
in
accordance
with
the
Site
TPM.

3.1.2.1
Qualification
Requirements
The
Site
TPM
and
TIP
document
the
applicable
qualification
criteria
for
TRU
Waste
Program
personnel.

3.1.2.2
Training
Requirements
The
TWCP
TIP
documents
the
training
requirements
for
personnel
supporting
the
TRU
Waste
Program.
RFETS
management
having
employees
performing
tasks
directly
in
support
of
the
TRU
Waste
Program
(
performing
to
procedures
on
activities
described
in
this
document
and
the
TWCP
QAPjP)
are
responsible
for
ensuring
their
employees
meet
the
training
requirements
in
the
TWCP
TIP.

The
Training,
Scheduling,
and
Records
database
provides
the
official
status
of
training.
Training
records
are
maintained
and
transferred
to
the
Waste
Records
Center
according
to
instructions
in
the
Site
TPM
and
TIP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
50
3.1.3
Quality
Improvement
The
RFETS
Management
organizations
are
responsible
for
ensuring
compliance
to
quality
improvement
requirements
by
creating
a
culture
of
continuous
improvement
of
items,
services,
activities
and
processes.
Quality
Improvement
is
achieved
through
the
management
assessment,
surveillance,
independent
assessment,
nonconformance,
and
corrective
action
processes.

3.1.3.1
Quality
Affecting
Problems
Quality­
affecting
problems
and
items,
activities,
and
processes
that
do
not
meet
established
requirements
are
identified,
documented,
reported,
controlled,
and
corrected.
Quality
problems
may
be
identified
by
RFETS
Management
organizations
or
by
an
external
source.

3.1.3.1.1
Problem
Identification
RFETS
personnel
are
responsible
for
promptly
reporting
to
management
any
problem
condition
identified
as
adverse
to
quality.
Management
at
all
levels
fosters
a
"
no­
fault"
attitude
to
encourage
the
identification
of
quality­
affecting
problems.
Conditions
adverse
to
waste
acceptability
are
identified
promptly
through
inspections,
tests,
surveillances,
and
audits
and
corrected
as
soon
as
practical.
Corrective
actions
for
quality­
affecting
problems
are
implemented
and
characterized,
as
described
in
3­
X31­
CAP­
001,
Corrective
Action
Process,
according
to
their
significance
based
on
the
greatest
potential
for:

 
Posing
adverse
risks
to
the
environment
and
human
health;

 
Adversely
impacting
the
quality
and
reliability
of
waste
operations;
and
 
Affecting
the
ability
to
meet
quality
requirements.

3.1.3.1.2
Problem
Types
Quality­
affecting
problems
may
involve:

 
Noncompliance
with
a
QA
program
requirement.
A
noncompliance
is
classified
as
a
Condition
Adverse
to
Quality
(
CAQ)
or
Significant
Condition
Adverse
to
Quality
(
SCAQ).

 
Nonconforming
items,
including
suspect/
counterfeit
items
or
data,
which
do
not
conform
to
specified
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
51
3.1.3.2
Nonconformances
RFETS
organizations
ensure
compliance
to
specific
quality
requirements
by
identifying,
classifying
and
controlling
conditions
adverse
to
quality,
and
by
ensuring
adequate
control
and
disposition
of
nonconforming
items.

3.1.3.2.1
Documenting
and
Evaluating
Nonconforming
Items
The
documentation
and
evaluation
of
nonconforming
items
and
data
are
conducted
according
to
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items.
Characteristics
that
do
not
conform
to
specified
criteria
are
documented
with
nonconformance
reports
(
NCRs)
which
are
reviewed
and
evaluated
by
competent
personnel
for
corrective
actions.
Waste
package
nonconformances
are
specifically
addressed
in
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances,
and
documented
with
waste
nonconformance
reports
(
WNCRs).

3.1.3.2.2
Identifying
Nonconforming
Items
or
Data
Nonconforming
items,
data,
or
nonconforming
waste
packages
are
identified
by
marking,
tagging,
or
segregating
as
described
in
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items;
and
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances.

3.1.3.2.3
Reporting
Nonconformances
The
TWCP
Site
PQAO
provides
written
notification
to
the
CBFO
QA
Manager
and
National
TRU
Programs
Assistant
Manager
of
all
non­
administrative
nonconformances
related
to
applicable
WIPP­
WAP
requirements
(
i.
e.,
a
failure
to
meet
a
DQO)
first
identified
during
the
TWCP
Site
PM
review
level
within
five
(
5)
days
of
identification
and
validation.
The
TWCP
Site
PQAO
then
provides
a
nonconformance
report
to
CBFO
within
thirty
(
30)
days
of
identification.
This
process
is
described
in
PRO­
940­
WIPP­
010,
WIPP
TRU
Waste
Characterization
Project
Level
Data
Review
and
Reporting.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
52
3.1.3.2.4
Segregating
Nonconforming
Items
When
a
nonconformance
is
identified,
controls
are
established
to
prevent
further
processing,
delivery,
installation,
or
use
of
nonconforming
items
pending
the
evaluation
and
approval
of
the
disposition.
Nonconforming
items,
data,
or
nonconforming
waste
packages
are
identified
and
segregated
according
to
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items
and
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances.
Nonconforming
waste
packages
are
tracked
in
the
WEMS
system
with
controls
to
prevent
the
nonconforming
waste
package
from
being
shipped
off­
site.

3.1.3.2.5
Disposition
of
Nonconforming
Items
or
Data
Procedure
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances,
addresses
review
and
disposition
of
nonconforming
waste
packages.
Packages
not
meeting
certification
requirements
may
be
returned
to
the
waste
generating
organization
for
corrective
action.
Return
of
the
rejected
waste
package
to
its
originating
organization
is
dependent
upon
area
storage
capacity,
90
day
storage
limitations,
and
radiation
and
chemical
protective
equipment
requirements.
WNCR
dispositions
are
documented
by
describing
the
corrective
actions
to
be
taken
in
the
space
provided
on
the
WNCR.
Independent
verification
of
corrective
actions
is
performed
by
the
WC&
O
prior
to
closure.

Nonconforming
items
or
data
are
controlled
according
to
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items.
These
NCRs
are
tracked
in
the
Plant
Action
Tracking
System
in
accordance
with
3­
X31­
CAP­
001,
Corrective
Action
Process.

NCRs
pertaining
to
TRUPACT­
II
packages
are
submitted
to
the
WIPP
management
and
operation
(
M&
O)
contractor
per
the
requirements
of
DOE/
WIPP­
02­
3183,
CH
Packaging
Program
Guidance,
for
formal
disposition.

3.1.3.2.6
Quality
Trending
of
Nonconformances
TRU
waste
related
nonconformance
documentation
is
periodically
analyzed
by
the
TWCP
Site
PQAO
to
identify
quality
trends
in
accordance
with
Section
3.1.3.3.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
53
3.1.3.3
Corrective
Action
3.1.3.3.1
Identifying
Conditions
Adverse
to
Quality
(
CAQ)

A
CAQ
occurs
when
a
QA
requirement
has
not
been
met.

3.1.3.3.2
Classification
of
Conditions
Adverse
to
Quality
The
TWCP
Site
PQAO
reviews
all
documented
noncompliances
to
determine
if
the
noncompliance
identified
impacts
the
TRU
Waste
Program
according
to
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems.
Classification
of
CAQs
is
based
on
the
effect
the
CAQ
has
on
compliance
to
regulatory
requirements
for
operability,
TRU
waste
characterization,
TRU
waste
certification,
TRU
waste
containment
and
the
effective
implementation
of
the
QAPD.
Any
CAQ
that
is
determined
to
be
noncompliant
with
a
WIPP­
WAP
requirement
is
treated
as
an
SCAQ.

3.1.3.3.3
Conditions
Adverse
to
Quality
The
TWCP
Site
PQAO
reviews
all
documented
quality­
affecting
problems
to
determine
if
the
problem
identified
impacts
the
TRU
Waste
Program
and
meets
the
criteria
of
CAQ
according
to
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems.
Corrective
actions
for
identified
CAQs
are
implemented
as
determined
by
the
cognizant
Responsible
Manager
according
to
3­
X31­
CAP­
001,
Corrective
Action
Process,
and
completed
as
soon
as
practical.

3.1.3.3.4
Significant
Conditions
Adverse
to
Quality
The
TWCP
Site
PQAO
reviews
all
documented
quality­
affecting
problems
to
determine
if
the
problem
identified
impacts
the
TRU
Waste
Program
and
meets
the
criteria
of
SCAQ
according
to
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems.
Corrective
actions
for
identified
SCAQs
are
implemented
as
determined
by
the
cognizant
Responsible
Manager
according
to
3­
X31­
CAP­
001,
Corrective
Action
Process.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
54
3.1.3.3.5
Corrective
Action
Planning
Procedure
3­
X31­
CAP­
001,
Corrective
Action
Process
initiates,
documents,
and
tracks
corrective
actions.
SCAQs
and
associated
CAPs
are
reviewed
by
the
TWCP
Site
PQAO
according
to
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems.

Cause
analysis
is
performed
when
SCAQs
are
identified
(
refer
to
MAN­
062­
CAUSEANALYSIS,
Cause
Analysis
Requirements
Manual).
SCAQs
may
result
in
issuance
of
a
stop
work
order
by
the
Cognizant
Responsible
Manager
in
conjunction
with
the
TWCP
Site
PQAO,
and
the
TRU
Program.

3.1.3.3.6
Work
Suspension
Stop
work
orders
are
issued
according
to
procedure
1­
V10­
ADM­
15.02,
Stop
Work
Action.
SCAQs
resulting
in
Stop
Work
Actions
must
be
corrected
prior
to
resuming
waste
processing.
Completion
of
corrective
actions
is
verified
by
the
cognizant
Project
quality
organization
or
Site
Quality
Program
prior
to
releasing
the
work
suspension.

3.1.3.3.7
Corrective
Action
Follow­
Up
As
described
in
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems,
the
TWCP
Site
PQAO
verifies
corrective
actions
for
SCAQs
are
completed
according
to
3­
X31­
CAP­
001,
Corrective
Action
Process.

3.1.3.3.8
Recurring
Conditions
Adverse
to
Quality
Recurring
conditions
are
evaluated
according
to
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems.

3.1.3.3.9
Quality
Trending
The
TWCP
Site
PQAO
trends
TRU
Waste
Program
related
quality­
affecting
problems
according
to
PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems,
and
identifies
opportunities
for
improvement.

Periodically
TRU
Waste
Program
may
review
the
radioactive
waste
management
activities.
This
activity
could
result
in
the
identification
of
programmatic
issues
and
quality­
affecting
problems,
or
significant
adverse
trends,
which
could
affect
the
certifiability
of
waste.
Follow­
up
actions
will
include
applicable
activities
defined
in
3­
X31­
CAP­
001,
Corrective
Action
Process.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
55
3.1.4
Document
Control
MAN­
001­
SDRM,
Site
Document
Requirements
Manual,
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
and
PRO­
1329­
DM­
03,
Site
Document
Control
define
the
RFETS
Document
Control
Program.
Procedures
and
documents
supporting
the
TRU
Waste
Program
are
maintained
in
document
control
systems
that
comply
with
the
requirements
of
the
QAPD.

The
RFETS
Document
Control
organization
ensures
compliance
to
specific
document
control
requirements
by
controlling
the
preparation,
modification,
review,
approval,
issuance,
distribution
and
use
of
TRU
Waste
Program­
related
documents.

3.1.4.1
Document
Preparation,
Review,
Approval,
and
Issuance
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
and
PRO­
1329­
DM­
03,
Site
Document
Control
define
the
process
by
which
TRU
Waste
Program­
related
documents
are
prepared,
reviewed,
approved
and
issued.

3.1.4.2
Document
Distribution
and
Use
PRO­
1329­
DM­
03,
Site
Document
Control
defines
the
process
used
to
distribute
TRU
Waste
Program­
related
documents.

3.1.4.3
Document
Changes
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
defines
the
change
process
of
TRU
Waste
Program­
related
documents.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
56
3.1.5
Records
QA
records
are
maintained
in
order
to
furnish
documented
evidence
that
wastes
are
generated,
packaged,
inspected,
assayed,
analyzed,
tested,
and
shipped
according
to
the
applicable
requirements.

The
RFETS
Waste
Records
Center
ensures
compliance
to
specific
record
maintenance
requirements
through
the
effective
implementation
of
the
RFETS
Records
System.
The
record
control
system
ensures
the
generation,
indexing,
classification,
retrieval,
storage
and
correction
of
TRU
Waste
Program­
related
QA
records.

3.1.5.1
Records
System
1­
V41­
RM­
001,
Records
Management
Manual,
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing,
and
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center
are
used
to
define
the
RFETS
Records
System.
The
Record
System
ensures
compliance
with
the
QAPD
for
TRU
Waste
Program­
related
records.

The
RFETS
procedure
for
the
control
of
records,
1­
V41­
RM­
001,
Records
Management
Manual,
refers
generators
of
TRU
Waste
Program
records
to
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center.
This
procedure
provides
instructions
for
maintenance
of
TRU
Waste
Program
records
in
compliance
with
the
QAPD.

3.1.5.2
Generating
QA
Records
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing
and
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center
define
the
process
used
to
control
TRU
Waste
Program­
related
QA
records.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
57
3.1.5.3
Indexing
QA
Records
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing
defines
the
process
used
to
index
TRU
Waste
Program­
related
QA
records.

3.1.5.4
Classifying
QA
Records
Records
pertaining
to
the
TRU
Waste
Program
are
defined
by
type
and
are
only
considered
valid
records
if
they
are
signed
and
dated
by
authorized
personnel
from
the
applicable
organizations.
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing
defines
the
process
used
to
classify
TRU
Waste
Program­
related
QA
records.

3.1.5.5
Receiving
QA
Records
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center
provides
instructions
for
receipt
of
QA
records
by
the
Waste
Records
Center.

3.1.5.6
Storage,
Preservation,
Safekeeping
and
Disposition
of
QA
Records
Procedure
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing,
provides
instructions
for
the
handling
of
records
in
the
Waste
Records
Center.
A
Records
Inventory
Disposition
Schedule
(
RIDS)
is
developed
and
maintained.
PRO­
767­
WIPP­
001,
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center,
and
RFETS­
SOP­
BACKUP­
001,
Server
Backup
Standard
Operating
Procedure
provide
instructions
for
the
preservation,
storage
and
safekeeping
of
TRU
Waste
Program­
related
QA
records.

3.1.5.7
Correcting
Information
in
QA
Records
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center
provides
instructions
for
correction
of
QA
records.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
58
3.2
Performance
Requirements
3.2.1
Work
Processes
Work
on
the
TRU
Waste
Program
is
performed
according
to
established
technical
standards
and
administrative
controls
(
procedures)
identified
in
this
document
and
the
TWCP
QAPjP.
Each
person
supporting
the
project
is
responsible
for
the
quality
of
his
or
her
work
and
has
the
goal
of
doing
work
correctly
the
first
time.
Management
of
the
project
has
established
processes
and
procedures
to
ensure
that
work
is
planned
and
performed
under
controlled
conditions
by
trained
personnel;
items
are
maintained
to
prevent
their
damage,
loss,
or
deterioration;
and
equipment
used
for
process
monitoring
or
data
collection
are
calibrated
and
maintained.

This
section
further
establishes
management
involvement
in
the
work
processes
through
their
interactions
with
personnel
performing
the
work
and
through
their
review
and
assessment
of
ongoing
and
completed
work.
This
will
help
ensure
that
the
definition
of
"
acceptable
work
performance"
is
clearly
communicated
and
that
personnel
are
provided
the
necessary
training,
resources,
and
administrative
controls
to
properly
accomplish
their
tasks.
These
processes
and
procedures
are
identified
in
this
document
and
the
TWCP
QAPjP.

3.2.1.1
Work
TRU
Waste
Program
work
processes
are
performed
through
procedures
implemented
to
meet
the
requirements
of
the
QAPD.
Qualified
processes
and
equipment,
approved
procedures,
qualified
personnel,
and
documentation
of
operating
conditions
control
waste
treatment
and
packaging
operations.
This
assures
that
waste
processing
activities
are
conducted
in
a
consistent,
repeatable,
and
acceptable
manner.
Waste
treatment
process
control
is
the
responsibility
of
operations
management
with
technical
support
provided
by
the
Waste
Requirements
Group.

Specific
control
criteria
for
treated
wastes,
untreated
wastes,
and
associated
waste
processes
are
addressed
in
this
section.
PCPs
are
developed
when
required
in
accordance
with
1­
M60­
WPC­
001,
Waste
Process
Control.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
59
3.2.1.1
Work
(
continued)

Solid
Radioactive
Waste
Packaging
­
Untreated
Wastes
Process
controls
for
untreated
solid
radioactive
waste
packaging
are:

 
Physical
control
of
all
TRU
waste
packages
using
locking
fixtures
or
limited
access
cages
(
including
packages
used
for
room
trash
collection
in
Radiation
Control
Areas);

 
Controlled
access
to
TRU
waste
packages,
opening
packages
only
during
filling,
inspection,
or
repacking
operations;

 
Approved,
revision­
controlled
solid
waste
packaging
procedures,
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
and
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions;
the
W/
RT,
the
Drum
Label
or
Box
Label;
and
the
NDA
count
sheets;

 
Approved,
revision­
controlled
WSRIC
Building
Books
issued
to
Building
Operations
management;

 
Required
waste
generator
Training
and
OJT
for
all
waste
packaging
personnel.

 
These
controls
assure
that
wastes
are
properly
identified,
and
comply
with
WIPP­
WAC
and
the
WIPP­
WAP.

Waste
Treatment
or
Packaging
Processes
­
Process
Control
Plans
(
PCPs)

Controls
that
assure
waste
treatment
and
packaging
operations
produce
consistent,
acceptable
wastes
are
specified
in
individual
PCPs.
The
PCP
requirements
supplement
general
quality
assurance
program
requirements
stated
in
this
document.
The
PCPs
are
developed
by
operations
management
per
1­
M60­
WPC­
001,
Waste
Process
Control.

Process
and
Equipment
Qualification
Waste
treatment
and
characterization
operations,
processes
and
equipment
are
tested
and
qualified
before
being
put
into
routine
production.
The
governing
document
for
initial
equipment
installation
acceptance
is
1­
PRO­
072­
001,
Inspection
and
Acceptance
Test
Program.
Appendix
1,
Application
of
Inspection
and
Acceptance
Testing,
of
1­
PRO­
072­
001,
Inspection
and
Acceptance
Test
Program,
provides
the
template
for
identifying
specific
applications
(
e.
g.,
Component
Checkout
(
CC)
Testing
or
Systems
Operability
(
SO)
Testing).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
60
3.2.1.1
Work
(
continued)

Process
and
Equipment
Qualification
(
continued)

Any
process
determined
to
be
a
critical
treatment
process,
a
final
treatment
process,
or
a
special
process,
and
which
produces
a
waste
form
that
must
meet
a
requirement,
or
whose
specified
quality
and
conformance
of
waste
cannot
be
determined
readily
by
inspection
or
test
before
shipment,
requires
a
PCP.

The
responsible
manager
of
the
process
being
evaluated
must
determine
the
need
for
a
PCP
or
PQP
in
accordance
with
1­
M60­
WPC­
001,
Waste
Process
Control.
If
necessary,
the
responsible
manager
will
then
coordinate
the
development
of
the
PQP,
performance
of
the
process
qualification,
and
development
of
the
PCP.
The
end
result
is
a
documented,
quantified
process
capability
report.
The
report
specifies
the
required
operating
parameters,
recommends
measuring
equipment
calibration
accuracy
and
precision,
and
when
appropriate
recommends
control
chart
monitoring
for
critical
process
parameters.

Radioactive
Waste
Measurement
­
NDA
The
NDA
process
is
controlled
through:
operator
training,
approved
procedures,
calibrated
instruments,
periodic
measurement
of
measurement
control
samples
and
evaluation
of
data,
daily
instrument
checks,
and
qualification
of
NDA
systems
to
meet
specific
data
quality
objectives.

When
subcontractor
NDA
equipment
services
are
used
on
the
TRU
Waste
Program
the
subcontractor
is
required
through
the
procurement
process
to
document
how
their
processes
meet
applicable
CBFO
requirements
and
WIPP­
WAC
requirements.

See
Appendix
4
of
this
manual
for
additional
details
on
NDA
systems.

3.2.1.2
Implementing
Procedures
RFETS
implementing
procedures
are
developed
and
maintained
according
to
MAN­
001­
SDRM,
Site
Document
Requirements
Manual;
PRO­
1329­
DM­
03,
Site
Document
Control;
and
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
61
3.2.1.2
Implementing
Procedures
(
continued)

Instructions,
Procedures,
and
Drawings
TRU
wastes
are
collected,
treated,
processed,
packaged,
inspected,
certified,
and
loaded
for
shipment
according
to
written
approved
instructions,
procedures,
and
drawings.
The
Site
Document
Control
Program
is
designed
such
that
Site
documents
to
prescribe
processes,
specify
requirements,
or
establish
design
are
prepared,
reviewed,
approved,
issued,
and
controlled
for
use
by
personnel
managing
or
performing
work..

Supporting
Processes
Departmental
procedures
provide
detailed
instructions
for
all
routine
processes
associated
with
waste
generation,
inspection,
test,
certification,
and
shipping
activities.
Operations
management
is
responsible
to
develop
procedures
that
adequately
describe
and
control
their
operations.

In
addition
to
operations
management
having
procedures
for
their
processes,
each
building
has
its
own
WSRIC
Building
Book.
A
WSRIC
Building
Book
has
all
the
routine
processes
for
a
building
listed
in
it,
along
with
the
waste
streams
associated
with
that
process.
Information
about
the
waste
stream
also
includes
whether
or
not
the
waste
produced
is
Low
Level
or
TRU.

RFETS
work
controls
are
provided
in
MAN­
071­
IWCP,
Integrated
Work
Control
Program
Manual,
and
MAN­
066­
COOP,
Site
Conduct
of
Operations
Manual.
No
WIPP
waste
characterization
requirements
are
met
through
controls
in
MAN­
071­
IWCP,
Integrated
Work
Control
Program
Manual,
or
through
MAN­
066­
COOP,
Site
Conduct
of
Operations
Manual.

3.2.1.3
Item
Identification
and
Control
Identification
and/
or
traceability
of
waste
streams,
waste
packages,
involved
packaging,
testing,
analytical
results,
and
other
items
associated
with
TRU
waste
management
are
required.
Items
such
as
waste
streams
and
waste
packages
are
uniquely
identified
from
the
initial
generation
or
receipt
up
to
and
including
use,
packaging,
storage,
and
transportation
to
the
WIPP.
Specific
waste
characteristics,
waste
generation
sources,
applicable
chemical
analyses,
and
any
inspections,
tests,
and
certifications
for
wastes
are
traceable
back
to
the
wastes
and
packages
by
documentation
records
maintained
in
accordance
with
the
records
retention
requirements
of
the
QAPD.
The
TWCP
QAPjP
identifies
quality
assurance
controls
for
waste
characterization
performed
at
RFETS
in
accordance
with
the
WIPP­
WAP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
62
3.2.1.3
Item
Identification
and
Control
(
continued)

The
key
document
that
records
traceability
information
is
the
W/
RT
(
refer
to
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions).
As
described
in
Section
4.3.1,
either
an
electronic
W/
RT
or
a
manual
W/
RT
may
be
used
for
packaging
activities.
The
W/
RT
data
collection
form
is
generated
for
each
waste
package
and
documents
the
employee
numbers
of
the
waste
generators,
Waste
Inspectors,
and
test
technicians
directly
involved
with
processing
that
waste
package.
The
form
also
documents
inspection
and
test
results,
waste
generation
source
(
process
number),
hazardous
constituent
number
(
if
applicable),
and
package
serial
number.
Waste
Management
personnel
control
the
development
of
waste
identification
and
characterization
information
through
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging.
MAN­
955­
099,
Waste
Requirements
Group
Operations
Manual,
provides
instructions
for
control
of
the
WGI.

Packaging
and
Waste
Segregation
Overview
The
following
provides
an
overview
listing
of
the
quality
controls
implemented
to
assure
TRU
waste
meets
requirements.

 
Controlled
procedures
for
waste
packaging,
segregation,
inspection,
assay,
transportation,
processing,
testing,
and
certification.

 
Training
and
qualification
of
waste
generators
and
waste
handlers
involved
in
repackaging,
sampling
and
visual
examination
processes,
Waste
Inspectors,
NDA
Operators,
Nondestructive
Test
(
NDT)
technicians,
and
other
TRU
Waste
Program
personnel.

 
Completed,
documented,
and
characterized
RFETS
waste
streams
published
in
the
WSRIC
Building
Books.

 
For
routinely
generated
wastes,
documented
traceability
of
each
item
placed
in
a
waste
package
to
the
generation
point
represented
by
the
unique
WSRIC
process
number.

 
Accountability
of
individual
waste
package
segregation,
characterization,
and
traceability
documentation
to
the
person(
s)
responsible.

 
Waste
reassessments
for
wastes
not
identified
by
a
WSRIC
process
number.

 
TRU
waste
package
access
control
during
all
phases
of
waste
generation,
packaging,
and
handling
using
locked
packages
and
qualified
package
custodians.

 
100%
verification
of
package
content
compliance
achieved
by
utilizing
the
waste
generator
and
a
waste
verifier
during
fill
operations.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
63
3.2.1.3
Item
Identification
and
Control
(
continued)

Packaging
and
Waste
Segregation
Overview
(
continued)

 
Independent
in­
process
sample
inspection
of
waste
packages
and
contents.

 
Independent
100%
waste
package
integrity
and
W/
RT
completeness
inspections.

 
RTR
of
waste
package
contents
(
when
required
by
the
WIPP­
WAP).

 
Routine,
systematic
surveillance
of
TRU
Waste
Program
activities.

 
Independent
audit
of
TRU
Waste
Program
activities
to
Quality
Assurance
Program
requirements.

 
Sampling
and
analysis
(
as
applicable)
of
TRU
waste
to
demonstrate
compliance
to
the
WIPP­
WAP
and
the
WIPP­
WAC.

The
Uniform
Hazardous
Waste
Manifest
records
the
EPA
Hazardous
Waste
Numbers
(
EPA
HWNs)
and
other
required
information
for
RCRA
regulated
hazardous
wastes.
More
specific
definitions
of
traceable
control
numbers
are
defined
below.

Content
Code
The
content
code
is
a
unique,
alpha­
numeric
code
which
identifies
the
generator
site,
the
generator's
waste
stream,
and
the
TRUPACT­
II
package
contents,
to
personnel
at
the
WIPP.
The
content
codes
are
established
and
controlled
by
DOE
WIPP.
A
list
of
all
shipping
content
codes
can
be
found
in
the
TRUCON
document,
DOE/
WIPP
89­
004.

Item
Description
Code
(
IDC)
Number
The
IDC
number
is
a
three
or
four
digit
number
assigned
to
a
waste
form
type,
such
as
plastics,
dry
combustibles,
light
metals,
etc.
These
numbers
provide
accountability,
allow
for
segregation
of
wastes
into
identifiable
forms
for
ease
of
processing,
and
when
assessing
nuclear
material
content
during
NDA.
The
IDCs
from
each
of
the
ten
DOE
sites
are
translated
into
content
codes
so
that
waste
streams
can
be
uniformly
identified.
Approved
waste
IDCs
are
documented
in
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual.
If
a
new
TRU/
TRM­
related
IDC
is
created,
approval
from
the
Site
Nuclear
Material
Control
group
is
required.
A
list
of
RFETS
IDCs
that
have
been
assigned
a
content
code
and
that
meet
the
WIPP­
WAC
is
contained
in
Section
6
of
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
64
3.2.1.3
Item
Identification
and
Control
(
continued)

Process
Number
The
process
number
designates
the
unique
RFETS
location
that
generated
the
wastes.
Each
building
has
a
complete
listing
of
the
waste
generating
processes
published
in
the
applicable
WSRIC
Building
Book.

Chemical
Constituent
Code
The
Chemical
Constituent
Code
(
CCC)
is
a
two­
character
alpha
or
numeric
designator
used
to
identify
chemical
constituents
associated
with
a
particular
waste
stream.
The
numbers
are
defined
by
Waste
Systems
for
use
by
waste
generators
in
identifying
and
segregating
wastes.
RCRA
CCCs
identify
constituents
in
the
waste
stream
which
are
RCRA
regulated.
Non­
RCRA
CCCs
identify
constituents
in
the
waste
stream
which
are
not
RCRA
regulated.

EPA
Hazardous
Waste
Number
NOTE:
WRG
prepares
WGIs
to
communicate
waste
characterization
(
including
HWNs)
and
packaging
requirements
to
waste
generators
at
the
floor
level.
Acceptable
Knowledge
(
AK)
is
re­
evaluated
at
the
Project
Level
based
on
confirmatory
testing
(
e.
g.,
RTR,
headspace
gas
sampling,
and/
or
solid
sampling)
as
described
in
the
TWCP
QAPjP,
Section
B4.
Prior
to
shipment,
waste
package
information
is
reviewed
and
certified
by
the
WCO.

The
EPA
HWN
is
required
by
Title
40
CFR,
Part
261,
Subparts
C
and
D.
This
number
indicates
the
characteristic
wastes,
the
nonspecific
source
wastes,
the
specific
source
wastes,
and
the
commercial
chemical
products
that
are
regulated
as
hazardous
waste
under
this
statute.
This
number
is
recorded
on
each
package
on
the
Hazardous
Waste
Label.
The
waste
generator
is
responsible
for
assigning
the
EPA
HWN
to
all
waste
packages.

Waste
Package
Numbers
Waste
packages
are
assigned
a
unique
number
with
bar
code
as
they
are
issued
to
waste
generator
organizations.
Three
identical
bar
code
labels
are
attached
to
the
drum
under
the
drum
ring
approximately
120
degrees
apart.
Bar
codes
are
applied
to
the
flat
sides
of
the
SWBs.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
65
3.2.1.3
Item
Identification
and
Control
(
continued)

Tamper
Indicating
Device
(
TID)
Number
The
TIDs
are
strips
of
mylar
tape
imprinted
with
a
unique
bar
code
number.
The
TIDs
are
attached
to
all
sealed
drums
and
SWBs
containing
Special
Nuclear
Material
(
Pu
isotopes).
The
tape
cannot
be
removed
without
visible
damage
to
the
TID.
The
Nuclear
Material
Control
department
controls
the
issue
of
TIDs
per
MAN­
010­
MCA,
Materials
Control
and
Accountability
Manual
and
4­
P16­
SA­
TID­
001,
Tamper­
Indicating
Devices
(
TIDs).

Material
Transfer
and
Storage
Label
The
Material
Transfer
and
Storage
Label
(
RF­
46148,
sometimes
referred
to
as
a
"
Checkerboard
Label")
or
an
alternate
method,
as
specified
in
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
is
used
to
identify
individual
waste
items.
Each
waste
item
will
have
a
checkerboard
label
placed
on
it.
The
label
has
a
block
for
an
identification
number.
The
waste
generator
is
responsible
for
assigning
and
recording
this
number
on
the
label
and
on
the
appropriate
block
on
the
W/
RT.

Employee
Numbers
The
unique
employee
numbers
of
waste
generators,
Waste
Inspectors,
RTR
operators,
NDA
counter
operators,
Radiation
Control
Technologists,
and
others
are
recorded
during
each
stage
of
waste
processing
on
the
W/
RT
and
other
associated
documents.
Sub­
contractor
personnel
use
Site
Wide
Personnel
Locator
numbers
in
lieu
of
the
employee
number.

Radioactive
Material
Tag/
Label
The
Radioactive
Material
Tag/
Label
(
form
RF
46751)
is
applied
to
the
exterior
of
waste
drums
or
boxes.
Requirements
for
this
label
are
defined
in
the
Site
Radiological
Control
Manual.

Other
Procedures
for
Item
Identification
and
Control
The
RFETS
procedure
providing
requirements
for
controlling
items
is
as
follows:

 
1­
A67­
QAP­
08.01,
Identification
and
Control
of
Items.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
66
3.2.1.4
Special
Processes
Special
processes
are
those
processes
whose
results
are
highly
dependent
on
control
of
process,
the
skill
of
the
operator
and/
or
processes
where
inspection
or
testing
of
results
is
not
performed
easily.
Listed
below
are
the
applicable
special
processes
associated
with
the
TRU
waste
programs.

Real­
Time
Radiography
(
RTR)

RTR
is
designated
as
a
"
special"
process
due
to
the
skill
required
to
accurately
interpret
radiographs
of
sealed
waste
packages.
The
RTR
operators
must
be
certified
prior
to
conducting
waste
package
radiography.
Training
and
certification
of
RFETS
RTR
operators
is
conducted
by
the
NDT
department
in
accordance
with
5­
NDT­
TC­
1A,
Training,
Qualification,
and
Certification
of
Nondestructive
Testing
Personnel.
Training
and
certification
of
mobile
RTR
operators
is
conducted
in
accordance
with
the
mobile
vendor
training
plan.
RTR
procedures
contain
instructions
for
performing
verifications
of
waste
packages
and
packages
contents
using
RTR.
See
the
TWCP
QAPjP,
Sections
B1­
3,
B1­
7,
B3­
4,
B3­
10,
and
B3­
12
for
details.

Leak
Testing
of
the
TRUPACT­
II
Package
TRUPACT­
II
package
helium
leak
testing
is
designated
as
a
"
special"
process
since
the
effectiveness
of
the
test
is
based
on
operator
knowledge,
which
is
obtained
through
formalized
training.
Procedure
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test,
contain
instructions
for
performing
a
verification
leak
test
on
the
TRUPACT­
II
package.
NDA
leak
test
operators
are
trained
and
certified
by
the
NDT
department
in
accordance
with
5­
NDT­
TC­
1A,
Training,
Qualification,
and
Certification
of
Nondestructive
Testing
Personnel.

3.2.1.5
Handling,
Storage
and
Shipping
The
following
are
the
primary
procedures
for
controlling
the
marking,
handling,
storage,
labeling,
staging,
and
shipping
of
waste
packages
in
order
to
prevent
damage
or
loss,
to
minimize
deterioration,
and
to
assure
safety
of
operations:

 
1­
PRO­
Q11­
WO­
1221,
Controls
for
Updating
Waste
Package
Information
in
WEMS
 
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure
 
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging
 
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions
 
MAN­
010­
MCA,
Materials
Control
&
Accountability
Manual
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
67
3.2.1.5
Handling,
Storage
and
Shipping
(
continued)

 
MAN­
T91­
STSM­
001,
Site
Transportation
Safety
Manual.

 
Waste
generators,
Waste
Inspectors,
custodians,
field
technicians,
and
certification
officials
verify
and
document
compliance
to
these
procedures
from
the
initial
point
of
generation
to
final
disposal.

 
Marking
and
labeling
requirements
for
off­
site
shipment
are
defined
in
PRO­
T13­
Traffic­
306,
Labeling
and
Marking
TRUPACT
Packages.

Handling
and
Storage
TRU
wastes
are
stored
in
RFETS
approved
and
designated
areas.
Mixed
TRU
waste
is
stored
in
RCRA
Part
B
permitted
storage
areas.
Wastes
that
are
scheduled
for
off­
site
shipment
are
processed
through
the
Building
664
and
Building
440
staging
areas
by
Waste
Operations
personnel.
Nuclear
Material
Control
personnel
authorize
and
track
the
movement
of
nuclear
material
throughout
RFETS.
Dock
inspection,
RTR
verification,
document
review,
and
storage
are
conducted
in
accordance
with
established
procedures,
drawings,
and
specifications.
Procedure
PRO­
1418­
WO­
TRUOP,
TRUPACT­
II
Operations,
describes
the
physical
handling
and
loading
of
waste
packages
into
the
TRUPACT­
II
for
off­
site
shipment.

Waste
Shipping
The
Traffic
Management
department
coordinates
the
off­
site
shipment
of
TRU
waste
to
the
WIPP
disposal
site.
All
TRU
waste
shipments
consigned
to
the
WIPP
will
be
made
in
accordance
with
applicable
DOT,
EPA,
WIPP­
WAP,
state,
and
local
hazardous
waste
regulations,
including
WIPP
transportation
requirements
and
applicable
requirements
of
the
Certificate
of
Compliance.
Procedures
for
waste
transfer
are
specified
in
MAN­
T91­
STSM­
001,
Site
Transportation
Safety
Manual
and
Traffic
Management
procedures
(
e.
g.,
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations).

Regulated
wastes
are
collected
in
three
areas:
satellite
collection
areas,
90­
day
accumulation
areas,
and
permitted
storage
areas.
Management
of
RFETS
hazardous
waste
storage
areas
complies
with
federal
requirements
40
CFR
Parts
262,
264,
and
265
and
the
associated
Colorado
State
requirements
in
6
CCR
1007­
3
Parts
262,
264,
and
265.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
68
3.2.1.5
Handling,
Storage
and
Shipping
(
continued)

Waste
Shipping
(
continued)

The
satellite
and
90­
day
waste
collection
areas
are
managed
by
KH.
A
master
list
of
the
waste
collection
areas
is
maintained.
This
list
includes
information
on
the
location
of
the
area,
the
waste
that
can
be
managed
in
the
area,
and
the
responsible
individual.
Any
modification
to
the
existing
storage
areas
should
be
coordinated
with
KH.

The
CDPHE
RCRA
Part
A
and
Part
B
Permits
discuss
interim
status
and
permitted
units
that
exist
at
RFETS.
These
documents
give
detailed
information
on
the
location,
material
types,
and
quantities
of
hazardous
wastes
that
reside
at
RFETS.
KH
 
Environmental
Systems
and
Stewardship
is
responsible
for
ensuring
that
the
Part
A
and
the
Part
B
permits
are
accurate
and
contain
current
information.
This
responsibility
includes
drawings
of
the
permitted
storage
units.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
69
3.2.2
Design
Control
Design
processes
are
controlled
through
RFETS
procedures
and
processes
identified
in
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure.
The
TRU
Waste
Program
does
not
perform
design.
See
Section
4.6.3
for
explanatory
information
regarding
design
control
as
it
applies
to
the
POC.

Facilities
and
Equipment
Engineering
provides
engineering
design
packages
and
configuration
control
of
facilities
and
equipment.
This
includes
maintenance
of
existing
equipment
and
installation
of
new
equipment
and
facilities.
The
Engineering
department
prepares
engineering
packages
including
technical
drawings
and
associated
specifications.
Engineering
maintains
and
archives
associated
records.
An
overview
of
the
engineering
process
is
provided
in
MAN­
027­
SERM,
Site
Engineering
Requirements
Manual.

Radiation
Detection
Instruments
RFETS
does
not
design
radiation
detection
instruments.
However,
RFETS
does
utilize
radiation
detection
instruments
in
designed
systems.
The
Radiation
Instrumentation
department
maintains
control
of
portable
assay
equipment
and
concurs
with
system
design
drawing
changes
when
the
design
includes
the
use
of
radiation
detection
instruments.
Design
control
for
the
use
of
radiation
detection
instruments
in
designed
systems
is
specified
in
RFETS
engineering
documents.

Radioactive
Assay
Equipment
Nondestructive
assay
equipment
is
purchased
from
commercial
vendors
according
to
specifications
developed
by
Measurements.
Measurements
maintains
all
drawings
and
maintenance
records.
See
Appendix
4
for
additional
details
on
NDA
systems.

Design
control
of
NDA
equipment
is
maintained
by:

 
Facilities
Engineering
through
the
use
of
configuration
control
and
design
control
procedures;
and
 
Nondestructive
Assay
through
the
selection,
validation
and
qualification
of
NDA
counters
and
associated
documentation.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
70
3.2.3
Procurement
Procurement
documents
address
design,
fabrication,
and
quality
assurance
requirements,
and
are
reviewed
by
appropriate
organizations,
disciplines,
and
subject
matter
experts
to
assure
they
contain
adequate
scope
of
work,
technical
requirements,
supplier
quality
assurance
program
requirements
and
provisions
for
acceptance.

The
Procurement
Engineering
and
Quality
Assurance
organization
ensures
that
suppliers
of
materials
and
items
are
evaluated,
approved,
and
continually
verified
based
on
adequate
criteria.
The
Procurement
organization
supports
the
RFETS
TRU
Waste
Program
by
establishing
a
procurement
system
that
ensures
materials
and
items
perform
as
specified
and
comply
with
applicable
regulatory,
technical
and
quality
requirements.

The
procurement
system
ensures
compliance
to
the
following
specific
requirements:
control
of
procurement
documentation,
procurement
planning,
supplier
selection,
proposal/
bid
evaluation,
supplier
performance
evaluations,
acceptance
of
items
or
services,
and
control
of
nonconforming
and
commercial
grade
items.

3.2.3.1
Procurement
Planning
MAN­
134­
PPM,
Procurement
Program
Manual
defines
the
procurement
planning
activities.

3.2.3.2
Supplier
Selection
1­
J55­
ADM­
08.10,
Subcontractor
Quality
Evaluations
defines
the
methods
for
the
performance
of
quality
assurance
evaluation
activities.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
71
3.2.3.3
Proposal/
Bid
Evaluation
The
procurement
initiating
organization
is
responsible
for
developing
procurement
requisitions
for
waste
commodities
in
accordance
with
MAN­
134­
PPM,
Procurement
Program
Manual.
Metrology
reviews
requisitions
for
test
and
measuring
equipment
after
the
procurement
specifications
are
generated
per
MAN­
134­
PPM,
Procurement
Program
Manual.

The
Procurement
Engineering
and
Quality
Assurance
group
performs
evaluations
in
accordance
with
1­
J55­
ADM­
08.10,
Subcontractor
Quality
Evaluations,
and
maintains
the
Evaluated
Subcontractors
List.
Purchase
Orders
are
developed
based
on
procurement
specifications,
which
specify
receipt
and
source
inspection
requirements.

3.2.3.4
Procurement
Document
Control
The
procurement
document
control
system
is
defined
in
MAN­
134­
PPM,
Procurement
Program
Manual;
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance;
PRO­
1306­
ARIBA,
Ariba
Buyer
Users
Guide;
and,
for
design
packages,
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure.
The
procurement
document
controls
specified
in
these
manuals
apply
to:

 
Waste
packages,
associated
hardware
and
ancillary
packaging
materials;

 
Capital
equipment,
piping,
treatment
units
and
other
installed
items
used
to
treat
or
process
waste;

 
Radioactivity
measuring
equipment;

 
Waste
analysis
laboratory
chemicals,
reagents,
materials,
and
equipment;

 
Measuring
and
test
equipment
used
in
waste
treatment
or
processing;
and
 
Contracted
waste
management
services.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
72
3.2.3.5
Procurement
Document
Review
and
Approval
MAN­
134­
PPM,
Procurement
Program
Manual;
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance
and
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure
define
the
procurement
document
review
and
approval
process.
Procurement
document
changes
are
subject
to
the
same
degree
of
control
as
the
original
documents.

Management
prepares
purchase
requisitions
according
to
MAN­
134­
PPM,
Procurement
Program
Manual.
Quality
attributes
are
specified
in
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance;
or
in
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure.

The
Procurement
organization
prepares
solicitations
for
waste
commodities,
submits
them
to
suppliers,
and
receives
offers
as
part
of
the
bidding
process,
per
the
KH
Procurement
System
Manual.
When
required
by
the
requisition,
Procurement
lets
contracts
to
successful
bidders
on
the
Evaluated
Subcontractors
List.
The
Waste
Requirements
Group
(
WRG)
and
Site
PQAO
review
requisitions
for
WIPP­
related
commodities
to
ensure
project
requirements
are
included.

3.2.3.6
Supplier
Performance
Evaluations
MAN­
134­
PPM,
Procurement
Program
Manual;
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance
and
1­
J55­
ADM­
08.10,
Subcontractor
Quality
Evaluations
define
the
supplier
performance
evaluation
process.

3.2.3.7
Acceptance
of
Items
or
Services
Items
and
services
purchased
to
support
the
TRU
Waste
Program
are
controlled
at
all
stages
of
procurement
from
requisition
and
purchase
order
preparation,
specification
development
and
approval,
approval
and
selection
of
suppliers,
supplier
bid
evaluation
and
award,
verification,
control
of
nonconformance
and
corrective
action,
acceptance
of
item
or
service,
and
maintenance
of
records.
The
system
control
procedures
are
found
in
MAN­
134­
PPM,
Procurement
Program
Manual;
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance;
PRO­
1306­
ARIBA,
Ariba
Buyer
Users
Guide;
and
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
73
3.2.3.7
Acceptance
of
Items
or
Services
(
continued)

Acceptance
of
Items
Supplied
items
are
purchased,
inspected,
and
certified
in
accordance
with
direction
and
criteria
contained
in
procurement
specifications,
or
purchasing
documents.
Inspection
and/
or
verification
is
performed
to
verify
vendor
products
comply
with
procurement
specifications
when
delivered
in
accordance
with
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification.
When
items
do
not
conform
to
requirements
they
are
dispositioned
in
accordance
with
applicable
NCR
procedures.

All
component
replacement
and
maintenance
involving
TRUPACT­
II
packages
are
performed
under
the
direct
instructions
of
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance;
DOE/
WIPP
02­
3184,
CH
Packaging
Operations
Manual;
and
DOE/
WIPP
02­
3185,
CH
Packaging
Maintenance
Manual;
Department
of
Energy
procedures
controlled
through
document
control
processes
at
CBFO.

Acceptance
of
Services
Site
and/
or
TRU
Waste
Program
management
may
elect
to
subcontract
TRU
waste
characterization
or
waste
processing
operations
based
on
cost
effectiveness
or
other
management
initiatives.
Contract
management
personnel
select
suppliers
from
the
Evaluated
Subcontractor
List
for
purchases
designated
to
be
made
from
an
approved
supplier.
If
requested,
a
subcontractor
evaluation
is
performed
by
Procurement
Engineering
and
Quality
Assurance.
This
evaluation
may
be
based
on
evaluation
of
existing
or
subcontractor
provided
documents
or
records,
or
by
a
direct
evaluation
of
the
subcontractor's
facilities,
personnel,
and
quality
assurance
program.
When
services
are
procured
for
subcontractor
owned
and/
or
operated
systems,
the
following
additional
requirements
apply:

 
The
statement
of
work
for
the
prospective
subcontractor
shall
be
reviewed
by
the
TWCP
Site
PM
and
TWCP
Site
PQAO
to
ensure
appropriate
TRU
Waste
Program
requirements
are
incorporated
and
specified
as
contract
deliverables.
KH
organizations
preparing
statements
of
work
for
subcontractor
owned
or
operated
systems
shall
provide
copies
of
statements
of
work
to
the
TRU
Waste
Program
office
for
review
and
approval.

 
Subcontractors
selected
to
provide
services
must
demonstrate
implementation
of
QA
program
requirements
that
apply
to
scope
of
work
activities.
The
subcontractor's
QA
program
must
be
approved
and
placed
on
the
Evaluated
Subcontractors
List
when
specified
in
the
procurement
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
74
3.2.3.7
Acceptance
of
Items
or
Services
(
continued)

Acceptance
of
Services
(
continued)

 
The
subcontractor
shall
prepare
an
interface
document
in
accordance
with
PRO­
1132­
WIPP­
012,
Preparation
of
an
Interface
Document
for
Vendor
Owned
or
Operated
Systems,
that
clearly
defines
the
organizational
working
relationship
with
the
subcontracting
organization
and
the
TRU
Waste
Program
office.
The
interface
document
addresses
implementation
details
of
how
the
vendor
quality
assurance
program
integrates
with
TRU
Waste
Program
requirements.
The
interface
document
provides
review/
concurrence/
approval
requirements
of
subcontractor
procedures
and
documents.
The
interface
document
SHALL
be
reviewed
and
approved
by
the
TWCP
Site
PM
and
the
TWCP
Site
PQAO.

 
If
the
subcontractor
is
providing
new
waste
treatment
or
certified
WIPP
characterization
services
to
the
program,
a
PCP
and/
or
a
PQP
and
reports
shall
be
prepared
that
demonstrates
operations
comply
with
TRU
Waste
Program
requirements.
The
PCPs
or
PQPs
shall
be
prepared
in
accordance
with
1­
M60­
WPC­
001,
Waste
Process
Control.

TRU
Waste
Program
Management
shall
accept
TRU
waste
related
services
by
any
or
all
of
the
following
methods:

 
Technical
verification
of
data
produced.

 
Surveillance
and/
or
audit
of
the
activity.

 
Review
of
objective
evidence
for
conformance
to
the
procurement
document
requirements
such
as
certifications
or
test
reports.

3.2.3.8
Control
of
Supplier
Nonconformances
MAN­
134­
PPM,
Procurement
Program
Manual
and
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification
address
the
supplier
nonconformance
control
process.

3.2.3.9
Commercial
Grade
Items
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance
and
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification
address
the
use
of
commercial
grade
items.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
75
3.2.4
Inspection
&
Testing
Inspections
are
planned
and
performed
at
various
points
from
initial
waste
generation
through
final
shipment.
The
status
of
certification
activities
is
maintained
from
the
point
of
waste
generation
through
the
final
shipment
inspection
through
the
waste
packaging
procedures.
Required
certification
activities
are
identified,
described,
and
referenced
in
waste
certification
procedures:

 
1­
PRO­
072­
001,
Inspection
&
Acceptance
Test
Program;

 
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification;
and
 
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.

 
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection.

Inspections
that
verify
conformance
to
certification
requirements
are
performed
by
personnel
other
than
those
who
performed
the
work.
Procedure
1­
PRO­
072­
001,
Inspection
&
Acceptance
Test
Program
addresses
the
inspection
and
testing
requirements.

This
procedure
addresses
the
qualification
of
inspection
and
test
personnel,
qualification
of
non­
destructive
examination
personnel,
inspection
and
test
planning,
types
of
inspection
and
testing
performed,
and
inspection
and
test
documentation.

3.2.4.1
Qualification
of
Inspection
and
Test
Personnel
Only
personnel,
qualified
by
using
written
instructions
and
defined
acceptance
criteria,
perform
inspection
and
test
activities.
Qualification
results
are
documented
and
maintained
as
part
of
the
certification
records.
PLN­
97­
007,
TWCP
Training
Implementation
Plan
and
MAN­
094­
TPM,
Training
Program
Manual
address
the
qualification
of
inspection
and
test
personnel.

3.2.4.2
Qualification
of
Nondestructive
Examination
(
NDE)
Personnel
PLN­
97­
007,
TWCP
Training
Implementation
Plan,
MAN­
094­
TPM,
Training
Program
Manual,
and
5­
NDT­
TC­
1A,
Training
Qualification
and
Certification
of
NDT
Personnel
address
the
qualification
of
NDE
personnel.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
76
3.2.4.3
Inspection
Inspections
performed
to
verify
conformance
of
an
item
or
activity
to
specific
requirements
are
planned,
controlled
and
documented
to
assure
consistent,
repeatable,
and
retrievable
results.
Waste
inspection
procedures
establish
the
inspection
points,
define
the
Waste
Inspector
responsibilities,
include
standards
for
acceptance
and
rejection,
and
provide
instructions
for
inspection
performance.

These
inspections
assess
package
integrity,
package
contents
conformance,
and
package
documentation,
labeling,
and
marking.
Nonconformance
to
criteria
is
documented
according
to
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances
on
a
Waste
Nonconformance
Report
(
WNCR).
The
copy
of
the
WNCR
is
attached
to
the
package
documentation
and
returned
to
the
waste
generator
or
Solid
Waste
Operations
for
corrective
actions.

The
following
inspections
are
performed:

 
Pre
Use
­
inspection
of
drums
or
SWBs
conducted
by
the
waste
generator
prior
to
use
(
refer
to1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging
for
packaging
type,
and
to
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
for
pre­
use
inspection);

 
In
Process
­
performed
at
management
discretion
during
waste
generation,
to
ensure
wastes
comply
with
IDC
designation,
contain
no
free
liquids,
compressed
gases
or
gross
levels
of
particulates
or
other
prohibited
materials,
includes
dock
inspection
performed
on
filled
and
sealed
boxes
and
drums
on
process
building
docks
to
assess
package
integrity,
labeling,
handling
damage
and
proper
documentation
(
refer
to
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection);

 
Final
Inspection
­
performed
just
prior
to
loading
drums
or
SWBs
into
the
TRUPACT­
II
package,
to
ensure
proper
documentation
and
package
integrity
(
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection;
and
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification);

 
Traffic
Management
inspection
of
TRUPACT­
IIs
are
in
accordance
with
PROT95
OSTP­
002,
Off­
Site
Transportation
Procedure,
to
ensure
compliance
with
applicable
DOT
and
DOE
requirements;

 
TRUPACT­
II
Vehicle
Inspection
­
to
ensure
proper
loading
of
vehicle
and
the
condition
of
the
tractor,
trailer,
and
TRUPACT­
II
packages
performed
by
the
carrier,
Traffic
Management,
and
the
Colorado
State
Patrol.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
77
3.2.4.3
Inspection
(
continued)

Inspection
points
in
the
waste
stream
verify
the
performance
of
required
activities.
Passage
of
a
waste
package
through
an
inspection
point
is
verified
by
the
Waste
Inspector
signing
and/
or
stamping
the
W/
RT.
Waste
items
found
nonconforming
must
be
tagged
with
a
Waste
Nonconformance
Status
Tag
(
RF­
47841)
and
segregated
from
conforming
waste
items.

The
progress
and
control
of
waste
packages
through
the
waste
stream
is
maintained
by
forms,
labels
and
markings
which
require
the
performance
of
specific
tasks
to
ensure
compliance
of
each
waste
package
to
the
WIPP­
WAC
and
the
WIPP­
WAP.
The
performance
of
identified
activities
is
documented
by
the
waste
generator
or
responsible
party
by
affixing
their
signature
at
the
appropriate
location
on
the
documentation.
The
serialization
of
each
waste
package
and
use
of
these
numbers
on
all
documentation
ensures
traceability
through
the
system.
The
inspection
status
of
waste
is
clearly
marked
on
the
forms,
labels,
and
marking
attached
to
the
waste
packages.

3.2.4.4
Test
Requirements
Testing
activities
ensure
the
capability
of
an
item
to
meet
specified
requirements
by
subjecting
the
item
to
physical,
chemical,
environmental
or
operating
conditions.
Tests
performed
to
verify
conformance
of
an
item
or
activity
to
specific
requirements
are
planned,
controlled
and
documented
to
assure
consistent,
repeatable,
and
retrievable
results.
The
tests
associated
with
the
TRU
Waste
Program
are:

 
Equipment
Systems
Operations
Tests
or
component
checkout
(
per
1­
PRO­
072­
001,
Inspection
and
Acceptance
Test
Program)

 
TRUPACT
II
Leak
Testing
(
per
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test.)

 
Waste
Characterization
Process
Qualification
Tests
(
per
1­
M60­
WPC­
001,
Waste
Process
Control)

 
NDA
Qualification
Plans
(
Refer
to
Appendix
4)

 
Gas
Generation
Testing
(
Refer
to
RS­
020­
001,
Gas
Generation
Testing
Program
Quality
Assurance
Project
Plan.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
78
3.2.4.5
Monitoring,
Measuring,
Testing
and
Data
Collection
Equipment
To
prevent
inadvertent
use
of
malfunctioning
or
otherwise
defective
equipment,
inspection
and
test
personnel
clearly
designate
and
document
the
operating
status
of
equipment
associated
with
waste
management
activities.
Operational
status
controls
are
contained
in
MAN­
066­
COOP,
Site
Conduct
of
Operations
Manual,
and
MAN­
072­
OS&
IH
PM,
Occupational
Safety
&
Industrial
Hygiene
Program
Manual,
Chapter
9:
Lockout/
Tagout.

3.2.4.6
Use
and
Control
of
Measuring
and
Testing
Equipment
All
test
and
measurement
equipment
used
is
controlled
and
calibrated
in
accordance
with
requirements
specified
in
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management.
Calibration
of
test
and
measuring
equipment
may
be
performed
either
internally,
using
in­
house
reference
standards,
or
externally
by
national
certifying
agencies
or
manufacturers.
All
reference
standards
have
valid
relationships
to
nationally
recognized
standards,
for
example,
National
Institute
of
Science
and
Technology
(
NIST).
If
national
standards
do
not
exist,
the
basis
for
calibration
is
documented.
All
test
and
measuring
equipment
are
uniquely
identified.

Several
RFETS
organizations,
including
Metrology,
Analytical
Services,
and
Measurements,
have
responsibilities
for
controlling
and
calibrating
test
and
measuring
equipment.
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management,
establishes
Metrology
as
responsible
for
approving
all
other
calibrating
organizations
through
an
active
surveillance
program.
Calibrating
organizations
perform
calibrations
in
accordance
with
this
procedure,
which
describes
the
recall
system
establishing
the
traceability
of
all
standards
and
test
and
measuring
equipment
under
the
purview
of
Metrology.
All
calibrating
facilities
shall
have
mechanisms
in
place
for
evaluating
inspections
or
tests
where
out­
of­
tolerance
instruments
were
used.
These
mechanisms
shall
include
methods
for
evaluating
the
data
obtained
from
the
use
of
these
instruments,
and
methods
for
re­
testing
or
correcting
the
data
to
ensure
data
accuracy.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
79
3.2.4.6
Use
and
Control
of
Measuring
and
Testing
Equipment
(
continued)

As
part
of
its
surveillance
program,
Metrology
assures
that
RFETS
calibrating
organizations
comply
with
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management.
All
calibrating
organizations
must
establish
a
control
system
for
the
equipment
under
their
purview,
which
includes
unique
identification
of
test
and
measuring
equipment.
All
calibrating
organizations
must
also
use
approved
procedures
for
performing
calibrations
of
test
and
measuring
equipment.
Those
instruments
that
are
calibrated
shall
be
calibrated
in
an
environmentally
controlled
area
and
the
environmental
data
recorded
and
maintained
(
e.
g.
temperature,
humidity,
and
dust
concentrations).
Reference
standards
must
either
be
certified
by
the
Metrology
Laboratories
or
be
obtained
from
a
nationally
recognized
source.
Calibrating
organizations
must
establish
calibration
frequencies
and
a
mechanism
for
ensuring
that
only
calibrated
equipment
is
used
for
this
project.

Measurements
is
responsible
for
tracking
NDA
standard
certification.

3.2.4.7
Calibration
Nondestructive
Assay
Radiometric
Counters
Calibration
NDA
equipment
used
to
assay
TRU
waste
is
calibrated
and
qualified
according
to
approved
procedures
before
assays
of
waste
packages
are
performed.
Calibration
and
qualification
of
each
measurement
system
currently
used
to
assay
or
planned
to
assay
TRU
waste
are
described
in
Appendix
4
of
this
document.
Systems
are
calibrated
with
standards
used
to
determine
the
response
characteristics
of
a
measurement
system.
Whenever
possible
radioactive
calibration
standards
shall
be
obtained
from
suppliers
maintaining
nationally
accredited
measurement
programs.
Evidence
of
such
traceability
and
certificates
for
individual
standards
shall
be
obtained
from
the
standards
suppliers.

RFETS
still
uses
Chemical
Standards
Laboratory
(
CSL)
calibration
standards
that
were
prepared
in
accordance
with
PRO­
697­
MLC­
00013,
Preparation
and
Certification
of
Nondestructive
Assay
Standards
and
Sources.
The
RFETS
plutonium
oxide
stream
used
to
prepare
NDA
standards
has
been
characterized
using
measurement
systems
traceable
to
NIST
and/
or
New
Brunswick
Laboratory
(
NBL).
Calibration
standards
are
re­
certified
using
PRO­
1566­
NDA­
STD,
Evaluating
NDA
Standards
for
Continued
Use.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
80
3.2.4.7
Calibration
(
continued)

Nondestructive
Assay
Radiometric
Calibration
Verification
Measurement
control
procedures
and
the
controlling
software
of
each
NDA
counter
system
ensure
proper
operating
status
of
the
NDA
counter.
It
is
usually
possible
to
verify
the
proper
function
of
the
instruments
with
rugged,
long­
lived
sources.
Since
the
data
obtained
from
these
"
check"
sources
is
not
directly
used
to
calculate
analytical
data,
they
do
not
have
to
be
traceable
to
primary
calibration
standards,
but
only
need
to
be
adequately
characterized
for
the
proposed
usage.
The
principal
requirements
for
such
sources
are
that
they
be
long­
lived,
simple
to
reposition
with
respect
to
the
detector(
s),
of
sufficiently
high
activity
to
obtain
adequate
counting
statistics
in
short
count
times,
and
relatively
insensitive
to
handling.
TRANSURANIC
(
TRU)
WASTE
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3.3
Assessment
Requirements
3.3.1
Management
Assessments
Managers
at
all
levels
of
the
project
periodically
assess
performance
of
their
organizations
to
determine
the
effectiveness
of
QA
program
provisions.
The
TWCP
Site
PM
schedules
and
performs
management
assessments
in
accordance
with
3­
W24­
MA­
002,
Kaiser­
Hill
Management
Assessment
Program.

3.3.2
Independent
Assessments
The
independent
assessment
program
implemented
for
the
TRU
Waste
Program
is
described
in
this
section.
It
is
implemented
as
part
of
overall
RFETS
independent
assessment
activities.
Operations
and
functional
managers
are
required
to
provide
audit
and
surveillance
personnel
free
access
to
documents,
work
areas,
workers,
and
supervision
during
independent
assessment
activities.

Material
Stewardship
QA
coordinates
and
issues
an
annual
schedule
of
surveillances
using
input
from
the
Site
PQAO
and
other
involved
quality
organizations.
Material
Stewardship
QA
performs
this
coordination
to
ensure
that
focus
areas
that
may
be
identified
by
DOE
or
RFETS
managers
are
included,
and
to
reduce
redundant
surveillance
activities.
The
schedule
is
distributed
to
the
TWCP
Site
PM
and
involved
quality
managers.
Corrective
actions
are
documented
and
tracked
according
to
3­
X31­
CAP­
001,
Corrective
Action
Process.

Surveillances
are
performed
to:
1)
monitor
work
in
progress;
2)
verify
compliance
with
established
requirements
and
procedures;
3)
identify
actual
and
potential
conditions
adverse
to
quality;
4)
obtain
timely
corrective
action
commitment
from
cognizant
managers
for
identified
conditions
adverse
to
quality;
5)
provide
notification
to
responsible
managers
of
the
status
and
performance
of
work
under
surveillance;
and
6)
verify
timely
implementation
of
corrective
action.

Audits
and
surveillances
of
activities
performed
by
other
organizations
are
reviewed
by
the
TWCP
Site
PQAO
for
applicability
to
project
activities.
These
audits
and
surveillances
may
substitute
for
project
surveillances
when
project
affecting
activities
are
evaluated.
Conditions
adverse
to
quality
identified
in
these
surveillances
are
monitored
in
project
trending
of
conditions
adverse
to
quality.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
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02/
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2004
PAGE
82
3.3.2.1
Surveillances
Surveillances
of
the
TRU
Waste
Project
are
coordinated
by
the
TWCP
PQAO
and
performed
by
technically
qualified
personnel,
knowledgeable
of
and
independent
of
the
areas
assessed.
The
surveillances
are
performed
according
to
PRO­
985­
SURV,
Performance
of
Surveillances.

3.3.2.2
Audits
An
annual
independent
assessment
or
a
series
of
smaller
independent
assessments
of
the
TRU
Waste
Program
is
performed.

3.3.2.2.1
Scheduling
Audits
The
annual
audit
is
scheduled
according
to
1­
W37­
IA­
002,
Integrated
Planning
and
Scheduling
of
Assessment
Activities.

3.3.2.2.2
Planning
and
Preparation
for
Audits
Procedure
3­
B52­
IA­
003,
Conduct
of
Independent
Assessment
Activities,
is
used
to
plan
and
perform
the
assessment
and
report
the
audit
results.

3.3.2.2.3
Audit
Team
Selection
Procedure
3­
B52­
IA­
003,
Conduct
of
Independent
Assessment
Activities
addresses
the
process
for
audit
team
selection.

3.3.2.2.4
Auditor
Qualification
Personnel
performing
audits
are
qualified
according
to
procedure
1­
N92­
ADM­
02.03,
Training
and
Qualification
of
Assessment
and
Surveillance
Personnel.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
83
3.3.2.2.5
Technical
Specialist
Qualification
Technical
specialists
for
the
independent
audit
teams
are
supplied
for
the
audit
team
by
the
TRU
Waste
Program.
The
technical
specialists
supplied
shall
be
independent
of
the
processes
to
be
audited.
Qualification
of
Technical
Specialist
is
addressed
in
section
3.3.2.4.4.

3.3.2.2.6
Lead
Auditor
Qualification
Procedure
1­
N92­
ADM­
02.03,
Training
and
Qualification
of
Assessment
and
Surveillance
Personnel
addresses
the
qualification
requirements
for
Lead
Auditors.

3.3.2.2.7
Performing
Audits
Audits
are
performed
in
accordance
with
procedure
3­
B52­
IA­
003,
Conduct
of
Independent
Assessment
Activities.

3.3.2.2.8
Reporting
Audit
Results
Procedure
3­
X31­
CAP­
001,
Corrective
Action
Process,
defines
the
site­
level
process
for
documenting
and
characterizing
corrective
actions
identified
during
the
assessment.
The
Plant
Action
Tracking
System
(
refer
to
3­
X31­
CAP­
001,
Corrective
Action
Process)
provides
for
tracking
of
corrective
actions.

3.3.2.2.9
Audit
Response
and
Follow­
up
Responses
and
follow­
up
to
audits
by
management
of
the
audited
organization
is
directed
by
the
requirements
in
3­
X31­
CAP­
001,
Corrective
Action
Process.

3.3.2.2.10
Audit
Records
Audit
records
are
controlled
according
to
1­
V41­
RM­
001,
Records
Management
Manual.

Records
storage
is
performed
in
accordance
with
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
84
3.4
Sample
Control
Requirements
The
sampling
and
analysis
of
RFETS
wastes
is
planned,
controlled,
and
performed
in
accordance
with
the
TWCP
QAPjP.
The
specific
waste
streams
characterized
through
sample
collection
and
analysis
must
be
specified.
The
results
of
these
efforts
are
compiled
into
reports
contained
in
the
WSRIC
Building
Books
which
provide
information
for
the
RCRA
Part
B
operating
permit
application.
The
WSRIC
Building
Books
are
the
source
of
much
of
the
waste
characterization
data
needed
for
certification
of
TRU
waste
to
the
WIPP­
WAC.

3.4.1
Sample
Control
Requirements
The
WIPP­
WAP
defines
the
requirements
for
waste
sample
control
which
are
reiterated
and
implemented
by
the
TWCP
QAPjP.
Waste
sampling
is
performed
in
accordance
to
Waste
Sampling
and
Analysis
Plans
to
meet
specified
Data
Quality
Assurance
Objectives.

3.4.2
Sample
Identification
The
TWCP
QAPjP
specifies
the
requirements
and
implementing
procedures
for
sample
identification.

3.4.3
Handling,
Storage
And
Shipping
Samples
The
requirements
for
waste
sampling,
storage
and
analysis
and
data
quality
objectives
are
defined
in
the
WIPP­
WAP
and
are
reiterated
and
implemented
by
the
TWCP
QAPjP.

3.4.4
Disposition
Of
Sample
Nonconformance
All
waste
stream
analysis
data
are
required
to
be
validated
to
the
DQO
criteria,
and
data
sets
dispositioned
as
acceptable,
acceptable
with
qualifications,
or
unacceptable.
The
Waste
Operations
organization
is
required
to
disposition
data
sets,
initiate
corrective
actions
such
as
re­
sampling
if
necessary,
and
maintain
retrievable
records
of
these
activities.

CBFO
is
notified
of
any
non­
administrative
nonconformances
related
to
applicable
requirements
specified
in
the
WIPP­
WAP
which
are
first
identified
at
the
TWCP
Site
PM's
signature
release
level.
This
process
is
defined
in
PRO­
940­
WIPP­
010,
WIPP
TRU
Waste
Characterization
Project
Level
Data
Review
and
Reporting.

3.5
Scientific
Investigation
Requirements
RFETS
does
not
conduct
scientific
investigations.
TRANSURANIC
(
TRU)
WASTE
1­
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008­
WM­
001
MANAGEMENT
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02/
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2004
PAGE
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3.6
Software
Requirements
3.6.1
Software
Quality
Assurance
(
SQA)

TRU
Waste
Program
operations,
supported
by
software
systems,
are
controlled
during
development,
use,
and
maintenance,
to
ensure
that
the
software
performs
reliably
and
to
expectations.
1­
MAN­
004­
CSMM,
Computer
Software
Management
Manual,
and
MAN­
134­
PPM,
Procurement
Program
Manual
are
the
procedures
that
control
the
purchase
or
development
and
maintenance
of
computer
software.
These
software
programs
also
comply
with
the
requirements
of
the
QAPD,
Section
6
­
Software
Requirements.
Each
user
identifies
how
their
system
complies
with
the
requirements
of
the
QAPD,
Section
6
­
Software
Requirements.

The
following
describes
the
primary
software
systems
and
software
QA
compliance:

 
The
WEMS
is
a
multi­
user
software
package
that
operates
on
the
Site
computer
network.
This
system
tracks
all
waste
types
(
TRU/
TRU
Mixed,
LLW/
LLW
Mixed,
and
Hazardous)
from
"
cradle­
to­
grave"
and
is
the
responsibility
of
the
Waste
Systems
organization.
The
WEMS
software
tracks
individual
waste
packages
during
the
waste
generation,
packing,
storage,
and
shipping
process
and
is
used
to
prepare
load
lists
to
waste
disposal
sites.
Waste
Systems
is
responsible
for
maintaining
4­
F72­
WEM­
WP1205,
WEMS
and
WSRIC
Software
Quality
Assurance
Compliance,
for
WEMS
which
addresses
Software
QA.
Software
validation
testing
for
WEMS
is
performed
according
to
4­
F72­
WEM­
WP­
1205,
WEMS
and
WSRIC
Software
Quality
Assurance
Compliance.

 
All
software
used
to
control
NDA
equipment
and
report
results
is
demonstrated
to
satisfy
the
requirements
of
the
QAPD,
Section
6.
Software
compliance
for
each
measurement
system
currently
used
to
assay
or
planned
to
assay
TRU
waste
is
maintained
according
to
PRO­
548­
SSOC­
SQA,
Software
Management
for
Nondestructive
Assay
Systems.

 
Headspace
Analytical
Services
and
the
Analytical
Laboratories
use
a
laboratory
data
management
system
to
support
TRU
Waste
Program
activities.
This
software
is
part
of
the
analytical
instrumentation
used
for
analysis.
Software
Quality
Assurance
on
this
software
is
described
in
L­
4031,
Software
Quality
Assurance1
and
PRO­
1668­
SQA,
TRU
Waste
Characterization
Program
(
TWCP)
Software
Quality
Assurance.

1
This
document
will
be
deactivated
in
February
2004.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
86
4.0
RFETS
TRU
WASTE
PACKAGING
&
CERTIFICATION
This
section
describes
the
characterization,
packaging,
and
certification
process
followed
at
RFETS
to
prepare
TRU
waste
for
shipment
to
WIPP.
The
Waste
Packaging
QA
program
requirements
from
10
CFR
71,
Subpart
H
are
addressed
in
Section
4.6.

4.1
Characterization
Process
Acceptable
Knowledge
(
AK)
is
used
to
characterize
TRU
waste.
Certification
of
RFETS
to
the
WIPP
disposal
and
transportation
criteria
is
accomplished
using
a
"
tiered"
or
hierarchical
approach.
The
certification
process
begins
with
the
waste
generator
who
must
generate
waste
to
procedures
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
and
other
applicable
documents.
Procedures
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
and
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
apply
to
all
personnel
involved
in
radioactive
line
and
non­
line
generated
waste
packaging
activities
both
inside
and
outside
the
Protected
Area
(
PA).

The
first
part
of
the
actual
waste
certification
process
is
performed
by
the
waste
generator
who
affirms
by
signature
on
the
W/
RT
that
the
waste
is
properly
identified,
segregated,
and
packaged
in
accordance
to
the
procedures.
In
addition,
a
verification
signature
is
required
by
a
person
(
not
the
same
person
that
signed
the
waste
generator
signature)
who
is
trained
and
qualified
to
package
and
segregate
waste
for
the
area
of
the
package
origin.
Details
on
the
W/
RT
and
the
waste
generator
statements
are
provided
in
Section
4.3.1.

During
the
waste
handling
and
packaging
process,
applicable
information
on
the
waste
package
paperwork
is
entered
into
the
WEMS,
in
addition
to
the
information
obtained
from
the
count
sheets
(
from
NDA
of
package)
and
Hazardous
Waste
Label.
Information
pertinent
to
the
certification
is
continually
entered
into
WEMS
as
the
package
is
transferred
on­
site.
(
See
Section
4.3.2
for
more
information
on
WEMS.)

The
signatures
on
the
waste
package
paperwork
and
information
from
WEMS
are
used
by
the
WCO
to
assess
the
package
and
its
contents
for
compliance
with
the
certification
requirements.
Section
4.2
provides
more
details
on
other
information
used
as
a
basis
for
certification
by
the
WCO.
The
WCO
affirms
compliance
for
each
waste
package
by
completing
the
checklist
in
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
Certification
is
also
indicated
through
an
entry
in
WEMS.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
87
4.1
Characterization
Process
(
continued)

Certification
that
waste
shipments
comply
with
DOT
requirements
is
provided
on
the
Bill
of
Lading,
and
signed
by
the
TCO
or
designated
alternate,
after
all
other
certifications
are
complete.
Certification
that
mixed
waste
shipments
comply
with
RCRA
requirements
is
provided
on
the
Uniform
Hazardous
Waste
Manifest,
also
signed
by
the
TCO
after
all
other
certifications
are
complete.
Mixed
waste
requires
a
Uniform
Hazardous
Waste
Manifest.

This
tiered
approach
provides
instructions
to
all
involved
personnel
so
that
all
wastes
are
properly
characterized,
identified,
in
compliance
with
requirements,
and
ready
for
off­
site
shipment.
The
following
sections
provide
descriptions
of
the
responsibilities
and
functions
of
each
unit
in
this
tiered
approach.

AK
was
used
to
characterize
legacy
wastes
packaged
prior
to
the
full
implementation
of
the
TWCP
(
December
16,
1992).
Specific
criteria
for
AK
data
contents
and
assembly
are
contained
in
the
WIPP­
WAP.
RFETS
uses
a
three
phase
process
to
characterize
TRU
wastes
by
means
of
AK
information:
1)
compiling
enough
AK
documentation
for
an
auditable
record,
2)
confirming
AK
information
using
radiography,
sampling
and
analysis
(
as
applicable),
and
3)
audit
of
AK
records.
The
TWCP
QAPjP,
Section
B4­
3b,
describes
the
RFETS
program
for
development,
assembly,
and
approval
of
AK
records.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
88
4.2
TRU
Waste
Certification
Official
(
WCO)

The
WCO
is
independent
of
waste
generation
organizations.
The
WCO
is
responsible
for
certifying
that
wastes
shipped
from
RFETS
comply
with
applicable
WIPP
disposal
requirements,
and
associated
state
and
federal
regulations.
A
complete
description
of
WCO
responsibilities
is
included
under
Section
3.1.1.1.4.
This
certification
is
based
on
review
and
verification
of,
but
not
limited
to,
the
following
information:

 
Overall
waste
generation/
packaging
system;

 
The
waste
generator's
statement
on
the
waste
package
paperwork
stating
that
wastes
are
properly
packaged
and
identified
according
to
applicable
procedures;

 
In­
process
package
contents
inspection
results;

 
RTR
dispositions;

 
RTR
Technician(
s)
certification
status;

 
Nondestructive
Assay
(
NDA)
or
radiochemical
analysis
for
determination
of
waste
type
as
TRU
waste,
dependent
on
point
of
origin
of
the
waste;

 
Applicable
WEMS
data
(
Fissile
Gram
Equivalent
(
FGE),
PE­
Ci,
Wattage
Limits,
etc.);

 
Physical
condition
of
the
waste
package
(
dents,
rust,
etc.);

 
Installation
of
correct
filters
on
waste
boxes
and
drums;

 
Documentation
accuracy,
completeness,
legibility,
and
compliance
to
limits
during
certification
processing
activities
and
verification
of
shipment
documentation;

 
Verification
that
the
waste
IDC
has
been
correctly
identified
and
documented;

 
Waste
package
marking,
labeling,
and
stenciling
is
complete,
accurate,
and
in
compliance
with
Traffic
Management
department
procedures;

 
Computer
data
input
(
WEMS)
for
completeness
and
accuracy
during
certification
processing
activities
and
for
electronic
transmittal
of
information
to
WIPP
by
WEMS
Program
Management;

 
Loading
of
accepted
waste
packages
for
shipment;
and
 
Surveillance
or
audit
information.

The
WCO
must
assess
the
information
presented
and
based
on
this
documentation,
determine
whether
the
waste
in
question
meets
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
89
4.3
Waste
Packaging
and
Documentation
Requirements
All
TRU
waste
is
packaged
under
controlled
conditions,
and
those
conditions
are
documented
on
approved
data
collection
forms.
All
instructions
necessary
to
assure
that
wastes
are
packaged
to
comply
with
the
WIPP­
WAC
are
provided
to
operations
personnel.
In
the
event
that
procedures
are
unclear
or
incomplete,
the
waste
generator
shall
cease
packaging
operations,
obtain
information
from
the
WRG,
and
initiate
revisions
to
procedures
that
clarify
or
address
the
situation.
The
following
requirements
must
be
met
when
packaging
TRU
waste:

 
Packaging
in
compliance
to
current
packaging
procedures:
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Travelers
Instructions;
individual
process
procedures
for
those
packages
which
are
attached
to
gloveboxes
and
are
not
covered
by
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
and
MAN­
010­
MCA,
Materials
Control
&
Accountability
Manual
for
packaging
and
handling
55
gallon
drums
inside
the
PA;

 
Use
of
current
data
collection
form;

 
Waste
generators
are
currently
trained
in
waste
handling
courses;

 
Waste
data
is
entered
into
WEMS
(
see
Section
4.3.2
for
details);

 
Waste
streams
are
identified
and
characteristics
documented
using
the
WSRIC
Building
Books.

4.3.1
Waste/
Residue
Traveler
The
W/
RT
is
used
as
an
in­
process
control
document
that
provides
objective
evidence
of
activities
associated
with
packaging
of
radioactive
and
radioactive
mixed
line
and
non­
line
generated
waste.

Currently
either
an
electronic
W/
RT
or
a
manual
W/
RT
may
be
used
for
packaging
activities.
If
an
electronic
W/
RT
is
to
be
used,
a
printout
of
the
electronic
W/
RT
is
obtained
prior
to
waste
generation.
The
electronic
W/
RT
is
printed
from
the
ETraveler
form
in
WEMS.
Portions
of
the
electronic
W/
RT
are
electronically
filled­
in
based
on
information
provided
to
WEMS
from
the
WGI
information.
Unpopulated
portions
of
the
electronic
W/
RT
are
filled­
in
by
hand.
When
using
the
manual
W/
RT,
all
portions
of
the
W/
RT
are
filled­
in
by
hand.
Throughout
this
document
(
i.
e.,
the
TWMM)
discussion
pertaining
to
the
W/
RT
is
generalized
(
i.
e.,
including
both
the
electronic
W/
RT
and
the
manual
W/
RT).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
90
4.3.1
Waste/
Residue
Traveler
(
continued)

Individual
packaging
procedures
sequence
W/
RT
completion
steps
as
they
occur
in
packaging
evolution.
All
radioactive
waste
generated
after
December
12,
1992
(
the
implementation
date
of
applicable
TRU
waste
packaging
procedures)
are
required
to
have
a
W/
RT.
Prior
to
December
12,
1992,
a
Drum
Label
was
used
to
provide
objective
evidence
of
activities
associated
with
packaging
of
radioactive
waste.
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions,
provides
instructions
for
personnel
to
complete
W/
RT
information.

The
W/
RT
is
the
documented,
approved
source
of
"
process
knowledge"
information
describing
the
presence
or
absence
of
RCRA
regulated
materials
for
each
waste
package.
The
waste
generator
is
responsible
for
the
accuracy
of
process
knowledge
information
and
affirms
this
by
signature
on
the
W/
RT
for
each
item
placed
in
a
waste
package,
see
Section
4.3.1.1
for
more
details.
Waste
generators
are
required
to
obtain
written
guidance
from
Waste
Management
­
Technical
Operations
in
the
event
that
process
knowledge
characterization
information
is
suspect,
incomplete,
or
inaccurate.
Waste
generators
are
required
to
file
a
WCF
or
initiate
a
WCR
if
process
material
inputs
or
outputs
change
per
WSRIC.

4.3.1.1
Generator
Waste
Identification
Statements
The
waste
generator
is
responsible
for
accurate
and
complete
identification
of
wastes
that
are
packaged
for
off­
site
disposal.
This
statement
affirms
that
to
the
best
of
the
waste
generator's
knowledge,
the
contents
of
each
waste
package
or
item
placed
in
the
package
are
properly
identified
and
documented
on
the
W/
RT.
A
second
waste
generator
verification
signature
affirms
that
the
package
was
visually
inspected
by
a
second
party
and
complies
with
waste
acceptance
criteria.
The
waste
generator
and
waste
verifier
signatures
appear
on
the
W/
RT.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
91
4.3.2
Waste
and
Environmental
Management
System
(
WEMS)

WEMS
is
a
secure
computer
database
used
for
the
storage
and
management
of
data
related
to
waste
packages.
WEMS
users
are
responsible
for
adherence
to
security
requirements
and
procedures.
WEMS
User
Authorizations
are
requested
from
the
WEMS
system
administrator.

Packages
are
initially
entered
into
WEMS
when
they
are
empty
and
they
are
tracked
through
waste
processing
operations
until
the
waste
is
sent
to
an
off­
site
facility.
Information
obtained
from
the
W/
RT
is
entered,
as
well
as
information
obtained
from
package
count
sheets,
the
Hazardous
Waste
Label,
and
other
source
documents.
Detailed
operational
instructions
are
provided
in
1­
PRO­
087­
WEMSWP
1201,
WEMS
Waste
Package
Inventory,
Tracking,
and
Control.

Prior
to
off­
site
shipment,
packages
are
verified
and
certified
in
WEMS.
Detailed
operational
instructions
are
provided
in
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.
These
functions
are
summarized
below:

 
Verification
Function
Prior
to
shipping,
all
waste
package
data
must
be
verified
for
accuracy
and
completeness.
This
data
verification
includes
the
resolution
of
any
discrepancies
between
the
data
in
WEMS
and
the
data
shown
on
the
documentation
accompanying
the
package.

 
Certification
Once
a
package
has
been
verified
as
correct
in
WEMS
it
is
reviewed
for
certification.
The
package
is
certified
in
WEMS
when
it
meets
all
the
criteria
for
shipment
and
is
acceptable
for
the
appropriate
off­
site
facility.

 
Shipping
Reports
and
Electronic
Data
Transmission
Shipping
reports
are
available
to
assist
the
users
in
preparing
a
load
for
a
shipment.
Data
is
electronically
transferred
to
the
WIPP
Waste
Information
System
(
WWIS).

WEMS
is
programmed
to
halt
the
verification
of
final
waste
package
information
and
to
display
an
error
message
when
data
is
missing
from
required
fields.
When
applicable,
field
validation
is
performed
on
data
in
required
fields
with
the
information
checked
against
a
table
of
values.
For
optional
entry
fields,
data
is
checked
when
data
is
entered.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
92
4.3.3
Waste
Stream
and
Residue
Identification
and
Characterization
(
WSRIC)
Building
Books
4.3.3.1
Description
The
WSRIC
is
a
comprehensive
site­
wide
assessment
of
current
waste
and
residue
generating
processes.
The
WSRIC
Building
Books
provide
waste
characterization
information
for
waste
generating
processes
for
each
building.
Waste
streams
are
characterized
and
assigned
unique
numbers
for
waste
management
purposes.
The
WSRIC
provides
preliminary
designations
of
waste
streams
as
RCRA
regulated
or
non­
RCRA
regulated.

WSRIC
Building
Books
are
controlled
and
maintained
by
Waste
Systems
according
to
4­
H19­
WSRIC­
001,
Waste
Characterization
and
Reverification;
and
PRO­
1003­
WSRIC­
ADMIN,
WSRIC
Administration
Guidance.
Operations
Management
has
prime
responsibility
to
assure
that
process
knowledge
information
contained
in
the
books
is
current
and
accurate.

4.3.3.2
Process
Knowledge
and
Analytical
Characterization
The
WSRIC
Building
Books
provide
documented,
reviewed,
and
approved
characterization
of
wastes
based
on
process
knowledge
and
analytical
data
(
see
Section
4.1).
Chemical
and
physical
waste
parameters
characterized
by
analysis
will
also
be
provided
in
WSRIC,
as
this
information
becomes
available
through
95­
WP/
SAP­
001,
Transuranic
(
TRU/
TRM)
Waste
Sampling
Plan.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
93
4.3.3.3
Maintenance,
Control,
Review
and
Approval
Document
control,
review
and
approval
of
the
WSRIC
Building
Books
is
performed
according
to
4­
H19­
WSRIC­
001,
Waste
Characterization
and
Reverification.
The
operations
approval
indicates
that
the
processing
material
inputs
and
outputs
are
accurately
described;
and
the
Waste
Disposal
approval
indicates
that
the
materials
are
properly
designated
as
RCRA
or
non­
RCRA
wastes.
The
waste
generator
is
responsible
for
maintaining
WSRIC
accuracy
when
process
changes
occur
by
submitting
a
WCF
or
initiating
a
WCR
per
4­
H19­
WSRIC­
001,
Waste
Characterization
and
Reverification.

4.3.3.4
Use
The
WSRIC
provides
characterization
information
for
waste
and
residue
packaging
and
handling;
however,
the
definitive
source
of
process
knowledge
information
is
provided
by
the
waste
generator
on
the
W/
RT
as
wastes
are
generated.
Information
excerpted
from
the
WSRIC
Building
Books
may
be
reformatted
and
posted
by
operations
personnel
at
process
lines
or
waste
generation
sources.
This
posted
information
must
be
controlled
through
the
building
conduct
of
operation
protocols
and
approved
by
the
Operations
Manager
(
or
cognizant
designee).

4.3.4
Backlog
Waste
Reassessment
Baseline
Book
(
BWRBB)

In
1994
and
1995,
the
Backlog
Waste
Reassessment
project
was
responsible
for
compiling
characterization
information
for
process
waste
and
residues
generated
prior
to
the
implementation
of
the
WSRIC
and
the
W/
RT
programs.
Information
from
numerous
sources
was
reviewed
to
assess
the
characterization
of
the
containers
in
the
backlog
inventory.
The
results
of
this
assessment
were
documented
in
the
BWRBB.
The
resulting
changes
to
container
characterization
were
incorporated
into
WEMS
and
on
container
documentation,
if
necessary.
The
BWRBB
is
maintained
as
a
controlled
document
and
updated
to
reflect
current
container
characterization
as
new
information
becomes
available
for
the
inventory.
In
addition,
the
BWRBB
is
being
utilized
to
document
changes
to
container
characterization
resulting
from
Waste
Non­
Conformance
Reports
and
other
waste
certification
and
analyses
activities
through
the
waste
reassessment
in
accordance
with
4­
H19­
WSRIC­
001,
WSRIC
Characterization
and
Reverification.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
94
4.4
Shipment
Certification
Statements
Each
shipment
of
waste
is
collectively
certified
to
DOT
requirements
using
the
Bill
of
Lading.
Hazardous
waste
shipments
are
collectively
certified
using
the
Uniform
Hazardous
Waste
Manifest.
Certification
statements
are
signed
by
the
TCO
after
all
other
internal
certifications
are
signed
by
the
involved
groups.

Additional
shipping
documents
required
for
the
shipment
of
waste
to
WIPP
include
the
PCTCD,
OPCTCD,
and
the
PATCD.
These
documents
will
be
reviewed,
verified,
and
signed
by
the
TCO.
Refer
to
Section
6
for
additional
information
on
these
documents.

4.5
RFETS
IDCs
Certifiable
to
WIPP
Operations
and
Safety
Criteria
and
TRUPACT­
II
Payload
Control
Criteria
Table
6­
2
provides
a
listing
of
the
RFETS
waste
materials
(
by
IDC
descriptions)
which
have
been
shown
to
be
certifiable
to
the
requirements
listed
in
Sections
2.1
and
2.2
of
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
95
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
96
4.6
Packaging
QA
Program
Plan
The
Packaging
QA
Program
Plan
describes
the
RFETS
QA
Program
for
TRU
Waste
Packaging.
The
QA
Requirements
for
packaging
are
found
in
10
CFR
71,
Subpart
H.
Preparation
guidance
is
found
in
Regulatory
Guide
7.10,
Annex
2
(
NRC
1986)
Quality
Assurance
Programs
Applicable
to
Procurement,
Use,
Maintenance,
and
Repair
of
Packaging
Used
in
Transport
of
Radioactive
Material.
A
Packaging
QA
Program
consistent
with
the
provisions
of
Subpart
H
of
10
CFR
71
is
required
in
order
to
deliver
packaged
licensed
material
to
a
carrier
for
transport.

This
section
describes
how
the
requirements
are
met
for
the
TWCP.
This
section
follows
the
guidance
given
in
Regulatory
Guide
7.10,
Annex
2,
(
NRC
1986)
Quality
Assurance
Programs
Applicable
to
Procurement,
Use,
Maintenance,
and
Repair
of
Packaging
Used
in
Transport
of
Radioactive
Material.
The
section
numbers
and
titles
follow
those
in
Annex
2
beginning
with
Section
4.6.1,
Organization,
which
corresponds
with
Section
2.1,
Organization
in
Annex
2.

4.6.1
Organization
Section
3.1.1.1,
of
this
document,
defines
the
organization
responsible
for
TWCP
activities.
Controls
over
activities
important
to
safety
are
defined
in
accordance
with
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading,
and
implemented
through
Site
infrastructure
QA
documents.
QA
personnel
have
the
responsibility
and
authority
to
stop
unsatisfactory
work
and
delivery
or
installation
of
nonconforming
material
according
to
1­
V10­
ADM­
15.02,
Stop
Work
Action,
and
have
direct
access
to
management
levels
to
ensure
that
QA
procedures
important
to
safety
have
been
accomplished.

Section
3.1.1.1.3
of
this
document
identifies
the
responsibilities
of
the
principal
personnel
for
the
overall
QA
program;
the
TWCP
Site
PM,
who
has
overall
authority
and
responsibility
for
the
TWCP
QA
program;
the
TWCP
Site
PQAO;
the
Material
Stewardship
QA
Manager;
and
the
KH
Quality
Program
Manager.
The
TWMM
is
approved
by
the
TWCP
Site
PM.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
97
4.6.2
Quality
Assurance
Program
4.6.2.1
Scope
of
Quality
Assurance
Program
The
scope
of
the
Packaging
QA
Program
includes
packaging
and
transport
of
55­
gallon
waste
drums
and
SWBs
and
the
receiving,
preparation,
and
loading
of
the
TRUPACT­
II.
Procedures
are
established
and
identified
in
this
plan
which
ensure
that
activities
important
to
safety
are
performed
using
suitable
equipment
and
under
suitable
environmental
conditions.
These
procedures
identify
QA/
QC
responsibilities
for
implementing
activities
important
to
safety.
The
Site
TPM
and
the
TWCP
TIP
are
implemented
to
identify
and
document
training
and
qualification
necessary
for
personnel
to
adequately
perform
their
functions.

4.6.2.2
Applicability
of
Quality
Assurance
Program
CBFO
provides
the
QA
Program
for
the
TRUPACT­
II
packaging.
The
TRUPACTII
has
been
authorized
by
a
Certificate
of
Compliance
per
the
Nuclear
Regulatory
Commission
regulation
10
CFR
71.
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance;
DOE/
WIPP
02­
3184,
CH
Packaging
Operations
Manual;
and
DOE/
WIPP
02­
3185,
CH
Packaging
Maintenance
Manual;
are
followed
in
maintaining
the
TRUPACT­
II
for
use.
Loading
and
preparation
of
the
TRUPACT­
II
is
covered
by
the
program
in
this
section.
Where
it
has
been
determined
that
Packaging
QA
Program
requirements
apply
to
the
loading
and
preparation
of
the
TRUPACT­
II,
controls
are
specifically
identified
relative
to
the
TRUPACT­
II.

The
program
described
here
is
currently
applicable
to
55
gallons
drums,
the
POC
and
SWBs
used
for
shipment
of
TRU
waste
to
the
WIPP.
Receiving
the
TRUPACT­
II
vessels
at
RFETS,
and
loading
and
preparing
the
TRUPACT­
II
for
shipment
is
also
covered
by
the
Packaging
QA
Program.

Items
and
activities
important
to
safety
are
categorized
and
identified
in
accordance
with
PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading.

4.6.3
Design
Control
The
TWCP
complies
with
design
configuration
for
the
POC
(
Reference
DOE/
CAO
Drawing
No.
163­
001)
through
the
application
of
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure.
Refer
to
PRO­
284­
POC­
001,
Pipe
Overpack
Component
Initial
Assembly
Process
for
the
applicable
RFETS
POC
fabrication
drawings.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
98
4.6.4
Procurement
Document
Control
4.6.4.1
Packaging
Procurement
The
procurement
document
control
system
is
defined
in
MAN­
134­
PPM,
Procurement
Program
Manual;
the
KH
Procurement
System
Manual;
and
Engineering
procedures.
The
55­
gallon
drum,
POC,
ten
drum
overpack
(
TDOP),
and
SWB
packages
are
procured
according
to
specifications
that
are
controlled
by
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure;
and
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance.
The
Process
Specification
identifies
the
appropriate
certifications
to
be
provided
by
the
manufacturer
and
provides
the
information
necessary
for
receipt
at
RFETS.

TRUPACT­
II
vessels
are
government­
furnished
equipment
maintained
according
to
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance;
DOE/
WIPP
02­
3184,
CH
Packaging
Operations
Manual;
and
DOE/
WIPP
02­
3185,
CH
Packaging
Maintenance
Manual.
DOE
maintains
the
Certificate
of
Compliance
for
the
TRUPACT­
II
vessels.
RFETS
verifies
the
vessel
number
against
a
list
of
certified
vessels
through
PRO­
T43­
Traffic­
528,
TRUPACT
II
Operations.

4.6.4.2
Replacement
Part
Procurement
Procedure
MAN­
134­
PPM,
Procurement
Program
Manual;
KH
Procurement
System
Manual;
and
procurement
specifications
provide
for
procurement
of
replacement
parts
for
drums,
POCs,
TDOPs,
and
SWBs.

Replacement
parts
for
TRUPACT­
II
vessels
are
not
procured
by
RFETS,
but
are
obtained
according
to
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance.

4.6.4.3
High
Purity
Helium
Procurement
High
purity
helium
used
for
leak
testing
TRUPACT­
II
seals
is
procured
according
to
MAN­
134­
PPM,
Procurement
Program
Manual.
The
vendor
provides
certification
for
product
purity
which
exceeds
the
purity
specified
by
ANSI
N14.5­
1997,
Radioactive
Materials
 
Leakage
Tests
on
Packages
for
Shipment.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
99
4.6.5
Instructions,
Procedures,
and
Drawings
4.6.5.1
Preparation
of
Packaging
for
Use
Waste
generators
package
waste
in
accordance
with
1­
PRO­
079­
WGI­
001,
Waste
Generating,
Characterization,
and
Packaging.
A
WGI
is
then
provided
to
the
waste
generator.
The
WGI
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
provide
instructions
for
the
waste
generator
to
put
the
waste
package
into
use.

TRUPACT­
II
vessels
are
prepared
for
use
following
PRO­
1418­
WO­
TRUOP,
TRUPACT­
II
Operations.

4.6.5.2
Repair,
Rework,
and
Maintenance
The
procedure
PRO­
1406­
SWB,
Standard
Waste
Box
Repair/
Replacement
Operations
provides
controls
for
field
repair
and
replacement
parts
for
SWBs.
No
repair
or
maintenance
of
drums
is
performed.
Drums
and
SWBs
may
be
reworked
if
nonconformances
to
requirements
are
determined
to
exist.
Waste
generation
and
packaging
processes
include
appropriate
inspection
steps
and
hold­
points
that
assure
waste
is
properly
packaged.
Any
deficiencies
identified
in
the
waste
generation
and
packaging
processes
are
documented
on
WNCRs.
WNCRs
on
waste
packages
are
issued
according
to
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances.
Dispositioning
of
nonconformances
assures
packaging
is
reworked
to
meet
the
requirements
of
the
waste
packaging
requirements
in
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure.

No
repair
or
rework
of
TRUPACT­
II
vessels
is
performed.
Maintenance
of
TRUPACT­
II
vessels
is
accomplished
according
to
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance;
and
DOE/
WIPP
02­
3185,
CH
Packaging
Maintenance
Manual.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
100
4.6.5.3
Loading
and
Unloading
Contents
The
documents
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
provide
instructions
for
loading
radioactive
materials
into
the
drum
and
SWB
packaging.

TRUPACT­
II
vessels
are
loaded
in
accordance
with
the
following
procedures:

 
PRO­
1418­
WO­
TRUOP,
TRUPACT­
II
Operations
 
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test
Maintenance
and
calibration
of
TRUPACT­
II
leak
testing
equipment
to
the
guidelines
of
ANSI
N14.5­
1997,
Radioactive
Materials
 
Leakage
Tests
on
Packages
for
Shipment
requirements
is
performed
according
to
equipment
manufacturer's
instructions
and
procedure
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test.

4.6.5.4
Transport
of
Packages
Traffic
and
Transportation
coordinates
the
on­
site
transfer
of
waste
packages.
Requirements
for
assuring
packages
are
properly
marked,
secured
and
transported
are
specified
in
MAN­
T91­
STSM­
001,
Site
Transportation
Safety
Manual
and
PRO­
015­
NMT­
003,
On­
Site
Transfer
Procedure.

Measures
are
included
in
PRO­
T43­
Traffic­
528,
TRUPACT
II
Operations,
to
assure
TRUPACT­
II
vessels
are
in
good
condition,
are
adequately
secured,
properly
sealed,
and
properly
marked.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
101
4.6.6
Document
Control
Controls
to
assure
that
documents
affecting
packaging
are
controlled,
that
the
most
recent
versions
or
revisions
are
available
to
those
persons
using
the
documents,
and
that
changes
are
reviewed
and
approved
are
contained
in
MAN­
001­
SDRM,
Site
Document
Requirements
Manual;
PRO­
1329­
DM­
03,
Site
Document
Control;
and
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents.

As
a
minimum,
that
control
should
be
exercised
over
the
following
documents:

 
QA
and
QC
Manuals
 
Operating
Procedures
 
Maintenance
Procedures
 
Inspection
and
Test
Procedures
 
Loading
and
Unloading
Procedures
 
Packaging
for
Transport
Procedures
 
Repair
Procedures,
and
 
Procurement
Procedures
MAN­
001­
SDRM,
Site
Document
Requirements
Manual,
requires
that
the
8
bulleted
items
listed
above,
as
well
as
other
RFETS
documents,
are
controlled.

PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents,
requires
that
changes
to
items
1­
8
above
are
reviewed
and
approved
by
appropriate
organizations.

PRO­
1329­
DM­
03,
Site
Document
Control,
requires
that
the
8
bulleted
items
listed
above
are
verified,
distributed,
and
that
the
most
recent
version
or
revision
is
available
to
those
persons
responsible
for
using
those
documents.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
102
4.6.7
Control
of
Purchased
Material,
Equipment,
and
Services
The
following
documents
provide
direction
for
the
control
of
purchased
material,
equipment,
and
services:

 
MAN­
134­
PPM,
Procurement
Program
Manual
 
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance
 
PRO­
1306­
ARIBA,
Ariba
Buyer
Users
Guide
 
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure
 
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification
TRUPACT­
II
vessels
are
not
purchased
by
RFETS.

For
details
regarding
how
these
documents
address
design,
fabrication,
and
quality
assurance
requirements
for
procurement
of
items
and
services
see
Section
3.2.3.2.4,
Procurement
Document
Control;
Section
3.2.3.2.5,
Purchasing;
and
Section
3.2.3.2.7,
Control
of
Purchased
Items
and
Services.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
103
4.6.8
Identification
and
Control
of
Materials,
Parts,
and
Components
Identification
and/
or
traceability
of
TRU
waste
packages
(
drums
and
SWBs)
is
ensured
through
several
measures.
Waste
packages
are
uniquely
identified
from
the
initial
receipt
up
to
and
including
use,
packaging,
storage,
and
transportation
to
the
WIPP.

The
key
document
that
records
traceability
information
is
the
W/
RT
(
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions).
As
described
in
Section
4.3.1,
either
an
electronic
W/
RT
or
a
manual
W/
RT
may
be
used
for
packaging
activities.
The
WR/
T
data
collection
form
is
generated
for
each
waste
package
and
documents
the
employee
numbers
of
the
waste
generators,
waste
verifiers,
Waste
Inspectors,
and
test
technicians
directly
involved
with
processing
the
waste
package.
The
form
also
documents
inspection
and
test
results,
waste
generation
source
(
process
number),
hazardous
constituent
number
(
if
applicable),
and
package
serial
number.
Waste
Management
 
Technical
Operations
personnel
control
the
development
of
waste
identification
and
characterization
information
through
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging.

Refer
to
Section
3.2.1.3
of
this
document
for
further
information
on
the
identification
and
control
of
materials,
parts,
and
components.

4.6.9
Control
of
Special
Processes
The
TRUPACT­
II
verification
leak
check
is
the
only
special
process
in
the
Packaging
QA
Program.
Procedure
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test,
ensure
that:
1)
Procedures,
equipment,
and
personnel
are
qualified
in
accordance
with
applicable
codes,
standards,
and
specifications;
2)
Operations
are
performed
by
qualified
personnel
and
accomplished
in
accordance
with
written
process
sheets
with
recorded
evidence
of
verification;
and
3)
Qualification
records
of
procedures,
equipment,
and
personnel
are
established,
filed,
and
kept
current.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
104
4.6.10
Inspection
Control
4.6.10.1
Receipt
Inspection
Receipt
Inspection
is
performed
to
assure
packaging
meets
procurement
specifications
in
accordance
with
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification.
Nonconformances
are
documented
according
to
procedure
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items.

TRUPACT­
II
vessels
are
inspected
when
received
on­
site
according
to
PRO­
T43­
Traffic­
528,
TRUPACT
II
Operations.

4.6.10.2
Maintenance
Inspections
of
packaging
during
use
and
prior
to
shipment
is
performed
by
Waste
Inspectors
according
to
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection.

TRUPACT­
II
vessels
maintenance
inspections
are
performed
in
accordance
with
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance;
and
DOE/
WIPP
02­
3185,
CH
Packaging
Maintenance
Manual.

4.6.10.3
Final
Inspection
Final
inspection
of
the
packaging
is
performed
according
to
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection,
and
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
Also
see
Section
6.6
of
this
document
for
controls
implemented
for
the
final
inspection
and
certification
of
packaging
and
the
TRUPACT­
II.

Final
inspection
measures
for
TRUPACT­
II
vessels
are
included
in
PRO­
T95­
OSTP­
002,
Off­
Site
Transportation
Procedure;
PRO­
T13­
Traffic­
306,
Labeling
and
Marking
TRUPACT
Packages;
and
PRO­
T43­
Traffic­
528,
TRUPACT
II
Operations.
The
above
procedures
ensure
inspections
verify
the
following
have
been
complied
with:

 
All
shipping
papers
are
properly
completed,

 
Packages
are
legibly,
conspicuously
and
durably
marked
as
required
by
DOT
regulations,

All
inspections
are
performed
by
personnel
who
are
independent
from
the
individual
performing
the
work
being
inspected.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
105
4.6.11
Test
Control
The
TRUPACT­
II
verification
leak
check
is
the
only
testing
conducted
as
part
of
the
Packaging
QA
Program.
Testing
is
controlled
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test.
See
Sections
3.9.6.2
and
4.6.9
for
additional
details.

4.6.12
Control
of
Measuring
and
Test
Equipment
Measuring
and
test
equipment
(
M&
TE)
is
calibrated,
adjusted,
and
maintained
according
to
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management.
Measuring
and
test
equipment
are
labeled
to
assure
calibration
at
prescribed
intervals
or
prior
to
use.
Calibration
records
are
maintained
to
identify
historical
information
and
assure
traceability
to
nationally
recognized
standards.
Procedure
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management,
describes
the
action
to
take
to
validate
previous
inspection/
test
results
if
M&
TE
is
found
to
be
out
of
calibration.
See
Section
3.2.4.3.1
of
this
document
for
additional
details
and
controls
related
to
M&
TE.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
106
4.6.13
Handling,
Storage,
and
Shipping
4.6.13.1
Handling
and
Storage
Measures
to
ensure
that
special
handling
and
lifting
equipment
is
used
are
established
through
the
MAN­
072­
OS&
IH
PM,
Occupational
Safety
&
Industrial
Hygiene
Program
Manual,
Chapter
11:
Powered
Industrial
Trucks
and
Chapter
12:
Hoisting
and
Rigging.

Special
handling
or
storage
provisions
for
packaging
(
e.
g.,
shock
absorbers,
tags,
or
markings
to
adequately
protect
and
identify
critical
components)
are
used
for
the
TRUPACT­
II
vessels
according
to
instructions
in
the
TRUPACT­
II
loading
procedures
(
PRO­
1418­
WO­
TRUOP,
TRUPACT­
II
Operations;
PRO­
1419­
WOLKTST
TRUPACT­
II
Shipping
Leak
Test;
and
PRO­
1411­
WO­
WASTE,
Waste
Receiving,
Transfer,
&
Handling).

On­
site
sample
transfer
is
discussed
in
the
TWCP
QAPjP,
Section
B1­
5.

4.6.13.2
Preparation
for
Release
and
Shipment
TRU
waste
packaging
is
inspected
by
Traffic
Management
prior
to
shipment
according
to
PRO­
T95­
OSTP­
002,
Off­
Site
Transportation
Procedure;
and
PRO­
T13­
Traffic­
306,
Labeling
and
Marking
TRUPACT
Packages.

Inspection
of
the
TRUPACT­
II
for
certification
and
shipment
is
performed
according
to
PRO­
T95­
OSTP­
002,
Off­
Site
Transportation
Procedure;
PRO­
T43­
Traffic­
528,
TRUPACT
II
Operations;
and
PRO­
T30­
Traffic­
515,
Preparation
and
Retention
of
Hazardous
Materials
Shipping
Documents.

4.6.14
Inspection,
Test,
and
Operating
Status
The
measure
for
ensuring
the
inspection
and
operating
status
of
drum
and
SWB
waste
packaging
is
the
W/
RT.
Instructions
for
preparing
the
W/
RT
are
provided
in
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions.

The
operating
status
of
the
TRUPACT­
II
vessels
is
identified
through
the
use
of
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance;
DOE/
WIPP
02­
3184,
CH
Packaging
Operations
Manual;
and
DOE/
WIPP
02­
3185,
CH
Packaging
Maintenance
Manual.

See
Section
3.2.4
for
additional
details.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
107
4.6.15
Control
of
Nonconforming
Materials,
Parts,
or
Components
Controls
for
the
identification,
segregation,
disposition,
and
evaluation
of
nonconforming
packaging
are
provided
in
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items;
and
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances.
See
Section
3.1.3.2.3
for
additional
detail
of
the
control
of
the
nonconformance
process.

4.6.16
Corrective
Action
4.6.16.1
Reporting
Conditions
adverse
to
waste
acceptability
are
identified
promptly
through
inspections,
tests,
surveillances,
and
audits
and
corrected
as
soon
as
practical.
Corrective
actions
are
initiated,
documented
and
tracked
in
accordance
with
3­
X31­
CAP­
001,
Corrective
Action
Process.

4.6.16.2
Closeout
Closeout
to
ensure
that
corrective
actions
have
been
implemented
is
performed
according
to
instructions
in
3­
X31­
CAP­
001,
Corrective
Action
Process.
The
individuals
responsible
for
closeout
are
identified
in
this
procedure.

See
Section
3.1.3.2.4
of
this
document
for
additional
detail
of
the
corrective
action
process.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
108
4.6.17
Quality
Assurance
Records
4.6.17.1
General
Records
are
maintained
and
transmitted
to
the
TWCP
files
according
to
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center.
In
addition
to
the
following,
Section
3.1.5
of
this
document
provides
more
additional
description
of
Quality
Assurance
Records.

4.6.17.2
Generating
Records
Measures
to
ensure
that
documents
designated
as
QA
records
are
legible
and
completed
to
reflect
the
work
accomplished
and
are
processed
quickly
to
avoid
unnecessary
delay
when
the
record
is
needed
have
been
established.
These
measures
are
contained
in
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center,
and
the
RIDS.

4.6.17.3
Receipt,
Retrieval,
and
Disposition
of
Records
A
receipt
system
is
established
in
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center.
Measures
to
ensure
records
maintained
are
identifiable
and
retrieval
and
are
not
disposed
of
until
prescribed
conditions
are
satisfied
are
contained
in
the
RIDS
and
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing.

4.6.17.4
Storage,
Preservation,
and
Safekeeping
Measures
for
storage,
protection,
and
safekeeping
of
records
are
provided
in
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center;
and
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
109
4.6.18
Audits
An
independent
assessment
(
or
a
series
of
smaller
independent
assessments)
of
the
TWCP
is
performed
annually
by
MS
Quality
Assurance.
The
scope
of
the
audit
includes
the
Packaging
QA
Program
requirements.
Procedure
3­
B52­
IA­
003,
Conduct
of
Independent
Assessment
Activities,
is
used
to
plan
and
perform
the
assessment
and
report
the
audit
results.
Procedure
3­
X31­
CAP­
001,
Corrective
Action
Process,
defines
the
site
level
process
for
documenting,
characterizing
and
tracking
corrective
actions
identified
during
the
assessment.
Additional
description
of
the
audit
process
is
provided
in
Sections
3.3.2
and
3.3.2.4
of
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
110
5.0
RFETS
CERTIFICATION
TO
WIPP
WASTE
ACCEPTANCE
CRITERIA
The
requirements
and
associated
criteria
for
acceptance
of
defense
TRU
waste
at
WIPP
for
disposal
(
the
WIPP­
WAC
Section
3)
and
the
method(
s)
of
compliance
employed
at
RFETS
to
meet
these
criteria
are
specified
in
the
following
subsections.
The
acceptance
criteria
of
the
WIPP­
WAC
describe
the
controlling
(
i.
e.,
the
most
restrictive)
requirements
to
be
used
by
RFETS
in
preparing
waste
for
transportation
to
and
disposal
at
the
WIPP.
In
some
instances
the
acceptance
criteria
and
regulatory
requirements
are
synonymous.
The
WIPP­
WAC
requirements
are
derived
from
several
source
documents:
the
WIPP
SAR,
the
TRUPACT­
II
Certificate
of
Compliance,
the
WIPP
Land
Withdrawal
Act,
the
WIPP
Hazardous
Waste
Facility
Permit,
and
the
Criteria
for
the
Certification
and
Re­
Certification
of
the
Waste
Isolation
Pilot
Plant's
Compliance
with
the
40
CFR
Part
191
 
Disposal
Regulations.
Definitions
of
terms
used
in
this
document
are
included
as
Section
9.1.

5.1
General
All
of
the
requirements
and
associated
criteria
from
the
WIPP­
WAC
are
addressed
in
this
section.
However,
some
of
these
criteria
are
not
limiting
when
the
restrictions
for
TRUPACT­
II
payload
control
and
the
WIPP
Waste
Acceptance
Criteria
are
combined.
The
TRUPACT­
II
payload
criteria
that
are
defined
in
the
TRAMPAC
parallel
the
WIPP­
WAC
for
many
of
the
restrictions.
In
the
cases
where
the
WIPPWAC
and
the
TRAMPAC
have
identified
equivalent
criteria
or
where
the
TRAMPAC
criteria
are
more
restrictive,
Section
6.0
of
this
TWMM,
RFETS
TRUPACT­
II
Payload
Compliance
Plan,
is
referenced
to
demonstrate
compliance.

The
WIPP
Waste
Acceptance
Requirements
and
Criteria
(
WIPP­
WAC,
Section
3)
are
organized
into
five
main
categories
in
this
document.
These
categories
(
and
their
corresponding
section
numbers)
include
the
following:

 
Container
Properties
(
Section
5.2);

 
Radiological
Properties
(
Section
5.3);

 
Physical
Properties
(
Section
5.4);

 
Chemical
Properties
(
Section
5.5);
and
 
Data
Packages
(
Section
5.6);
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
111
5.1
General
(
continued)

Within
each
of
these
categories
the
specific
requirement(
s)
is
quoted
and
the
method(
s)
of
compliance
documented.
Only
CH­
TRU
wastes
from
a
properly
characterized
and
approved
waste
stream
may
be
certified
as
meeting
the
requirements
and
associated
criteria
contained
in
the
WIPP­
WAC.
Any
waste
payload
package
from
a
waste
stream
that
has
not
been
preceded
by
an
appropriate
certified
WSPF
is
not
acceptable
for
disposal
at
WIPP.

RFETS
plans
and
procedures,
as
referenced
in
this
document,
contain
details
of
the
processes,
controls,
techniques,
tests,
and
other
actions
to
be
applied
to
each
TRU
payload
package,
waste
stream,
and
shipment.
Methods
of
compliance
with
each
requirement
are
described
and
the
specific
procedure
cited.
These
methods
of
compliance
include
procedural
controls,
administrative
controls,
and
waste
generation
process
controls.
The
QA
requirements
applicable
to
waste
characterization,
certification,
and
transportation
are
addressed
in
the
TWCP
QAPjP,
and
Sections
3,
4.6,
and
Appendix
4
of
this
TWMM.
The
data
resulting
from
the
implementation
of
the
plans
and
procedures
will
form
the
basis
for
verifying
that
CH­
TRU
waste
to
be
sent
to
WIPP
is
certified
to
meet
the
WIPP­
WAC
by
the
responsible
site
certifying
official.

RFETS
shall
transmit
required
characterization,
certification,
and
shipping
data
to
WIPP
using
the
WWIS.
The
WWIS
is
an
electronic
database
equipped
with
edit/
limit
checks
to
ensure
that
the
data
representing
the
waste
payload
packages
are
in
compliance
with
the
WIPP­
WAC.
Before
shipping
TRU
waste
payload
packages
from
a
WIPP­
accepted
waste
stream,
RFETS
shall
transmit
the
required
waste
characterization,
certification,
and
shipping
data
via
WWIS
to
WIPP.
RFETS
may
periodically
be
requested
to
transmit
payload
package
radiography
reports
or
other
data
to
WIPP.
WIPP
will
not
accept
any
waste
package
shipments
for
disposal
if
the
waste
payload
package
information
has
not
been
correctly
submitted
and
approved
for
shipment
by
the
WWIS
Data
Administrator.
The
WWIS
User's
Manual
provides
the
information
needed
by
TRU
waste
sites
to
perform
tasks
associated
with
transmittal
of
the
payload
package's
characterization,
certification,
and
shipment
information
to
WIPP.

RFETS
will
be
notified
of
revisions
to
external
regulatory
requirements
by
CBFO.
Revisions
of
requirements
in
referenced
documents
not
controlled
by
the
DOE
(
but
by,
for
example,
the
EPA,
NRC,
or
NMED)
shall
have
precedence
over
the
values
specified
in
the
WIPP­
WAC
if
they
are
more
restrictive.
These
changes
will
be
incorporated
in
future
revisions
of
the
WIPP­
WAC.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
112
5.1.1
DOE
Operations
and
Safety
Requirements
The
WIPP
SAR
addresses
CH­
TRU
waste
handling
and
emplacement
operations.
The
waste
accepted
for
emplacement
in
the
WIPP
must
conform
to
the
SAR
and
the
associated
technical
safety
requirements.
The
WIPP
SAR
documents
the
safety
analyses
that
develop
and
evaluate
the
adequacy
of
the
WIPP
safety
bases
necessary
to
ensure
the
safety
of
workers,
the
public,
and
the
environment
from
the
hazards
posed
by
WIPP
waste
receiving,
handling,
and
emplacement
operations.
The
WIPP
SAR
establishes
and
evaluates
the
adequacy
of
the
safety
bases
in
response
to
WIPP
normal
and
abnormal
operations
and
postulated
accident
conditions.
In
addition
to
the
requirements
found
in
the
WIPP
SAR,
requirements
from
best
practices
and
operational
experience
are
also
listed
in
this
section.

5.1.1.1
Methods
of
Compliance
Compliance
with
the
applicable
Operations
and
Safety
Requirements
are
described
throughout
Section
5
of
this
document.

5.1.2
NRC
Transportation
Safety
Requirements
for
the
TRUPACT­
II
Acceptable
methods
for
payload
compliance
are
defined
in
the
TRAMPAC.
For
shipments
to
WIPP,
RFETS
must
prepare
a
site­
specific
TRAMPAC
describing
how
it
will
ensure
compliance
with
each
payload
parameter.
This
technical
plan
shall
contain
sufficient
detail
to
allow
reviewers
to
adequately
understand
and
evaluate
the
compliance
methodology
for
each
payload
parameter.

RFETS
shall
have
a
packaging
QA
program
that
defines
the
QA
activities
that
apply
to
the
use
of
NRC­
approved
transportation
packagings
in
accordance
with
10
CFR
Part
71,
subpart
H.

5.1.2.1
Methods
of
Compliance
The
RFETS
TRAMPAC
is
defined
in
Section
6.0
of
this
document.
The
corresponding
packaging
QA
program
is
described
in
Section
4.6
of
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
113
5.1.3
NMED
Hazardous
Waste
Facility
Permit
Requirements
TRU
waste
is
classified
as
TRU
mixed
waste
if
it
contains
hazardous
constituents
regulated
under
RCRA.
Only
TRU
mixed
waste
and
TRU
waste
that
have
been
characterized
in
accordance
with
the
WIPP­
WAP
and
that
meet
the
TSDF
waste
acceptance
criteria
as
presented
in
permit
conditions
II.
C.
3.
a
through
II.
C.
3.
k
of
the
WIPP
Hazardous
Waste
Facility
Permit
will
be
shipped
to
WIPP
for
disposal
in
the
permitted
underground
hazardous
waste
disposal
unit.

Prior
to
disposal,
RFETS
shall
develop
and
implement
a
QAPjP
that
addresses
all
the
applicable
requirements
specified
in
the
WIPP­
WAP.
In
accordance
with
attachment
B5
of
the
WIPP­
WAP,
the
QAPjP
will
include
the
qualitative
or
quantitative
criteria
for
making
a
hazardous
waste
determination.
RFETS
QAPjP
will
be
reviewed
and
approved
by
the
CBFO.

5.1.3.1
Methods
of
Compliance
The
TWCP
QAPjP
describes
compliance
with
the
WIPP­
WAP.
The
TWCP
QAPjP
is
approved
by
CBFO.

5.1.4
EPA
Compliance
Certification
Decision
Requirements
Title
40
CFR
Part
194.24(
c)
states
that
the
DOE
shall
specify
the
limiting
values
for
waste
components
to
be
emplaced
in
the
repository.
Appendix
WCL
(
Waste
Component
Limits)
of
the
Compliance
Certification
Application
(
CCA)
identifies
the
repository
limits
for
several
waste
components
including
free
water,
metals;
and
cellulose,
plastic,
and
rubber
(
CPR).
Although
the
CCA
does
not
specify
limiting
values
for
the
activities
and
masses
of
specific
radionuclides,
Table
4­
6
of
the
CCA
identifies
the
listed
values
for
a
number
of
radionuclides
that
are
considered
in
the
Performance
Assessment.
To
demonstrate
that
the
cumulative
total
activities
of
the
specified
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
are
consistent
with
the
levels
used
for
the
Performance
Assessment
and
the
compliance
certification
decision,
reporting
and
tracking
of
the
specified
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
is
necessary,
as
required
by
Table
4­
10
of
the
CCA.
TRU
waste
payload
packages
shall
contain
more
than
100
nanocuries
per
gram
of
waste
(
nCi/
g)
of
alpha­
emitting
TRU
isotopes
with
half­
lives
greater
than
20
years,
as
specified
in
Section
3.3.3
of
the
WIPP­
WAC.

The
repository
limit
for
free
water
is
a
maximum
of
1684
m3
and
is
met
by
the
residual
liquid
criterion
specified
in
Section
3.4.1
of
the
WIPP­
WAC.
TRANSURANIC
(
TRU)
WASTE
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008­
WM­
001
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MANUAL
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7
02/
12/
2004
PAGE
114
5.1.4
EPA
Compliance
Certification
Decision
Requirements
(
continued)

The
limits
for
metals
are
a
minimum
of
2
×
107
kg
for
ferrous
metals
and
2
×
103
kg
for
nonferrous
metals.
These
limits
will
be
met
in
the
total
repository
inventory
by
the
metals
that
constitute
the
waste
payload
packages
alone;
thus,
WIPP
tracks
and
reports
the
number
and
type
of
payload
packages
emplaced
in
the
repository
as
reported
in
the
WWIS
by
the
sites
(
see
WIPP­
WAC
Section
3.2.1).

The
repository
limit
for
CPR
is
a
maximum
of
2
×
107
kg.
RFETS
estimates
the
CPR
weights
and
reports
these
estimates
in
the
WWIS
on
a
payload
package
basis
as
required
by
WIPP­
WAC
Section
3.6.1.

RFETS
must
quantify
and
report
the
activities
and
masses
of
specific
radionuclides
for
the
purpose
of
tracking
the
total
radionuclide
inventory
of
the
repository
as
specified
in
Section
3.3.1
of
the
WIPP­
WAC.
The
presence
or
absence
of
these
specific
radionuclides
is
determined
from
AK,
radioassay,
or
both
in
accordance
with
Appendix
A
of
the
WIPP­
WAC.
The
results
of
this
determination
are
reported
in
the
WWIS
on
a
payload
package
basis.

5.1.4.1
Methods
of
Compliance.

Site
compliance
with
free
liquid
requirements
is
discussed
in
Section
5.4.1
of
this
document.
The
information
necessary
for
compliance
with
the
metals
limit
is
provided
as
described
in
Section
5.2.1
of
this
document.
The
weights
of
cellulose,
plastic,
and
rubber
(
CRP)
are
estimated
during
the
characterization
processes
(
RTR
or
Visual
Examination)
described
in
the
TWCP
QAPjP.
These
weights
are
reported
to
the
WWIS
through
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification;
and
4­
K47­
WEM­
WP1210,
WEMS
Offsite
Shipping
Module.
The
quantification
and
reporting
of
radionuclides
is
performed
as
described
in
Section
5.3.1
of
this
document.

5.1.5
Land
Withdrawal
Act
Requirements
The
term
"
WIPP"
means
the
Waste
Isolation
Pilot
Plant
project
authorized
under
Section
213
of
the
Department
of
Energy
National
Security
and
Military
Applications
of
Nuclear
Energy
Authorization
Act
of
1980
(
Pub.
L.
96­
164;
93
Stat.
1259­
1265)
to
demonstrate
the
safe
disposal
of
radioactive
waste
materials
generated
by
atomic
energy
defense
activities.
Hence,
by
law,
WIPP
can
accept
only
radioactive
waste
generated
by
atomic
energy
defense
activities
of
the
United
States.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
115
5.1.5
Land
Withdrawal
Act
Requirements
(
continued)

The
DOE
and
its
predecessor
agencies
were
engaged
in
a
broad
range
of
activities
that
fall
under
the
heading
of
atomic
energy
defense
activities.
A
TRU
waste
is
eligible
for
disposal
at
WIPP
if
it
has
been
generated
in
whole
or
in
part
by
one
or
more
of
the
following
functions:

 
Naval
reactors
development
 
Weapons
activities,
including
defense
inertial
confinement
fusion
 
Verification
and
control
technology
 
Defense
nuclear
materials
productions
 
Defense
nuclear
waste
and
materials
by­
products
management
 
Defense
nuclear
materials
security
and
safeguards
and
security
investigations
 
Defense
research
and
development
Using
AK,
RFETS
determines
that
each
waste
stream
to
be
disposed
of
at
WIPP
is
"
defense"
TRU
waste.

High­
level
radioactive
waste
or
spent
nuclear
fuel
shall
neither
be
transported,
emplaced,
nor
disposed
of
at
WIPP.
Also,
no
transuranic
waste
may
be
transported
by
or
for
the
DOE
to
or
from
WIPP,
except
in
packages
(
1)
the
design
of
which
has
been
certified
by
the
NRC,
and
(
2)
that
have
been
determined
by
the
NRC
to
satisfy
its
quality
assurance
requirements.

5.1.5.1
Methods
of
Compliance
The
RFETS'
TRU
waste
was
generated
by
Atomic
Energy
defense
activities
only.
Using
AK,
RFETS
determined
that
each
waste
stream
to
be
disposed
of
at
WIPP
is
defense
waste.
This
is
documented
in
an
auditable
record
and
summarized
in
RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information.
Furthermore,
based
on
review
of
AK
information,
there
is
no
historical
evidence
or
record
of
high­
level
waste
or
spent
nuclear
fuel
ever
being
handled
at
RFETS.
RFETS
did
not
and
does
not
generate
or
possess
any
high­
level
waste
or
spent
nuclear
fuel.

The
RFETS
TRAMPAC
is
defined
in
Section
6.0
of
this
document.
The
corresponding
packaging
QA
program
is
described
in
Section
4.6
of
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
116
5.2
Container
Properties
5.2.1
Description
Acceptance
Criterion.
Each
payload
package
shall
be
assigned
to
a
payload
shipping
category.
Authorized
payload
packages
include:

 
55­
gallon
drums
(
either
direct
loaded
or
containing
a
POC)

 
SWBs
(
either
direct
loaded,
or
containing
up
to
four
direct
loaded
55­
gallon
drums,
or
containing
one
bin)

 
TDOPs
(
either
containing
up
to
ten
direct
loaded
55­
gallon
drums,
six
85­
gallon
drum
overpacks,
or
one
SWB)

Payload
packages
shall
meet
U.
S.
Department
of
Transportation
(
DOT)
Specification
7A,
Type
A,
packaging
requirements.
Payload
packages
must
be
made
of
steel
and
be
in
good
and
unimpaired
condition
prior
to
shipment
from
RFETS.
To
demonstrate
compliance
with
the
requirement
that
payload
packages
be
in
good
and
unimpaired
condition,
the
exterior
of
all
payload
packages
shall
undergo
100%
visual
examination
prior
to
loading
into
a
TRUPACT­
II.
The
results
of
this
visual
examination
shall
be
documented
using
the
payload
package
integrity
checklist
contained
in
Appendix
3.
A
payload
package
in
good
and
unimpaired
condition
1)
does
not
have
significant
rusting,
2)
is
of
sound
structural
integrity,
and,
3)
does
not
leak.
Significant
rusting
is
a
readily
observable
loss
of
metal
due
to
oxidation
(
e.
g.,
flaking,
bubbling,
or
pitting)
that
causes
degradation
of
the
payload
package's
structural
integrity.
Rusting
that
causes
discoloration
of
the
payload
package
surface
or
consists
of
minor
flaking
is
not
considered
significant.
A
payload
package
is
not
of
sound
structural
integrity
if
it
has
breaches
or
significant
denting/
deformation.
Breaching
is
defined
as
a
penetration
in
the
payload
package
that
exposes
the
internals
of
the
packaging.
Significant
denting/
deformation
is
defined
as
damage
to
the
payload
package
that
results
in
creasing,
cracking,
or
gouging
of
the
metal,
or
damage
that
affects
payload
package
closure.
Dents
or
deformations
that
do
not
result
in
creasing,
cracking,
or
gouging
or
affect
payload
package
closure
are
not
considered
significant.
RFETS
will
report
to
the
WWIS
the
number
and
types
of
payload
packages
planned
for
shipment
to
the
WIPP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
117
5.2.1.1
Methods
of
Compliance
See
Section
6.5.1
for
description
of
compliance
with
shipping
category
requirements.

Per
document
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
only
55­
gallon
drums
(
direct
fill
or
containing
a
POC)
or
SWBs
are
approved
TRU
waste
packages
for
use
at
the
site.
Both
of
these
packages
are
composed
of
steel
and
are
non­
combustible.

Procedure
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
and
applicable
WGIs,
that
are
prepared
in
accordance
with
procedure
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging,
specify
packaging
instructions
that
ensure
that
packagings
used
to
package
transuranic
waste
are
Specification
7A,
Type
A
packages.

Procedure
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection,
provides
instructions
for
the
performance
of
a
final
inspection
of
each
payload
package
prior
to
certification
and
shipment
that
ensures
that
payload
packages
are
in
good
condition.
The
Container
Integrity
Checklist
is
used
when
examining
the
payload
package
condition.

RFETS
reports
the
number
and
type
of
waste
packages
in
the
WWIS.
Inspections,
tests,
or
other
certifications
are
conducted
at
the
manufacturer
to
assure
drums
and
SWBs
meet
RFETS
specifications.
See
Section
6.2.1.1
for
additional
information
related
to
compliance
of
payload
packages
to
the
requirements
of
the
TRUPACT­
II
SAR.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
118
5.2.2
Weight
Limits
and
Center
of
Gravity
Acceptance
Criterion.
Each
payload
package,
payload
assembly,
and
loaded
TRUPACT­
II
shall
comply
with
the
weight
limits
shown
in
Table
5­
2.
Weight
calculations
for
the
payload
assembly
must
include
the
measurement
error.
The
total
weight
of
the
top
seven
55­
gallon
drums
or
SWB
of
the
payload
assembly
shall
be
less
than
or
equal
to
the
total
weight
of
the
bottom
seven
55­
gallon
drums
or
SWB,
respectively.
The
total
weight
of
the
top
five
55­
gallon
drums
or
three
85­
gallon
drum
overpacks
in
a
TDOP
shall
be
less
than
or
equal
to
the
total
weight
of
the
bottom
five
55­
gallon
drums
or
three
85­
gallon
drum
overpacks,
respectively.
Calibrations
of
the
scales
used
to
make
these
weight
determinations
shall
be
in
accordance
with
the
National
Institute
of
Standards
and
Technology
(
NIST)
Handbook
44
or
an
equivalent
standard.

5.2.2.1
Methods
of
Compliance
NOTE:
The
RFETS
maximum
weight
of
a
55­
gallon
drum
is
limited
to
800
lbs.
per
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual.

Methods
of
compliance
are
described
in
Section
6.2.3.2.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
119
5.2.3
Assembly
Configurations
Acceptance
Criterion.
Payload
package
assembly
configurations
authorized
for
shipment
in
the
TRUPACT­
II
shall
be
in
accordance
with
Table
5­
1.

Although
85­
gallon
drum
overpacks
are
acceptable
at
WIPP,
they
are
not
authorized
for
transport
in
a
TRUPACT­
II
as
individual
payload
packages.

5.2.3.1
Methods
of
Compliance
Methods
of
compliance
are
described
in
Section
6.2.1.2.

5.2.4
Removable
Surface
Contamination
Acceptance
Criterion.
Removable
surface
contamination
on
CH­
TRU
waste
payload
packages,
payload
assemblies,
and
packagings
shall
not
exceed
20
dpm/
100
cm2
alpha
and
200
dpm/
100
cm2
beta­
gamma.
The
fixing
of
surface
contamination
to
meet
these
criteria
is
not
allowed
by
WIPP
in
accordance
with
best
management
practices
for
ensuring
worker
radiation
dose
as
low
as
reasonable
achievable.

5.2.4.1
Methods
of
Compliance
The
documents
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging;
and
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions,
include
steps
for
completing
the
W/
RT
which
instructs
the
RCT
to
complete
the
signature
block
of
the
form
thereby
assuring
that
the
removable
alpha
surface
contamination
is
<
20
dpm/
100
cm2.
Payload
packages
and
assemblies
are
surveyed
for
compliance
with
the
removable
surface
contamination
criteria
prior
to
shipment
in
accordance
with
applicable
Radiological
Safety
Practices
(
RSP)
procedures
and
instructions.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
120
5.2.5
Identification/
Labeling
Acceptance
Criterion.
Each
payload
package
shall
be
labeled
with
a
unique
package
identification
number
using
bar
code
labels
permanently
attached
in
conspicuous
locations.
The
payload
package
identification
number
shall
be
in
medium
to
low
density
Code
39
bar
code
symbology
as
required
by
American
National
Standards
Institute
(
ANSI)
standard
ANSI/
AIM
BC1­
1995
in
characters
at
least
one­
inch
high
and
alphanumeric
characters
at
least
one­
half
inch
high.
In
the
case
of
55­
gallon
drums,
the
bar
code
identification
labels
shall
be
placed
at
three
locations
approximately
120
degrees
apart
so
that
at
least
one
label
is
clearly
visible
when
the
drums
are
assembled
into
a
seven­
pack
(
i.
e.,
a
label
must
be
visible
after
slip
sheets
and
wrapping
are
applied).
In
the
case
of
SWBs,
bar
code
labels
are
required
on
the
flat
sides
of
the
SWBs.
For
TDOPs,
a
minimum
of
one
bar
code
is
required.

Payload
packages
shall
be
marked
"
Caution
Radioactive
Material"
using
a
yellow
and
magenta
label
as
specified
in
10
CFR
Part
835.
Those
payload
packages
whose
contents
are
also
RCRA
regulated
(
mixed­
TRU)
shall
be
additionally
marked
"
Hazardous
Waste"
as
specified
in
40
CFR
Part
262.32.

If
an
empty
55­
gallon
drum
is
used
as
dunnage
to
complete
a
payload
configuration,
the
dunnage
package
shall
be
labeled
with
the
following
information:

 
Unique
package
identification
number
 
"
EMPTY"
or
"
DUNNAGE"

If
a
seven­
pack
of
only
dunnage
55­
gallon
drums
or
a
dunnage
SWB
is
used
in
the
TRUPACT­
II,
the
package(
s)
shall
be
labeled
only
"
EMPTY"
or
"
DUNNAGE."
The
unique
package
identification
number
label
is
not
required
for
a
seven­
pack
of
dunnage,
55­
gallon
drums,
or
a
dunnage
SWB.

5.2.5.1
Methods
of
Compliance
Payload
package
identification
and
labeling
is
performed
in
accordance
with
procedure
PRO­
T13­
Traffic­
306,
Labeling
and
Marking
TRUPACT
Packages.
This
procedure
specifies
instructions
that
ensure
payload
packages
comply
with
the
requirements
for
payload
package
identification
and
labeling.
Refer
to
Section
6.2.4.2
for
additional
information
on
compliance
to
the
requirements
for
payload
package
identification/
labeling.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
121
5.2.6
Dunnage
Acceptance
Criterion.
RFETS
shall
use
empty
55­
gallon
drums
or
a
SWB
as
dunnage
to
complete
a
payload
configuration
if
too
few
payload
packages
are
available
that
meet
transportation
requirements.
The
dunnage
package(
s)
must
meet
the
specifications
of
Appendix
2.1
of
the
TRAMPAC
with
the
exception
that
dunnage
packages
shall
have
open
vent
ports
(
i.
e.,
not
filtered
or
plugged).

To
maximize
the
efficiency
of
disposal
operations
at
the
WIPP,
the
use
of
dunnage
drums
should
be
minimized.
In
the
event
the
use
of
dunnage
drums
cannot
be
avoided,
the
preferred
practice
for
maximizing
the
efficiency
of
waste
handling
and
the
utilization
of
disposal
room
capacity
is
to
ship
them
in
assemblies
(
i.
e.,
a
sevenpack
assembly
of
55­
gallon
drums).
The
use
of
dunnage
drums
is
reviewed
and
approved
concurrently
with
the
review
and
approval
of
shipment
assemblies
by
the
WWIS
Data
Administrator
on
a
case­
by­
case
basis.

5.2.6.1
Methods
of
Compliance
Dunnage
packages
consist
of
55­
gallon
drums
and
SWBs
that
are
inspected
to
verify
they
meet
the
requirements
as
described
in
Section
6.2.2.2.
Instructions
specified
in
procedure
DOE/
WIPP
02­
3183,
CH
Packaging
Program
Guidance,
ensure
dunnage
drums
or
SWBs
have
open
vent
ports.
Refer
to
Sections
6.2.2.2
and
6.2.4.2
for
additional
information
on
compliance
with
the
dunnage
requirements.

5.2.7
Filter
Vents
Acceptance
Criterion.
Payload
packages
that
have
been
stored
in
an
unvented
condition
(
i.
e.,
no
filter
and/
or
unpunctured
liner)
shall
be
aspirated
for
a
specific
length
of
time
as
described
in
the
TRAMPAC
to
ensure
equilibration
of
any
gases
that
may
have
accumulated
in
the
closed
payload
package.

Each
payload
package
shall
have
one
or
more
filter
vents
that
meet
the
specifications
of
Appendix
2.5
of
the
TRAMPAC.
The
model
number
of
each
filter
vent
or
combination
of
filter
vents
installed
on
a
payload
package
shall
be
reported
to
the
WWIS.
A
listing
of
available
CBFO
filter
vent
models
is
provided
on
the
CBFO
Web
Page.

5.2.7.1
Methods
of
Compliance
See
Section
6.5.3.2
for
methods
of
compliance
with
aspiration
requirements.

Refer
to
Section
6.2.5.2
for
methods
of
compliance
with
the
filter
vent
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
122
5.3
Radiological
Properties
With
respect
to
the
required
radiological
properties
identified
within
this
section,
they
can
be
divided
into
two
distinct
groups.

The
first
group
includes
the
activities
and
masses
of
the
ten
WIPP­
tracked
radionuclides
(
i.
e.,
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
and
the
TRU
alpha
activity
concentration
(
i.
e.,
>
100
nCi/
g
of
alpha­
emitting
TRU
isotopes
with
half
lives
greater
than
20
years)
of
the
waste.
This
set
of
radiological
properties
is
regulated
by
the
EPA
in
accordance
with
40
CFR
Parts
191
and
194.
Estimates
of
their
activities
and
masses
shall
be
derived
from
a
system
of
controls
certified
by
CBFO
that
includes
AK,
computations,
measurements,
sampling,
etc.
Appendix
4
provides
the
methods
and
requirements
by
which
to
characterize
the
radiological
composition
of
the
CH­
TRU
waste
utilizing
radioassay
techniques.

The
second
group
includes
the
remaining
radionuclides
contributing
to
the
fissile
gram
equivalent
(
FGE),
the
plutonium­
239
equivalent
curies
(
PE­
Ci),
and
the
decay
heat
of
the
payload
package.
This
set
of
radiological
data
is
regulated
both
by
the
NRC
as
specified
in
the
TRAMPAC
and
the
CBFO
as
required
by
the
WIPP
Technical
Safety
Requirements.
PE­
Ci
quantities
shall
be
calculated
for
each
payload
package
in
accordance
with
Appendix
B
of
the
WIPP­
WAC.
Any
TRAMPAC
compliant
method
may
be
used
to
quantify
the
remaining
radiological
properties
at
the
discretion
of
RFETS.
Appendix
4
provides
radioassay
methods
by
which
to
characterize
the
remaining
radiological
properties.
However,
the
resulting
data
(
e.
g.,
AK
from
Safeguards
and
Security
data),
the
source/
method
from
which
the
data
was
generated,
and
the
basis
for
the
reliability
of
the
data
shall
be
submitted
to
and
approved
by
CBFO
prior
to
use.

5.3.1
Radionuclide
Composition
Acceptance
Criterion.
The
activities
and
masses
of
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs
shall
be
established
on
a
payload
package
basis
for
purposes
of
tracking
their
contributions
to
the
total
WIPP
radionuclide
inventory.
The
estimated
activities
and
masses,
including
their
associated
total
measurement
uncertainties
(
TMU)
expressed
in
terms
of
one
standard
deviation,
for
these
ten
radionuclides
shall
be
reported
to
the
WWIS
on
a
payload
package
basis.
For
any
of
these
ten
radionuclides
whose
presence
can
be
substantiated
from
AK,
direct
measurement,
computations,
or
a
combination
thereof,
and
whose
measured
data
are
determined
to
be
below
the
lower
limit
of
detection
(
LLD)
for
that
radionuclide,
RFETS
shall
report
the
character
string
"<
LLD"
to
the
WWIS
for
the
activity
and
mass
of
that
radionuclide;
otherwise
a
value
of
zero
shall
be
reported.
See
Appendix
4,
Section
A4.3,
for
information
pertaining
to
the
development
and
application
of
LLD.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
123
5.3.1
Radionuclide
Composition
(
continued)

In
addition,
all
radionuclides
other
than
the
ten
WIPP­
tracked
radionuclides
(
i.
e.,
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
that
contribute
to
95%
of
the
radioactive
hazard
for
the
payload
package
shall
be
reported
on
the
TRUPACT­
II
bill
of
lading
or
manifest
in
accordance
with
49
CFR
Part
172.203
and
49
CFR
Part
173.433.
The
activities
and
masses
of
these
other
radioisotopes
shall
also
be
reported
to
the
WWIS
along
with
their
associated
TMU,
expressed
in
terms
of
one
standard
deviation
for
each
waste
package.

5.3.1.1
Methods
of
Compliance
See
Section
6.3.1.2.

5.3.2
Pu­
239
Fissile
Gram
Equivalent
Acceptance
Criterion.
For
each
payload
package
and
loaded
TRUPACT­
II,
the
sum
of
239Pu
FGE
plus
two
times
its
associated
TMU,
expressed
in
terms
of
one
standard
deviation,
shall
comply
with
the
limits
in
Table
5­
3.
The
values
calculated
for
239Pu
FGE
and
its
associated
TMU
(
expressed
in
terms
of
one
standard
deviation)
shall
be
reported
to
the
WWIS
for
each
payload
package.

5.3.2.1
Methods
of
Compliance
The
quantity
of
radioactive
material
in
payload
packages
is
determined
by
approved
and
authorized
assay
methods
(
refer
to
Appendix
4).
Assay
is
either
performed
directly
on
the
payload
package
or
on
all
of
the
smaller
waste
packages
composing
the
payload
package.
If
the
payload
package
is
not
directly
assayed,
then
the
assay
values
(
and
uncertainties)
for
the
payload
package
are
calculated
from
the
associated
assay
results
for
all
of
the
smaller
packages
composing
the
payload
package.
The
assay
results
are
used
to
calculate
the
Pu­
239
FGE
and
associated
uncertainty.

The
Pu­
239
FGE
of
the
radionuclides
in
each
waste
package
is
reported
to
WIPP
using
the
WWIS.
Refer
to
Section
6.3.1.2
for
more
specific
information
on
the
methods
of
compliance
for
the
Pu­
239
FGE
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
124
5.3.3
TRU
Alpha
Activity
Concentration
Acceptance
Criterion.
TRU
waste
payload
packages
shall
contain
more
than
100
nCi/
g
of
alpha­
emitting
TRU
isotopes
with
half­
lives
greater
than
20
years.
Without
taking
into
consideration
the
TMU,
the
TRU
alpha
activity
concentration
for
a
payload
package
is
determined
by
dividing
the
TRU
alpha
activity
of
the
waste
by
the
weight
of
the
waste.
The
weight
of
the
waste
is
the
weight
of
the
material
placed
into
the
payload
package
(
i.
e.,
the
net
weight
of
the
package).
The
weight
of
the
waste
is
typically
determined
by
subtracting
the
tare
weight
of
the
payload
package
(
including
the
weight
of
the
rigid
liner
and
any
shielding
external
from
the
waste,
if
applicable)
from
the
gross
weight
of
the
payload
package.
In
the
event
waste
packages
(
e.
g.,
55­
gallon
drums)
that
have
been
radioassayed
are
overpacked
in
a
payload
package
(
e.
g.,
in
an
SWB),
RFETS
shall
sum
the
individual
TRU
alpha
activity
values
of
the
individual
waste
packages
and
divide
by
the
sum
of
the
individual
net
waste
weights
(
i.
e.,
less
container,
shielding,
and
liner
weights
as
appropriate)
to
determine
the
activity
per
gram
for
the
payload
package.
Loading
a
55­
gallon
POC
with
cans
is
considered
direct
loading
­
not
overpacking
for
the
purposes
of
calculating
the
weight
of
the
package.
The
TRU
alpha
activity
concentration
shall
be
reported
to
the
WWIS;
however,
there
are
no
reporting
requirements
for
its
associated
TMU.

5.3.3.1
Methods
of
Compliance
Approved
and
authorized
assay
methods
are
used
to
quantitate
the
radioactive
material
in
payload
packages.
RFETS
assay
methods
and
procedures
are
described
in
Appendix
4.
Calibrated
scales
are
used
to
measure
the
weight
of
payload
packages
and/
or
their
contents
in
accordance
with
approved
procedures
PRO­
1411­
WO­
WASTE,
Waste
Receiving,
Transfer
and
Handling
and/
or
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
VV)
and
Data
Review.
The
assay
results
and
weight
measurements
are
used
to
calculate
the
TRU
alpha
activity
concentration.
Both
the
assay
results
and
the
weight
measurements
are
entered
into
the
site
Waste
and
Environmental
Management
System
(
WEMS).
WEMS
software
specifications
for
Calculated
and
Assigned
fields
define
the
methods
that
WEMS
uses
to
calculate
the
TRU
alpha
activity
concentration
including
subtraction
of
the
tare
weight
(
including
the
rigid
liner
and
any
added
shielding),
if
applicable,
prior
to
performing
the
calculation.
WEMS
software
specifications
also
provide
the
methodology
used
by
WEMS
to
ensure
transuranic
payload
packages
comply
with
the
TRU
alpha
activity
concentration
restrictions.

Verification
that
correct
data
is
input
and
used
by
WEMS
for
calculation
of
TRU
alpha
activity
concentration
is
performed
during
the
"
WIPP
Verify"
function
described
in
4­
G83­
WEM­
WP­
1209,
WEMS
Package
Verification
and
Certification.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
125
5.3.4
Pu­
239
Equivalent
Activity
Acceptance
Criterion.
PE­
Ci
limits
are
shown
in
Table
5­
4.
PE­
Ci
quantities
shall
be
calculated
for
each
payload
package
(
see
WIPP­
WAC
Appendix
B)
and
reported
to
WIPP
using
the
WWIS.
There
are
no
reporting
requirements
for
the
associated
TMU.

5.3.4.1
Methods
of
Compliance
Approved
and
authorized
assay
methods
are
used
to
quantitate
the
radioactive
material
in
payload
packages.
The
assay
results
are
used
to
calculate
the
PE­
Ci
for
each
payload
package
as
specified
in
Appendix
B
to
the
WIPP­
WAC
in
WEMS.
WEMS
software
specifications
for
Calculated
and
Assigned
fields
define
the
methods
that
WEMS
uses
to
calculate
the
PE­
Ci
for
each
payload
package.
WEMS
software
specifications
also
provide
the
methodology
used
by
WEMS
to
ensure
transuranic
payload
packages
comply
with
the
PE­
Ci
restrictions
prior
to
certification
and
shipment.

Verification
that
correct
data
is
input
and
used
by
WEMS
for
calculation
of
PE­
Ci
is
performed
during
the
"
WIPP
Verify"
function
described
in
4­
G83­
WEM­
WP­
1209,
WEMS
Package
Verification
and
Certification.
PE­
Ci
values
for
each
package
are
transmitted
to
the
WWIS
using
WEMS
in
accordance
with
4­
K47­
WEM­
WP1210,
WEMS
Offsite
Shipping
Module.

Most
of
the
waste
generated
at
the
site
is
not
treated
or
overpacked
(
i.
e.,
55­
gallon
drums
overpacked
into
a
SWB
or
a
TDOP).
In
general,
waste
is
treated
or
overpacked
if
needed
to
produce
a
waste
form
or
package
in
compliance
with
all
applicable
disposal
waste
acceptance
criteria
or
other
site­
specific
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
126
5.3.5
Radiation
Dose
Rate
Acceptance
Criterion.
The
external
radiation
dose
equivalent
rate
of
individual
payload
packages
shall
be
 
200
mrem/
h
at
the
surface.
The
external
radiation
dose
equivalent
rate
of
the
TRUPACT­
II
shall
be
 
200
mrem/
h
at
the
surface
and
 
10
mrem/
h
at
2
meters.
Additional
internal
payload
package
shielding,
beyond
that
identified
in
Appendix
2.1
of
the
TRAMPAC
as
an
integral
component
of
the
payload
package,
shall
not
be
used
to
meet
this
criterion.
Total
dose
equivalent
rate
and
the
neutron
contribution
to
the
total
dose
equivalent
rate
shall
be
reported
for
each
payload
package
in
the
WWIS.

5.3.5.1
Methods
of
Compliance
Radiation
dose
rates
are
determined
as
described
in
Section
6.3.2.2.
Neutron
contributions
to
the
total
payload
package
dose
rate
are
reported
separately
in
the
WWIS
as
specified
in
procedure
4­
K47­
WEM­
WP1210,
WEMS
Offsite
Shipping
Module.

5.3.6
Decay
Heat
Acceptance
Criterion.
The
sum
of
the
decay
heat
for
each
payload
package
plus
its
TMU
shall
be
less
than
or
equal
to
the
limits
of
the
assigned
shipping
category
specified
in
Table
5.5­
1
of
Appendix
5.5
of
the
TRAMPAC.
For
CH­
TRU
waste
from
Los
Alamos
National
Laboratory
Technical
Area
54
assigned
content
Code
LA
154,
compliance
with
the
decay
heat
requirements
is
pursuant
to
Appendix
1.2
of
the
TRAMPAC.
For
those
payload
packages
that
exceed
the
decay
heat
limit,
a
determination
of
compliance
with
the
unified
flammable
(
gas/
volatile
organic
compound
[
VOC])
concentration
limit
as
specified
in
the
TRAMPAC
allows
the
payload
package
to
be
shipped
in
the
TRUPACT­
II
package
under
test
category.
The
values
calculated
for
decay
heat
and
its
associated
TMU
(
expressed
in
terms
of
one
standard
deviation)
shall
be
reported
to
the
WWIS
for
each
payload
package.

5.3.6.1
Methods
of
Compliance
Compliance
with
decay
heat
requirements
is
described
in
Section
6.5.2.2.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
127
5.4
Physical
Properties
5.4.1
Residual
Liquids
Acceptance
Criterion.
Liquid
waste
is
prohibited
at
WIPP.
Waste
shall
contain
as
little
residual
liquid
as
is
reasonably
achievable
by
pouring,
pumping,
and/
or
aspirating.
Internal
containers
shall
also
contain
no
more
than
1
inch
or
2.5
cm
in
the
bottom
of
the
internal
containers.
The
total
residual
liquid
in
any
payload
package
shall
not
exceed
1
percent
by
volume
of
that
payload
package.
If
visual
examination
methods
are
used
in
lieu
of
radiography,
then
the
detection
of
any
liquids
in
non­
transparent
internal
containers
will
be
addressed
by
using
the
total
volume
of
the
internal
container
when
determining
the
total
volume
of
liquids
within
the
payload
package.

5.4.1.1
Methods
of
Compliance
Compliance
is
provided
through
the
use
of
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging;
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
VV)
and
Data
Review;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
associated
WGI(
s);
and/
or
radiography,
or
the
appropriate
Residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP.
To
comply
with
49
CFR,
RFETS
procedures
do
not
permit
the
packaging
of
free
liquids.
The
document
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
includes
the
requirement
to
thoroughly
dry
all
wastes
prior
to
packaging
when
possible.
When
it
is
not
possible
to
thoroughly
dry
the
waste
items,
the
waste
must
be
packaged
in
contact
with
enough
suitable
absorbent
to
accommodate
twice
the
amount
of
any
liquid
that
could
potentially
accumulate
due
to
gravity
or
condensation.

Refer
to
Section
6.2.6.2
for
additional
information
on
compliance
with
the
liquids
restriction.

5.4.2
Sealed
Containers
Acceptance
Criterion.
Payload
packages
shall
be
verified
to
be
free
of
sealed
containers
greater
than
4
liters.

5.4.2.1
Compliance
Methods
Refer
to
Section
6.2.8.2
for
information
on
compliance
with
the
prohibition
of
sealed
containers
greater
than
4
liters
in
volume.
Unvented
rigid
containers
greater
than
4
liters
in
volume
are
either
headspace
gas
sampled
or
are
vented
prior
to
initiating
headspace
drum
age
and
equilibrium
criteria.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
128
5.5
Chemical
Properties
5.5.1
Pyrophoric
Materials
Acceptance
Criterion.
Pyrophoric
radioactive
materials
shall
be
present
only
in
small
residual
amounts
(<
1
percent
by
weight)
in
payload
packages
and
shall
be
generally
dispersed
in
the
waste.
Radioactive
pyrophorics
in
concentrations
>
1
percent
by
weight
and
all
nonradioactive
pyrophorics
shall
be
reacted
(
or
oxidized)
and/
or
otherwise
rendered
nonreactive
prior
to
placement
in
the
payload
package.
Nonradionuclide
pyrophoric
materials
are
not
acceptable
at
WIPP.

5.5.1.1
Methods
of
Compliance
The
document
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
provides
the
requirement
to
exclude
pyrophoric
materials
from
being
packaged.
WGIs
provide
instructions
for
excluding
pyrophoric
materials
from
being
packaged
with
the
waste
by
referring
to
AK
characterization.

AK
documentation
verifies
no
pyrophoric
materials
are
present
in
TRU
waste.
This
documentation
is
contained
in
an
auditable
record
and
summarized
in
RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information.

Additional
discussion
of
compliance
is
provided
in
the
TRAMPAC
section
of
this
document.
Specifically,
Section
6.4.1.2
addresses
compliance
with
the
restriction
on
pyrophoric
materials.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
129
5.5.2
Hazardous
Waste
Acceptance
Criterion.
Hazardous
wastes
not
occurring
as
co­
contaminants
with
TRU
wastes
(
non­
mixed
hazardous
wastes)
are
not
acceptable
at
WIPP.
Each
CHTRU
mixed
waste
package
shall
be
assigned
one
or
more
EPA
hazardous
waste
codes
as
appropriate.
Only
EPA
hazardous
waste
codes
listed
as
allowable
in
the
Hazardous
Waste
Facility
Permit
may
be
managed
at
WIPP.
Wastes
exhibiting
the
characteristic
of
ignitability,
corrosivity,
or
reactivity
(
EPA
hazardous
waste
numbers
of
D001,
D002,
or
D003)
are
not
acceptable
at
WIPP.
In
the
context
of
the
WIPP­
WAC,
hazardous
waste
codes
are
synonymous
with
hazardous
waste
numbers.

5.5.2.1
Methods
of
Compliance
AK
is
the
basis
for
compliance
and
verification
to
the
hazardous
waste
criterion.
AK
documentation,
in
the
form
of
WSRIC
process
descriptions
and
Backlog
Waste
Reassessments,
is
used
to
assign
EPA
HWNs
to
waste
packages.
A
detailed
description
of
the
RFETS
AK
process
and
controls
is
presented
in
the
TWCP
QAPjP,
Section
B4.

The
documents
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
specify
requirements
and
instructions
to
segregate
non­
mixed
waste
from
mixed
waste
to
prevent
commingling
of
RCRA
regulated
waste
with
non­
RCRA
regulated
waste.
These
documents
also
specify
that
waste
may
contain
hazardous
constituents
as
co­
contaminants
of
the
waste
only.
Assigned
EPA
HWNs
are
entered
into
WEMS
on
a
waste
package
basis
(
1­
PRO­
087­
WEMS­
WP­
1201,
WEMS
Waste
Package
Inventory,
Tracking,
and
Control)
and
subsequently
verified
to
ensure
accuracy
(
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification).
The
WEMS
software
disqualifies
transuranic
waste
packages
with
assigned
EPA
HWNs
(
including
HWNs
D001,
D002,
and
D003)
that
are
not
included
on
the
list
of
EPA
Hazardous
Waste
Numbers
Acceptable
at
WIPP.

A
complete
discussion
of
how
information
on
these
constituents
and
compounds
is
collected
and
reported,
along
with
references
to
implementing
procedures,
is
provided
in
the
TWCP
QAPjP,
Section
B.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
130
5.5.3
Chemical
Compatibility
Acceptance
Criterion.
TRU
waste
containing
incompatible
materials
or
materials
incompatible
with
payload
package
and
packaging
materials,
shipping
container
materials,
other
wastes,
repository
backfill,
or
seal
and
panel
closure
materials
are
not
acceptable
for
transport
in
the
TRUPACT­
II
and
disposal
at
the
WIPP.
Chemical
constituents
shall
conform
to
the
lists
of
allowable
materials
in
Tables
4­
1
through
4­
8
of
the
TRAMPAC.
Other
chemicals
or
materials
not
identified
in
these
tables
are
allowed
provided
that
they
meet
the
requirements
for
trace
constituents
as
specified
in
Section
4.3
of
the
TRAMPAC.

5.5.3.1
Methods
of
Compliance
Compliance
with
chemical
compatibility
requirements
is
accomplished
by
only
shipping
wastes
under
approved
TRUCON
codes.
Chemical
compatibility
is
evaluated
during
the
submittal
and
authorization
of
site
TRUCON
codes.
Chemical
compatibility
is
accomplished
by
only
shipping
waste
that
comply
with
the
TRUPACT­
II
chemical
lists
for
the
assigned
TRUCON
code
and
waste
material
type.
Refer
to
Sections
6.4.3
and
6.4.4
for
additional
information
on
the
TRUPACT­
II
chemical
lists.

5.5.4
Explosives,
Corrosives,
and
Compressed
Gases
Acceptance
Criterion.
Waste
shall
contain
no
explosives,
corrosives,
or
compressed
gases
(
pressurized
containers).

5.5.4.1
Methods
of
Compliance
The
TRAMPAC
Section
(
Section
6.4.2.2)
documents
compliance
with
the
restriction
on
explosives,
corrosives,
and
compressed
gases.
These
prohibited
items
are
controlled
through
a
combination
of
AK,
RTR
and
visual
examination.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
131
5.5.5
Headspace
Gas
Concentrations
Acceptance
Criterion.
The
headspace
gas
of
payload
packages
shall
be
sampled
and
analyzed
in
accordance
with
an
approved
site
specific
QAPjP,
as
defined
in
the
WIPP
WAP,
to
determine
VOC
concentrations.

Flammable
VOCs
are
restricted
to
 
500
ppm
in
the
payload
package
headspace.
For
those
payload
packages
that
exceed
the
flammable
VOC
limit,
a
determination
of
compliance
with
the
unified
flammable
(
gas/
VOC)
concentration
limit
as
described
in
the
TRAMPAC
allows
the
payload
package
to
be
shipped
in
the
TRUPACT­
II
under
the
test
category.

Test
category
payload
packages
shall
be
tested
to
quantify
the
hydrogen/
methane,
VOC,
and
total
gas
generation
rates
(
as
appropriate)
for
purposes
of
determining
if
all
applicable
limits
are
met.

5.5.5.1
Methods
of
Compliance
The
RFETS
TWCP
QAPjP
is
the
approved
site­
specific
QAPjP
at
Rocky
Flats.
Headspace
gas
sampling
and
analysis
of
payload
packages
is
performed
to
determine
VOC
concentrations
in
accordance
with
the
RFETS
TWCP
QAPjP.

Flammable
VOCs
are
restricted
to
 
500
ppm
in
the
payload
package
headspace.
Payload
packages
that
exceed
the
500
ppm
flammable
VOC
limit
are
categorized
as
Test
Category
Waste
and
evaluated
to
determine
compliance
with
the
unified
flammable
(
gas/
VOC)
concentration
limits
as
described
in
the
TRAMPAC
(
see
Section
6.5.2.1).

Test
category
payload
packages
are
tested
to
quantify
the
hydrogen/
methane,
VOC
and
total
gas
generation
rate
(
as
appropriated)
to
determine
if
the
payload
package
is
shippable
in
the
TRUPACT­
II.
The
methods
used
to
test
and
qualify
test
category
waste
for
shipment
in
the
TRUPACT­
II
are
described
in
detail
in
Section
6.5.2.3.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
132
5.5.6
Polychlorinated
Biphenyls
Acceptance
Criterion.
Waste
shall
contain
no
polychlorinated
biphenyl
(
PCB)
concentrations
equal
to
or
greater
than
50
parts
per
million
(
ppm).

5.5.6.1
Methods
of
Compliance
Compliance
is
accomplished
through
AK
and/
or
through
sampling
and
analysis
in
accordance
with
the
TWCP
QAPjP
and
95­
WP/
SAP­
001,
Transuranic
(
TRU/
TRM)
Waste
Sampling
Plan.
Waste
streams
containing
PCBs
are
identified
in
the
WSRIC
Building
Books.
Individual
packages
containing
PCBs
are
identified
in
the
BWRBB.
This
information
is
tracked
in
WEMS
for
each
PCB­
contaminated
package.
Waste
potentially
containing
PCBs
in
concentration
equal
to
or
greater
than
50
ppm
are
not
shipped
to
WIPP
for
disposal.

5.6
Data
Package
Contents
5.6.1
Characterization
and
Certification
Data
Acceptance
Criterion.
RFETS
shall
prepare
a
WSPF
for
each
waste
stream.
Each
WSPF
shall
be
approved
by
the
CBFO
prior
to
the
first
shipment
of
that
waste
stream.
Characterization
and
certification
information
for
each
payload
package
shall
be
submitted
to
the
WWIS
and
approved
by
the
Data
Administrator.
Sites
are
required
to
estimate
the
CPR
weights
and
report
these
estimates
in
the
WWIS
on
a
payload
package
basis.
Any
payload
package
from
a
waste
stream
that
has
not
been
preceded
by
an
appropriate
certified
WSPF
is
not
acceptable
at
WIPP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
133
5.6.1.1
Compliance
Methods
WSPFs
are
prepared
and
submitted
to
WIPP
for
review
and
acceptance
in
accordance
with
PRO­
944­
WIPP­
008,
Completion
of
Waste
Stream
Profile
Form
for
Waste
to
be
Disposed
of
at
WIPP.
Characterization
and
certification
data
are
maintained
in
WEMS
and
transmitted
to
the
WWIS
in
accordance
with
4­
K47­
WEM­
WP1210,
WEMS
Offsite
Shipping
Module;
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification;
and
1­
PRO­
110­
WP­
1212,
WIPP
Waste
Information
System
(
WWIS)
Data
Entry.
Prior
to
WSPF
approval,
WEMS
software
controls
allow
characterization
data
to
be
transmitted
to
WWIS,
but
prevent
transmission
of
certification
data.
Once
a
WSPF
is
approved
by
CBFO
and
an
approval
date
is
entered
into
the
WWIS
and
WEMS,
WEMS
software
controls
allow
transmission
of
certification
data
to
the
WWIS
for
payload
packages
in
the
waste
stream.
Assignment
of
payload
packages
to,
and
assembly
of,
TRUPACT­
II
payloads
is
controlled
by
the
e­
TRAMPAC
system
in
WWIS.
The
e­
TRAMPAC
system
prevents
payload
packages
from
being
assembled
into
TRUPACT­
II
payloads
until
the
payload
package
certification
data
are
approved
in
the
WWIS
by
a
WWIS
Data
Administrator.
This
prevents
any
payload
package
from
being
shipped
to
WIPP
prior
to
approval
of
a
WSPF.

The
quantity
of
cellulosics,
plastics
and
rubber
(
CPR)
(
and
other
waste
material
parameters)
are
estimated
either
by
RTR
or
Visual
Verification
in
accordance
with
approved
procedures
as
described
in
the
RFETS
TWCP
QAPjP.

5.6.2
Shipping
Data
Acceptance
Criterion.
Sites
shall
prepare
either
a
bill
of
lading
or
a
uniform
hazardous
waste
manifest
for
CH­
TRU
waste
shipments
as
required
by
the
transportation
requirements.
The
land
disposal
restriction
notification
for
CH­
TRU
mixed
waste
shipments
shall
state
that
the
waste
is
not
prohibited
from
land
disposal.
For
shipment
in
TRUPACT­
II,
the
following
documents
shall
be
prepared
for
packages
and
assemblies,
as
appropriate:
payload
container
transportation
certification
document;
overpack
payload
container
transportation
certification
document;
and
payload
assembly
transportation
certification
document.

5.6.2.1
Methods
of
Compliance
The
Uniform
Hazardous
Waste
Manifest
and/
or
the
Bill
of
Lading
is
completed
according
to
Traffic
Management
procedures.
A
LDR
notification
for
TRU
mixed
waste
shipments
is
generated
in
WEMS.
The
LDR
notification
states
that
the
waste
is
not
prohibited
from
land
disposal.
Refer
to
Section
6.6.2
for
information
on
completion
and
processing
of
PCTCDs,
OPCTCDs
and
PATCDs
that
are
prepared
for
payload
packages
and
assemblies.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
134
Table
5­
1,
Payload
Package
Assembly
Configurations
NUMBER
OF
PAYLOAD
PACKAGES
IN
ASSEMBLY
PAYLOAD
PACKAGE
CONFIGURATION
14
55­
gallon
drums
14
55­
gallons
drums,
each
containing
one
standard
POC
14
55­
gallons
drums,
each
containing
one
S100
POC
14
55­
gallons
drums,
each
containing
one
S200
POC
2
SWBs
2
SWBs,
each
containing
one
(
1)
bin
2
SWB,
each
containing
up
to
four
(
4)
55­
gallon
drums
1
TDOP,
containing
up
to
ten
(
10)
55­
gallon
drums
1
TDOP,
containing
up
to
six
(
6)
85­
gallon
drums
(
each
85­
gallon
drum
containing
one
55­
gallon
drum)
1
TDOP,
containing
one
(
1)
SWB
1
TDOP,
containing
one
(
1)
bin
within
a
SWB
1
TDOP,
containing
up
to
four
(
4)
55­
gallon
drums
within
a
SWB
Table
5­
2,
Weight
Limits
COMPONENT
MAXIMUM
WEIGHT
(
LBS)
Individual
Payload
package
55­
Gallon
Steel
Drum
(
DOT
Spec.
17C)
<
1,000
55­
Gallon
Steel
Drum
(
DOT
Spec.
17H)
<
1,000
55­
Gallon
Steel
Drum
(
UN/
1A2/
X320/
S)
<
700
55­
Gallon
Steel
Drum
(
UN/
1A2/
X325/
S)
<
716
55­
Gallon
Steel
Drum
(
UN/
1A2/
X400/
S)
<
822
55­
Gallon
Steel
Drum
(
UN/
1A2/
X425/
S)
<
937
55­
Gallon
Steel
Drum
(
UN/
1A2/
X430/
S)
<
948
55­
Gallon
Steel
Drum
(
UN/
1A2/
X435/
S)
<
959
55­
Gallon
Drum
Overpacked
in
SWB
<
1,450
SWB
<
4,000
TDOP
<
6,700
POC
Payload
package
Standard
POC
­
6"
diameter
<
328
Standard
POC
­
12"
diameter
<
547
S100
POC
<
650
S200
POC
<
547
Payload
package
Assembly
Payload
Assembly
of
14
55­
gallon
drums
<
7,265
Payload
Assembly
of
two
SWBs
<
7,265
TRUPACT­
II
<
19,250
Truck
(
Tractor/
Trailer)
<
80,000
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
135
Table
5­
3,
Pu­
239
FGE
Limits
PACKAGE
TYPE
PU­
239
FGE
LIMITa
55­
gallon
drum
(
including
all
POCs)
<
200
SWB
<
325
TDOP
<
325
TRUPACT­
II
(
containing
either
14
55­
gallon
drums,
2
SWBs,
or
1
TDOP)
<
325b
TRUPACT­
II
(
containing
either
14
standard,
14
S100,
or
14
S200
POCs)
<
2800b
a
The
above
limits
additionally
require
that
each
payload
package
contain
no
more
than
trace
quantities
(
less
than
or
equal
to
1
percent
by
weight
of
the
contents)
of
beryllium.
b
Payloads
that
contain
greater
than
trace
quantities
of
beryllium
shall
be
acceptable
for
transport
in
a
TRUPACT­
II
only
if
the
Pu­
239
FGE
plus
two
times
the
measurement
error
is
less
than
or
equal
to
100.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
136
Table
5­
4,
PE­
Ci
Limits
WASTE
PACKAGE
PACKAGING
CONFIGURATION
239PU
PE­
Ci
LIMIT
Direct
load
 
all
approved
waste
forms
<
80
Direct
load
 
solidified/
vitrified
waste
only
<
1,800
Overpacked
into
a
85­
gallon
drum,
SWB,
or
TDOP
 
all
approved
waste
forms
<
1,100
55­
gallon
drum
in
good
condition
Overpacked
into
a
85­
gallon
drum,
SWB,
or
TDOP
 
solidified/
vitrified
waste
only
<
1,800
Overpacked
into
a
85­
gallon
drum,
SWB,
or
TDOP
 
all
approved
waste
forms
<
80,
<
130,
<
130
respectively
55­
gallon
drum
in
damaged
condition
Overpacked
into
a
85­
gallon
drum,
SWB,
or
TDOP
 
solidified/
vitrified
waste
only
<
1,800
55­
gallon
POC
in
good
condition
Direct
load
 
all
approved
waste
forms
<
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
<
1,100
85­
gallon
drum
in
good
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
<
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
<
130
85­
gallon
drum
in
damaged
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
<
1,800
Direct
load
(
or
a
bin)
 
all
approved
waste
forms
<
130
Direct
load
(
or
a
bin)
 
solidified/
vitrified
waste
only
<
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
<
1,100
SWB
in
good
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
<
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
<
130
SWB
in
damaged
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
<
1,800
TRANSURANIC
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02/
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PAGE
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This
page
is
intentionally
blank
TRANSURANIC
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MANAGEMENT
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PAGE
138
6.0
TRUPACT­
II
AUTHORIZED
METHODS
FOR
PAYLOAD
CONTROL
(
TRAMPAC)
COMPLIANCE
PLAN
6.1
Introduction
The
TRAMPAC
is
the
governing
document
for
payload
shipments
in
the
TRUPACT­
II.
All
users
of
the
TRUPACT­
II
are
required
to
comply
with
all
payload
requirements
outlined
in
the
TRAMPAC,
using
one
or
more
of
the
methods
described
therein.

Each
site
shipping
TRU
waste
in
the
TRUPACT­
II
is
required
to
prepare
a
sitespecific
TRAMPAC
Compliance
Plan.
This
section
of
the
TWMM
(
i.
e.,
Section
6.0)
constitutes
the
TRAMPAC
Compliance
Plan
for
RFETS.

This
TRAMPAC
Compliance
Plan
identifies
requirements
and
responsibilities
for
the
management
of
TRU
and
TRU
mixed
waste
in
order
to
ensure
compliance
with
the
payload
restrictions
of
the
TRUPACT­
II
package
as
outlined
in
the
TRAMPAC.
The
TRAMPAC
lists
the
restrictions
on
the
waste
to
be
transported
in
the
TRUPACT­
II
and
the
allowable
methods
for
determination
and
control
of
these
restrictions,
and
this
TRAMPAC
Compliance
Plan
also
identifies
applicable
procedures
to
demonstrate
how
RFETS
complies
with
each
of
the
TRUPACT­
II
payload
restrictions.
Appendix
10
correlates
TRUPACT­
II
payload
restrictions
to
applicable
RFETS
procedures.
The
RFETS
procedures
will
also
be
shown
to
be
acceptable
methods
for
payload
control
and/
or
determination
and
verification
as
is
dictated
by
the
TRAMPAC.
Adherence
to
the
TRAMPAC
Compliance
Plan
ensures
that
RFETS
TRU
and
TRU
mixed
wastes
are
characterized,
packaged,
and
controlled
according
to
the
methods
and
procedures
described
herein
and
will
qualify
for
transport
in
the
TRUPACT­
II
package.

6.1.1
Scope
The
scope
of
the
RFETS
TRAMPAC
Compliance
Plan
is
to
define
and
identify
the
methods
used
to
ensure
that
only
authorized
contents
are
shipped
in
the
TRUPACT­
II
package
from
RFETS.

6.1.2
Purpose
The
purpose
of
this
TRAMPAC
Compliance
Plan
is
to:

 
Define
the
applicable
requirements
for
a
payload
to
be
transported
in
the
TRUPACT­
II.

 
Describe
the
methods
of
compliance
used
at
RFETS
to
prepare
and
characterize
the
contact­
handled
(
CH)
TRU
materials
or
other
payload
materials
prior
to
transport
in
a
TRUPACT­
II
package,
including
the
quality
control
(
QC)
and
quality
assurance
(
QA)
programs
that
shall
be
applied
to
these
methods.
TRANSURANIC
(
TRU)
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PAGE
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6.1.3
Requirements
Requirements
are
established
to
ensure
compliance
of
the
payload
with
the
transportation
parameters
of
the
TRUPACT­
II
packaging.
This
TRAMPAC
Compliance
Plan
identifies
payload
requirements
under
the
following
categories:

 
Container
and
Physical
Properties
 
Nuclear
Properties
 
Chemical
Properties
 
Gas
Generation
 
Payload
Assembly
 
Quality
Assurance.

6.1.4
Methods
of
Compliance
The
TRAMPAC
describes
all
allowable
methods
to
be
used
for
determining
compliance
with
each
payload
requirement
and
the
controls
imposed
on
the
use
of
each
method.
This
TRAMPAC
Compliance
Plan
describes
the
specific
allowable
methods
used
at
RFETS
to
ensure
that
the
payload
is
compliant
with
each
requirement
and
is
qualified
for
shipment.

Compliance
with
transportation
requirements
applies
to
the
following
two
categories
of
waste:

1.
Waste
Generated
Under
a
Formal
Certification
Program.
Payload
packages
in
this
category
(
designated
"
100
Series")
are
characterized
individually
based
on
process
knowledge
and
visual
examination
at
the
time
of
waste
generation.
For
sites
using
a
set
of
site/
equipment­
specific
procedures
for
payload
control
for
compliance,
an
independent
verification
of
compliance
must
be
performed
prior
to
transport
for
no
less
than
10
percent
of
the
100
Series
payload
packages
transported
from
each
site
per
year.
This
independent
verification
may
consist
of
a
second
operator
verifying
the
package
contents
or
waste
records
during
the
waste
generation
process
or
RTR.
TRANSURANIC
(
TRU)
WASTE
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MANAGEMENT
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2004
PAGE
140
6.1.4
Methods
of
Compliance
(
continued)

2.
Waste
Generated
Prior
to
Site
Implementation
of
a
Formal
Certification
Program.
Payload
packages
in
this
category
(
designated
"
200
Series")
are
characterized
based
on
process
knowledge.
An
independent
verification
of
compliance
shall
be
performed
prior
to
transport
for
200
Series
waste
using
visual
examination,
RTR,
measurement,
etc.,
under
a
statistical
sampling
program.

NOTE:
All
waste
currently
at
RFETS
was
generated
after
a
formal
certification
program
was
established
at
the
Site
in
the
mid­
1980s
and
so
is
categorized
as
"
100
Series"
waste.

A
summary
of
the
methods
of
compliance
used,
individually
or
together,
for
TRUPACT­
II
payload
control
is
provided
in
the
following
subsections.

6.1.4.1
Visual
Examination
Visual
examination
at
the
time
of
waste
generation
may
be
used
to
qualify
waste
for
transport
(
e.
g.,
100
Series
waste).
The
operator(
s)
of
a
waste
generating
area
shall
visually
examine
the
physical
form
of
the
waste
according
to
site/
equipment­
specific
procedures,
and
remove
all
prohibited
waste
forms,
prior
to
its
placement
in
the
payload
package.
Observation
of
the
waste
generation
process
by
an
independent
operator
may
be
used
as
an
independent
verification
of
the
compliance
prior
to
closure
of
the
payload
package.
Visual
examination
under
a
sampling
program
may
be
used
to
verify
the
absence
of
prohibited
items
(
e.
g.,
200
Series
waste).
See
the
TWCP
QAPjP,
Section
B­
3c
for
details.

6.1.4.2
Visual
Inspection
Visual
inspection
may
be
used
to
evaluate
compliance
with
specific
restrictions
(
e.
g.,
visual
inspection
of
payload
package
type,
marking,
number
of
filters,
etc.).
Visual
inspection
by
a
second
operator
may
be
considered
independent
verification.

6.1.4.3
Real­
Time
Radiography
RTR
may
be
used
as
an
independent
verification
to
qualify
waste
for
transport.
RTR
shall
be
used
to
nondestructively
examine
the
physical
form
of
the
waste,
and
to
verify
the
absence
of
prohibited
waste
forms,
after
the
payload
package
is
closed.
Site/
equipment­
specific
QA
and
QC
procedures
should
ensure
that
RTR
operator(
s)
are
properly
trained
and
qualified.
See
Section
3.2.4.2.2
for
additional
details.
TRANSURANIC
(
TRU)
WASTE
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008­
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001
MANAGEMENT
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VERSION
7
02/
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2004
PAGE
141
6.1.4.4
Records
and
Database
Information
Information
obtained
from
existing
site
records
and/
or
databases
or
knowledge
of
process
may
be
used
as
a
basis
for
reporting
the
absence
of
prohibited
waste
forms
within
waste
packages.
This
information
can
be
verified
using
RTR
and/
or
a
waste
sampling
program.

6.1.4.5
Administrative
and
Procurement
Controls
Site­
specific
administrative
and
procurement
controls
may
be
used
to
show
that
the
payload
package
contents
are
monitored
and
controlled,
and
to
demonstrate
the
absence
of
prohibited
items.

6.1.4.6
Sampling
Programs
Sampling
programs
may
be
used
as
an
independent
verification
of
the
compliance
(
e.
g.,
for
200
Series
waste).
A
site­
specific
sampling
program
designed
to
address
all
payload
requirements
needing
verification
is
recommended.

6.1.4.7
Measurement
Direct
measurement
or
evaluation
based
on
analysis
using
the
direct
measurement
may
be
used
to
qualify
waste
(
e.
g.,
direct
measurement
of
the
weight
or
analysis
of
assay
data
to
determine
decay
heat).

6.1.5
TRUCON
Document
The
TRUCON
document
is
a
catalog
of
authorized
contents
for
the
TRUPACT­
II
and
provides
specific
information
on
the
transportation
parameters
for
each
RFETS
authorized
content
code.
Content
codes
in
TRUCON
describe
how
a
particular
waste
form
complies
with
the
TRAMPAC.
Each
code
is
assigned
to
one
or
more
payload
shipping
categories.
A
shipping
category
places
restrictions
on
the
transportation
parameters
that
are
discussed
in
this
TRAMPAC
Compliance
Plan.

A
content
code
begins
with
a
two­
letter
abbreviation
to
identify
the
shipping
site
(
i.
e.,
RF
denotes
RFETS).
This
is
followed
by
a
three­
digit
number:
AXX.
If
A
is
"
1,"
this
indicates
that
the
waste
was
generated
after
a
formal
certification
program
was
established
at
the
Site.
If
A
is
"
2"
this
indicates
that
the
waste
was
generated
before
a
formal
certification
program
was
established
at
the
Site.
Note:
The
vast
majority
of
waste
currently
at
RFETS
was
generated
after
a
formal
certification
program
was
established
at
the
Site
in
the
mid­
1980s
and
so
is
categorized
as
"
100
Series
waste."
TRANSURANIC
(
TRU)
WASTE
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001
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7
02/
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2004
PAGE
142
6.1.5
TRUCON
Document
(
continued)

The
XX
is
a
number
representing
a
general
waste
form
(
glass,
metals,
combustibles,
filter
waste,
etc.).
The
TRUCON
document
provides
descriptions
for
these
general
waste
form
codes.
For
the
RFETS
content
codes,
a
letter
suffix
is
added
to
identify
different
packaging
configurations.

The
content
codes
defined
in
TRUCON
fully
characterize
the
waste
and
provide
descriptions
for
compliance
with
the
following
parameters:

 
Content
Description
 
Storage
Site
(
if
applicable)

 
Generating
Site
 
Waste
Description
 
Generating
Source(
s)

 
Waste
Form
 
Waste
Packaging
 
Assay
 
Free
Liquids
 
Explosives/
Compressed
Gases
 
Pyrophorics
 
Corrosives
 
Chemical
Compatibility
 
Payload
Package
Venting
and
Aspiration
 
Additional
Criteria
 
Shipping
Category.

 
Maximum
Allowable
Wattage
TRANSURANIC
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PAGE
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6.1.5
TRUCON
Document
(
continued)

All
payload
packages
must
have
an
approved
TRUCON
code
to
be
eligible
for
shipment
in
the
TRUPACT­
II.
Table
6­
7
lists
the
RFETS
content
codes.
If
RFETS
requires
the
transportation
of
TRU
waste
in
the
TRUPACT­
II
that
is
not
listed
in
Table
6­
7,
the
revision
or
addition
of
a
content
code
must
be
requested
in
writing
and
submitted
to
the
TRUPACT­
II
Cognizant
Engineer.
The
process
for
requesting
a
new
or
revised
content
code
is
outlined
in
Section
1.5
of
the
TRAMPAC.
Specifically,
a
shipping
site
is
required
to
perform
the
following
actions
to
add
or
revise
a
TRUCON
code:

1.
The
Site
prepares
in
writing
a
draft
TRUCON
code
containing
sufficient
information
to
satisfy
all
of
the
necessary
elements
of
a
TRUCON
code,
previously
identified.
If
the
request
is
for
a
TRUCON
code
revision,
only
the
revised
elements
require
preparation
and
documentation.
The
site
shall
ensure
that
the
information
submitted
in
the
form
of
a
TRUCON
code
addition
or
revision
accurately
describes
the
waste
and
waste
generating
processes
to
the
best
of
their
knowledge.

2.
The
site
submits
the
draft
TRUCON
code
or
TRUCON
code
elements
in
writing
to
the
TRUPACT­
II
Cognizant
Engineer
for
review.

3.
If
the
request
is
approved,
a
site
may
begin
using
the
new
or
revised
TRUCON
code
once
official
notification
is
received
from
the
TRUPACT­
II
Cognizant
Engineer.
Sites
may
not
use
proposed
TRUCON
code
additions
or
revisions
to
make
shipments
in
the
TRUPACT­
II
prior
to
receipt
of
written
notification
from
the
TRUPACT­
II
Cognizant
Engineer.
TRANSURANIC
(
TRU)
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PAGE
144
6.1.6
Compliance
Program
RFETS
documents
and
demonstrates
compliance
with
the
TRAMPAC
in
a
site/
equipment­
specific
set
of
procedures
for
payload
control
as
identified
and
described
in
this
TRAMPAC
Compliance
Plan.
The
TRAMPAC
Compliance
Plan
is
submitted
to
CBFO
for
approval.
This
TRAMPAC
Compliance
Plan
has
been
prepared
in
accordance
with
the
TRAMPAC.

6.1.6.1
Transportation
Certification
Official
(
TCO)

The
TCO
is
responsible
for
administratively
verifying
the
compliance
of
payload
packages
and
the
payload
assembly
with
transportation
requirements.
The
TCO
approves
by
signature
on
the
transportation
certification
documents
every
payload
for
transport.

A
similar
position
(
i.
e.,
WCO)
is
responsible
for
verifying
that
all
waste
prepared
for
shipment
to
the
WIPP
meets
the
specified
WIPP­
WAC.
The
functions
of
the
two
positions
may
be
performed
by
the
same
or
different
official(
s).

6.1.6.2
Carlsbad
Field
Office
(
CBFO)

The
CBFO
is
responsible
for
the
performance
of
compliance
verification
audits,
which
are
conducted
prior
to
the
first
shipment
and
periodically
thereafter,
to
evaluate
TRUPACT­
II
payload
compliance.
Audit
activities
include
document
review
and
interview
of
operators
on
a
job­
function
basis
relative
to
meeting
the
applicable
criteria.
The
audit
team
will
grant
or
deny
waste
certification
and
waste
transportation
authorization
based
on
objective
findings.

6.1.7
Quality
Assurance
The
QA
requirements
applicable
to
the
use
of
the
TRUPACT­
II
packaging
are
Title
10,
Code
of
Federal
Regulations
(
CFR),
Part
71,
Subpart
H.
The
use,
operation,
and
maintenance
of
the
TRUPACT­
II
are
conducted
under
a
QA
program
approved
by
the
DOE
field
office.
The
compliance
of
a
payload
to
be
transported
in
the
TRUPACT­
II
is
determined
by
the
user
under
a
QA
program
approved
by
the
CBFO.
The
packaging
QA
program
is
described
in
Section
4.6.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
145
6.2
Container
and
Physical
Properties
Requirements
6.2.1
Container
Descriptions
6.2.1.1
Requirements
Only
the
following
payload
packages
are
authorized
for
shipment
in
the
TRUPACTII
(
see
the
TRAMPAC,
Section
2.1):

 
55­
Gallon
Drum
(
including
standard,
S100,
or
S200
POCs)

 
100­
Gallon
Drum
 
SWB
 
TDOP
All
packages
transported
within
the
TRUPACT­
II
shall
comply
with
the
specifications
in
the
TRAMPAC,
Appendix
2.1.
The
maximum
number
of
packages
per
TRUPACT­
II
and
authorized
packaging
configurations
are
as
follows:

 
Fourteen
55­
gallon
drums
 
Fourteen
standard
POCs
 
Fourteen
S100
POCs
 
Fourteen
S200
POCs
 
Six
100­
gallon
drums
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
146
6.2.1.1
Requirements
(
continued)

 
Two
SWBs
 
Two
SWBs,
each
SWB
containing
up
to
four
55­
gallon
drums1
 
Two
SWBs,
each
SWB
containing
one
bin
 
One
TDOP
 
One
TDOP,
containing
up
to
ten
55­
gallon
drums1
 
One
TDOP,
containing
up
to
six
85­
gallon
drums
each
overpacking
one
55­
gallon
drum1
 
One
TDOP,
containing
one
SWB
 
One
TDOP,
containing
up
to
four
55­
gallon
drums
within
an
SWB1
 
One
TDOP,
containing
one
bin
within
an
SWB.

NOTE:
Use
of
all
payload
configurations
above
may
not
currently
be
implemented
(
e.
g.,
bin).
Prior
to
using
a
payload
configuration
not
currently
in
use,
procedures
must
be
developed
and
implemented.
Mention
of
all
payload
package
types
is
for
information
only.

6.2.1.2
Methods
of
Compliance
and
Verification
Compliance
is
accomplished
using
administrative
and
procurement
controls
demonstrating
that
payload
packages
have
been
procured
to
the
specifications
of
the
TRAMPAC,
Appendix
2.1
(
see
Packaging
QA
Program
Plan
­
Section
4.6).

As
required
by
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
waste
packaging
materials
(
e.
g.,
drums,
SWBs,
and
POCs)
are
inspected
upon
receipt
from
vendors,
if
required,
in
accordance
with
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification,
by
the
appropriate
receiving
certification
and
inspection
organization(
s)
to
ensure
conformance
to
procurement
specifications.
Waste
packages,
hardware,
package
liners,
and
ancillary
equipment
are
procured
in
accordance
with
MAN­
134­
PPM,
Procurement
Program
Manual.
Procurement
specifications
are
prepared
in
accordance
with
the
1­
V51­
COEMDES
210,
Site
Engineering
Process
Procedure,
and
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance.

1
Empty
packages
or
spacers
are
required
if
fewer
packages
are
overpacked.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
147
6.2.1.2
Methods
of
Compliance
and
Verification
(
continued)

Procedure
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
and
applicable
WGIs,
that
are
prepared
in
accordance
with
procedure
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging,
include
instructions
for
inspecting
the
integrity
of
the
drum
or
SWB
before
loading,
packaging,
or
use.

Procedure
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection,
provides
instruction
for
the
performance
of
a
final
inspection
of
each
payload
package
prior
to
certification
and
shipment.
Procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification,
provides
instructions
for
verifying
the
integrity
of
the
payload
package
as
part
of
the
waste
certification
process.

Payloads
are
created
in
the
e­
TRAMPAC
system
in
WWIS.
Software
controls
in
the
e­
TRAMPAC
system
ensure
that
created
payloads
comply
with
one
of
the
authorized
payload
configurations.
A
PATCD
is
generated
from
e­
TRAMPAC
for
each
payload
and
the
PATCD
specifies
the
exact
composition
of
each
payload
configuration.
The
payload
configuration
as
specified
on
the
PATCD
is
verified
in
accordance
with
instructions
in
procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.

6.2.2
Dunnage
6.2.2.1
Requirements
A
shipper
shall
use
empty
55­
gallon
drums,
100­
gallon
drums,
or
an
SWB
as
dunnage
to
complete
a
payload
configuration
if
too
few
payload
packages
are
available
that
meet
transportation
requirements.
Dunnage
must
meet
the
specifications
of
the
TRAMPAC,
Appendix
2.1,
with
the
exception
that
dunnage
shall
have
open
vent
ports
(
i.
e.,
not
filtered
or
plugged).

Dunnage
shall
be
marked
in
accordance
with
Section
6.2.4.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
148
6.2.2.2
Methods
of
Compliance
and
Verification
Dunnage
drums
may
be
assembled
into
a
seven­
pack
(
55­
gallon)
or
three­
pack
(
100­
gallon)
of
only
dunnage
drums,
or
they
may
be
assembled
into
a
seven­
pack
or
three­
pack
with
drums
of
waste
that
meet
all
applicable
requirements.
In
the
latter
case,
the
dunnage
drum(
s)
must
be
labeled
with
a
unique
package
identification
number
like
the
waste
drums
because
of
requirements
associated
with
the
WWIS.
All
dunnage
packages
must
be
labeled
"
EMPTY"
or
"
DUNNAGE."
Waste
Operations
is
responsible
for
preparing
dunnage
drums
for
shipment,
which
is
discussed
in
the
TRUPACT­
II
loading
procedures.
WEMS
initiates
and
tracks
dunnage
drums
used
for
TRUPACT­
II
shipments
in
accordance
with
4­
K47­
WEMWP1210
WEMS
Offsite
Shipping
Module.

Dunnage
containers
are
visually
inspected
to
verify
compliance
with
the
dunnage
requirements
in
accordance
with
procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
149
6.2.3
Container/
Assembly
Weight
and
Center
of
Gravity
6.2.3.1
Requirements
6.2.3.1.1
Requirements
for
Package/
Assembly
Weight
NOTE:
Actual
payload
assembly
weights
are
limited
by
"
as­
built"
TRUPACT­
II
weights
and
DOT
requirements
for
a
loaded
tractor/
trailer.

Each
payload
package,
payload
assembly,
and
loaded
TRUPACT­
II
shall
comply
with
the
following
weight
limits:

 
328
pounds
per
6­
inch
diameter
standard
POC
 
547
pounds
per
12­
inch
diameter
standard
POC
 
650
pounds
per
S100
POC
 
547
pounds
per
S200
POC
 
1,000
pounds
per
55­
gallon
drum
(
Note:
The
RFETS
limit
is
800
lbs.)

 
1,000
pounds
per
100­
gallon
drum
 
4,000
pounds
per
SWB
 
6,700
pounds
per
TDOP
 
7,265
pounds
per
payload
of
up
to
14
55­
gallon
drums
or
up
to
6
100­
gallon
drums,
including
pallet,
guide
tubes,
slip
sheets
(
optional),
banding
material
and
reinforcing
plate,
OR
 
7,265
pounds
per
payload
of
two
SWBs,
including
adjustable
sling
(
optional)
AND
 
19,250
pounds
for
payload
and
TRUPACT­
II
package
(
as
built
weight
of
TRUPACT­
II
is
approximately
13,050
lbs.).

6.2.3.1.2
Requirements
for
Center
of
Gravity
The
total
weight
of
the
top
seven
55­
gallon
drums,
three
100­
gallon
drums,
or
SWB
of
the
payload
assembly
shall
be
less
than
or
equal
to
the
total
weight
of
the
bottom
layer
of
drums
or
the
bottom
SWB.
The
total
weight
of
the
top
five
drums
in
a
TDOP
shall
be
less
than
or
equal
to
the
total
weight
of
the
bottom
five
drums.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
150
6.2.3.2
Methods
of
Compliance
and
Verification
6.2.3.2.1
Methods
of
Compliance
and
Verification
for
Package/
Assembly
Weight
Weighing
of
Individual
Payload
Packages
Compliance
is
verified
by
measurement.
Each
payload
package
(
or
dunnage)
is
weighed
on
a
calibrated
scale
in
accordance
with
approved
procedures
PRO­
1411­
WO­
WASTE,
Waste
Receiving,
Transfer
and
Handling
and/
or
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
VV)
and
Data
Review.
The
weight
and
the
measurement
error
of
each
payload
package
is
recorded
in
the
TRUPACT­
II
PCTCD.
RFETS
uses
a
measurement
error
of
one
standard
deviation
or
greater
for
all
weight
measurements.

One
of
two
methods
is
used
to
calculate
the
total
weight
of
the
TRUPACT­
II
payload:

 
If
total
payload
weight
is
obtained
by
summing
the
weights
of
the
individual
payload
packages
or
dunnage
(
plus
265
pounds
for
pallets,
reinforcing
plates,
slip
sheets,
guide
tubes,
banding
material,
etc.),
it
includes
the
square
root
of
the
sum
of
the
squares
of
the
individual
measurement
errors.

 
If
the
total
payload
is
weighed
as
an
assembly,
the
measurement
includes
the
error.

The
weight
and
the
measurement
error
is
reported
in
accordance
with
the
PATCD.

The
scale
calibrations
are
performed
in
accordance
with
the
National
Institute
for
Standards
and
Technology
(
NIST)
Handbook
44
or
an
equivalent
standard.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
151
6.2.3.2.1
Methods
of
Compliance
and
Verification
for
Package/
Assembly
Weight
(
continued)

The
document
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
defines
gross
weight
limits
for
payload
packages.
55­
gallon
drums
(
without
POC)
have
a
limit
of
800
lbs.
The
gross
weight
of
each
payload
package
is
recorded
on
the
W/
RT
and
in
WEMS.
The
recorded
weight
of
the
payload
package
includes
the
addition
of
the
error
and
is
verified
as
part
of
the
"
Radioactive
Verify"
function
as
described
in
procedure
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.
A
payload
package
that
does
not
comply
with
the
weight
limit
or
container
certification
weight
(
allowable
Type
A
test
weight
limit)
is
segregated
for
repackaging
or
other
corrective
action.
WEMS
ensures
compliance
with
TRUPACT­
II
limitations.
Procedure
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection,
provides
instructions
for
final
inspection
to
verify
that
the
acceptance
criteria
for
the
weight
of
the
waste
packages
are
not
exceeded;
and
also
contains
the
instructions
for
final
loading
of
waste
packages.
These
procedures,
as
well
as
Traffic
Management
procedure,
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations,
address
verification
that
the
weight
of
waste
packages
does
not
exceed
the
acceptance
criteria.

Trained
and
qualified
personnel
calibrate
and
maintain
the
scale
and
document
those
actions
in
accordance
with
formal
operating
and
QA
procedures.
Calibration
is
in
accordance
with
NIST
Handbook
44.
Metrology
is
responsible
for
oversight
of
the
RFETS
Calibration
program.
Procedure
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management,
describes
the
process
and
instructions
used
for
the
calibration
of
measurement
and
test
equipment
such
as
scales.

6.2.3.2.2
Methods
of
Compliance
and
Verification
for
Center
of
Gravity
The
weight
and
measurement
error
of
each
payload
package
and
of
the
total
TRUPACT­
II
payload
is
calculated
and
reported
in
the
PATCD
as
generated
through
the
e­
TRAMPAC
system
in
WWIS.
The
e­
TRAMPAC
system,
in
conjunction
with
procedure
DOE/
WIPP
02­
3184,
CH
Packaging
Operations
Manual
ensures
compliance
with
the
total
TRUPACT­
II
payload
weight,
center
of
gravity
restrictions,
and
all
applicable
DOT
weight
restrictions.
The
total
weight
includes
the
square
root
of
the
sum
of
the
squares
of
the
individual
measurement
errors
or,
if
weighed
as
an
assembly,
includes
the
error
in
the
measurement.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
152
6.2.4
Container
Marking
6.2.4.1
Requirements
Each
payload
package
and
dunnage
shall
be
labeled
with
a
unique
container
identification
number.

If
an
empty
55­
or
100­
gallon
drum
or
SWB
is
used
as
dunnage
to
complete
a
payload
configuration,
the
dunnage
package
shall
be
labeled
with
the
following
information:

 
Unique
container
identification
number
 
"
EMPTY"
or
"
DUNNAGE."

If
a
seven­
pack
of
only
dunnage
55­
gallon
drums,
a
three­
pack
of
only
dunnage
100­
gallon
drums,
or
a
dunnage
SWB
is
used
in
the
TRUPACT­
II,
the
package(
s)
will
be
labeled
"
EMPTY"
or
"
DUNNAGE."
The
unique
container
identification
number
is
not
required
for
these
configurations.

6.2.4.2
Methods
of
Compliance
and
Verification
Labeling
and
marking
is
performed
in
accordance
with
instruction
in
PRO­
T13­
Traffic­
306,
Labeling
and
Marking
TRUPACT
Packages.

Compliance
is
demonstrated
through
a
visual
inspection
of
each
payload
and
dunnage
package
in
accordance
with
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
The
package
is
recorded
(
through
the
use
of
the
unique
package
identification
number)
on
the
PCTCD.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
153
6.2.5
Filter
Vents
6.2.5.1
Requirements
Each
payload
package
to
be
transported
in
the
TRUPACT­
II,
including
all
payload
packages
that
are
overpacked
in
other
payload
packages,
shall
have
one
or
more
filter
vents
that
meet
the
specifications
of
the
TRAMPAC,
Appendix
2.5.
Filter
vents
in
plastic
bags
used
as
confinement
layers
within
payload
packages
shall
also
meet
the
specifications
in
the
TRAMPAC,
Appendix
2.5.
Filters
procured
and
used
comply
with
the
applicable
efficiency,
flow,
and
hydrogen
diffusion
requirements
specified
in
the
TRAMPAC,
Appendix
2.5.
The
minimum
number
of
filter
vents
required
is
as
follows:

 
One
filter
per
heat­
sealed
plastic
bag
 
One
filter
per
filtered
metal
can
 
One
filter
per
55­
gallon
drum
 
One
filter
per
55­
gallon
drum
overpacked
in
an
SWB
 
One
filter
per
100­
gallon
drum
 
Two
filters
per
SWB
 
Two
filters
per
Bin
 
Nine
filters
per
TDOP
 
One
filter
per
standard,
S100,
or
S200
POC.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
154
6.2.5.2
Methods
of
Compliance
and
Verification
Compliance
is
demonstrated
by
one,
or
a
combination,
of
the
following
methods:

 
Administrative
and
procurement
controls
demonstrating
that
filter
vents
have
been
procured
to
the
specifications
of
the
TRAMPAC,
Appendix
2.5.

 
Visual
inspection
to
the
specifications
of
the
TRAMPAC,
Appendix
2.5.

 
Sampling
by
measurement
of
filter
characteristics
to
the
specifications
of
the
TRAMPAC,
Appendix
2.5.

Site­
specific
QA
and
procurement
procedures
provide
verification
that
filters
meet
the
specifications.
Visual
inspection
provides
verification
that
the
correct
number
of
filters
has
been
installed
on
each
payload
package.

Filters
are
procured
in
accordance
with
MAN­
134­
PPM,
Procurement
Program
Manual.
Procurement
specifications
for
filters
are
prepared
in
accordance
with
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure,
and
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance.

Procedure
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection,
provides
instructions
for
ensuring
that
the
minimum
number
of
filters
are
installed
in
the
drums
and
the
SWBs.
In
addition,
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
and
associated
WGIs
provide
instructions
for
ensuring
that
the
minimum
number
of
filters
are
installed
in
the
drum
and
SWB
at
the
time
of
waste
packaging.
Procedure
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
also
provides
specifications
for
the
filters.
These
filters
meet
the
criteria
specified
in
the
TRAMPAC,
Appendix
2.5.

Verification
that
the
correct
number
and
type
of
filters
are
installed
on
payload
packages
is
accomplished
by
visual
inspection
per
procedure
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
155
6.2.6
Liquids
6.2.6.1
Requirements
NOTE:
49
CFR
allows
no
free
liquids
in
solid
material
packages.

Liquid
waste
is
prohibited
in
payload
packages,
except
for
residual
amounts
in
welldrained
inner
containers.
The
total
volume
of
residual
liquid
in
a
payload
package
is
restricted
to
less
than
1
volume
percent
of
the
payload
package
(
e.
g.,
drum
or
SWB).

6.2.6.2
Methods
of
Compliance
and
Verification
Compliance
is
demonstrated
by
one,
or
a
combination,
of
the
following
methods:

 
Review
of
records
and
database
information,
which
may
include
knowledge
of
process
 
RTR
 
Visual
examination
 
Sampling
program.

Documents
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Radioactive
Waste
Packaging
Procedure;
and
wastespecific
WGIs
are
used
to
specify
packaging
requirements
to
the
waste
generators
or
operators,
defining
those
waste
items
and
materials
that
are
prohibited
from
the
waste.
These
instructions
identify
methods
for
ensuring
that
free
liquids
are
not
present
in
the
payload
package.
RFETS
prohibits
the
presence
of
free
liquids
in
the
payload
packages
for
both
on­
site
transfers
and
off­
site
shipments,
as
defined
in
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
156
6.2.6.2
Methods
of
Compliance
and
Verification
(
continued)

Verification
of
compliance
is
accomplished
using
visual
examination,
in­
process
inspection,
and/
or
RTR.
Specifically,
verification
of
compliance
with
the
physical
form
restrictions
in
each
payload
package
is
accomplished
using
the
following
methods:

1.
Documented
independent
visual
examination
of
the
waste
contents
at
the
time
of
packaging
per
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review;
associated
WGI(
s);
and/
or
the
appropriate
Residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP;
and/
or
2.
Radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.

Independent
visual
examination
of
the
waste
contents
at
the
time
of
packaging
involves
using
a
second
operator
(
or
QA
inspector),
other
than
the
operator
who
filled
the
payload
package,
to
inspect
the
waste
and
verify
that
the
physical
waste
form
is
in
compliance
with
applicable
requirements.
This
second
operator
documents
the
verification
by
signature
on
the
W/
RT.

Payload
packages
rejected
at
RTR
for
non­
compliance
with
the
physical
form
criteria
are
identified
and
controlled
as
nonconformances
in
accordance
with
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances.
RFETS
RTR
operators
are
trained
in
accordance
with
5­
NDT­
TC­
1A,
Training,
Qualification,
and
Certification
of
Nondestructive
Testing
Personnel.
Training
and
certification
of
mobile
vendor
RTR
operators
is
in
accordance
with
the
mobile
vendor
training
plan
(
refer
to
the
TWCP
QAPjP).
Additional
RFETS
training
that
orients
mobile
vendor
RTR
personnel
to
the
RFETS
TWCP
is
required
per
the
TWCP
TIP.

Compliance
for
previously
packaged
TRU
waste
is
verified
by
periodic
visual
examination
of
a
random
sample
of
previously
packaged
waste
in
accordance
with
PRO­
1358­
440­
VERP,
Glovebox
and
C­
Cell
Waste
Operations;
PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR1;
PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
3712;
and/
or
4­
H80­
776­
ASRF­
007,
Visual
Examination
for
Confirmation
of
RTR3.

1
This
procedure
is
inactive
as
of
November
14,
2003.
2
This
procedure
is
inactive
as
of
August
12,
2003.
3
This
procedure
is
inactive
as
of
November
6,
2001.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
157
6.2.7
Sharp
or
Heavy
Objects
6.2.7.1
Requirements
Sharp
or
heavy
objects
in
the
waste
shall
be
blocked,
braced,
or
suitably
packaged
as
necessary
to
provide
puncture
protection
for
the
payload
packages
containing
these
objects.

6.2.7.2
Methods
of
Compliance
and
Verification
Compliance
is
demonstrated
by
one,
or
a
combination,
of
the
following
methods:

 
Review
of
records
and
database
information,
including
knowledge
of
process
 
RTR
 
Visual
examination
 
Sampling
program.

Documents
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
and
the
use
of
WGIs
per
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging,
where
applicable,
provide
packaging
and
documentation
instructions
to
ensure
that
sharp
or
heavy
objects
are
suitably
blocked,
braced,
or
packaged
to
preclude
damage
to
the
payload
package.

Compliance
for
previously
packaged
transuranic
waste
is
verified
by
radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.
Additionally,
compliance
is
also
verified
through
periodic
visual
examination
of
a
random
sample
of
previously
packaged
waste
performed
in
accordance
with
PRO­
1358­
440­
VERP,
Glovebox
and
C­
Cell
Waste
Operations;
PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR1;
PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
3712;
and/
or
4­
H80­
776­
ASRF­
007,
Visual
Examination
for
Confirmation
of
RTR3.

1
This
procedure
is
inactive
as
of
November
14,
2003.
2
This
procedure
is
inactive
as
of
August
12,
2003.
3
This
procedure
is
inactive
as
of
November
6,
2001.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
158
6.2.8
Sealed
Containers
6.2.8.1
Requirements
Sealed
containers
greater
than
4
liters
are
prohibited
except
for
Waste
Material
Type
II.
2
packaged
in
a
metal
container;
Waste
Material
Type
II.
2
in
metal
cans
does
not
generate
any
flammable
gas
(
see
the
TRAMPAC,
Appendix
5.1).

NOTE:
The
type
II.
2
exception
is
not
allowed
for
shipments
to
WIPP
per
the
WIPP­
WAC,
Section
3.4.2.

6.2.8.2
Methods
of
Compliance
and
Verification
Compliance
is
demonstrated
by
one,
or
a
combination,
of
the
following
methods:

 
Review
of
records
and
database
information,
including
knowledge
of
process
 
RTR
 
Visual
examination
 
Sampling
program.

Verification
of
compliance
is
accomplished
using
visual
examination,
and/
or
RTR.
Specifically,
verification
of
compliance
with
the
sealed
containers
restrictions
in
each
payload
package
is
accomplished
using
the
following
methods:

1.
Documented
independent
visual
examination
of
the
waste
contents
at
the
time
of
packaging
per
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review;
associated
WGI(
s);
and/
or
the
appropriate
Residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP;
and/
or
2.
Radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
159
6.2.8.2
Methods
of
Compliance
and
Verification
(
continued)

Compliance
for
previously
packaged
transuranic
waste
is
verified
by
periodic
visual
examination
of
a
random
sample
of
previously
packaged
waste
performed
in
accordance
with
PRO­
1358­
440­
VERP,
Glovebox
and
C­
Cell
Waste
Operations;
PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR1;
PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
3712;
and/
or
4­
H80­
776­
ASRF­
007,
Visual
Examination
for
Confirmation
of
RTR3.
Containers
with
volumes
greater
than
four
liters
may
be
present
in
the
waste
only
if
there
is
verifiable
evidence
that
they
are
not
sealed
(
e.
g.,
documented
or
visible
absence
of
cap,
presence
of
a
puncture
in
the
container,
or
test
data
that
demonstrates
that
the
container
is
not
sealed).

6.3
Nuclear
Properties
Requirements
The
nuclear
properties'
requirements
outlined
in
this
section
require
a
knowledge
of
isotopic
composition
and
quantity
of
fissile
material.
The
four
major
product
material
isotopic
compositions
are:

 
Weapons­
grade
plutonium
(
Pu)
(
primarily
Pu­
239)

 
Fuel­
grade
plutonium
(
primarily
Pu­
239)

 
Heat­
source
plutonium
(
primarily
Pu­
238)

 
Other
transuranic
isotopes.

RFETS
process
areas
usually
only
handle
product
materials
of
specific
isotopic
composition
(
e.
g.,
weapons­
grade
plutonium
composition
is
shown
in
Section
6.3.1.2).
Therefore,
the
isotopic
composition
in
the
waste
from
specific
process
areas
remains
constant
since
product
isotopic
composition
is
closely
controlled
to
meet
production
isotopic
specification
requirements.

Plutonium
is
also
recovered
from
scrap
material
to
produce
product
material.
TRU
wastes
generated
from
scrap
recovery
operations
are
assigned
the
same
plutonium
isotopic
composition
as
the
product
material.
The
recovery
operation
removes
the
non­
plutonium
radionuclides
[
e.
g.,
241Am]
from
the
scrap
material.
The
removed
radionuclides
are
concentrated
in
the
recovery
operation's
waste
streams,
and
additional
analyses
(
e.
g.,
gamma
ray
pulse
height
analysis)
are
performed
on
the
waste
streams,
to
determine
their
isotopic
composition.

1
This
procedure
is
inactive
as
of
November
14,
2003.
2
This
procedure
is
inactive
as
of
August
12,
2003.
3
This
procedure
is
inactive
as
of
November
6,
2001.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
160
6.3
Nuclear
Properties
Requirements
(
continued)

Other
product
material
mixtures
are
occasionally
produced
by
special
request,
and
the
isotopic
compositions
of
these
special
mixtures
[
e.
g.,
varying
ratios
of
241Am,
244Cm,
and
252Cf]
are
thoroughly
characterized
by
the
production
facility.

Research
and
development
facilities
provide
support
to
the
plutonium
production
facilities
and
utilize
a
production
facility's
product
specification
data
[
determined
by
mass
spectrometry
(
MS)]
when
assigning
the
radioisotopic
composition
to
their
waste.

Facilities
that
produce
or
utilize
special
(
non­
plutonium)
TRU
radionuclides
have
more
variability
in
the
isotopic
distribution
in
the
waste.
There
is
less
reliance
on
production
records
and
specifications
for
determining
isotopic
distribution.

Facilities
that
examine
special
reactor
fuels
have
the
most
detailed
and
traceable
data
regarding
the
isotopic
composition
of
the
waste.
The
quantity
of
waste
generated
from
these
activities
is
very
small
and
highly
characterized.
The
initial
isotopic
composition
of
the
fuel,
neutron
flux,
irradiation
time,
and
cooldown
time
are
measured
and
documented.
The
isotopic
composition
of
the
irradiated
fuel
is
calculated
based
on
the
data
mentioned
above,
or
the
isotopic
composition
of
the
irradiated
fuel
is
confirmed
by
radiochemical
analysis.
The
isotopic
composition
of
the
waste
shall
be
determined
by
either
referencing
the
irradiated
fuel
analysis
or
by
direct
measurement
of
the
waste
by
segmented
gamma
scan.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
161
6.3.1
Nuclear
Criticality
6.3.1.1
Requirements
NOTE:
Pu­
239
fissile
gram
equivalent
(
FGE)
measurement
error
refers
to
standard
error
(
i.
e.,
FGE
measurement
error
at
one
standard
deviation
=
1
sigma).

A
payload
package
shall
be
acceptable
for
transport
only
if
the
Pu­
239
FGE
plus
two
times
the
measurement
error
is
less
than
200
grams
for
a
55­
or
100­
gallon
drum,
200
grams
for
a
standard,
S100,
or
S200
POC,
325
grams
for
an
SWB,
or
325
grams
for
a
TDOP.
Note:
If
a
payload
package
will
be
overpacked,
FGE
limits
apply
only
to
the
outermost
payload
package
of
the
overpacked
configuration.

A
TRUPACT­
II
shall
be
acceptable
for
transport
only
if
the
Pu­
239
FGE
plus
two
times
the
measurement
error
is
less
than
or
equal
to
325
grams
for
a
TRUPACT­
II
with
a
payload
of
14
55­
gallon
drums,
6
100­
gallon
drums,
2
SWBs,
or
1
TDOP;
or
2,800
grams
for
a
TRUPACT­
II
with
a
payload
of
14
standard,
S100,
or
S200
POCs.

The
above
limits
additionally
require
that
each
payload
package
contain
no
more
than
trace
quantities
(
less
than
or
equal
to
1
percent
by
weight
of
the
contents)
of
beryllium.
Payloads
that
contain
greater
than
trace
quantities
of
beryllium
shall
be
acceptable
for
transport
in
a
TRUPACT­
II
only
if
the
Pu­
239
FGE
plus
two
times
the
measurement
error
is
less
than
or
equal
to
100.

6.3.1.2
Methods
of
Compliance
and
Verification
Compliance
with
the
FGE
requirements
involves
the
following
steps:

 
Determination
of
the
isotopic
composition
 
Determination
of
the
quantity
of
radionuclides
 
Calculation
of
the
FGE
and
compliance
evaluation
Each
of
these
steps
is
discussed
in
detail
in
the
following.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
162
6.3.1.2
Methods
of
Compliance
and
Verification
(
continued)

Isotopic
Composition
The
isotopic
composition
of
the
waste
may
be
determined
from
direct
measurements
taken
on
the
product
material
during
the
processing
or
post­
process
certification,
analysis
of
the
waste,
or
from
existing
records.
The
isotopic
composition
of
the
waste
need
not
be
determined
by
direct
analysis
or
measurement
of
the
waste
unless
process
information
is
not
available.

Pu­
239
FGE
for
other
fissile
or
fissionable
isotopes,
including
special
actnide
elements,
shall
be
obtained
using
the
American
National
Standards
Institute
(
ANSI)/
American
Nuclear
Society
(
ANS)
method
ANSI/
ANS­
8.15­
1981,
Nuclear
Criticality
Control
of
Special
Actinide
Elements,
or
an
equivalent
method.

The
two
allowed
analytical
methods
for
determining
isotopic
composition
are:

 
Mass
Spectrometry
(
MS)

 
Gamma
ray
pulse
height
analysis
Depending
on
the
mixture
of
radionuclides
present
in
the
waste,
one
or
both
of
the
methods
may
be
required.
These
assay
methods
are
described
in
greater
detail
in
the
TRAMPAC.

MS
is
a
primary
method
for
determining
the
radioisotopic
composition
in
product
material
(
e.
g.,
plutonium
isotopic
composition).
The
plutonium
isotope
analyses
shall
be
performed
in
accordance
with
the
following
American
Society
for
Testing
and
Materials
(
ASTM)
MS
methods:
ASTM
C
696­
80,
Methods
for
Chemical,
Mass
Spectrometric,
and
Spectrochemical
Analysis
of
Nuclear­
Grade
Uranium
Dioxide
Powders
and
Pellets;
ASTM
C
697­
86,
Methods
for
Chemical,
Mass
Spectrometric,
and
Spectrochemical
Analysis
of
Nuclear­
Grade
Plutonium
Dioxide
Powders
and
Pellets;
ASTM
C
759­
79,
Methods
for
Chemical,
Mass
Spectrometric,
and
Spectrochemical,
Nuclear,
and
Radiochemical
Analysis
of
Nuclear­
Grade
Plutonium
Nitrate
Solutions;
and
ASTM
C
853­
82,
Standard
Test
Methods
for
Nondestructive
Assay
of
Special
Nuclear
Materials
Contained
in
Scrap
and
Waste,
or
equivalent
methods.

Gamma
ray
pulse
height
analysis
or
MS
is
used
to
determine
the
isotopic
composition
for
gamma­
emitting
radionuclides.
Gamma
ray
pulse
height
analysis
shall
be
performed
in
accordance
with
ASTM
C
1030­
84,
or
an
equivalent
method.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
163
6.3.1.2
Methods
of
Compliance
and
Verification
(
continued)

The
isotopic
composition
of
the
waste
streams
generated
at
RFETS
is
well
characterized
through
destructive
measures
performed
on
product
material
during
processing
and
this
acceptable
knowledge
(
AK)
is
documented
in
an
auditable
record.
Therefore,
the
isotopic
composition
of
a
particular
waste
stream
need
not
be
determined
by
direct
methods
of
analysis
or
measurement
unless
process
information
is
not
available.

All
nondestructive
assay
(
NDA)
equipment
used
for
assaying
TRU
waste
is
equipped
with
the
ability
to
determine
the
isotopic
composition
of
wastes
for
which
the
counters
are
qualified
to
assay.
If
isotopic
information
is
measured,
then
this
information
supercedes
the
isotopic
compositions
determined
by
AK
as
described
above.

The
plutonium
used
at
the
RFETS
is
weapons
grade
(
WG)
plutonium.
The
isotopic
distribution
has
been
well
characterized
and
was
routinely
checked
and
verified
during
operations
at
the
RFETS
using
one
of
the
two
allowed
analytical
methods
identified
previously
(
gamma
ray
pulse
height
analysis
or
MS).
The
standard
isotopic
distribution
for
WG
plutonium
is
as
follows:

Isotope
Weight%
Pu­
238
0.016
Pu­
239
93.737
Pu­
240
5.872
Pu­
241
0.332
Pu­
242
0.043
Table
6­
1
lists
the
Pu­
239
FGE,
as
well
as
the
decay
heat
and
specific
activity,
of
many
additional
radionuclides.

AK
is
utilized
to
determine
the
possible
presence
of
radionuclides
other
than
weapons
grade
plutonium
in
TRU
waste.
Specifically,
AK
as
described
in
RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information,
provides
information
by
which
waste
packages
can
be
identified
to
contain
radionuclides
other
than
weapons
grade
plutonium
based
on
the
area
and
date
of
generation
of
the
waste.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
164
6.3.1.2
Methods
of
Compliance
and
Verification
(
continued)

Quantity
of
Radionuclides
The
quantity
of
the
radionuclides
in
each
payload
package
is
estimated
by
either
a
direct
measurement
or
records
of
the
individual
payload
package,
a
summation
of
assay
results
from
individual
packages
in
a
payload
package,
or
a
direct
measurement
on
a
representative
sample
of
a
waste
stream
(
such
as
solidified
inorganics).
An
assay
refers
to
one
of
several
radiation
measurement
techniques
that
determine
the
quantity
of
nuclear
material
in
TRU
wastes.
In
certain
cases,
AK
is
used
to
quantify
radionuclides.
If
assay
is
performed
to
quantify
radionuclides,
then,
one
or
a
combination
of
the
following
allowed
assay
methods
is
used:

 
Passive
Gamma
[
e.
g.,
Tomographic
Gamma­
Ray
Scanner
(
TGS)]

 
Radiochemical
assay
(
alpha
and
gamma
spectroscopy)

 
Passive
neutron
coincidence
counting
(
PNCC)
 
including
high
efficiency
neutron
counting
 
Passive­
active
neutron
assay
(
PAN)

 
Calorimetry.

Appendix
4
provides
a
description
of
the
currently
used
and
planned
NDA
methods
and
compliance
of
these
methods
with
applicable
requirements.
These
methods
comply
with
the
assay
methods
described
in
the
TRAMPAC,
Attachment
B.

General
assay
requirements
that
apply
for
determination
and
control
of
radionuclide
quantity
are:

 
The
selection
and
use
of
an
assay
method(
s)
must
be
identified
in
this
document
as
an
allowable
method(
s)
with
prescribed
controls
implemented.

 
The
applicable
waste
content
code
descriptions
list
the
specific
assay
method(
s)
and
their
applications(
s).

 
Operating
and
QA
procedures
describe
the
assay
method(
s)
and
the
controls
imposed
on
the
assay
operations.
The
controls
include
performing
calibration
and
background
measurements.
The
calibration
and
background
measurements
must
fall
within
the
stated
acceptable
ranges
before
assays
are
performed.

 
QA
plans
and
procedures
include
oversight
of
assay
methods
and
controls.

 
A
specialized
training
program
for
assay
operators
must
be
provided.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
165
6.3.1.2
Methods
of
Compliance
and
Verification
(
continued)

Calculation
of
the
FGE
and
Compliance
Evaluation
The
FGE
of
each
payload
package
is
calculated
from
the
isotopic
composition
and
quantity
of
radionuclides
to
ensure
that
the
FGE
plus
two
times
the
measurement
error
is
less
than
or
equal
to
the
applicable
limit
for
each
payload
package.
The
Pu­
239
FGE
of
each
payload
package
is
recorded
in
the
PCTCD
and
OPCTCD,
as
applicable.

The
total
Pu­
239
FGE
for
a
TRUPACT­
II
payload
is
calculated
and
recorded
in
the
PATCD.
The
total
Pu­
239
FGE
error
is
the
square
root
of
the
sum
of
the
squares
of
twice
the
individual
Pu­
239
FGE
errors.
This
error
is
added
to
the
calculated
TRUPACT­
II
payload
FGE
to
determine
compliance
with
the
applicable
payload
FGE
limit.

Associated
WEMS
software
specifications
define
the
methods
and
controls
that
WEMS
uses
to
calculate
the
FGE
for
each
payload
package.
The
e­
TRAMPAC
software
system
in
the
WWIS
also
calculates
FGE
for
each
payload
package
and
verifies
compliance
with
the
FGE
limits
prior
to
WWIS
approval.
Furthermore,
the
e­
TRAMPAC
system
provides
the
methods
and
controls
used
for
calculation
of
FGE
for
assembled
TRUPACT­
II
payloads.
These
software
specifications/
systems
provide
the
methodology
used
to
ensure
compliance
with
the
FGE
limits
and
verify
that
the
FGE
limits
are
not
exceeded.

Verification
that
correct
data
is
input
and
used
by
WEMS
for
calculation
of
FGE
is
performed
during
the
"
WIPP
Verify"
and
"
Radioactive
Verify"
functions
described
in
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.

Verification
of
compliance
with
FGE
restrictions
for
each
individual
payload
package
is
performed
as
part
of
the
waste
certification
process
as
described
in
procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
Verification
of
calculated
payload
FGE
values
are
performed
by
the
TCO
prior
to
transport
in
a
TRUPACT­
II
package
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.

Pu­
239
FGE
is
obtained
using
American
National
Standards
Institute/
American
Nuclear
Society
(
ANSI/
ANS)
­
8.15­
1981.
The
total
TRUPACT­
II
Pu­
239
FGE
error
is
calculated
using
the
square
root
of
the
sum
of
the
squares
of
twice
the
individual
payload
package
Pu­
239
FGE
errors.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
166
6.3.2
Radiation
Dose
Rates
6.3.2.1
Requirements
The
external
radiation
dose
rates
of
individual
payload
packages
shall
be
less
than
or
equal
to
200
mrem/
hr
at
the
surface.
The
external
radiation
dose
rates
of
the
TRUPACT­
II
shall
be
equal
to
or
less
than
200
mrem/
hr
at
the
surface
and
equal
to
or
less
than
10
mrem/
hr
at
2
meters.

Internal
payload
package
shielding
shall
not
be
used
to
meet
the
above
requirement,
except
for
POC
configurations
as
shown
in
the
TRAMPAC,
Appendices
2.2
through
2.4.
Payload
packages
that
meet
the
above
radiation
dose
rate
requirements
may
be
shielded
to
levels
that
are
ALARA.

NOTE:
Any
payload
package
(
except
for
the
POC
configurations)
that
exceeds
the
200
mrem/
hr
surface
reading
without
shielding
shall
not
be
transported.

In
addition,
S100
and
S200
POC
payloads
shall
meet
the
curie
limits
in
the
TRAMPAC,
Appendices
2.3
and
2.4,
respectively.

Maximum
surface,
1
meter
and
2
meter
dose
rates
are
measured
and
recorded
on
the
Contamination
Dose
Information
Required
for
Shipment
of
TRUPACT­
II
form
in
accordance
with
PRO­
497­
RSP­
09.7,
TRUPACT­
II
Contamination
and
Radiation
Survey
Requirements.
The
information
is
transferred
to
the
WEMS
system.
Payload
packages
that
have
neutron
contribution
are
noted
on
the
package
label.
Surface
dose
rate
must
not
exceed
200
mrem/
hr
and
1
meter
(
or
2
meter)
dose
rate
must
not
exceed
10
mrem/
hr.
The
document
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
specifies
the
requirements
associated
with
the
TRUPACT­
II
dose
rate
restrictions.
Neutron
dose
rates
of
individual
payload
packages
are
transmitted
to
the
WWIS
using
WEMS
in
accordance
with
4­
K47­
WEM­
WP1210,
WEMS
Offsite
Shipping
Module.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
167
6.3.2.2
Methods
of
Compliance
and
Verification
The
document
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
also
requires
that
the
payload
package
be
measured
before
using
lead
shielding.
This
value
is
recorded
on
the
W/
RT
in
accordance
with
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions,
as
well
as
documenting
that
shielding
is
being
used.
The
W/
RT
is
an
in­
process
control
document
that
provides
objective
evidence
of
radiation
monitoring
activities
associated
with
the
packaging
of
radioactive
waste
and
radioactive
mixed
waste.

The
TRUPACT­
II
surface
is
surveyed
before
shipping,
and
the
highest
combined
gamma
and
neutron
reading
is
recorded
in
WEMS
and
reported
on
the
PATCD.
The
PATCD
is
generated
from
WEMS
and
is
used
by
Traffic
Management
to
ensure
that
the
TRUPACT­
II
payload
meets
all
of
the
requirements
of
the
TRAMPAC,
Section
6.
TRUPACT­
II
loading
procedures
ensure
that
each
loaded
TRUPACT­
II
is
surveyed
for
radiation
dose
rates
as
part
of
the
overall
TRUPACT­
II
loading
operation
and
process.

Monitoring/
surveying
is
performed
according
to
the
applicable
Radiological
Safety
Practices
procedures
and
with
instruments
whose
calibration
is
traceable
to
a
national
standard.
WEMS,
supplemented
with
100%
verification
by
the
WCO
and
TCO,
provides
assurance
that
the
surveyed
value
meets
the
TRUPACT­
II
restrictions.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
168
6.4
Chemical
Properties
Requirements
The
chemical
properties
of
waste
are
controlled
and
restricted
so
that
all
payload
packages
are
safe
for
handling
and
transport.
Chemical
constituents
in
a
payload
shall
not
be
in
a
form
that
could
be
reactive
during
transport.

6.4.1
Pyrophoric
Materials
A
pyrophoric
(
solid)
is
defined
as:

Any
solid
material,
other
than
one
classed
as
an
explosive,
which
under
normal
conditions
is
likely
to
cause
fires
through
friction,
retained
heat
from
manufacturing
or
processing,
or
which
can
be
ignited
readily
and
when
ignited
burns
so
vigorously
and
persistently
as
to
create
a
serious
transportation,
handling,
or
disposal
hazard.
Included
are
spontaneously
combustible
and
water
reactive
materials.

Examples
of
pyrophoric
radionuclides
are
metallic
plutonium
and
americium.
Examples
of
nonradioactive
pyrophorics
are
organic
peroxides,
sodium
metal,
and
chlorates.

All
waste
generating
sites
administratively
control
the
procurement,
distribution,
use,
and
disposal
of
nonradioactive
pyrophoric
materials.
In
general,
pyrophoric
materials
are
not
permitted
in
TRU
process
areas.
The
quantity
of
pyrophoric
materials
that
does
enter
any
process
is
strictly
limited
and
controlled
by
site
safety
considerations.

6.4.1.1
Requirements
for
Control
of
Pyrophoric
Materials
Pyrophoric
radioactive
materials
shall
be
present
only
in
small
residual
amounts
(
less
than
1%
by
weight)
in
payload
packages.
Radioactive
pyrophorics
in
concentrations
greater
than
1%
by
weight
and
all
nonradioactive
pyrophorics
are
reacted
(
or
oxidized)
and/
or
rendered
nonreactive
prior
to
placement
in
the
payload
package.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
169
6.4.1.2
Methods
of
Compliance
and
Verification
Compliance
is
demonstrated
by
one,
or
a
combination,
of
the
following
methods:

 
Review
of
records
and
database
information,
which
may
include
knowledge
of
process
 
Administrative
and
procurement
controls,
and
 
the
appropriate
residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP.

The
documents
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Reporting,
and
associated
WGIs
provide
instructions
for
excluding
all
pyrophoric
materials
from
being
packaged
with
the
waste
by
referring
to
AK
characterization.
AK
documentation
verifies
that
pyrophoric
radionuclides
are
less
than
1%
by
weight
in
the
waste
forms.
This
documentation
is
contained
in
an
auditable
record
and
summarized
in
RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information.

6.4.2
Explosives,
Corrosives,
and
Compressed
Gases
An
explosive
is
defined
as:

Any
chemical
compound,
mixture,
or
device,
the
primary
or
common
purpose
of
which
is
to
function
by
explosion
(
i.
e.,
with
substantial
instantaneous
release
of
gas
and
heat).

Examples
of
explosives
are
ammunition,
dynamite,
black
powder,
detonators,
nitroglycerin,
urea
nitrate,
and
picric
acid.

Corrosives
are
defined
as:

Aqueous
materials
(
i.
e.,
water
based
liquids),
which
have
a
pH
less
than
or
equal
to
2,
or
greater
than
or
equal
to
12.5.

The
physical
form
of
the
waste
and
waste
generating
procedures
at
the
sites
ensure
that
the
waste
is
in
a
nonreactive
form.
All
waste
generating
sites
control
the
procurement,
distribution,
use,
and
disposal
of
explosives.
Most
sites
have
lists
of
restricted
materials
that
include
explosives.
Typically,
the
TRU
waste
generating
and
storage
sites
do
not
allow
explosives
in
the
same
facility
as
TRU
waste.
In
addition,
sampling
programs
for
pH
of
inorganic
sludges
have
shown
that
the
sludges
consistently
meet
the
limitation
on
corrosives.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
170
6.4.2.1
Requirements
for
Control
of
Explosives,
Corrosives,
and
Compressed
Gases
Explosives,
corrosives,
and
compressed
gases
(
pressurized
containers)
are
prohibited
from
the
payload.

6.4.2.2
Methods
of
Compliance
and
Verification
Compliance
shall
be
by
one,
or
a
combination,
of
the
following
methods:

 
Visual
examination
of
the
waste
 
Administrative
and
procurement
controls
 
RTR
 
Sampling
program
 
Review
of
records
and
database
information,
which
may
include
knowledge
of
process.

Waste­
generating
processes
are
assessed
for
safety
hazards
such
as
potential
explosion
hazards
and
potential
inadvertent
production
of
explosive
materials.
Documents
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
and
any
associated
WGIs
strictly
prohibit
explosives
from
the
packaged
waste.

The
Site
Transportation
Safety
Manual
prohibits
explosives
in
TRU
waste
generating
areas
at
RFETS.
Traffic
Management
must
be
notified
before
the
arrival
of
any
explosives,
and
Transportation
personnel
will
move
and/
or
escort
any
explosives.

The
document
MAN­
071­
IWCP,
Integrated
Work
Control
Program
Manual,
describes
the
process,
called
the
Integrated
Safety
Management
process,
used
to
plan,
control,
and
perform
RFETS
work.
This
process
includes
procedures
and
instructions
on
hazard
identification
and
analysis.
If
potential
explosive
hazards,
among
others,
are
identified,
then
actions
and
procedures
are
planned
and
executed
to
control
the
hazard.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
171
6.4.2.2
Methods
of
Compliance
and
Verification
(
continued)

Specifically,
verification
of
the
absence
of
free
liquid,
and
thus
corrosive
material,
for
each
payload
package
is
accomplished
using
the
following
methods:

1.
Documented
independent
visual
examination
of
the
waste
contents
at
the
time
of
packaging
per
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review;
associated
WGI(
s);
and/
or
the
appropriate
Residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP;
and/
or
2.
Radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.

Compressed
gases
(
pressurized
containers)
are
prohibited
by
waste
generating
instructions.

Verification
of
the
absence
of
compressed
gases
(
pressurized
containers)
for
each
payload
package
is
accomplished
using
the
following
methods:

1.
Documented
independent
visual
examination
of
waste
contents
at
the
time
of
packaging
per
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review;
associated
WGI(
s);
and/
or
the
appropriate
Residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP;
and/
or
2.
Radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.

Compliance
for
previously
packaged
transuranic
waste
is
verified
by
periodic
visual
examination
of
a
random
sample
of
previously
packaged
waste
performed
in
accordance
with
PRO­
1358­
440­
VERP,
Glovebox
and
C­
Cell
Waste
Operations;
PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR1;
PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
3712;
and/
or
4­
H80­
776­
ASRF­
007,
Visual
Examination
for
Confirmation
of
RTR3.

1
This
procedure
is
inactive
as
of
November
14,
2003.
2
This
procedure
is
inactive
as
of
August
12,
2003.
3
This
procedure
is
inactive
as
of
November
6,
2001.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
172
6.4.3
Chemical
Composition
The
chemical
constituents
allowed
in
a
given
waste
material
type
(
e.
g.,
concreted
inorganic
particulate
waste)
are
restricted
so
that
a
conservative
bounding
G
value
can
be
established
for
the
gas
generation
potential
in
each
waste
material
type.

Compliance
with
the
allowable
chemical
lists
in
the
TRAMPAC
Tables
4­
1
through
4­
8
(
reproduced
here
as
Table
6­
2)
has
been
demonstrated
for
all
chemical
lists
corresponding
to
TRUCON
Content
Codes.
The
assignment
of
any
content
code
to
a
waste
material
type
will
also
be
conservative
with
respect
to
G
values.
For
example,
if
an
inorganic
solid
waste
material
type
contains
materials
that
do
not
comply
with
the
materials
listed
in
TRAMPAC
Table
4­
4
(
e.
g.,
solid
organics
excluding
packaging),
it
shall
be
classified
as
Waste
Material
Type
III.
1
(
solid
organics),
which
has
twice
the
bounding
G
value.

6.4.3.1
Requirements
Chemical
constituents
in
a
payload
shall
conform
to
the
allowable
chemical
lists
in
Table
6­
2.
Total
quantity
of
the
trace
chemicals/
materials
(
materials
that
occur
individually
in
the
waste
in
quantities
less
than
1
percent
[
weight])
not
listed
as
allowed
materials
for
a
given
waste
material
type
in
any
payload
package
is
restricted
to
less
than
5
percent
(
weight).

6.4.3.2
Methods
of
Compliance
and
Verification
Compliance
shall
be
by
one,
or
a
combination,
of
the
following
methods:

 
Review
of
records
and
database
information,
which
may
include
knowledge
of
process
 
Administrative
and
procurement
controls
 
Sampling
program.

AK
(
process
knowledge)
is
the
primary
basis
for
compliance
and
verification
to
the
restrictions
associated
with
chemical
properties.
AK
documentation,
in
the
form
of
WSRIC
process
descriptions
and
Backlog
Waste
Reassessments,
and
waste
packaging
instructions
are
used
to
verify
compliance
with
chemical
property
restrictions.
A
detailed
description
of
the
RFETS
AK
process
and
controls
used
is
presented
in
the
TWCP
QAPjP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
173
6.4.3.2
Methods
of
Compliance
and
Verification
(
continued)

Only
waste
containers
with
approved
TRUCON
codes
are
shipped
in
the
TRUPACT­
II.
In
certain
cases
sampling/
analysis
(
i.
e.,
a
sampling
program)
may
be
used
to
demonstrate
compliance
to
the
allowable
chemical
lists
for
an
approved
TRUCON
code.
Typically,
these
situations
involve
demonstrating
that
a
certain
chemical
(
water
for
instance)
exists
as
a
trace
constituent
and
does
not
exceed
one
weight
percent
in
the
waste
matrix.
In
these
circumstances,
a
representative
sampling
program
of
a
waste
stream
(
or
waste
stream
lot)
is
conducted
in
accordance
with
a
sampling
and
analysis
plan.
The
results
from
the
sampling
program
are
statistically
evaluated
to
determine
the
upper
95%
confidence
limit
(
UCL95)
for
the
sample
mean.
The
UCL95
is
then
compared
to
the
applicable
chemical
composition
limit
for
a
given
constituent.
If
the
UCL95
is
less
than
the
applicable
limit,
then,
the
evaluated
chemical
constituent
is
considered
to
be
below
the
limit
in
the
waste
matrix
for
the
waste
stream/
waste
stream
lot.
If
the
UCL95
is
greater
than
the
limit,
then,
the
concentration
of
the
evaluated
chemical
constituent
is
considered
to
be
potentially
above
the
limit
for
the
waste
stream/
waste
stream
lot.

Content
codes
approved
in
the
TRUCON
document
(
DOE/
WIPP
89­
004)
comply
with
the
chemical
composition
requirements.
Any
proposed
change
in
process
technology
at
RFETS
for
a
given
content
code
shall
be
evaluated
for
compliance
with
the
chemical
lists
of
Table
6­
2.
This
change
shall
be
evaluated
and
approved
by
the
TRUPACT­
II
Cognizant
Engineer
for
compliance
with
existing
waste
material
type
restrictions.
All
changes
in
the
chemical
characteristics
of
the
waste
shall
be
recorded,
and
the
date
of
the
new
process,
description
of
the
process,
and
list
of
new
chemicals
submitted
to
the
TRUPACT­
II
Cognizant
Engineer
as
described
in
Section
6.1.5.
The
WCO
verifies
that
the
assigned
content
code
for
a
payload
package
to
be
shipped
off­
site
is
listed
in
the
TRUCON
document
during
certification
of
the
payload
package
as
described
in
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
174
6.4.4
Chemical
Compatibility
The
allowable
chemical/
materials
listed
in
Table
6­
2
restrict
the
chemical
composition
of
the
TRUPACT­
II
payload.
The
basis
for
evaluating
chemical
compatibility
is
contained
in
the
EPA
document
"
A
Method
for
Determining
the
Compatibility
of
Hazardous
Wastes"
(
EPA­
600/
2­
80­
076).
This
method
provides
a
systematic
means
of
analyzing
the
chemical
compatibility
for
specific
combinations
of
chemical
compounds
and
materials.
Any
incompatibilities
between
the
payload
and
the
packaging
shall
be
evaluated
separately
if
not
covered
by
the
EPA
method.
As
described
in
the
TRUPACT­
II
SAR,
Appendix
2.10.12,
the
EPA
method
classifies
individual
chemical
compounds
into
chemical
groups
and
identifies
the
potential
adverse
reactions
resulting
from
incompatible
combinations
of
the
groups.

6.4.4.1
Requirements
Chemical
compatibility
shall
be
ensured
for
the
following
four
conditions:

 
Chemical
compatibility
of
the
waste
form
within
each
individual
payload
package.

 
Chemical
compatibility
between
contents
of
payload
packages
during
hypothetical
accident
conditions.

 
Chemical
compatibility
of
the
waste
forms
with
the
TRUPACT­
II
Inner
Containment
Vessel
(
ICV).

 
Chemical
compatibility
of
the
waste
forms
with
the
TRUPACT­
II
O­
ring
seals.

6.4.4.2
Methods
of
Compliance
and
Verification
Compatibility
of
all
waste
material
types
has
been
demonstrated
for
transport
in
the
TRUPACT­
II
using
the
chemicals
listed
in
Table
6­
2.
The
restrictions
imposed
on
the
chemical
constituents
of
the
content
codes
ensure
compliance
with
the
compatibility
requirements.
Only
RFETS
content
codes
approved
in
the
TRUCON
document
(
DOE/
WIPP
89­
004)
are
shipped.
The
WCO
verifies
that
the
assigned
content
code
for
a
payload
package
to
be
shipped
off­
site
is
listed
in
the
TRUCON
document
during
certification
of
the
payload
package
as
described
in
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
The
WCO
also
verifies
that
no
chemicals
or
materials
are
incompatible
and
only
wastes
that
meet
the
approved
TRUPACT­
II
chemical
lists,
Table
6­
2,
are
in
the
package.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
175
6.5
Gas
Generation
Requirements
Gas
generation,
concentrations,
and
pressures
during
transport
of
CH­
TRU
wastes
in
a
TRUPACT­
II
payload
are
restricted
as
follows:

 
For
any
package
containing
water
and/
or
organic
substances
that
could
radiolytically
generate
combustible
gases,
determination
must
be
made
by
tests
and
measurements
or
by
analysis
of
a
representative
package
such
that
the
following
criterion
is
met
over
a
period
of
time
that
is
twice
the
expected
shipment
time:
The
hydrogen
generated
must
be
limited
to
a
molar
quantity
that
would
be
no
more
than
5
percent
by
volume
of
the
innermost
layer
of
confinement
(
or
equivalent
limits
for
other
inflammable
gases)
if
present
at
standard
temperature
and
pressure
(
STP)
(
i.
e.,
no
more
than
0.063
gram­
moles/
cubic
foot
at
14.7
pounds
per
square
inch
absolute
and
32oF).

 
The
gases
generated
in
the
payload
and
released
into
the
ICV
cavity
shall
be
controlled
to
maintain
the
pressure
within
the
TRUPACT­
II
ICV
cavity
below
the
acceptable
design
pressure
of
50
pounds
per
square
inch
gauge
(
psig).

The
analysis
presented
in
the
TRUPACT­
II
SAR,
Section
3.4.4.3,
shows
that
all
payloads
authorized
for
transport
in
the
TRUPACT­
II
will
comply
with
the
design
pressure
limit
for
both
twice
the
expected
shipping
period
and
a
one­
year
period.

Specific
requirements
associated
with
the
restrictions
on
gas
generation
during
transport
of
a
TRUPACT­
II
payload
are
described
in
detail
below.

6.5.1
Payload
Shipping
Category
The
CH­
TRU
waste
at
the
DOE
sites
has
been
classified
into
"
payload
shipping
categories"
to
evaluate
and
ensure
compliance
with
the
gas
generation
requirements.

Shipping
Category
Definition
A
shipping
category
is
defined
by
the
following
parameters:

 
Chemical
composition
of
the
waste
(
waste
type)

 
Gas
generation
potential
of
the
waste
material
type
(
quantified
by
the
"
G
value"
for
hydrogen,
which
is
the
number
of
molecules
of
hydrogen
generated
per
100
electron
volts
of
energy
absorbed)

 
Gas
release
resistance
(
type
of
payload
package
and
type
and
maximum
number
of
confinement
layers
used).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
176
6.5.1
Payload
Shipping
Category
(
continued)

For
any
given
payload
package,
the
shipping
category
provides
a
basis
to
determine
the
gas
generation
potential
of
the
contents
and
the
resistance
to
gas
release
of
the
packaging
configuration.
This
enables
evaluation
of
compliance
with
the
gas
generation
requirements.
Two
payload
shipping
category
notations
are
available.
Either
notation
may
be
used
by
a
shipping
site.
Descriptions
of
the
two
notations
are
presented
below.

Numeric
Shipping
Category
Notation
The
numeric
shipping
category
notation
(
initiated
in
Revision
17
of
the
TRUPACT­
II
SAR)
is
a
ten­
digit
code:

XX
YYYY
ZZZZ
where,

XX
=
The
waste
type,
which
indicates
the
chemical
composition
of
the
waste
YYYY
=
The
G
value,
or
gas
generation
potential,
of
the
waste
material
type
multiplied
by
102
ZZZZ
=
The
resistance
to
hydrogen
release
of
the
packaging
configuration
multiplied
by
10
­
4.

A
description
of
each
of
the
parameters
follows.

Waste
Type
Payloads
for
the
TRUPACT­
II
package
are
subdivided
into
four
(
4)
waste
types
based
on
physical
and
chemical
form
as
shown
in
Table
6­
3.
Table
6­
3
also
shows
the
shipping
category
notation
denoting
each
waste
type.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
177
6.5.1
Payload
Shipping
Category
(
continued)

Waste
Material
Type
(
G
Value)

The
four
waste
types
can
be
further
subdivided
into
waste
material
types.
The
waste
material
types
define
the
gas
generation
potential
of
the
waste,
and
a
listing
of
the
chemicals/
materials
allowed
in
each
waste
material
type
is
presented
in
Table
6­
2.
An
effective
bounding
G
value
quantifying
the
gas
generation
potential
of
each
waste
material
type
is
assigned
based
on
the
chemicals
allowed.
The
determination
of
bounding
G
values
for
each
waste
material
type
is
shown
in
the
TRAMPAC,
Appendices
5.1
and
5.2.
Table
6­
4
presents
the
waste
material
types
and
their
respective
bounding
G
values,
along
with
the
shipping
category
notation
denoting
the
bounding
G
value.

Total
Resistance
The
determination
of
the
total
resistance
to
gas
release
of
a
payload
package
requires
a
knowledge
of
the
type
and
maximum
number
of
layers
of
confinement
used
to
package
the
waste.
CH­
TRU
materials
are
typically
placed
in
a
payload
package
within
multiple
layers
of
plastic
and/
or
metal
cans
that
act
as
layers
of
confinement
for
radionuclides
during
waste
handling
operations.
The
payload
safety
analysis
considers
the
layers
of
confinement
as
barriers
that
impede,
but
do
not
preclude,
the
release
of
gases
from
inside
the
layers
of
confinement
(
e.
g.,
plastic
bags
or
metal
cans)
to
the
outside
of
the
payload
package.
Allowable
closure
methods
for
confinement
layers
are
specified
in
the
TRAMPAC,
Appendix
5.3.
The
plastic
layers
of
confinement
in
payload
packages
are
of
three
types
 
liner
bags,
inner
bags,
and
filtered
bags.
As
described
in
the
TRAMPAC,
Appendices
2.5
and
2.6,
the
release
rates
for
these
three
types
of
bags
have
been
quantified
or
presented
as
specifications.
Any
other
type
of
confinement
layer
(
other
than
the
three
types
of
plastic
bags
or
metal
cans
with
filters)
used
at
RFETS
shall
be
shown
to
be
equivalent
to
one
of
these
for
purposes
of
minimum
hydrogen
release.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
178
6.5.1
Payload
Shipping
Category
(
continued)

The
numeric
shipping
category
notation
used
to
denote
the
total
resistance
to
hydrogen
release
of
the
packaging
configuration
of
a
payload
package
is
the
sum
of
the
resistances
from
all
confinement
layers
(
seconds/
mole)
multiplied
by
10­
4,
rounded
up,
and
reported
as
four
digits
(
ZZZZ).
For
example,
the
shipping
category
notation
for
a
total
resistance
of
1,395,163
seconds/
mole
is
"
0140."
The
shipping
category
assignment
for
a
55­
gallon
drum
containing
solid
inorganic
waste
packaged
within
two
filtered,
plastic
liner
bag
layers
is:

20
0170
0140
Where,

20
=
Waste
Type
II
0170
=
G
value
(
1.7)
of
Waste
Material
Type
II.
1
(
x
102)

0140
=
Total
resistance
to
hydrogen
release
(
x
10­
4)
of
two
filtered
liner
bags.

Alphanumeric
Shipping
Category
Notation
The
alphanumeric
shipping
category
notation
(
used
through
Revision
16
of
the
TRUPACT­
II
SAR)
was
based
on
the
same
parameters
as
the
numeric
notation
(
initiated
in
Revision
17
of
the
TRUPACT­
II
SAR),
but
conveyed
the
information
through
a
different
set
of
notations.
The
alphanumeric
shipping
category
notation
is
based
on
the
waste
material
type,
the
payload
package
type,
and
the
type
and
number
of
confinement
layers
within
a
payload
package.
An
example
of
the
alphanumeric
shipping
category
notation
is:

II.
1A2af
Where,

II.
1
=
The
Waste
Material
Type
(
solid
inorganics
in
plastic
bags,
see
Table
6­
4)

A
=
The
type
of
payload
package
(
55­
gallon
drum,
see
Table
6­
5)

2
=
The
number
of
confinement
layers
(
2
bag
layers,
see
Table
6­
6)

af
=
The
type
of
confinement
layers
(
filter
drum
liner
bags,
see
Table
6­
6)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
179
6.5.1.1
Requirements
Payload
Package
Shipping
Category
Notation
Each
payload
package
shall
be
assigned
to
an
approved
payload
shipping
category,
and
each
payload
shipping
category
shall
have
information
on
the
following
components:

 
Waste
type,
which
shall
match
the
content
code
description
from
the
TRUCON
 
Waste
material
type,
which
defines
the
gas
generation
potential
and
shall
match
the
content
code
description
from
the
TRUCON
 
Total
resistance
to
gas
release
by
the
packaging
confinement
layers.
Total
resistance
has
specific
requirements
associated
with:

Confinement
Layers:
The
inner
layers
of
confinement
around
the
waste
materials
in
the
payload
packages
shall
be
plastic
bags
and/
or
metal
cans
that
meet
the
specifications
outlined
in
the
TRAMPAC,
Appendix
5.3.
Any
other
type
of
confinement
layers
used
at
the
sites
shall
be
shown,
by
testing
or
analysis,
to
be
equivalent
to
one
of
the
approved
confinement
layers
described
in
the
TRAMPAC,
Appendix
5.3.
"
Equivalency"
shall
be
established
by
demonstration
of
a
hydrogen
release
rate
greater
than
or
equal
to
that
of
the
approved
confinement
layers.
For
waste
within
a
given
content
code,
the
maximum
number
of
layers
of
confinement
shall
comply
with
that
specified
in
the
TRUCON.

Rigid
Liners:
The
rigid
liner,
if
present,
in
a
payload
package
shall
be
punctured
by
a
 
0.3­
inch
diameter
hole,
or
fitted
with
an
equivalent
filter
vent
as
specified
in
the
TRAMPAC,
Appendix
2.1.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
180
6.5.1.1
Requirements
(
continued)

Each
payload
package
shall
have
an
assigned
shipping
category
that
is
included
in
an
approved
content
code
in
the
TRUCON
document.
Table
2
of
the
TRUCON
document
lists
all
approved
content
codes
and
the
corresponding
assigned
shipping
categories.

NOTE:
As
described
in
Section
6.5.1.2.1,
the
payload
shipping
category
notation
for
waste
material
type,
which
denotes
effective
gas
generation
potential,
is
replaced
with
the
notation
for
dose­
dependent
gas
generation
potential
specified
in
Table
6­
4
when
the
payload
package
meets
the
watt*
year
criteria
(
Waste
Material
Type
II.
1
[
20]
and
Waste
Type
III
[
30]
only)
of
>
0.012.

Complete
descriptions
of
all
content
codes
listed
are
categorized
in
the
TRUCON
document.

Payload
Assembly
Shipping
Category
Notation
A
payload
assembly
may
be
made
up
of
payload
packages
with
the
same,
equivalent,
or
different
(
nonequivalent)
shipping
categories.

If
individual
payload
packages
each
assigned
the
same
shipping
category
are
assembled
into
a
single
payload,
each
payload
package
is
limited
to
the
same
decay
heat
limit
or
gas
generation
rate
limit.

For
payload
shipping
categories
to
be
considered
equivalent,
the
payload
packages
must
be
described
by
the
same
waste
type,
but
may
be
described
by
different
waste
material
types
and/
or
have
different
gas
release
resistance
factors,
provided
that
the
decay
heat
or
the
hydrogen
gas
generation
rate
for
each
payload
package
is
bound
by
the
lowest
decay
heat
limit
or
hydrogen
gas
generation
rate
limit
of
all
payload
packages
in
the
assembly.
These
payload
packages
are
then
considered
to
have
shipping
categories
equivalent
to
the
shipping
category
of
the
package
with
the
lowest
decay
heat
limit
or
hydrogen
gas
generation
rate
limit
in
the
assembly.
If
individual
payload
packages
each
assigned
to
an
equivalent
shipping
category
are
assembled
into
a
payload,
each
payload
package
is
limited
to
the
decay
heat
limit
or
gas
generation
rate
limit
of
the
"
governing"
shipping
category.
An
assembly
may
also
be
made
up
of
payload
packages
with
different
shipping
categories
as
described
in
Section
6.5.2.4.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
181
6.5.1.2
Methods
of
Compliance
and
Verification
6.5.1.2.1
Assignment
of
Shipping
Category
to
an
Individual
Payload
Package
TRUCON
Content
Codes
and
Approved
Shipping
Categories
The
TRUCON
(
DOE/
WIPP
89­
004)
document
catalogs
content
codes,
which
describe
the
authorized
contents
and
compliance
methods
for
waste
to
be
transported
in
the
TRUPACT­
II.
Each
content
code
may
be
assigned
multiple
shipping
categories
to
describe
the
variations
in
waste
form
and
packaging
configurations
within
the
content
code.
One
shipping
category
is
assigned
to
each
payload
package.

RFETS
uses
the
WEMS
to
assign
a
shipping
category
listed
in
the
TRUCON
document
for
the
appropriate
RFETS
waste
form
and
packaging
configuration
for
the
following:

 
Payload
packages
of
Waste
Type
I
(
10)
and
Waste
Material
Types
II.
2
and
II.
3
(
20)

 
Payload
packages
of
Waste
Material
Type
II.
1
(
20)
and
Waste
Type
III
(
30)
that
do
not
meet
the
criteria
used
to
apply
dose­
dependent
G
values
(
watt*
year
 
0.012).

The
shipping
categories
listed
in
the
TRUCON
document
reflect
the
application
of
the
effective
G
value.
As
defined
in
the
TRAMPAC,
payload
packages
of
Waste
Material
Type
II.
1
(
20)
and
Waste
Type
III
(
30)
that
meet
the
watt*
year
criteria
shall
be
assigned
a
shipping
category
that
uses
a
dose­
dependent
G
value.
Table
6­
4
provides
the
dose­
dependent
G
values
and
the
four
digit
notations
to
be
used
as
the
"
YYYY"
portion
of
the
numeric
shipping
category
for
qualifying
packages
of
these
Waste
Types.

Based
on
data
entered
into
the
WEMS
for
actual
watt
loading
and
age
of
the
payload
package,
RFETS
uses
the
e­
TRAMPAC
system
in
WWIS
to
assign
a
shipping
category
that
reflects
the
application
of
a
dose­
dependent
G
value
for
the
following:

 
Payload
packages
of
Waste
Material
Type
II.
1
(
20)
and
Waste
Type
III
(
30)
that
meet
the
criteria
for
the
application
of
dose­
dependent
G
values
(
watt*
year
>
0.012).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
182
6.5.1.2.1
Assignment
of
Shipping
Category
to
an
Individual
Payload
Package
(
continued)

Table
6­
7
lists
the
RFETS
content
codes,
correlating
item
description
codes
(
IDCs),
associated
shipping
categories
as
assigned
in
the
TRUCON
document
(
with
effective
G
value)
and,
as
applicable,
associated
shipping
categories
assigned
with
dosedependent
G
values,
and
the
applicable
decay
heat
limits
for
each
shipping
category.

Waste
packaging
procedures
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
provide
instructions
and
requirements
for
the
packaging
of
solid
transuranic
waste.
These
procedures
require
waste
to
be
segregated
by
physical
form
as
identified
by
IDCs
and
require
specific
WGIs
be
prepared
prior
to
generation
and
packaging
of
transuranic
waste.
Among
other
things,
the
WGIs
specify
the
IDC,
the
packaging
configuration
to
be
used
to
package
waste
at
the
point
of
generation,
and
the
associated
content
code
to
which
the
waste
is
being
packaged
to
comply.

Verification
of
the
IDC
in
a
payload
package
is
accomplished
using
the
following
methods:

1.
Documented
independent
visual
examination
of
the
waste
contents
at
the
time
of
packaging
per
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging;
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review;
associated
WGI(
s);
and/
or
the
appropriate
Residues
repackaging
procedures
as
referenced
in
the
TWCP
QAPjP;
and/
or
2.
Radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.

For
previously
packaged
waste
(
i.
e.,
transuranic
waste
generated
prior
to
WGI
implementation),
the
associated
TRUCON
content
code
is
assigned
to
a
payload
package
using
the
TRUCON
document
(
DOE/
WIPP
89­
004)
and
information
about
its
packaging
configuration
and
the
IDC
of
the
package
contents
are
entered
during
the
"
WIPP
Verify"
function
described
in
procedure
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
183
6.5.1.2.1
Assignment
of
Shipping
Category
to
an
Individual
Payload
Package
(
continued)

The
WCO
verifies
that
the
assigned
content
code
for
a
payload
package
to
be
shipped
off­
site
is
listed
in
the
TRUCON
document
during
certification
of
the
payload
package
as
described
in
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
Based
upon
its
assigned
content
code,
the
filter
model
installed
into
the
payload
package,
its
watt
loading,
and
age,
WEMS
then
assigns
a
shipping
category
to
each
payload
package.

The
shipping
category
information
is
recorded
in
Appendix
7
or
8,
as
applicable.

Verification
of
Shipping
Category
Verification
of
the
shipping
category
is
performed
by
looking
up
the
authorized
shipping
category
for
the
appropriate
content
code
of
the
payload
package
in
the
TRUCON
document.
For
Waste
Material
Type
II.
1
(
20)
and
Waste
Type
III
(
30),
determine
if
payload
package
meets
the
watt*
year
criteria
of
>
0.012.
If
payload
packages
of
Waste
Material
Type
II.
1
(
20)
or
Waste
Type
III
(
30)
meet
watt*
year
>
0.012,
look
up
the
numeric
shipping
category
notation
for
dose­
dependent
G
value
in
Table
6­
7.
The
Numeric
Payload
Shipping
Category
Worksheet
(
Appendix
5)
may
be
completed
as
part
of
verifying
the
payload
package
shipping
category.
Instructions
for
completing
the
worksheet
are
located
in
the
TRAMPAC,
Appendix
5.4.
Record
the
shipping
category
information
on
the
PCTCD
or
OPCTCD,
as
appropriate.

Addition
of
New
Shipping
Categories
Any
proposed
change
in
payload
packaging
configuration
resulting
in
a
new
payload
shipping
category
for
a
given
content
code
shall
be
submitted
to
the
TRUPACT­
II
Cognizant
Engineer
for
evaluation.
The
procedure
for
submitting
requests
to
the
Cognizant
Engineer,
in
compliance
with
the
TRAMPAC
requirements,
is
described
in
Section
6.1.5
of
this
document.
RFETS
may
begin
using
the
new
shipping
category
upon
written
notification
of
approval
from
the
Cognizant
Engineer.
Transport
of
the
waste
may
also
be
allowed
under
a
more
conservative
approved
shipping
category
for
the
content
code
(
listed
in
the
TRUCON
document)
if
the
waste
material
criteria
and
the
packaging
restriction
of
both
the
content
code
and
shipping
category
are
met.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
184
6.5.1.2.2
Assignment
of
Shipping
Category
to
a
Payload
Assembly
The
assignment
of
a
shipping
category
for
payload
assemblies
comprised
of
payload
packages
with
same
or
equivalent
shipping
categories
is
described
in
Section
6.6.2.4
of
this
document.
RFETS
mixing
of
different
shipping
categories
within
a
payload
assembly
is
described
in
Section
6.6.2.5
of
this
document.

6.5.1.2.3
Compliance
With
Specific
Requirements
for
Total
Resistance
The
following
paragraphs
outline
the
methods
of
compliance
and
verification
for
confinement
layers
and
rigid
liners.

Confinement
Layers
RTR,
visual
examination,
administrative
and
procedural
controls,
or
a
combination
of
these
methods
are
used
to
demonstrate
that
the
method
of
closure
for
each
layer
of
confinement
is
in
accordance
with
the
TRAMPAC,
Appendix
5.3.
Any
other
type
of
confinement
layers
used
at
RFETS
shall
be
shown,
by
testing
or
analysis,
to
be
equivalent
to
one
of
the
approved
confinement
layers
described
in
the
TRAMPAC,
Appendix
5.3.
If
necessary,
RFETS
shall
establish
"
equivalency"
by
demonstration
of
a
hydrogen
release
rate
greater
than
or
equal
to
that
of
the
approved
confinement
layers.
The
waste
generation
procedures
specify
the
maximum
number
of
confinement
layers
for
each
content
code.
For
previously
packaged
waste,
the
maximum
number
of
layers
is
determined
from
the
waste
management
practices
in
use
at
the
time
the
waste
was
packaged
and
available
records
and
database
information.
This
is
confirmed
as
part
of
a
sampling
program.

Waste
packaging
procedures
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation,
and
Packaging,
and
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure,
provide
instructions
and
requirements
for
the
packaging
of
solid
transuranic
waste.
These
procedures
specify
waste
packaging
requirements
and
require
specific
WGIs
be
prepared
prior
to
generation
and
packaging
of
transuranic
waste.
Among
other
things,
the
WGIs
specify
the
packaging
configuration
to
be
used
to
package
waste
at
the
point
of
generation
and
the
restrictions
on
the
layers
of
confinement
as
specified
in
the
TRUCON
document.
The
WGIs
and
waste
packaging
procedures
include
instructions
to
ensure
that
packaging
of
line
and
non­
line
generated
waste
to
be
transported
in
the
TRUPACT­
II
complies
with
the
descriptions
in
Table
6­
7.
Additionally,
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
specifies
the
allowable
method
of
closure
for
bags
in
payload
packages.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
185
6.5.1.2.3
Compliance
With
Specific
Requirements
for
Total
Resistance
(
continued)

For
previously
packaged
waste
(
i.
e.,
TRU
waste
generated
prior
to
WGI
implementation),
the
maximum
number
of
layers
of
confinement
(
bags)
is
known
from
the
waste
management
techniques
in
use
at
the
time
the
waste
is
packaged.
For
instance,
standard
operating
practice
has
always
involved
double
bagging
(
i.
e.,
two
layers
of
confinement)
any
waste
items
to
be
removed
from
a
glove
box.
If
a
payload
waste
package
was
not
attached
to
the
glovebox
proper,
then
these
doublebagged
waste
items
would
be
place
into
a
drum
that
could
have
contained
one
or
two
drum
liner
bags,
depending
on
the
waste
management
practices
in
use
at
the
time
the
waste
was
generated.
Therefore,
based
on
this
historical
practice,
the
maximum
number
of
layers
of
confinement
of
this
waste
material
would
be
four
(
up
to
two
possible
waste
item
layers
and
up
to
two
drum
liner
bags).

Compliance
with
the
restrictions
on
inner
confinement
layers
is
verified
by
periodic
visual
examination
of
a
random
sample
of
previously
packaged
waste
in
accordance
with
PRO­
1358­
440­
VERP,
Glovebox
and
C­
Cell
Waste
Operations;
PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR1;
PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
3712;
and/
or
4­
H80­
776­
ASRF­
007,
Visual
Examination
for
Confirmation
of
RTR3.
Radiography
of
the
waste
contents
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP,
is
used
to
verify
the
restrictions
for
liner
bag
confinement
layers.

Rigid
Liner
The
requirements
for
the
rigid
liner
shall
be
met
by
procurement
controls
and
site
QA
procedures.
Venting
of
the
lid
of
a
liner
for
newly
generated
waste
shall
be
controlled
administratively
(
i.
e.,
buying
only
punctured
liners)
or
by
visual
examination
of
the
liner
prior
to
closure.
For
retrievably
stored
waste,
RTR
or
sampling
programs
and
existing
records
shall
be
used
to
verify
that
the
liner
meets
the
requirements.

1
This
procedure
is
inactive
as
of
November
14,
2003.
2
This
procedure
is
inactive
as
of
August
12,
2003.
3
This
procedure
is
inactive
as
of
November
6,
2001.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
186
6.5.1.2.3
Compliance
With
Specific
Requirements
for
Total
Resistance
(
continued)

Approved
rigid
liners
for
TRU
waste
drums
are
specified
in
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual,
and
associated
WGIs
as
either
a
vented
Type
III
rigid
liner,
or
Type
IV
rigid
liner.
Type
IV
rigid
liners
may
be
procured
and
received
from
the
vendor
with
puncture
holes.
Type
III
rigid
liners
typically
are
not
received
with
puncture
holes
from
the
vendor.
Procedures
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure;
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual;
and
associated
WGIs
require
waste
generators
to
ensure
that
the
rigid
liner
lid
is
punctured
prior
to
use
in
packaging
waste.
The
use
of
a
punctured
rigid
liner
for
a
given
drum
is
documented
on
the
associated
drum's
W/
RT,
in
accordance
with
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions.

RTR
of
drums
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP
is
used
to
identify/
verify
the
presence
of
a
rigid
liner.
Venting
and/
or
verification
of
venting
of
potential
unvented
rigid
liner
lids
is
accomplished
during
headspace
gas
sampling
performed
in
accordance
with
procedures
referenced
in
the
TWCP
QAPjP.

TRU
waste
that
was
previously
supercompacted
was
packaged
inside
of
a
Type
V
rigid
liner.
The
Type
V
rigid
liner,
like
the
Type
IV,
was
typically
procured
and
received
from
the
vendor
with
a
puncture
hole.
The
use
of
a
punctured
Type
V
rigid
liner
for
supercompacted
waste
drums
is
documented
on
each
applicable
drum
W/
RT.

For
legacy
waste,
puncturing
of
unvented
rigid
liners
is
accomplished
in
compliance
with
the
venting
and
aspiration
requirements
as
described
in
Subsection
6.5.3.

Verification
that
rigid
liners
are
punctured
or
vented
is
accomplished
visually
through
in­
process
inspections
(
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection)
or
waste
characterization
headspace
gas
sampling
activities
conducted
in
accordance
with
the
TWCP
QAPjP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
187
6.5.1.2.4
Alphanumeric
Shipping
Category
Notation
For
the
alphanumeric
shipping
category
notation
(
used
through
Revision
16
of
the
TRUPACT­
II
SAR),
verification
of
the
shipping
category
requirements
shall
be
by
comparison
of
the
shipping
category
for
the
payload
package
with
the
allowable
shipping
categories
from
the
information
in
the
TRUCON.
This
is
performed
as
part
of
the
WEMS
WIPP
Verification
function
in
accordance
with
procedure
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.
The
shipping
category
information
is
also
recorded
in
Appendix
7
or
8,
as
applicable.

6.5.2
Compliance
With
Flammable
(
Gas/
VOC)
Concentration
Limits
TRU
wastes
to
be
transported
in
the
TRUPACT­
II
are
restricted
so
that
no
flammable
mixtures
can
occur
in
any
layer
of
confinement
during
shipment.
While
the
predominant
flammable
gas
of
concern
is
hydrogen,
the
presence
of
methane
and
flammable
VOCs
is
also
limited
along
with
hydrogen
to
ensure
the
absence
of
flammable
(
gas/
VOC)
mixtures
in
TRU
waste
payloads.

Payload
packages
to
be
transported
in
the
TRUPACT­
II
can
be
classified
into
one
of
two
categories
based
on
compliance
with
the
flammable
(
gas/
VOC)
limits:

 
Analytical
Category
­
Under
the
analytical
category,
a
conservative
analysis
is
used
to
impose
decay
heat
limits
on
individual
payload
packages
to
ensure
that
flammable
(
gas/
VOC)
limits
are
met.
Specifically,
flammable
VOCs
are
restricted
to
less
than
or
equal
to
500
parts
per
million
(
ppm)
in
the
payload
package
headspace
(
to
ensure
that
their
contribution
to
flammability
is
negligible),
and
a
bounding
G
value
is
used
to
conservatively
estimate
the
potential
for
flammable
gas
generation
due
to
radiolysis.
This
G
value
accounts
for
both
hydrogen
and
methane
gas
generation
potential
based
on
the
waste
type.
The
5%
limit
on
hydrogen
concentration
is
then
met
by
imposing
a
decay
heat
limit
that
restricts
the
amount
of
radioactive
material
that
can
be
present
in
the
payload
package.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
188
6.5.2
Compliance
With
Flammable
(
Gas/
VOC)
Concentration
Limits
(
continued)

 
Test
Category
­
Payload
packages
that
do
not
meet
the
analytical
category
limits
are
classified
as
test
category.
Under
the
test
category,
one
of
two
options
is
used
for
determining
compliance
with
flammable
(
gas/
VOC)
limits:
(
1)
Measurement
of
the
headspace
of
payload
packages
for
flammable
(
gas/
VOC)
concentrations
and
determination
of
the
potential
flammability
of
the
(
gas/
VOC)
mixture
in
the
innermost
layer
of
confinement
during
transportation,
and
(
2)
Full­
Drum
Testing
to
determine
compliance
with
flammable
(
gas/
VOC)
limits
for
individual
payload
packages.

VOC
absorbing
or
adsorbing
material
(
such
as
granular
activated
carbon
to
adsorb
carbon
tetrachloride)
may
be
placed
in
a
payload
package
provided
that
RFETS
personnel
can
verify
or
demonstrate
the
following
through
testing,
analysis,
or
AK:

1.
The
absorbent/
adsorbent
remains
effective
in
retaining
VOCs
from
the
time
of
waste
packaging
through
the
end
of
the
maximum
shipping
period
in
the
TRUPACT­
II,
and
2.
A
flammable
mixture
of
gases
does
not
exist
in
the
innermost
layer
of
confinement,
and
3.
The
total
concentration
of
potentially
flammable
VOCs
does
not
exceed
500
ppm
in
the
headspace
of
a
payload
package.

Only
payload
packages
that
meet
the
flammable
(
gas/
VOC)
limits
based
on
these
determinations
are
eligible
for
shipment
in
the
TRUPACT­
II.
Implementation
of
compliance
methods
under
the
analytical
and
test
categories
is
described
in
the
following
subsections
and
is
summarized
in
Figure
6­
1.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
189
6.5.2
Compliance
With
Flammable
(
Gas/
VOC)
Concentration
Limits
(
continued)

Figure
6­
1
presents
a
logic
flow
diagram
for
performing
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits.
Figures
5­
1
through
5­
5
of
the
TRAMPAC
provides
expanded
logic
and
detailed
descriptions
of
each
step
of
this
compliance.
The
compliance
evaluation
by
analysis
requires
data
associated
with
the
payload
package,
which
is
gathered
from
one
or
more
of
the
methods
of
payload
compliance
listed
in
Section
6.1.4
of
this
document.

NOTE:
The
e­
TRAMPAC
system
in
the
WWIS
will
verify
compliance
with
flammable
(
gas/
VOC)
concentration
limits.
RFETS
will
ship
only
payloads
that
comply
with
the
flammable
(
gas/
VOC)
limits
as
ensured
by
the
e­
TRAMPAC
system
in
the
WWIS.

The
evaluation
of
compliance
with
flammable
(
gas/
VOC)
concentration
limits
under
either
the
analytical
category
or
the
test
category
requires
the
determination
of
the
flammable
VOC
concentration.
A
list
of
flammable
VOCs
is
provided
in
Table
6­
10.

As
applicable,
RFETS
determines
the
flammable
VOC
concentration
through
AK,
which
may
include
results
from
previous
headspace
gas
sampling
data.
If
a
payload
package
headspace
concentration
of
flammable
VOCs
cannot
be
established
to
be
 
500
ppm
based
on
the
payload
package
AK
data,
then
the
flammable
VOC
concentration
of
the
payload
package
headspace
must
be
measured.

Per
the
requirements
of
the
WIPP­
WAP,
a
statistical
sample
or
100%
of
all
payload
packages
in
each
waste
stream
must
be
headspace
gas
sampled
and
analyzed
for
VOCs,
which
includes
most
of
the
flammable
VOCs
listed
in
Table
6­
10.
Flammable
VOCs
not
included
in
the
WIPP­
WAP
target
analyte
list
will
be
detected
as
tentatively
identified
compounds
(
TICs)
as
part
of
the
headspace
VOC
analysis,
or
will
be
added
to
the
target
analyte
list
and
analyzed
as
target
analytes.
Headspace
gas
sampling
and
analysis
is
performed
in
accordance
with
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System;
L­
4231,
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold1;
L­
4146,
Headspace
Gas
Sampling
of
Waste
Containers2;
and
L­
4111,
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization2.

1
This
procedure
has
been
cancelled
as
of
June
18,
2003,
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.
2
These
procedures
are
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
190
6.5.2.1
Determination
of
Flammable
Volatile
Organic
Compounds
Concentration
Analysis
data
are
validated
and
then
input
into
WEMS
and
the
WEMS
software
sums
the
results
for
the
flammable
VOCs.
WEMS
software
specifications
then
ensure
that
any
payload
package
that
exceeds
500
ppm
flammable
VOCs
in
the
headspace
is
identified
as
test
category
waste
as
described
in
procedure
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.

If
a
payload
package
headspace
concentration
of
flammable
VOCs
can
be
established
to
be
 
500
ppm,
then
compliance
with
the
flammable
(
gas/
VOC)
limits
is
determined
under
the
analytical
category
as
described
in
Section
6.5.2.2.

The
TRAMPAC,
Appendix
5.6,
specifies
drum
age
criteria
(
DAC)
(
i.
e.,
minimum
number
of
days)
for
the
measurement
of
headspace
flammable
VOCs.
If
the
payload
package
meets
the
DAC
for
the
applicable
packaging
configuration,
the
measured
headspace
flammable
VOC
concentration
is
evaluated.
If
the
payload
package
has
not
yet
met
the
DAC,
the
90­
percent
steady­
state
headspace
flammable
VOC
concentration
must
be
calculated
from
the
measured
concentration
as
described
in
the
TRAMPAC,
Appendix
5.6.
If
the
measured
headspace
flammable
VOC
concentration
or
the
calculated
steady­
state
payload
package
headspace
flammable
VOC
concentration
is
less
than
or
equal
to
500
ppm,
the
evaluation
of
compliance
with
the
flammable
(
gas/
VOC)
limits
is
determined
under
the
analytical
category
as
described
in
Section
6.5.2.2.
If
the
measured
or
calculated
headspace
flammable
VOC
concentration
exceeds
500
ppm,
the
evaluation
of
compliance
with
the
flammable
(
gas/
VOC)
limits
is
determined
under
the
test
category
as
described
in
Section
6.5.2.3.

The
e­
TRAMPAC
system
in
WWIS
applies
the
appropriate
DAC
to
the
headspace
flammable
VOC
concentration
measurement,
performs
any
required
calculation
of
the
steady­
state
headspace
flammable
VOC
concentration,
and
identifies
any
payload
package
that
exceeds
the
500
ppm
limit.

NOTE:
If
WIPP­
WAP
requirements
pertaining
to
the
DAC
are
more
restrictive
than
those
specified
in
the
TRAMPAC,
Appendix
5.6,
the
application
of
the
DAC
will
be
in
accordance
with
the
WIPP­
WAP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
191
6.5.2.2
Analytical
Category
Compliance
Compliance
with
the
flammable
(
gas/
VOC)
concentration
limits
is
demonstrated
under
the
analytical
category
if
the
payload
package
meets
all
of
the
following
conditions:

 
The
total
concentration
of
potentially
flammable
VOCs
within
the
payload
package
headspace
is
less
than
or
equal
to
500
ppm
(
as
determined
in
Section
6.5.2.1)

 
The
payload
package
is
classified
as
Waste
Types
I
(
10),
II
(
20),
or
III
(
30).

If
the
payload
package
exceeds
500
ppm
or
is
classified
as
Waste
Type
IV,
compliance
with
the
flammable
(
gas/
VOC)
concentration
limits
must
be
demonstrated
under
the
test
category
as
described
in
Section
6.5.2.3.

NOTE:
The
compliance
evaluation
described
in
this
section
assumes
that
the
payload
package
under
consideration
is
proposed
for
shipment
with
payload
packages
belonging
to
the
same
or
an
equivalent
shipping
category.
If
the
payload
package
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
packages
of
different
shipping
categories
and/
or
dunnage
packages,
compliance
is
evaluated
as
described
in
Section
6.6.2.5.

If
the
payload
package
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
packages
of
the
same
or
equivalent
shipping
category,
RFETS
evaluates
compliance
with
the
analytical
decay
heat
limit.
An
analytical
decay
heat
limit
is
established
for
each
payload
shipping
category
such
that
the
hydrogen
generated
during
twice
the
expected
shipping
time
results
in
a
molar
quantity
of
not
more
than
5%
by
volume
in
any
layer
of
confinement
in
the
payload
package.
The
analytical
decay
heat
limit
for
Rocky
Flats
approved
shipping
categories
listed
in
the
TRUCON
document
are
specified
in
Table
6­
7.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
192
6.5.2.2
Analytical
Category
Compliance
(
continued)

The
TRUCON
document
only
specifies
shipping
categories
and
decay
heat
limits
for
overpack
configurations
in
which
55­
gallon
drums
are
overpacked
into
an
SWB
fitted
with
two
filters.
The
assignment
of
shipping
categories
and
decay
heat
limits
for
other
overpacked
payload
configurations
are
determined
based
on
information
presented
in
the
TRUPACT­
II
SAR
Appendix
3.6.13
as
follows:

 
Ten
55­
gallon
drums
overpacked
in
a
TDOP
is
equivalent
to
14
55­
gallon
drums
in
a
TRUPACT­
II.
Therefore,
the
shipping
category
and
decay
heat
limit
for
a
55­
gallon
drum
overpacked
in
a
TDOP
is
the
same
as
a
non­
overpacked
55­
gallon
drum
listed
in
the
TRUCON
document.
For
example:
if
the
shipping
category
for
a
55­
gallon
drum
of
TRUCON
code
RF116A
waste
is
3003400041,
then,
this
shipping
category
(
3003400041)
would
also
be
the
shipping
category
for
each
of
10
55­
gallon
drums
of
TRUCON
code
RF116A
waste
overpacked
in
a
TDOP.

 
Eight
55­
gallon
drums
overpacked
in
two
SWBs
with
four
filters
in
each
SWB
is
equivalent
to
14
55­
gallon
drums
in
a
TRUPACT­
II.
Therefore,
the
shipping
category
and
decay
heat
limit
for
a
55­
gallon
drum
overpacked
in
an
SWB
fitted
with
four
filters
is
the
same
as
a
non­
overpacked
55­
gallon
drum
listed
in
the
TRUCON
document.
For
example:
if
the
shipping
category
for
a
55­
gallon
drum
of
TRUCON
code
RF116A
waste
is
3003400041,
then,
this
shipping
category
(
3003400041)
would
also
be
the
shipping
category
for
each
of
4
55­
gallon
drums
of
TRUCON
code
RF116A
waste
overpacked
in
a
SWB
equipped
with
4
filters.

 
Four
55­
gallon
drums
overpacked
in
an
SWB,
overpacked
in
a
TDOP
is
equivalent
to
eight
55­
gallon
drums
overpacked
in
two
SWBs
with
two
filters
each
in
a
TRUPACT­
II.
Therefore,
the
shipping
category
and
decay
heat
limit
for
a
55­
gallon
drum
overpacked
in
a
SWB,
overpacked
in
a
TDOP,
is
the
same
as
a
55­
gallon
drum
that
is
overpacked
in
a
SWB
with
two
filters
(
i.
e.,
SWB
Overpack)
listed
in
the
TRUCON
document.
For
example:
if
the
shipping
category
for
an
SWB
Overpack
(
i.
e.,
55­
gallon
drums
overpacked
in
an
SWB)
of
TRUCON
code
RF116A
waste
is
3003400215,
then,
this
shipping
category
(
3003400215)
would
also
be
the
shipping
category
for
each
of
4
55­
gallon
drums
of
TRUCON
code
RF116A
waste
overpacked
in
a
SWB,
overpacked
in
a
TDOP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
193
6.5.2.2
Analytical
Category
Compliance
(
continued)

 
One
SWB
overpacked
in
a
TDOP
is
equivalent
to
two
SWBs
in
a
TRUPACT­
II.
Therefore,
the
shipping
category
and
decay
heat
limit
for
an
SWB
overpacked
in
a
TDOP
is
the
same
as
a
non­
overpacked
SWB
listed
in
the
TRUCON
document.
For
example:
if
the
shipping
category
for
an
SWB
of
TRUCON
code
RF117A
waste
is
2001700041,
then,
this
shipping
category
(
2001700041)
would
also
be
the
shipping
category
for
an
SWB
of
TRUCON
code
RF117A
waste
overpacked
in
a
TDOP.

 
Six
55­
gallon
drums
in
six
85­
gallon
drums,
overpacked
in
a
TDOP,
is
equivalent
to
eight
55­
gallon
drums
overpacked
in
two
SWBs
with
two
filters
each
in
a
TRUPACT­
II.
Therefore,
the
shipping
category
and
decay
heat
limit
for
a
55­
gallon
drum
overpacked
in
an
85­
gallon
drum,
overpacked
in
a
TDOP,
is
the
same
as
a
55­
gallon
drum
that
is
overpacked
in
a
SWB
with
two
filters
(
i.
e.,
SWB
Overpack)
listed
in
the
TRUCON
document.
For
example:
if
the
shipping
category
for
an
SWB
Overpack
(
i.
e.,
55­
gallon
drums
overpacked
in
an
SWB)
of
TRUCON
code
RF116A
waste
is
3003400215,
then,
this
shipping
category
(
3003400215)
would
also
be
the
shipping
category
for
each
of
six
55­
gallon
drums
of
TRUCON
code
RF116A
waste
overpacked
in
an
85­
gallon
drum,
overpacked
in
a
TDOP.

The
decay
heat
within
each
payload
package
plus
the
measurement
error
shall
be
less
than
or
equal
to
the
decay
heat
limit
shown
in
Table
6­
7
for
each
authorized
payload
shipping
category.

NOTE:
If
the
payload
package
meets
the
watt*
year
criteria
of
>
0.012,
the
shipping
category
reflecting
the
dose­
dependent
G
value
and
the
associated
decay
heat
limit
applies.

The
decay
heat
limit
for
an
authorized
shipping
category
associated
with
an
SWB
overpack
configuration
(
i.
e.,
drums
overpacked
in
SWBs)
applies
to
each
overpacked
drum
within
the
SWB
and
not
the
entire
SWB
itself.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
194
6.5.2.2
Analytical
Category
Compliance
(
continued)

The
total
decay
heat
from
all
payload
packages
in
a
TRUPACT­
II
shall
be
less
than
or
equal
to
40
watts.

NOTE:
Decay
heat
error
refers
to
standard
error
(
i.
e.,
decay
heat
error
at
one
standard
deviation
=
1
sigma).

WEMS
and
associated
software
specifications
define
the
methods
and
controls
that
WEMS
uses
to
calculate
the
decay
heat
for
each
payload
package.
The
e­
TRAMPAC
software
system
in
the
WWIS
also
calculates
decay
heat
for
each
payload
package
and
verifies
compliance
with
decay
heat
restrictions
prior
to
WWIS
approval.
Furthermore,
the
e­
TRAMPAC
system
provides
the
methods
and
controls
used
for
calculation
of
decay
heat
for
assembled
TRUPACT­
II
payloads.
These
software
specifications/
systems
provide
the
methodology
used
to
ensure
compliance
with
the
decay
heat
limits
in
Table
6­
7
and
verify
that
the
decay
heat
limits
are
not
exceeded.

Verification
that
correct
data
is
input
and
used
by
WEMS
for
calculation
of
decay
heats
is
performed
during
the
"
WIPP
Verify"
and
"
Radioactive
Verify"
functions
described
in
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.

Verification
of
compliance
with
decay
heat
restrictions
for
each
individual
payload
package
is
performed
as
part
of
the
waste
certification
process
as
described
in
PROX05
WC­
4018,
Transuranic
(
TRU)
Waste
Certification.
Verification
of
calculated
payload
decay
heat
values
are
performed
by
the
TCO
prior
to
transport
in
a
TRUPACT­
II
package
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.

Compliance
with
the
above
criteria
is
shown
by
ensuring
that
the
waste
is
listed
in
the
TRUCON
document,
and
that
the
restrictions
associated
with
the
shipping
category
assignment
are
met.
Section
6.5.1
of
this
document
describes
procedures
and
methods
for
meeting
shipping
category
criteria.
If
the
payload
package
meets
the
analytical
decay
heat
limit,
compliance
with
the
flammable
(
gas/
VOC)
limits
is
ensured.
If
the
payload
package
exceeds
the
analytical
decay
heat
limit,
compliance
with
the
flammable
(
gas/
VOC)
concentration
limits
may
be
demonstrated
through
mixing
the
package
in
a
payload
assembly
of
different
shipping
categories
as
described
in
Section
6.6.2.5
or
by
measurement/
test
as
described
in
Section
6.5.2.3.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
195
6.5.2.3
Test
Category
Compliance
Compliance
with
the
flammable
(
gas/
VOC)
concentration
limits
is
demonstrated
under
the
test
category
if
the
payload
package
meets
one
or
more
of
the
following
conditions:

 
The
total
concentration
of
potentially
flammable
VOCs
within
the
payload
package
headspace
exceeds
500
ppm.
Waste
Types
I
(
10),
II
(
20),
and
III
(
30)
belong
in
this
category.

 
The
decay
heat
loading
of
the
payload
package
exceeds
the
analytical
limit
for
the
shipping
category
of
that
payload
package.
Waste
Types
I
(
10),
II
(
20),
and
III
(
30)
belong
in
this
category.

 
A
waste
form
does
not
have
a
fully
characterized
bounding
G
value
from
previous
sampling
or
waste
stream
analysis.
Waste
Type
IV
(
40)
belongs
to
this
category.

The
packages
classified
as
test
category
waste
shall
meet
all
other
restrictions
of
this
document,
including
the
40­
watt
limit
on
total
decay
heat
from
all
payload
packages
in
a
TRUPACT­
II.

RFETS
qualifies
test
category
payload
packages
for
shipment
by
the
following
methods:

 
Measurement
 
Full­
Drum
Testing.

NOTE:
The
compliance
evaluation
described
in
this
section
assumes
that
the
payload
package
under
consideration
is
proposed
for
shipment
with
payload
packages
belonging
to
the
same
or
an
equivalent
shipping
category.
If
the
payload
package
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
packages
of
different
shipping
categories
and/
or
dunnage
packages,
compliance
is
evaluated
as
described
in
Section
6.6.2.5.
However,
the
data
obtained
from
the
performance
of
measurement
or
testing
may
be
used
in
the
compliance
demonstration
described
in
Section
6.6.2.5.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
196
6.5.2.3.1
Measurement
If
the
payload
package
exceeds
the
analytical
decay
heat
limit
and/
or
its
headspace
flammable
VOC
concentration
exceeds
500
ppm,
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
may
be
based
on
measurement
of
the
headspace
gas.
This
method
is
applicable
only
to
Waste
Types
I
(
10),
II
(
20),
and
III
(
30).

NOTE:
Full­
drum
testing
(
Section
6.5.2.3.2)
may
be
implemented
instead
of
measurement
to
qualify
test
category
waste
for
shipment.

RFETS
performs
headspace
gas
measurements
in
accordance
with
L­
4146,
Headspace
Gas
Sampling
of
Waste
Containers1;
L­
4231,
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold2;
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System;
and
L­
4111,
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization1.
For
overpacked
payload
packages,
measurement
of
the
payload
package
headspace
is
performed
prior
to
the
overpacking.
For
all
payload
packages,
flammable
(
gas/
VOC)
concentrations
may
be
conservatively
measured
in
an
inner
layer
of
confinement
rather
than
the
payload
package
headspace.

The
concentration
of
methane
present
in
the
headspace
of
the
payload
package
may
be
estimated
in
accordance
with
the
Quality
Assurance
Program
Plan
for
TRUPACT­
II
Gas
Generation
Test
Program
(
GGTP
QAPP)
and
RS­
020­
001,
Gas
Generation
Testing
Program
Quality
Assurance
Project
Plan
(
GGTP
QAPjP),
or
be
measured
in
accordance
with
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System;
L­
4231,
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold2;
L­
4146,
Headspace
Gas
Sampling
of
Waste
Containers1;
and
L­
4111,
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization1.
If
the
payload
package
headspace
methane
concentration
exceeds
1,250
ppm,
the
payload
package
is
not
eligible
for
shipment
and
must
be
segregated
for
repackaging,
treatment,
or
other
mitigation
measures.
If
the
payload
package
headspace
methane
concentration
is
less
than
or
equal
to
1,250
ppm,
and
the
payload
is
to
be
assembled
with
payload
packages
of
different
shipping
categories,
compliance
shall
proceed
according
to
the
methodology
described
in
Section
6.5.2.4.
Otherwise,
the
flammable
(
gas/
VOC)
concentration
within
the
innermost
layer
of
confinement
is
determined
using
the
measured
headspace
flammable
(
gas/
VOC)
concentrations
and
the
time
history
of
the
payload
package
as
described
in
Appendices
5.7
and
5.8
of
the
TRAMPAC.

1
These
procedures
are
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.
2
This
procedure
has
been
cancelled
as
of
June
18,
2003,
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
197
6.5.2.3.1
Measurement
(
continued)

Using
the
headspace
gas
measurement
and
the
time
history
of
the
payload
package,
a
mixture
lower
explosive
limit
(
MLEL)
(
or
flammable
gas
generation
rate)
is
calculated
as
described
in
Appendix
5.7
of
the
TRAMPAC.
If
the
sum
of
the
flammable
(
gas/
VOC)
concentration
in
the
innermost
layer
of
confinement
meets
the
MLEL,
the
payload
package
may
be
qualified
for
shipment.
If
not,
the
payload
package
must
be
subjected
to
Full­
Drum
Testing
as
described
in
Section
6.5.2.3.2.

The
WEMS
software
evaluates
the
headspace
methane
concentration
measurement
and
prevents
any
payload
package
that
exceeds
the
1,250
ppm
limit
from
being
verified
during
the
"
WIPP
Verify"
function
as
described
in
procedure
4­
G83­
WEMWP
1209,
WEMS
Waste
Package
Verification
and
Certification.

WEMS
and
associated
software
specifications
define
the
methods
and
controls
that
WEMS
uses
to
calculate
the
MLEL
for
each
payload
package.
These
software
specifications
also
provide
the
methodology
used
by
WEMS
to
ensure
compliance
with
the
applicable
MLEL
and
verify
that
the
MLEL
is
not
exceeded.
Additionally,
all
payload
packages
are
processed
through
the
e­
TRAMPAC
software
system
in
WWIS.
The
e­
TRAMPAC
system
also
verifies
compliance
with
the
applicable
MLEL
and
verifies
that
the
MLEL
is
not
exceeded.

Verification
that
correct
data
is
input
and
used
by
WEMS
for
calculation
of
MLEL
is
performed
during
the
"
WIPP
Verify"
and
"
Radioactive
Verify"
functions
described
in
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.

6.5.2.3.2
Full­
Drum
Testing
If
the
payload
package
exceeds
the
MLEL
(
as
described
in
Section
6.5.2.3.1)
or
is
Waste
Type
IV
(
40),
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
may
be
based
on
the
results
of
full­
drum
testing,
which
quantifies
the
gas
generation
rate
of
the
payload
package.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
198
6.5.2.3.2
Full­
Drum
Testing
(
continued)

Prior
to
full­
drum
testing,
the
concentration
of
methane
present
in
the
headspace
of
the
payload
package
must
be
estimated
in
accordance
with
RS­
020­
001,
GGTP
QAPjP,
or
be
measured
in
accordance
with
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
line
Integrated
System;
L­
4231,
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold1;
L­
4146,
Headspace
Gas
Sampling
of
Waste
Containers2;
and
L­
4111,
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization2.
If
the
payload
package
headspace
methane
concentration
exceeds
1,250
ppm,
the
payload
package
is
not
eligible
for
shipment
and
must
be
segregated
for
repackaging,
treatment,
or
other
mitigation
measures.
If
the
payload
package
headspace
methane
concentration
is
less
than
or
equal
to
1,250
ppm,
and
the
payload
is
to
be
assembled
with
payload
packages
of
different
shipping
categories,
compliance
shall
proceed
according
to
the
methodology
described
in
Section
6.5.2.4.
Otherwise,
the
total
gas
generation
rate
is
determined
from
fulldrum
testing
as
described
in
the
TRAMPAC,
Appendix
5.7.

RFETS
performs
full­
drum
testing
in
accordance
with
RS­
020­
001,
GGTP
QAPjP
and
the
criteria
specified
in
Table
6­
8.
Full­
drum
testing
is
accomplished
under
the
QA
program
defined
by
RS­
020­
001,
GGTP
QAPjP,
which
ensures
compliance
with
the
GGTP
QAPP.
For
overpacked
payload
packages,
full­
drum
testing
is
to
be
performed
prior
to
the
overpacking.

As
applicable,
if
the
determined
total
gas
generation
rate
exceeds
the
limit
for
the
appropriate
shipping
category,
mitigation
measures
must
be
taken
or
the
payload
package
may
be
evaluated
for
compliance
within
a
payload
assembly
of
different
shipping
categories
as
described
in
Section
6.6.2.5.
If
the
determined
total
gas
generation
rate
is
less
than
or
equal
to
the
limit
for
the
appropriate
shipping
category
as
specified
in
Table
6­
9,
the
flammable
gas
concentration
within
the
innermost
layer
of
confinement
must
be
determined
using
the
data
from
the
testing
as
described
in
the
TRAMPAC,
Appendices
5.7
and
5.8.
A
specific
MLEL
(
or
flammable
gas
generation
rate)
is
calculated
for
the
payload
package
as
described
in
the
TRAMPAC,
Appendix
5.7.
If
the
sum
of
the
flammable
gas
and
VOC
concentrations
exceeds
the
MLEL,
the
payload
package
does
not
comply
with
flammable
(
gas/
VOC)
limits.
Either
mitigation
measures
must
be
taken
or
the
payload
package
may
be
evaluated
for
compliance
within
a
payload
assembly
of
different
shipping
categories
as
described
in
Section
6.6.2.5.
If
the
flammable
(
gas/
VOC)
concentration
is
less
than
or
equal
to
the
MLEL,
the
payload
package
may
be
qualified
for
shipment.

1
This
procedure
has
been
cancelled
as
of
June
18,
2003,
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.
2
These
procedures
are
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
199
6.5.2.3.2
Full­
Drum
Testing
(
continued)

The
WEMS
software
evaluates
the
headspace
methane
concentration
measurement
and
prevents
any
payload
package
that
exceeds
the
1,250
ppm
limit
from
being
verified
during
the
"
WIPP
Verify"
function
as
described
in
procedure
4­
G83­
WEMWP
1209,
WEMS
Waste
Package
Verification
and
Certification.

Pursuant
to
the
TRAMPAC,
for
applicable
shipping
categories,
total
gas
generation
rate
data
are
input
to
WEMS.
The
WEMS
software
prevents
any
payload
package
that
exceeds
the
total
gas
generation
rate
limit
for
the
appropriate
shipping
category
from
being
verified
during
the
"
WIPP
Verify"
function
as
described
in
procedure
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.

WEMS
and
associated
software
specifications
define
the
methods
and
controls
that
WEMS
uses
to
calculate
the
MLEL
for
each
payload
package.
These
software
specifications
also
provide
the
methodology
used
by
WEMS
to
ensure
compliance
with
the
applicable
MLEL
and
verify
that
the
MLEL
is
not
exceeded.
Additionally,
all
payload
packages
are
processed
through
the
e­
TRAMPAC
software
system
in
WWIS.
The
e­
TRAMPAC
system
also
verifies
compliance
with
the
applicable
MLEL
and
verifies
that
the
MLEL
is
not
exceeded.

Verification
that
correct
data
is
input
and
used
by
WEMS
for
calculation
of
MLEL
is
performed
during
the
"
WIPP
Verify"
and
"
Radioactive
Verify"
functions
described
in
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.

6.5.2.4
Mixing
of
Shipping
Categories
in
a
Payload
Assembly
In
accordance
with
Appendix
6.3
of
the
TRAMPAC,
an
assembly
may
be
made
up
of
payload
packages
with
different
shipping
categories
by
ensuring
that
each
payload
package
does
not
contain
a
flammable
mixture
of
gases.
The
flammability
index
(
FI)
is
assessed
for
each
payload
package,
which
accounts
for
the
properties
of
each
of
the
other
packages
in
the
assembly.
Section
6.6.2.5
describes
the
procedure
for
qualifying
an
assembly
of
payload
packages
with
different
shipping
categories.
Unlimited
mixing
of
shipping
categories
within
a
single
payload
package
type
is
allowed
for
direct
loaded
payload
configurations,
with
the
FIs
calculated
based
on
each
payload
package
in
the
assembly.

For
payload
assemblies
comprised
of
overpacked
payload
configurations,
mixing
of
shipping
categories
is
allowed
provided
that
all
payload
packages
being
overpacked
meet
the
lowest
decay
heat
limit
or
lowest
hydrogen
gas
generation
rate
limit
("
governing
limit")
of
all
the
payload
packages
in
the
payload
assembly.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
200
6.5.3
Venting
and
Aspiration
6.5.3.1
Requirements
This
requirement
applies
only
to
unvented
payload
packages.
Payload
packages
that
have
been
stored
in
an
unvented
condition
(
i.
e.,
no
filter
and/
or
unpunctured
rigid
liner)
SHALL
be
aspirated
for
the
specific
length
of
time
to
ensure
equilibration
of
any
gases
that
may
have
accumulated
in
the
closed
payload
package.
For
payload
packages
with
waste
types
in
packaging
configurations
that
do
NOT
generate
any
flammable
gas,
aspiration
is
NOT
required
(
i.
e.,
Waste
Material
Type
II.
2)
(
Section
5.9.1
of
the
TRAMPAC).

6.5.3.2
Methods
of
Compliance
and
Verification
Three
options
are
available
for
meeting
aspiration
requirements
as
follows:

 
Option
1
­
Aspiration
Time
Based
on
Date
of
Payload
Package
Closure.
Compliance
shall
be
by
records
and
database
information.
For
this
option,
the
steps
outlined
below
shall
be
implemented
to
determine
the
aspiration
time
for
a
payload
package.

1.
The
potential
shipping
category
of
the
payload
package
shall
be
known.

2.
The
duration
for
which
the
payload
package
has
been
in
a
closed
condition
should
be
computed
from
a
knowledge
of
the
date
of
closure
of
the
drum.
This
closure
time
should
be
rounded
up
to
the
next
highest
time
period
listed
in
the
TRAMPAC,
Appendix
5.9,
Tables
5.9­
1
through
5.9­
3.

3.
The
required
aspiration
time
corresponding
to
this
closure
time
shall
then
be
read
from
the
same
table
under
the
column
listing
the
number
of
layers
of
confinement
associated
with
the
potential
shipping
category
of
the
payload
package.

4.
The
payload
package
shall
be
qualified
for
shipment
only
after
being
aspirated
for
at
least
this
period
of
time.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
201
6.5.3.2
Methods
of
Compliance
and
Verification
(
continued)

 
Option
2
­
Headspace
Gas
Sampling
at
the
Time
of
Venting.
Compliance
shall
be
by
measurement
of
headspace
gas
concentrations
and
records.
For
this
option,
the
steps
outlined
below
shall
be
implemented
to
determine
the
aspiration
time
for
a
payload
package.

1.
The
potential
shipping
category
of
the
payload
package
shall
be
known.

2.
At
the
time
of
venting,
a
headspace
sample
shall
be
taken
from
the
payload
package
headspace
(
Option
2A)
or
from
the
rigid
liner
headspace
(
Option
2B)
and
analyzed
for
the
hydrogen
concentration.

3.
The
measured
headspace
concentration
of
all
hydrogen
shall
be
rounded
up
to
the
next
highest
mole
percentage
listed
in
the
TRAMPAC,
Appendix
5.9,
Tables
5.9­
4
through
5.9­
9,
determined
by
Option
2A
or
2B,
as
appropriate.

4.
The
required
aspiration
time
corresponding
to
this
molar
percentage
shall
then
be
read
from
the
same
table
under
the
column
listing
the
number
of
layers
of
confinement
associated
with
the
potential
shipping
category
of
the
payload
package.

5.
The
payload
package
shall
be
qualified
for
shipment
only
after
being
aspirated
for
at
least
this
period
of
time.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
202
6.5.3.2
Methods
of
Compliance
and
Verification
(
continued)

 
Option
3
­
Headspace
Gas
Sampling
During
Aspiration.
Compliance
shall
be
by
direct
measurement
of
the
headspace
gas
concentration.
For
this
option,
the
steps
outlined
below
shall
be
implemented
to
determine
the
aspiration
time
for
a
payload
package.

1.
The
potential
shipping
category
of
the
payload
package
shall
be
known.

2.
Prior
to
measuring
the
hydrogen
concentration
in
the
payload
package
headspace,
the
drum
shall
be
vented
for
at
least
two
weeks.

3.
The
measured
headspace
concentration
of
hydrogen
shall
be
rounded
up
to
the
next
highest
mole
percentage
listed
in
the
TRAMPAC,
Appendix
5.9,
Tables
5.9­
10
through
5.9­
12.

4.
The
required
aspiration
time
corresponding
to
this
molar
percentage
shall
then
be
read
from
the
same
table
under
the
column
listing
the
number
of
layers
of
confinement
associated
with
the
potential
shipping
category
of
the
payload
package.

5.
The
payload
package
shall
be
qualified
for
shipment
only
after
being
aspirated
for
this
period
of
time.

Venting
and
aspiration
of
unvented
payload
packages
is/
was
performed
in
accordance
with
procedures
PRO­
1351­
440­
SWB,
Perma­
Con
Operations;
PRO­
717­
HDGAS­
371,
Headspace
Gas
Sampling,
Building
3711;
or
PRO­
1141­
WP­
4701,
Waste
Characterization
Gas
Sampling2.
Vent/
Puncture
dates
are
entered
into
WEMS
as
a
start
date
for
determining
aspiration
time.

Aspiration
times
are
determined
in
accordance
with
the
applicable
aspiration
method
and
are
also
entered
into
WEMS
per
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification.
WEMS
software
controls
ensure
that
applicable
payload
packages
aspirate
longer
than
the
required
aspiration
period
prior
to
being
certified
and
shipped.

1
This
procedure
is
inactive
as
of
May
12,
2003.
Headspace
gas
sampling
in
Building
371
has
been
discontinued.
2
This
procedure
is
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
203
6.6
Payload
Assembly
Requirements
This
section
presents
an
overview
of
the
control
procedures
that
shall
be
used
to
assemble
a
payload
qualified
for
transport
in
the
TRUPACT­
II.
The
parameters
described
in
previous
sections
shall
be
evaluated
for
selection
of
a
payload.
The
flowchart
of
transport
requirements
for
a
payload
package
is
shown
in
Figure
6­
2.
The
container
identification
(
ID)
number
shall
uniquely
identify
the
payload
package.
Each
payload
package
shall
have
an
assigned
shipping
category
and
content
code.
Wherever
applicable,
the
measured
parameters
(
weight,
fissile
material,
and
the
decay
heat)
shall
be
checked
against
the
limits
after
addition
of
the
measurement
error,
as
detailed
in
previous
sections.
If
any
of
the
limits
are
not
met
by
the
package,
it
shall
be
rejected
from
transport
(
subject
to
mitigation
or
repackaging),
marked,
and
segregated.

Assembled
payloads
shall
comply
with
the
authorized
payload
configurations
specified
in
Section
6.2.1.1
of
this
document.
A
TRUPACT­
II
payload
may
be
assembled
of
payload
packages
belonging
to
the
same
shipping
category,
equivalent
shipping
categories,
or
different/
nonequivalent
shipping
categories
(
e.
g.,
payload
may
consist
of
several
shipping
categories
and/
or
may
take
credit
for
void
volume
provided
by
dunnage
packages).
The
logic
for
selecting
a
payload
qualified
for
transport
in
the
TRUPACT­
II
when
all
payload
packages
belong
to
the
same
or
equivalent
shipping
category
is
presented
in
Figure
6­
3.
Payload
selection
shall
be
made
from
only
those
payload
packages
that
have
been
approved
for
shipment.
A
payload
comprised
of
individual
payload
packages
selected
from
the
same
or
equivalent
shipping
categories
shall
meet
the
requirements
for
weight,
center
of
gravity,
dose
rate,
fissile
quantity
limits,
and
decay
heat
limits
on
the
total
TRUPACT­
II
payload.
Payload
packages
belonging
to
different/
nonequivalent
shipping
categories
may
be
assembled
in
a
single
payload
(
with
or
without
dunnage
packages)
in
accordance
with
the
criteria
described
in
Section
6.6.2.5.

6.6.1
Requirements
Once
compliance
with
all
transportation
parameter
requirements
is
verified
and
Appendix
7
or
Appendix
8
(
and
Appendix
9,
as
applicable)
is
completed,
the
TRUPACT­
II
package
shall
be
authorized
for
shipment
by
the
site
TCO
by
completing
and
signing
the
PATCD
(
Appendix
6).
Shipping
records
shall
be
maintained
by
the
shipper
for
a
minimum
period
of
3
years.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
204
6.6.2
Methods
of
Compliance
and
Verification
Shipping
records
are
maintained
for
a
minimum
period
of
3
years
in
accordance
with
the
applicable
Records
Inventory
Disposition
Schedule
(
RIDS)
and
procedure
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center.

NOTE:
The
text
in
Sections
6.6.2.1
through
6.6.2.4
providing
instructions
for
payload
packages
and
assembly
qualification
is
reproduced
from
the
TRAMPAC.

6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)

RFETS
qualifies
an
individual
payload
package
for
transport
in
a
TRUPACT­
II
under
the
analytical
category
by
verifying
that
the
payload
package
meets
the
parameter
requirements/
limits
listed
in
Appendix
7,
PCTCD,
Analytical
Category
and,
if
applicable,
the
OPCTCD
in
Appendix
9.
The
PCTCD
is
completed
for
each
payload
package
to
be
directly
loaded
into
the
ICV.
If
overpack
payload
configurations
are
used,
the
PCTCD
is
completed
for
each
payload
package
to
be
overpacked,
and
the
OPCTCD
is
completed
for
the
payload
package
overpacking
the
other
payload
package(
s).
For
example,
if
four
55­
gallon
drums
are
overpacked
in
one
SWB,
the
PCTCD
is
completed
separately
for
each
55­
gallon
drum,
and
the
OPCTCD
is
completed
once
for
the
SWB.
However,
pipe
overpack
configurations
do
not
require
the
completion
of
the
OPCTCD.
Appendices
7
and
9
are
reproductions
of
the
forms
as
shown
in
the
TRAMPAC
and
are
reformatted
in
RFETS
procedures.
All
parameters
noted
on
the
original
TRAMPAC
form
are
included
in
the
modified
version.
Data
on
the
parameters
for
specific
payloads
are
obtained
by
the
methods
outlined
in
this
document
and
are
consistent
with
the
information
for
each
parameter
provided
in
the
TRUCON.

Appendix
7
is
completed
as
follows
(
The
section
numbers
in
parentheses
refer
to
sections
in
this
document
that
provide
requirement,
compliance,
and
verification
information
for
the
transportation
parameter
described):

 
Container
ID/
Container
Bar
Code
#
(
Section
6.2.4):
The
site­
specific
ID
number
is
unique
to
each
container
of
waste
(
payload
package)
and
provides
a
means
for
tracking
process
data
records
and
package
history.
These
records
on
the
properties
of
the
payload
package
are
referred
to
as
the
data
package.
The
container
ID
number
is
assigned
to
the
payload
package
prior
to
waste
packaging.
The
ID
number
appears
on
a
label
affixed
to
the
payload
package
and
can
be
read
for
visual
verification
or
for
electronic
retrieval
(
i.
e.,
bar
codes).
Information
necessary
for
transporting
payload
packages
is
entered
into
the
data
package
under
this
ID
number.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
205
6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)
(
continued)

 
Shipping
Category
(
Section
6.5.1):
The
proper
shipping
category
is
assigned
to
the
payload
package
either
by
1)
completing
the
Numeric
Payload
Shipping
Category
Worksheet
(
Appendix
5)
and
comparing
the
results
to
the
allowed
shipping
category
for
the
appropriate
content
code
in
the
TRUCON;
or
2)
by
choosing
the
appropriate
shipping
category
from
the
list
of
allowable
shipping
categories
for
the
content
code
in
the
TRUCON.
If
the
shipping
category
determined
by
completing
the
worksheet
does
not
match
any
of
the
shipping
categories
contained
in
the
TRUCON
for
the
content
code,
the
payload
package
is
not
eligible
for
shipment.

 
Content
Code
(
Section
6.5.1):
The
content
code
from
the
data
package
for
the
payload
package
is
approved
as
part
of
the
TRUCON
document
and
is
listed
in
Table
6­
7.
If
the
content
code
is
not
listed
in
the
TRUCON
document,
it
is
not
eligible
for
shipment.
The
methodology
by
which
a
shipping
category
is
assigned
to
a
content
code
is
shown
in
Figure
6­
4.
The
content
code
of
the
waste
determines
its
physical
and
chemical
form.
The
TRUCON
is
a
comprehensive
catalogued
description
of
this
flowchart
for
all
content
codes
that
are
allowed
to
be
transported
from
all
the
DOE
sites.

 
Container
Configuration
(
Section
6.2.1):
Select
the
appropriate
payload
package
configuration.
The
packages
shall
be
one
of
the
approved
types
in
one
of
the
following
authorized
configurations:

 
Direct
Load
Configurations:

 
55­
Gallon
Drum:
Waste
directly
loaded
into
one
55­
gallon
drum.
Complete
the
PCTCD
for
the
55­
gallon
drum.

 
100­
Gallon
Drum:
Waste
directly
loaded
into
one
100­
gallon
drum.
Complete
the
PCTCD
for
the
100­
gallon
drum.

 
SWB:
Waste
directly
loaded
into
one
SWB.
Complete
the
PCTCD
for
the
SWB.

 
TDOP:
Waste
directly
loaded
into
a
TDOP.
Complete
the
PCTCD
for
the
TDOP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
206
6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)
(
continued)

 
Container
Configuration
(
Section
6.2.1)
(
continued):

 
Fixed
Configurations:

 
Standard
POC:
Waste
packaged
in
one
pipe
component
overpacked
in
one
55­
gallon
drum,
as
described
in
Appendix
2.2
of
the
TRAMPAC.
Complete
the
PCTCD
for
the
standard
POC.

 
S100
POC:
Waste
packaged
in
one
pipe
overpacked
in
one
55­
gallon
drum,
as
described
in
Appendix
2.3
of
the
TRAMPAC.
Complete
the
PCTCD
for
the
S100
POC.

 
S200
POC:
Waste
packaged
in
one
pipe
overpacked
in
one
55­
gallon
drum,
as
described
in
Appendix
2.4
of
the
TRAMPAC.
Complete
the
PCTCD
for
the
S200
POC.

 
Bin
Overpack:
Waste
packaged
in
one
bin
overpacked
in
one
SWB.
Note:
the
bin
is
only
authorized
for
use
in
this
configuration.
Complete
the
PCTCD
for
the
bin
overpack.

 
85­
Gallon
Drum
Overpack:
Waste
packaged
in
one
55­
gallon
drum
overpacked
in
one
85­
gallon
drum.
Note
that
the
85­
gallon
drum
is
only
authorized
for
use
in
this
configuration.
Complete
the
PCTCD
for
the
85­
gallon
drum
overpack.

 
Overpacked
Configurations:

 
SWB
with
55­
Gallon
Drum(
s)
(
SWB
Overpack):
Waste
packaged
in
one
55­
gallon
drum
to
be
overpacked
in
one
SWB
(
up
to
four
55­
gallon
drums
per
SWB).
Complete
the
PCTCD
for
each
of
the
55­
gallon
drums
and
the
OPCTCD
for
the
SWB.

 
TDOP
with
55­
Gallon
Drum(
s):
Waste
packaged
in
one
55­
gallon
drum
to
be
overpacked
in
one
TDOP
(
up
to
ten
55­
gallon
drums
per
TDOP).
Complete
the
PCTCD
for
each
of
the
55­
gallon
drums
and
the
OPCTCD
for
the
TDOP.

 
TDOP
with
SWB
Overpack:
Waste
packaged
in
one
55­
gallon
drum
to
be
overpacked
in
one
SWB
(
up
to
four
55­
gallon
drums
per
SWB)
to
be
overpacked
in
one
TDOP
(
one
SWB
per
TDOP).
Complete
the
PCTCD
for
each
of
the
55­
gallon
drums
and
the
OPCTCD
once
for
the
SWB
and
once
for
the
TDOP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
207
6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)
(
continued)

 
Container
Configuration
(
Section
6.2.1)
(
continued):

 
Overpacked
Configurations
(
continued):

 
TDOP
with
85­
Gallon
Drum
Overpack(
s):
Waste
packaged
in
one
55­
gallon
drum
overpacked
in
one
85­
gallon
drum
to
be
overpacked
in
one
TDOP
(
up
to
six
85­
gallon
drum
overpacks
per
TDOP).
Complete
the
PCTCD
for
each
of
the
85­
gallon
drum
overpack(
s)
and
the
OPCTCD
for
the
TDOP.

 
TDOP
with
SWB:
Waste
packaged
in
one
SWB
to
be
overpacked
in
one
TDOP
(
one
SWB
per
TDOP).
Complete
the
PCTCD
for
the
SWB
and
the
OPCTCD
for
the
TDOP.

 
TDOP
with
Bin
Overpack:
Waste
packaged
in
one
bin
overpacked
in
one
SWB
to
be
overpacked
in
one
TDOP
(
one
bin
overpack
per
TDOP).
Complete
the
PCTCD
for
the
bin
overpack
and
the
OPCTCD
for
the
TDOP.

 
Certification
Site:
The
certification
site
is
recorded
as
the
location
at
which
transportation
certification
occurs.
For
newly
generated
waste,
this
is
the
generating
site.
For
retrievably
stored
waste,
it
may
be
either
the
generating
or
storage
site.

TRAMPAC
Transportation
Parameters
Compliance
information
for
the
TRAMPAC
transportation
parameters
shall
be
obtained
from
the
data
package
for
the
payload
package.
The
TCO
shall
indicate
compliance
with
each
requirement
in
the
space
provided.
The
following
criteria
shall
be
met:

 
Free
liquids
 
1
percent
of
payload
package
volume
(
Section
6.2.6).

 
Non­
radioactive
pyrophorics
are
not
present
(
Section
6.4.1).

 
Radioactive
pyrophorics
are
<
1
weight
percent
(
Section
6.4.1).

 
Explosives
are
not
present
(
Section
6.4.2).

 
Corrosives
are
not
present
(
Section
6.4.2).

 
Pressurized
containers
are
not
present
(
Section
6.4.2).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
208
6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)
(
continued)

TRAMPAC
Transportation
Parameters
(
continued)

 
Sealed
containers
>
4
liters
are
not
present,
except
for
Waste
Material
Type
II.
2
packaged
in
metal
cans
(
Section
6.2.8).

 
Drum
liner
(
if
present)
is
punctured/
filtered
(
Section
6.5.1.2.3).

 
Flammable
VOCs
 
500
ppm
in
payload
package
headspace
(
Section
6.5.2).

 
Radiation
dose
rates
 
200
mrem/
hr
at
surface
of
payload
package
(
Section
6.3.2).
If
the
payload
package
is
overpacked,
the
limit
applies
only
to
the
outermost
payload
package.

 
Filter
Identification
(
Section
6.2.5):
Identification
is
listed
for
the
type
and
appropriate
number
of
filters
as
determined
by
payload
package
type.
If
the
PCTCD
is
being
completed
for
a
fixed
configuration,
filter
information
is
listed
for
both
payload
packages.

Measured
Parameters
 
Weight
(
Section
6.2.3):
The
maximum
allowable
weight
for
the
appropriate
payload
package
type
shall
be
recorded.
If
the
payload
package
will
be
overpacked,
the
limit
for
the
maximum
allowable
weight
applies
only
to
the
outermost
payload
package
of
the
overpacked
configuration.

The
measured
weight
of
the
payload
package
may
be
obtained
from
its
data
package.
The
measured
payload
package
weight
plus
the
measurement
error
(
one
standard
deviation)
shall
be
compared
to
the
maximum
allowable
weight
limit
for
the
appropriate
payload
package
type.
If
the
PCTCD
is
being
completed
for
a
payload
package
that
will
be
overpacked
and
the
weight
of
the
entire
overpack
configuration
will
be
determined,
the
recorded
weight
of
the
individual
payload
package
to
be
overpacked
is
not
required.
Alternatively,
the
weights
of
the
individual
payload
packages
and
the
weight
of
the
empty
overpack
package
may
be
summed
to
determine
the
total
measured
weight
of
the
overpacked
configuration
in
the
completion
of
the
OPCTCD.
The
measured
weight
of
the
individual
payload
package
may
be
recorded
in
the
PCTCD
for
later
use
in
completing
the
OPCTCD
for
the
overpacked
configuration.
The
weight
of
the
overpack
configuration
plus
the
measurement
error
shall
be
recorded
in
the
OPCTCD
and
compared
to
the
maximum
allowable
weight
limit
for
the
outermost
payload
package
of
the
overpack
configuration.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
209
6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)
(
continued)

Measured
Parameters
(
continued)

 
Decay
Heat
(
Section
6.5.2.2):
The
maximum
allowable
decay
heat
limit
per
payload
package
for
the
applicable
payload
shipping
category
shall
be
recorded
from
the
determination
made
pursuant
to
Section
6.5.2.2.
The
measured
decay
heat
plus
the
measurement
error
(
one
standard
deviation)
of
the
payload
package
may
be
obtained
from
its
data
package.
Measured
decay
heats
are
determined
from
the
isotopic
composition
and
quantity
of
radionuclides,
as
described
in
Section
6.5.2.2
of
this
document.
The
measured
decay
heat
plus
the
measurement
error
shall
be
compared
to
the
maximum
allowable
decay
heat
limit
per
payload
package
for
the
appropriate
shipping
category
if
the
anticipated
payload
consists
of
payload
packages
belonging
to
the
same
(
or
equivalent)
shipping
category.
For
these
configurations,
compliance
with
flammable
gas
generation
limits
is
determined
by
compliance
with
decay
heat
limits.
For
payload
assemblies
where
credit
is
taken
for
dunnage
or
different
shipping
categories,
the
flammability
index,
based
on
the
assembled
payload,
determines
compliance
with
flammable
gas
generation
limits,
as
described
in
Appendix
6.3
of
the
TRAMPAC.
The
flammability
index
in
this
case
is
recorded
in
the
PATCD.
For
these
configurations,
indicate
under
"
Limit"
that
a
decay
heat
limit
for
the
payload
package
is
not
applicable.

 
Fissile
Mass
(
FGE)
(
Section
6.3.1):
The
maximum
allowable
fissile
mass
limit
for
the
appropriate
payload
package
type
shall
be
recorded.
If
the
payload
package
will
be
overpacked,
the
limit
for
maximum
allowable
fissile
mass
applies
only
to
the
outermost
payload
package
of
the
overpacked
configuration.
The
measured
fissile
mass
of
the
payload
package
may
be
obtained
from
its
data
package.
The
measured
payload
package
fissile
mass
value
plus
two
times
the
measurement
error
(
two
standard
deviations)
shall
be
compared
to
the
maximum
allowable
fissile
mass
limit
for
the
appropriate
payload
package
type
and
waste
contents.
If
the
PCTCD
is
being
completed
for
a
payload
package
that
will
be
overpacked,
the
measured
fissile
mass
of
the
individual
payload
package
may
be
recorded
in
the
PCTCD
for
later
use
in
completing
the
OPCTCD
for
the
overpack
configuration.
The
measured
fissile
mass
plus
two
times
the
measurement
error
(
two
standard
deviations)
for
the
entire
overpack
configuration
shall
be
recorded
in
the
OPCTCD
and
compared
to
the
maximum
allowable
fissile
mass
limit
for
the
outermost
payload
package
of
the
overpack
configuration
and
the
waste
contents.

 
Curie
Limits
(
Section
6.3.2.1):
Curie
limits
for
specific
radionuclides
apply
to
S100
and
S200
POCs
only
and
are
presented
in
Appendices
2.3
and
2.4,
respectively,
of
the
TRAMPAC.
The
TCO
shall
verify
that,
for
all
applicable
radionuclides,
the
measured
value
plus
error
(
one
standard
deviation)
meets
the
appropriate
curie
limit.
Compliance
shall
be
documented
on
the
PCTCD.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
210
6.6.2.1
Procedure
for
Certification
of
Individual
Payload
Packages
(
Analytical
Category)
(
continued)

Unvented
Waste
Parameters
 
Aspiration
Method
(
Section
6.5.3):
This
portion
of
the
PCTCD
applies
to
retrievably
stored
waste
only.

 
Aspiration
Method:
Option
1,
2A,
2B,
or
3
is
indicated.

 
Container
Closed
Time
(
Option
1
Only):
The
period
of
time
that
a
payload
package
has
been
unvented
in
storage
is
recorded.

 
Headspace
Hydrogen
Concentration
(
Options
2A,
2B,
and
3):
The
concentration
of
hydrogen
measured
in
the
headspace
is
recorded.

 
Aspiration
Period/
Table:
The
aspiration
time
for
the
option
chosen
is
noted,
along
with
the
appropriate
table
from
which
the
value
was
derived
(
i.
e.,
TRAMPAC,
Appendix
5.9,
Tables
5.9­
1
through
5.9­
12).
If
the
hydrogen
concentration
indicates
that
aspiration
is
not
needed,
a
zero
shall
be
entered.

 
Time
Container
Vented:
Indicate
the
number
of
days
the
payload
package
has
vented.
Verify
that
the
time
the
package
was
vented
complies
with
the
prescribed
aspiration
time
recorded
above.

 
TCO
(
Section
6.1.6.1):
The
TCO
verifies
that
all
of
the
requirements
for
the
above
transportation
parameters
are
met
as
stated
in
this
document.
The
TCO
signs
and
dates
the
PCTCD
upon
completion,
thereby
authorizing
the
payload
package
for
TRUPACT­
II
transport
(
or
to
be
overpacked
in
another
payload
package,
in
which
case
the
OPCTCD
is
also
completed).
If
the
requirements
are
not
met,
the
payload
package
is
rejected
(
nonconformance
disposition)
and
not
qualified
for
shipment.

The
information
listed
in
Appendix
7
(
and
Appendix
9,
as
applicable)
is
recorded
in
WEMS,
and
the
applicable
PCTCD
is
generated
from
the
entered
information.
WEMS
software
controls
ensure
compliance
with
applicable
payload
package
restrictions.
Procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification,
provides
instructions
for
verifying
that
the
information
is
complete
and
in
compliance
with
applicable
restrictions
for
each
payload
package.
The
TCO
ensures
payload
compliance
with
the
TRUPACT­
II
restrictions
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.
Additionally,
all
payload
packages
are
processed
through
the
e­
TRAMPAC
software
system
in
WWIS.
The
e­
TRAMPAC
system
also
verifies
compliance
with
the
applicable
payload
package
restrictions.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
211
6.6.2.2
Procedure
for
Certification
of
Individual
Payload
Packages
(
Test
Category)

RFETS
qualifies
an
individual
payload
package
for
transport
in
a
TRUPACT­
II
under
the
test
category
by
verifying
that
the
payload
package
meets
the
parameter
requirements/
limits
listed
in
Appendix
8,
PCTCD,
Test
Category,
and
Appendix
9
OPCTCD,
if
applicable.
The
PCTCD
is
completed
for
each
payload
package
to
be
directly
loaded
into
the
ICV.
If
payload
packages
are
overpacked,
the
PCTCD
is
completed
for
each
payload
package
overpacked,
and
the
OPCTCD
is
completed
for
the
payload
package
overpacking
other
payload
packages.
Appendix
8
is
a
reproduction
of
the
form
as
shown
in
the
TRAMPAC
and
is
modified
in
RFETS
procedures.
All
parameters
noted
on
the
form
are
included
in
the
modified
version.
Data
on
the
parameters
for
specific
payload
packages
are
obtained
by
the
methods
outlined
in
this
document.

Appendix
8
is
completed
as
follows:

 
Complete
items
described
for
Appendix
7
as
directed
above.

 
The
test
criteria
data
are
obtained
from
the
test
procedure
of
each
payload
package.
If
the
Unified
Flammable
Gas
Test
Procedure
(
TRAMPAC,
Appendix
5.7)
is
implemented
for
a
payload
package,
the
test
criteria
are
obtained
from
Attachment
A
of
Appendix
5.7
of
the
TRAMPAC.
The
TCO
shall
verify
and
indicate
on
the
PCTCD
that
all
test
criteria
have
been
met
pursuant
to
Attachment
A
of
Appendix
5.7
of
the
TRAMPAC.

 
TCO
(
Section
6.1.6.1):
The
TCO
verifies
that
all
of
the
requirements
for
the
above
transportation
parameters
are
met
as
stated
in
this
document.
The
TCO
signs
and
dates
the
PCTCD
upon
completion,
thereby
authorizing
the
payload
package
for
TRUPACT­
II
transport
(
or
to
be
overpacked
in
another
payload
package,
in
which
case
the
OPCTCD
is
also
completed).
If
the
requirements
are
not
met,
the
payload
package
is
rejected
(
nonconformance
disposition)
and
not
qualified
for
shipment.

The
information
associated
with
Test
Category
waste
is
recorded
in
WEMS,
and
the
applicable
PCTCD
is
generated
from
the
entered
information.
WEMS
software
controls
ensure
compliance
with
applicable
payload
package
restrictions.
Procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification,
provides
instructions
for
verifying
that
the
information
is
complete
and
compliance
with
applicable
restrictions
for
each
payload
package.
The
TCO
ensures
payload
compliance
with
the
TRUPACT­
II
restrictions
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.
Additionally,
all
payload
packages
are
processed
through
the
e­
TRAMPAC
software
system
in
WWIS.
The
e­
TRAMPAC
system
also
verifies
compliance
with
the
applicable
payload
package
restrictions.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
212
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
Appendix
9,
the
OPCTCD,
shall
be
completed
for
each
payload
package
overpacking
other
payload
packages.
Appendix
9
is
a
reproduction
of
the
form
as
shown
in
the
TRAMPAC
and
is
modified
in
RFETS
procedures.
Data
on
the
parameters
for
specific
payload
packages
are
obtained
by
methods
outlined
in
this
document.
The
OPCTCD
shall
be
completed
as
follows
(
section
numbers
in
parentheses
refer
to
the
sections
in
this
document
that
provide
requirements
and
compliance
and
verification
information
for
the
transportation
parameters
described):

Identification
Parameters
 
Overpack
Container
ID#/
Overpack
Container
Bar
Code
#
(
Section
6.2.4):
The
site­
specific
ID
number
is
unique
to
each
container
of
waste
(
payload
package)
and
provides
a
means
for
tracking
process
data
records
and
package
history.
These
records
on
the
properties
of
the
payload
package
are
referred
to
as
the
"
data
package."
The
container
ID
number
is
assigned
to
the
payload
package
prior
to
waste
packaging.
The
ID
number
appears
on
a
label
affixed
to
the
payload
package
and
can
be
read
for
visual
verification
or
for
electronic
retrieval
(
i.
e.,
bar
codes).
Information
necessary
for
transporting
payload
packages
is
entered
into
the
data
package
under
this
ID
number.

 
Governing
Payload
Shipping
Category
Number
(
Section
6.5.1):
The
governing
shipping
category
for
the
overpack
configuration
shall
be
determined
by
selecting
the
payload
shipping
category
of
the
overpacked
package
with
either
the
lowest
decay
heat
limit
or
the
lowest
hydrogen/
flammable
gas
generation
rate
limit.
These
values
shall
be
determined
by
consulting
the
appropriate
PCTCDs
completed
for
the
payload
package(
s)
to
be
overpacked.
The
payload
package
type
shall
be
the
same
for
all
packages
overpacked
within
the
overpack
payload
package.

 
Governing
Decay
Heat
Limit
(
Section
6.5.2.2):
The
maximum
allowable
decay
heat
per
payload
package
for
the
governing
payload
shipping
category
of
the
overpacked
configuration
shall
be
recorded
from
Table
6­
7
or
derived
using
the
methodology
described
in
Appendix
5.5
of
the
TRAMPAC.

 
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
(
Section
6.5.2.2
or
6.5.2.3):
The
governing
flammable
gas
generation
rate
limit
for
the
overpack
is
recorded
either
from
Table
6­
7
or
determined
using
the
methodology
described
in
Appendix
5.5
(
for
analytical
category
waste)
or
from
Attachment
A
of
Appendix
5.7
(
for
test
category
waste)
of
the
TRAMPAC.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
213
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
(
continued)

Identification
Parameters
(
continued)

 
Overpack/
Overpacked
Container
Type
(
Section
6.2.1):
Select
the
appropriate
Overpack
Container
Type
and
Overpacked
Container
Type.
The
payload
package
shall
be
one
of
the
approved
types
in
one
of
the
following
authorized
configurations:

 
SWB:

 
SWB
with
55­
Gallon
Drum(
s)
(
SWB
Overpack):
Waste
packaged
in
55­
gallon
drum(
s)
overpacked
in
one
SWB
(
up
to
four
55­
gallon
drums
per
SWB).
Complete
the
OPCTCD
for
the
SWB
using
information
from
the
PCTCD,
which
shall
be
completed
separately
for
each
55­
gallon
drum.
Select
"
SWB"
as
the
Overpack
Container
Type
and
"
55­
Gallon
Drum"
as
the
Overpacked
Container
Type.

 
TDOP:

 
TDOP
with
55­
Gallon
Drum(
s):
Waste
packaged
in
55­
gallon
drum(
s)
overpacked
in
one
TDOP
(
up
to
ten
55­
gallon
drums
per
TDOP).
Complete
the
OPCTCD
for
the
TDOP
using
information
from
the
PCTCD,
which
shall
be
completed
separately
for
each
55­
gallon
drum.
Select
"
TDOP"
as
the
Overpack
Container
Type
and
"
55­
Gallon
Drum"
as
the
Overpacked
Container
Type.

 
TDOP
with
SWB:
Waste
packaged
in
one
SWB
overpacked
in
one
TDOP
(
one
SWB
per
TDOP).
Complete
the
OPCTCD
for
the
TDOP
using
information
from
the
PCTCD,
which
shall
be
completed
for
the
SWB.
Select
"
TDOP"
as
the
Overpack
Container
Type
and
"
SWB"
as
the
Overpacked
Container
Type.

 
TDOP
with
SWB
Overpack
­
Waste
packaged
in
55­
gallon
drum(
s)
overpacked
in
one
SWB
(
up
to
four
55­
gallon
drums
per
SWB)
overpacked
in
one
TDOP
(
one
SWB
per
TDOP).
Complete
the
OPCTCD
for
the
SWB
using
information
from
the
PCTCD,
which
shall
be
completed
separately
for
each
55­
gallon
drum.
Also
complete
the
OPCTCD
separately
for
the
TDOP
using
information
from
the
OPCTCD
completed
for
the
SWB
overpacked
in
the
TDOP.
On
the
OPCTCD
for
the
SWB,
select
"
SWB"
as
the
Overpack
Container
Type
and
"
55­
Gallon
Drum"
as
the
Overpacked
Container
Type.
On
the
OPCTCD
for
the
TDOP,
select
"
TDOP"
as
the
Overpack
Container
Type
and
"
SWB
Overpack"
as
the
Overpacked
Container
Type.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
214
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
(
continued)

Identification
Parameters
(
continued)

 
Overpack/
Overpacked
Container
Type
(
Section
6.2.1)
(
continued):

 
TDOP
(
continued):

 
TDOP
with
85­
Gallon
Drum
Overpack(
s)
­
Waste
packaged
in
one
55­
gallon
drum
overpacked
in
one
85­
gallon
drum
overpacked
in
one
TDOP
(
up
to
six
85­
gallon
drum
overpacks
per
TDOP).
Complete
the
OPCTCD
for
the
TDOP
using
information
from
the
PCTCD,
which
shall
be
completed
separately
for
each
85­
gallon
drum
overpack.
Select
"
TDOP"
as
the
Overpack
Container
Type
and
"
85­
Gallon
Drum
Overpack"
as
the
Overpacked
Container
Type.

 
TDOP
with
Bin
Overpack
­
Waste
packaged
in
one
bin
overpacked
in
one
SWB
overpacked
in
one
TDOP
(
one
bin
overpack
per
TDOP).
Complete
the
OPCTCD
for
the
TDOP
using
information
from
the
PCTCD,
which
shall
be
completed
for
the
bin
overpack.
Select
"
TDOP"
as
the
Overpack
Container
Type
and
"
Bin
Overpack"
as
the
Overpacked
Container
Type.

 
Weight
Limit
(
Section
6.2.3):
The
maximum
allowable
weight
limit
for
the
appropriate
overpacking
payload
package
type
(
i.
e.,
SWB
or
TDOP)
shall
be
recorded.
The
limit
applies
only
to
the
outermost
payload
package.
If
an
SWB
Overpack
will
be
overpacked
in
a
TDOP,
the
limit
for
maximum
allowable
weight
applies
only
to
the
TDOP
of
the
overpacked
configuration.

 
Fissile
Mass
Limit
(
Section
6.3.1):
The
maximum
allowable
fissile
mass
limit
for
the
appropriate
payload
package
type
(
i.
e.,
SWB
or
TDOP)
shall
be
recorded.
The
limit
applies
only
to
the
outermost
payload
package.

 
Certification
Site:
The
certification
site
shall
be
recorded
at
the
location
at
which
transportation
certification
occurs.

 
Content
Code
(
Section
6.5.1):
The
content
code
from
the
data
package
for
the
payload
package
shall
be
approved
as
described
in
Section
6.5.1.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
215
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
(
continued)

TRAMPAC
Transportation
Parameters
Compliance
information
for
the
TRAMPAC
transportation
parameters
shall
be
obtained
from
the
data
package
for
the
payload
package.
The
TCO
shall
indicate
compliance
with
each
requirement
in
the
space
provided.
The
following
criteria
shall
be
met:

 
Radiation
dose
rate
 

200
mrem/
hr
at
surface
of
payload
package
(
Section
6.3.2):
The
limit
applies
only
to
the
outermost
payload
package.
If
an
SWB
overpack
will
be
overpacked
in
a
TDOP,
the
limit
for
radiation
dose
rate
applies
only
to
the
TDOP.
Compliance
with
this
parameter
requirement
is
verified
by
completing
the
OPCTCD
separately
for
the
TDOP.

 
Filter
Identification
(
Section
6.2.5):
Identification
shall
be
listed
for
the
type
and
appropriate
number
of
filters
as
determined
by
payload
package
type
(
i.
e.,
SWB
or
TDOP).
See
Section
6.2.5
for
the
number
of
filters
required
for
each
package
type.

Overpacked
Container
Measured
Parameters
 
Overpacked
Container
ID
Number
(
Section
6.2.4):
List
the
site­
specific
identification
number
for
each
of
the
overpacked
payload
packages.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
216
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
(
continued)

Overpacked
Container
Measured
Parameters
(
continued)

 
Measured
Weight
and
Measurement
Error
(
Section
6.2.3):
The
measured
weight
and
measurement
error
(
one
standard
deviation)
for
each
overpacked
payload
package
or
the
entire
overpack
configuration
shall
be
recorded.
The
measured
weight
and
measurement
error
may
be
obtained
from
PCTCD(
s)
or
OPCTCD
for
each
overpacked
payload
package.
The
measured
weight
of
the
individual
overpacked
payload
packages
is
not
required
if
the
entire
overpack
configuration
will
be
weighed.
If
the
weight
of
each
individual
overpacked
payload
package
is
recorded,
enter
the
weight
and
measurement
error
(
one
standard
deviation)
of
the
empty
overpack
payload
package
on
the
last
row.

Calculate
the
total
weight
as
the
sum
of
each
of
the
individual
weights
(
including
the
weight
of
the
empty
overpack
container),
and
record
this
value
in
the
appropriate
box.
Calculate
the
root­
mean
square
(
RMS)
error
for
the
overpack
configuration
as
the
square
root
of
the
sum
of
the
squares
of
the
individually
listed
errors,
and
record
this
value
in
the
appropriate
box.
If
the
entire
overpack
configuration
is
weighed,
record
the
total
weight
of
the
overpack
configuration
and
the
measurement
error
(
one
standard
deviation)
in
the
appropriate
boxes
(
in
this
case,
the
measurement
error
is
the
same
as
the
RMS
error).

The
total
weight
plus
the
total
RMS
error
of
the
entire
overpack
configuration
shall
be
recorded
in
the
space
provided
and
compared
to
the
maximum
allowable
weight
limit
for
the
outermost
payload
package
of
the
overpack
configuration
(
i.
e.,
4,000
lbs.
per
SWB
or
6,700
lbs.
per
TDOP).
As
noted
previously,
if
an
SWB
Overpack
will
be
overpacked
in
a
TDOP,
the
limit
for
maximum
allowable
weight
applies
only
to
the
TDOP
of
the
overpacked
configuration.

 
Measured
Decay
Heat
and
Measurement
Error
(
Section
6.5.2.2):
The
measured
decay
heat
value
and
measurement
error
(
one
standard
deviation)
for
each
overpacked
analytical
category
payload
package
shall
be
recorded.
The
measured
decay
heat
value
and
measurement
error
may
be
obtained
from
the
PCTCD(
s)
or
OPCTCD
for
each
overpacked
payload
package.

For
analytical
category
payload
packages,
the
decay
heat
value
plus
the
measurement
error
for
each
payload
package
shall
be
compared
individually
to
the
Governing
Decay
Heat
Limit
for
the
overpacked
configuration.
The
spaces
provided
for
"
Total"
and
"
Total
RMS
Error"
are
for
use
in
completing
the
OPCTCD.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
217
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
(
continued)

Overpacked
Container
Measured
Parameters
(
continued)

 
Decay
Heat
Limit
(
Section
6.5.2.2):
For
analytical
category
payload
packages,
the
maximum
allowable
decay
heat
limit
per
overpacked
payload
package
for
the
applicable
payload
shipping
category
shall
be
recorded
from
the
PCTCD(
s)
or
OPCTCD.
The
decay
heat
limits
are
recorded
for
use
in
determining
the
governing
decay
heat
limit.

 
Measured
Fissile
Mass
(
FGE)
and
Measurement
Error
(
Section
6.3.1):
The
measured
fissile
mass
and
two
times
the
measurement
error
(
two
standard
deviations)
for
each
payload
package
shall
be
recorded
as
obtained
from
the
PCTCD(
s)
or
OPCTCD
for
each
overpacked
payload
package.

The
subtotal
fissile
mass
plus
the
total
RMS
error
(
RMS
of
twice
each
individual
measurement
error)
of
the
entire
overpack
configuration
shall
be
compared
to
the
maximum
allowable
fissile
mass
limit
for
the
outermost
payload
package
of
the
overpack
configuration
and
the
waste
contents.

 
Hydrogen/
Flammable
Gas
Generation
Rate
(
Section
6.5.2.3):
The
hydrogen/
flammable
gas
generation
rate
for
each
overpacked
test
category
payload
package
shall
be
recorded.
The
hydrogen/
flammable
gas
generation
rate
limit
for
each
payload
package
(
analytical
or
test
category)
shall
be
recorded
for
later
use
in
completing
the
PATCD.

For
test
category
payload
packages,
the
hydrogen/
flammable
gas
generation
rate
for
each
payload
package
shall
be
compared
individually
to
the
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit.

 
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
(
Section
6.5.2.3):
For
test
category
and
analytical
category
payload
packages,
the
hydrogen/
flammable
gas
generation
rate
limit
per
overpacked
payload
package
for
the
applicable
payload
shipping
category
shall
be
recorded
from
the
PCTCD(
s)
(
test
category)
or
the
TRAMPAC
(
analytical
category).
The
hydrogen/
flammable
gas
generation
rate
limits
are
recorded
for
use
in
determining
the
governing
limit.

 
Certification
of
Compliance:
The
TCO
shall
indicate
compliance
with
the
requirements
for
weight,
fissile
mass,
decay
heat,
and
hydrogen/
flammable
gas
generation
rate
by
initials
in
the
spaces
provided.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
218
6.6.2.3
Procedure
for
Certification
of
Overpack
Payload
Packages
(
continued)

Overpacked
Container
Measured
Parameters
(
continued)

 
Transportation
Certification
Official
(
Section
6.1.6.1):
The
site
TCO
shall
verify
that
all
of
the
requirements
for
the
above
transportation
parameters
are
met
as
stated
in
this
document.
The
site
TCO
shall
sign
and
date
the
OPCTCD
upon
completion,
thereby
authorizing
the
payload
package
for
TRUPACT­
II
transport
or
to
be
overpacked
in
another
payload
package,
in
which
case
the
OPCTCD
must
be
completed
again.
If
the
requirements
are
not
met,
the
payload
package
is
rejected
(
nonconformance
disposition)
and
is
not
qualified
for
shipment.

The
information
associated
with
Test
Category
waste
is
recorded
in
WEMS,
and
the
applicable
PCTCD
is
generated
from
the
entered
information.
WEMS
software
controls
ensure
compliance
with
applicable
payload
package
restrictions.
Procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification,
provides
instructions
for
verifying
that
the
information
is
complete
and
compliance
with
applicable
restrictions
for
each
payload
package.
The
TCO
ensures
payload
compliance
with
the
TRUPACT­
II
restrictions
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.
Additionally,
all
payload
packages
are
processed
through
the
e­
TRAMPAC
software
system
in
WWIS.
The
e­
TRAMPAC
system
also
verifies
compliance
with
the
applicable
payload
package
restrictions.

6.6.2.4
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
or
Equivalent
Shipping
Category
RFETS
qualifies
a
payload
for
transport
in
the
TRUPACT­
II
by
verifying
that
the
payload
meets
the
parameter
requirements/
limits
listed
in
Appendix
6.
Appendix
6
is
a
reproduction
of
the
form
as
shown
in
the
TRAMPAC.

Appendix
6
is
completed
as
follows
(
section
numbers
in
parentheses
refer
to
sections
in
this
document
that
provide
requirement,
compliance,
and
verification
information
for
the
transportation
parameter
described):

Identification
Parameters
 
Shipment
#:
The
shipment
number
of
the
trailer
or
railcar
of
TRUPACT­
IIs
is
recorded.
For
shipments
by
railcar,
each
railcar
is
assigned
a
separate
shipment
number
or
shipment
number
prefix.

 
TRUPACT­
II
Outer
Containment
Assembly
(
OCA)
Body/
Lid
#:
The
identification
numbers
on
the
TRUPACT­
II
OCA
body
and
lid
are
recorded.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
219
6.6.2.4
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
or
Equivalent
Shipping
Category
(
continued)

Identification
Parameters
(
continued)

 
Governing
Payload
Shipping
Category
(
Section
6.5.1):
The
governing
shipping
category
of
the
payload
is
recorded
only
if
all
packages
belong
to
the
same
or
equivalent
shipping
category.
The
first
two
digits
(
representing
the
waste
type)
of
the
ten­
digit
payload
shipping
category
notation
are
the
same
for
all
payload
packages
making
up
a
payload.
The
value
of
the
other
digits
of
the
shipping
category
(
representing
the
bounding
G
value
and
the
total
resistance)
for
each
payload
package
may
differ
provided
the
decay
heat
limit
for
all
payload
packages
within
the
payload
is
conservatively
assumed
to
be
the
same
as
that
of
the
payload
package
with
the
lowest
decay
heat
limit.

The
procedures
for
certifying
payloads
of
mixed
shipping
categories,
including
dunnage
packages,
are
described
in
Section
6.6.2.5.

Visual
inspection
of
the
affixed
shipping
category
labels
on
each
payload
package
or
the
respective
PCTCD
(
Appendices
7
and
8)
or
OPCTCD
(
Appendix
9),
if
applicable,
ensures
the
appropriate
shipping
category
assignment
to
the
payload.

 
Governing
Payload
Shipping
Category
Decay
Heat
Limit
(
Section
6.5.2.2):
If
all
packages
belong
to
the
same
or
equivalent
shipping
category,
the
maximum
allowable
decay
heat
per
payload
package
for
the
governing
payload
shipping
category
shall
be
recorded
from
the
PCTCD
and
OPCTCD.
Mixing
of
shipping
categories
and
payloads
of
any
authorized
contents,
including
credit
for
dunnage,
is
allowed
as
described
in
Section
6.6.2.5.

 
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
(
Section
6.5.2.2):
If
all
packages
belong
to
the
same
or
equivalent
shipping
category,
the
maximum
allowable
hydrogen/
flammable
gas
generation
rate
per
payload
package
for
the
governing
payload
shipping
category
shall
be
recorded
from
PCTCD(
s)
and
OPCTCD(
s).
Mixing
of
shipping
categories
and
payloads
of
any
authorized
contents,
including
credit
for
dunnage,
is
allowed
as
described
in
Section
6.6.2.5.

 
Type
of
Payload
(
Section
6.2.1):
The
payload
configuration
consists
of
an
approved
type
of
payload
package.

 
Date
ICV
Closed:
The
date
that
the
ICV
is
closed
is
recorded.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
220
6.6.2.4
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
or
Equivalent
Shipping
Category
(
continued)

Identification
Parameters
(
continued)

 
Payload
Composition:
The
following
data
are
recorded
from
each
PCTCD
(
Appendices
7
and
8)
or
from
the
OPCTCD,
as
applicable,
for
each
payload
package
or
dunnage
comprising
the
payload.
Only
the
"
Container
ID
Number,"
"
Weight,"
and
weight
measurement
"
Error"
need
to
be
completed
for
dunnage
packages.
If
the
data
are
obtained
from
the
OPCTCD,
errors
should
be
the
calculated
RMS
errors
(
the
square
root
of
the
sum
of
the
squares
of
the
individually
listed
errors).

 
Payload
package
ID
number
or
"
DUNNAGE"
or
"
EMPTY"

 
Measured
weight
and
measurement
error
 
Measured
decay
heat
and
measurement
error
(
one
standard
deviation)

 
Measured
fissile
mass
and
two
times
the
measurement
error
(
two
standard
deviations
or
one
times
the
RMS
error
if
values
are
taken
from
an
OPCTCD)

 
Measured
hydrogen/
flammable
gas
generation
rate.

The
weight,
decay
heat,
and
fissile
mass
values
of
individual
payload
packages
and
dunnage
of
both
the
bottom
and
top
layers
are
summed,
and
the
total
measurement
error
for
each
parameter
shall
be
calculated
as
the
square
root
of
the
sum
of
the
squares
of
the
individual
measurement
errors
(
indicated
in
Appendices
7
and
8).
The
measurement
error
on
the
total
weight
can
also
be
determined
by
weighing
the
total
payload
assembly
and
determining
the
measurement
error.

 
Weight
of
Pallets,
Reinforcing
Plates,
Slip
Sheets,
Guide
Tubes,
Adjustable
Slings,
etc.
(
Section
6.2.3):
The
total
measured
weight
of
the
pallets,
reinforcing
plates,
slip
sheets
(
optional),
guide
tubes,
etc.,
(
or
265
pounds)
is
recorded.

 
Total
Weight/
Total
RMS
Weight
Error
(
Section
6.2.3):
The
sum
of
the
subtotal
weights
plus
the
weight
of
the
pallets,
reinforcing
plates,
slip
sheets,
guide
tubes,
etc.,
(
or
265
pounds)
and
the
RMS
weight
error
is
recorded.
If
the
weight
is
determined
through
a
single
measurement
of
the
payload
assembly,
the
associated
error
is
simply
the
error
for
that
one
measurement
(
one
standard
deviation).

 
Total
Decay
Heat/
Total
RMS
Decay
Heat
Error
(
Section
6.5.2):
The
sum
of
the
subtotal
decay
heats
and
the
total
RMS
error
is
recorded.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
221
6.6.2.4
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
or
Equivalent
Shipping
Category
(
continued)

Identification
Parameters
(
continued)

 
Total
Fissile
Mass/
Total
RMS
Error
(
Section
6.3.1):
The
sum
of
the
subtotal
fissile
masses
and
the
total
RMS
error
is
recorded.

 
Bottom
Assembly
Weight
plus
Subtotal
RMS
Error
(
Section
6.2.3):
The
subtotal
weight
plus
the
subtotal
RMS
error
of
the
bottom
layer
of
seven
55­
gallon
drums,
three
100­
gallon
drums,
seven
POCs,
SWB,
five
55­
gallon
drums,
or
4
85­
gallon
drums
in
a
TDOP
is
recorded
 
Top
Assembly
Weight
plus
Subtotal
RMS
Error:
The
subtotal
weight
plus
the
subtotal
RMS
error
for
the
top
layer
of
seven
55­
gallon
drums,
three
100­
gallon
drums,
seven
POCs,
SWB,
or
five
drums
in
a
TDOP
is
recorded..

 
Total
Weight
plus
Total
RMS
Error:
The
sum
of
the
total
weight
plus
the
weight
of
the
pallets,
reinforcing
plates,
slip
sheets,
guide
tubes,
adjustable
slings,
etc.,
plus
the
total
RMS
weight
error
is
recorded.

 
Total
Fissile
Mass
plus
Total
RMS
Error:
The
sum
of
the
total
fissile
mass
values
plus
the
total
RMS
fissile
mass
error
is
recorded.

 
Total
Decay
Heat
plus
Total
RMS
Error:
The
sum
of
the
total
decay
heat
values
plus
the
total
RMS
decay
heat
error
is
recorded.

Payload
Certification
Parameters
The
TCO
shall
indicate
compliance
with
the
following
requirements
by
initials
in
the
spaces
provided.

 
Decay
Heat
plus
Error
of
Each
Analytical
Category
Payload
Container
Less
Than
or
Equal
to
Governing
Decay
Heat
Limit
(
Section
6.5.2.2):
For
payload
packages
with
the
same
or
equivalent
payload
shipping
category
shipped
under
a
governing
payload
shipping
category,
all
analytical
category
payload
packages
shall
meet
the
governing
decay
heat
limit.

 
Hydrogen/
Flammable
Gas
Generation
Rate
of
Each
Test
Category
Payload
Container
Less
Than
or
Equal
to
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
(
Section
6.5.2.3):
For
payload
packages
with
the
same
or
equivalent
payload
shipping
category
shipped
under
a
governing
hydrogen/
flammable
gas
generation
rate,
all
payload
packages
shall
meet
the
governing
hydrogen/
flammable
gas
generation
rate
limit.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
222
6.6.2.4
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
or
Equivalent
Shipping
Category
(
continued)

Payload
Certification
Parameters
(
continued)

 
Bottom
Weight
Greater
Than
or
Equal
to
Top
Weight
(
Section
6.2.3):
The
subtotal
weight
plus
subtotal
RMS
weight
error
of
the
bottom
layer
of
seven
55­
gallon
drums,
three
100­
gallon
drums,
seven
pipe
overpacks,
one
SWB,
five
55­
gallon
drums
in
a
TDOP,
or
four
85­
gallon
drums
in
a
TDOP
shall
be
greater
than
or
equal
to
that
of
the
top
layer.

 
Total
Weight
plus
RMS
Error
Less
Than
or
Equal
to
7,265
Lbs.
(
Section
6.2.3):
The
total
measured
payload
weight
plus
the
weight
of
the
pallets,
reinforcing
plates,
etc.,
plus
the
total
RMS
weight
error
shall
be
less
than
or
equal
to
7,265
pounds.

 
Decay
Heat
plus
RMS
Error
Less
Than
or
Equal
to
40
Watts
(
Section
6.5.2.2):
The
total
measured
decay
heat
value
plus
the
total
RMS
decay
heat
error
shall
be
less
than
or
equal
to
the
design
limit
for
the
packaging.
The
design
limit
for
the
TRUPACT­
II
is
40
watts.

 
Fissile
Mass
(
Pu­
239
FGE)
plus
RMS
Error
Less
Than
or
Equal
to
Payload
Limit
(
Section
6.3.1):
The
total
measured
fissile
mass
(
Pu­
239
FGE)
plus
the
total
RMS
fissile
mass
error
shall
be
less
than
or
equal
to
the
maximum
allowable
fissile
mass
limit
established
for
the
payload
configuration
and
waste
contents.

 
Transportation
Certification
Official
(
Section
6.1.6.1):
The
Transportation
Certification
Official
shall
sign
and
date
the
PATCD
upon
verifying
that
the
TRAMPAC
transportation
requirements
are
met
and
the
payload
is
qualified
for
transport.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
223
6.6.2.4
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
or
Equivalent
Shipping
Category
(
continued)

Appendix
6
lists
the
information
that
is
required
to
be
recorded
for
a
TRUPACT­
II
payload
assembly.
A
TRUPACT­
II
shipment
is
authorized
only
if
all
the
payload
control
parameters
are
in
compliance.
The
TCO
is
responsible
for
verifying
this
compliance
before
authorizing
the
TRUPACT­
II
for
transport.

All
data
necessary
to
generate
the
information
required
in
Appendix
6
is
captured
in
WEMS
and
subsequently
transmitted
to
the
WWIS.
The
e­
TRAMPAC
system
in
WWIS
calculates
and
ensures
compliance
with
all
applicable
payload
restrictions
and
generates
the
PATCD
(
Appendix
6)
Procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification,
provides
instructions
for
verifying
that
the
information
is
complete
and
is
in
compliance
with
applicable
restrictions
for
each
payload
package.
The
TCO
ensures
payload
compliance
with
the
TRUPACT­
II
restrictions
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
224
6.6.2.5
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Different
Shipping
Categories
An
assembly
of
payload
packages
with
different
shipping
categories
may
be
approved
by
ensuring
that
each
payload
package
does
not
contain
a
flammable
mixture
of
gases,
while
accounting
for
the
properties
of
each
of
the
other
payload
packages
in
the
assembly,
which
may
include
dunnage
packages.
Each
payload
package
is
assessed
through
the
calculation
of
the
Flammability
Index
(
FI)
for
the
package,
which
accounts
for
the
properties
of
each
package
in
the
mixed
payload
assembly.
FI
is
only
applicable
to
mixed
payload
assemblies.

Unlimited
mixing
of
shipping
categories
is
allowed
for
payload
assemblies
of
directloaded
payload
configurations.
For
payload
assemblies
comprised
of
overpacked
payload
configurations,
mixing
of
shipping
categories
is
allowed
provided
that
all
payload
packages
being
overpacked
meet
the
lowest
decay
heat
limit
or
lowest
hydrogen
gas
generation
rate
limit
of
all
the
payload
packages
in
the
payload
assembly
as
described
in
Section
6.6.2.4.

RFETS
evaluates
payload
assemblies
of
direct­
loaded
payload
configurations
with
different
shipping
categories
by
the
following
procedure:

 
Appendix
6
is
completed
as
described
in
Section
6.6.2.4
with
the
exception
of
the
following
identification
parameters
and
payload
certification
parameters:

 
Identification
Parameters:

 
Governing
Payload
Shipping
Category
 
Governing
Payload
Shipping
Category
Decay
Heat
Limit
 
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
 
Payload
Certification
Parameters:

 
Decay
Heat
plus
Error
of
Each
Analytical
Category
Payload
Container
 
Governing
Limit
 
Hydrogen/
Flammable
Gas
Generation
Rate
of
Each
Test
Category
Payload
Container
 
Governing
Limit.

For
mixed
payloads,
mark
the
above
Appendix
6
sections
as
"
N/
A."

 
In
lieu
of
the
above
parameters,
the
following
payload
assembly
composition
parameter
and
payload
certification
parameter
must
be
completed
in
Appendix
6:

 
Payload
Assembly
Composition
Parameter:

 
Flammability
Index
 
Payload
Certification
Parameter:

 
Flammability
Index
of
Each
Payload
Container
 
50,000.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
225
6.6.2.5
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Different
Shipping
Categories
(
continued)

 
For
payload
assemblies
with
dunnage,
or
multiple
shipping
categories,
record
the
Flammability
Index
(
FI)
for
each
payload
package
under
the
Payload
Assembly
Composition
Parameter
section.
The
FI
determination
is
performed
by
the
e­
TRAMPAC
system
in
WWIS
using
data
transmitted
to
the
WWIS
from
the
WEMS.
The
e­
TRAMPAC
system
ensures
compliance
with
the
applicable
FI
criteria.
RFETS
qualifies
a
payload
for
shipment
only
if
the
FI
of
each
payload
package
is
equal
to
or
less
than
50,000.
If
one
or
more
payload
package(
s)
fail
the
FI
requirement,
the
payload
assembly
shall
be
reconfigured
until
all
payload
packages
satisfy
this
requirement.
Otherwise,
payload
packages
not
meeting
the
FI
requirement
shall
be
placed
in
the
test
category
or
rejected
from
transport,
subject
to
mitigation
or
repackaging.
All
other
PATCD
fields
must
be
completed
as
described
in
Section
6.6.2.4.
Procedure
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification,
provides
instructions
for
verifying
that
the
information
is
complete
and
is
in
compliance
with
applicable
restrictions.
The
TCO
ensures
compliance
with
the
TRUPACT­
II
restrictions
in
accordance
with
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations.

The
logic
for
determining
the
FI
for
each
payload
package
by
the
e­
TRAMPAC
is
consistent
with
that
described
in
Appendix
6.3
of
the
TRAMPAC.
This
logic
is
summarized
as
follows:

 
For
each
payload
package,
the
FI
is
calculated
as
the
ratio
of
the
actual
flammable
gas
generation
rate
to
the
allowable
flammable
gas
generation
rate
limit
multiplied
by
50,000.
The
FI
for
each
payload
package
must
be
less
than
or
equal
to
50,000
for
the
payload
to
be
eligible
for
shipment.

 
Allowable
Flammable
Gas
Generation
Rate.
Per
Section
6.5.2,
the
determination
of
allowable
flammable
gas
generation
rates
takes
into
account
the
concentrations
of
flammable
VOCs
within
the
innermost
layer
of
confinement,
if
present,
and
the
void
volume
of
any
dunnage
packages.
The
maximum
concentration
of
flammable
gas
and
flammable
VOCs
in
the
innermost
layer
is
limited
to
the
MLEL.
The
allowable
flammable
gas
concentration
(
AFGC)
is
calculated
as
the
difference
between
the
MLEL
and
the
sum
of
the
flammable
VOC
concentrations.
An
allowable
flammable
gas
generation
rate
for
each
payload
package
is
calculated
to
yield
a
maximum
flammable
gas
concentration
equivalent
to
the
AFGC.

 
For
analytical
category
payload
packages
or
test
category
payload
packages
that
have
headspace
concentrations
of
flammable
VOCs
less
than
or
equal
to
500
ppm,
the
AFGC
is
equal
to
the
MLEL
of
0.05
mole
fraction
(
i.
e.,
5
volume
percent).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
226
6.6.2.5
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Different
Shipping
Categories
(
continued)

 
For
test
category
payload
packages
(
i.
e.,
payload
packages
exceeding
the
analytical
decay
heat
limit,
payload
packages
with
headspace
flammable
VOC
concentrations
in
excess
of
500
ppm,
and
payload
packages
of
Waste
Type
IV),
the
AFGC
is
calculated
as
the
difference
between
the
MLEL
at
the
end
of
the
60­
day
shipping
period
and
the
innermost
confinement
layer
sum
of
flammable
VOC
concentrations.

 
Actual
Flammable
Gas
Generation
Rate.
For
analytical
category
payload
packages,
the
actual
flammable
gas
generation
rate
is
calculated
as:

(
)
(
)
(
)
eV
/
ond
sec
watt
.
N
eV
/
molecules
G
Q
CG
A
i
actual
,
i
 
=
 
19
10
602
1
100
where,

Qi
=
Decay
heat
of
payload
package
(
watts)
NA
=
Avogadro's
number
=
6.0225(
10)
23
molecules/
mole
G
=
Geff
(
flam
gas)
=
Effective
G
value
for
flammable
gas
(
molecules
of
hydrogen
formed/
100
eV
emitted
energy)

 
For
test
category
payload
packages,
the
actual
gas
generation
rate
is
obtained
either
through
measurement
of
the
flammable
gas
concentration
in
the
drum
or
liner
headspace
and
calculation
of
the
rate,
or
through
testing.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
227
6.7
Quality
Assurance
NOTE:
The
general
requirements
identified
in
the
TRAMPAC
are
addressed
in
the
TWCP
QAPjP.
The
specific
processes
are
detailed
in
the
radiography
procedures
referenced
in
the
TWCP
QAPjP
(
refer
to
the
TWCP
QAPjP,
Table
B­
1,
Section
B1­
3,
and
Section
B3­
4).

This
section
describes
the
QA
programs
applicable
to
the
TRAMPAC.
QA
programs
applicable
to
procurement,
design,
fabrication,
assembly,
testing,
use,
maintenance,
and
repair
of
the
TRUPACT­
II
packaging
are
found
in
the
TRUPACT­
II
SAR,
Section
9.0.

6.7.1
QA
Requirements
for
Payload
Compliance
Certification
of
authorized
contents
for
shipment
in
the
TRUPACT­
II
is
performed
under
a
written
QA
program
that
provides
confidence,
for
both
the
shipper
and
receiver,
that
the
TRAMPAC
requirements
are
met.
All
waste
is
described
in
an
approved
content
code.

6.7.2
QA
Compliance
and
Verification
This
TRAMPAC
Compliance
Plan
documents
the
compliance
methods
used
by
RFETS
in
meeting
the
requirements
of
the
TRAMPAC.
The
CBFO
managing
and
operating
contractor
will
perform
surveillance
of
these
compliance
procedures
to
ensure
all
the
requirements
of
the
TRAMPAC
are
met.
The
CBFO
will
periodically
audit
RFETS'
payload
compliance
QA
Program.

See
Section
3
for
information
on
the
QA
program
for
the
overall
management
of
TRU
and
TRU
mixed
waste
at
RFETS.
The
Packaging
QA
Program
is
described
in
Section
4.6
of
this
document.
Also
see
Section
2.2
of
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
228
Table
6­
1,
Pu­
239
Fissile
Gram
Equivalent,
Decay
Heat,
and
Specific
Activity
of
Many
Radionuclides
NUCLIDE
ATOMIC
NUMBER
Pu­
239FGEa
DECAY
HEATb
(
W/
g)
SPECIFIC
ACTIVITYc
(
Ci/
g)

H
3
1
0.00E+
00
3.28E­
01
9.76E+
03
C
14
6
0.00E+
00
1.32E­
03
4.51E+
00
Na
22
11
0.00E+
00
8.94E+
01
6.32E+
03
P
32
15
0.00E+
00
1.19E+
03
2.89E+
05
Cr
51
24
0.00E+
00
1.95E+
01
9.24E+
04
Mn
54
25
0.00E+
00
3.88E+
01
7.82E+
03
Fe
55
26
0.00E+
00
8.49E­
02
2.44E+
03
Fe
59
26
0.00E+
00
3.80E+
02
4.92E+
04
Co
57
27
0.00E+
00
7.29E+
00
8.55E+
03
Co
58
27
0.00E+
00
1.91E+
02
3.18E+
04
Co
60
27
0.00E+
00
1.76E+
01
1.14E+
03
Ni
59
28
0.00E+
00
3.22E­
06
8.08E­
02
Ni
63
28
0.00E+
00
6.05E­
03
5.98E+
01
Cu
64
29
0.00E+
00
7.21E+
03
3.89E+
06
Zn
65
30
0.00E+
00
2.89E+
01
8.24E+
03
As
73
33
0.00E+
00
1.02E+
01
2.25E+
04
Se
79
34
0.00E+
00
2.18E­
05
6.97E­
02
Kr
85
36
0.00E+
00
5.94E­
01
3.97E+
02
Rb
86
37
0.00E+
00
3.71E+
02
8.22E+
04
Sr
89
38
0.00E+
00
1.01E+
02
2.94E+
04
Sr
90
38
0.00E+
00
1.60E­
01
1.38E+
02
Y
88
39
0.00E+
00
2.24E+
02
1.41E+
04
Y
90
39
0.00E+
00
3.01E+
03
5.44E+
05
Y
90m
39
0.00E+
00
4.40E+
04
1.09E+
07
Y
91
39
0.00E+
00
8.83E+
01
2.45E+
04
Zr
88
40
0.00E+
00
4.46E+
01
1.80E+
04
Zr
90
40
0.00E+
00
N/
Ad
N/
Ad
Zr
90m
40
0.00E+
00
2.13E+
09
1.55E+
11
Zr
93
40
0.00E+
00
7.29E­
07
2.51E­
03
Zr
95
40
0.00E+
00
1.10E+
02
2.17E+
04
Nb
95
41
0.00E+
00
1.87E+
02
3.91E+
04
Nb
95m
41
0.00E+
00
6.11E+
02
3.81E+
05
Tc
99
43
0.00E+
00
8.49E­
06
1.70E­
02
Tc
99m
43
0.00E+
00
4.31E+
03
5.27E+
06
Ru
103
44
0.00E+
00
1.05E+
02
3.26E+
04
Ru
106
44
0.00E+
00
2.00E­
01
3.38E+
03
Rh
103m
45
0.00E+
00
7.55E+
03
3.25E+
07
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
229
Table
6­
1,
Pu­
239
Fissile
Gram
Equivalent,
Decay
Heat,
and
Specific
Activity
of
Many
Radionuclides
(
continued)

NUCLIDE
ATOMIC
NUMBER
Pu­
239FGEa
DECAY
HEATb
(
W/
g)
SPECIFIC
ACTIVITYc
(
Ci/
g)

Rh
106
45
0.00E+
00
6.74E+
07
3.56E+
09
Pd
107
46
0.00E+
00
2.83E­
08
5.14E­
04
Ag
109m
47
0.00E+
00
1.32E+
06
2.61E+
09
Ag
110
47
0.00E+
00
3.01E+
07
4.17E+
09
Ag
110m
47
0.00E+
00
7.99E+
01
4.80E+
03
Cd
109
48
0.00E+
00
1.68E+
00
2.61E+
03
Cd
113m
48
0.00E+
00
2.34E­
01
2.17E+
02
Sn
119m
50
0.00E+
00
2.38E+
00
4.48E+
03
Sn
121m
50
0.00E+
00
1.44E­
02
5.91E+
01
Sn
123
50
0.00E+
00
2.58E+
01
8.22E+
03
Sn
126
50
0.00E+
00
3.06E­
05
2.84E­
02
Sb
125
51
0.00E+
00
3.27E+
00
1.04E+
03
Sb
126
51
0.00E+
00
1.54E+
03
8.36E+
04
Sb
126m
51
0.00E+
00
1.01E+
06
7.85E+
07
Te
123
52
0.00E+
00
6.50E­
17
4.85E­
12
Te
123m
52
0.00E+
00
1.31E+
01
8.87E+
03
Te
125m
52
0.00E+
00
1.57E+
01
1.80E+
04
Te
127
52
0.00E+
00
3.59E+
03
2.64E+
06
Te
127m
52
0.00E+
00
5.21E+
00
9.43E+
03
I
125
53
0.00E+
00
6.38E+
00
1.76E+
04
I
129
53
0.00E+
00
9.34E­
08
1.79E­
04
I
131
53
0.00E+
00
4.23E+
02
1.25E+
05
Cs
134
55
0.00E+
00
1.33E+
01
1.31E+
03
Cs
135
55
0.00E+
00
3.82E­
07
1.15E­
03
Cs
137
55
0.00E+
00
9.74E­
02
8.80E+
01
Ba
133
56
0.00E+
00
6.82E­
01
2.53E+
02
Ba
137
56
0.00E+
00
N/
Ad
N/
Ad
Ba
137m
56
0.00E+
00
2.12E+
06
5.38E+
08
Ce
141
58
0.00E+
00
4.19E+
01
2.88E+
04
Ce
144
58
0.00E+
00
2.14E+
00
3.22E+
03
Pr
144
59
0.00E+
00
5.54E+
05
7.56E+
07
Pr
144m
59
0.00E+
00
6.22E+
04
1.81E+
08
Pm
146
61
0.00E+
00
2.22E+
00
4.43E+
02
Pm
147
61
0.00E+
00
3.44E­
01
9.38E+
02
Sm
146
62
0.00E+
00
3.47E­
07
2.38E­
05
Sm
147
62
0.00E+
00
3.04E­
10
2.30E­
08
Sm
151
62
0.00E+
00
3.10E­
03
2.66E+
01
Eu
150
63
0.00E+
00
5.95E­
01
6.46E+
01
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
230
Table
6­
1,
Pu­
239
Fissile
Gram
Equivalent,
Decay
Heat,
and
Specific
Activity
of
Many
Radionuclides
(
continued)

NUCLIDE
ATOMIC
NUMBER
Pu­
239FGEa
DECAY
HEATb
(
W/
g)
SPECIFIC
ACTIVITYc
(
Ci/
g)

Eu
152
63
0.00E+
00
1.35E+
00
1.78E+
02
Eu
154
63
0.00E+
00
2.39E+
00
2.67E+
02
Eu
155
63
0.00E+
00
3.42E­
01
4.70E+
02
Gd
152
64
0.00E+
00
2.77E­
13
2.18E­
11
Gd
153
64
0.00E+
00
2.96E+
00
3.53E+
03
Tm
168
69
0.00E+
00
8.39E+
01
8.44E+
03
Ta
182
73
0.00E+
00
5.60E+
01
6.31E+
03
Au
198
79
0.00E+
00
1.51E+
03
2.45E+
05
Tl
207
81
0.00E+
00
5.58E+
05
1.90E+
08
Tl
208
81
0.00E+
00
6.93E+
06
2.95E+
08
Tl
209
81
0.00E+
00
8.58E+
06
4.16E+
08
Pb
209
82
0.00E+
00
5.32E+
03
4.54E+
06
Pb
210
82
0.00E+
00
1.96E­
02
7.72E+
01
Pb
211
82
0.00E+
00
7.61E+
04
2.47E+
07
Pb
212
82
0.00E+
00
2.64E+
03
1.39E+
06
Pb
214
82
0.00E+
00
1.49E+
05
3.28E+
07
Bi
207
83
0.00E+
00
5.34E­
01
5.48E+
01
Bi
210
83
0.00E+
00
2.86E+
02
1.24E+
05
Bi
211
83
0.00E+
00
1.64E+
07
4.18E+
08
Bi
212
83
0.00E+
00
2.42E+
05
1.47E+
07
Bi
213
83
0.00E+
00
7.64E+
04
1.93E+
07
Bi
214
83
0.00E+
00
7.25E+
05
4.41E+
07
Po
209
84
0.00E+
00
4.94E+
00
1.68E+
01
Po
210
84
0.00E+
00
1.45E+
02
4.54E+
03
Po
211
84
0.00E+
00
4.58E+
09
1.04E+
11
Po
212
84
0.00E+
00
9.24E+
15
1.77E+
17
Po
213
84
0.00E+
00
6.26E+
14
1.26E+
16
Po
214
84
0.00E+
00
1.46E+
13
3.21E+
14
Po
215
84
0.00E+
00
1.29E+
12
2.95E+
13
Po
216
84
0.00E+
00
1.40E+
10
3.48E+
11
Po
218
84
0.00E+
00
9.90E+
06
2.78E+
08
At
211
85
0.00E+
00
3.05E+
04
2.06E+
06
At
217
85
0.00E+
00
6.74E+
10
1.61E+
12
Rn
219
86
0.00E+
00
5.30E+
08
1.30E+
10
Rn
220
86
0.00E+
00
3.44E+
07
9.22E+
08
Rn
222
86
0.00E+
00
5.01E+
03
1.54E+
05
Fr
221
87
0.00E+
00
6.71E+
06
1.77E+
08
Fr
223
87
0.00E+
00
1.10E+
05
3.87E+
07
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
231
Table
6­
1,
Pu­
239
Fissile
Gram
Equivalent,
Decay
Heat,
and
Specific
Activity
of
Many
Radionuclides
(
continued)

NUCLIDE
ATOMIC
NUMBER
Pu­
239FGEa
DECAY
HEATb
(
W/
g)
SPECIFIC
ACTIVITYc
(
Ci/
g)

Ra
223
88
0.00E+
00
1.83E+
03
5.18E+
04
Ra
224
88
0.00E+
00
5.37E+
03
1.59E+
05
Ra
225
88
0.00E+
00
2.78E+
01
3.92E+
04
Ra
226
88
0.00E+
00
2.88E­
02
1.00E+
00
Ra
228
88
0.00E+
00
2.76E­
02
2.76E+
02
Ac
225
89
0.00E+
00
1.99E+
03
5.80E+
04
Ac
227
89
0.00E+
00
3.68E­
02
7.32E+
01
Ac
228
89
0.00E+
00
1.80E+
04
2.24E+
06
Th
227
90
0.00E+
00
1.11E+
03
3.07E+
04
Th
228
90
0.00E+
00
2.71E+
01
8.29E+
02
Th
229
90
0.00E+
00
6.17E­
03
2.13E­
01
Th
230
90
0.00E+
00
5.75E­
04
2.04E­
02
Th
231
90
0.00E+
00
6.43E+
02
5.32E+
05
Th
232
90
0.00E+
00
2.68E­
09
1.11E­
07
Th
234
90
0.00E+
00
3.45E+
00
2.32E+
04
Pa
231
91
0.00E+
00
1.46E­
03
4.78E­
02
Pa
233
91
0.00E+
00
4.90E+
01
2.08E+
04
Pa
234
91
0.00E+
00
2.40E+
04
2.00E+
06
Pa
234m
91
0.00E+
00
3.40E+
06
6.87E+
08
U
232
92
0.00E+
00
6.93E­
01
2.16E+
01
U
233
92
1.00E+
00
2.84E­
04
9.76E­
03
U
234
92
0.00E+
00
1.82E­
04
6.32E­
03
U
235
92
1.00E+
00
6.04E­
08
2.19E­
06
U
236
92
0.00E+
00
1.78E­
06
6.54E­
05
U
237
92
0.00E+
00
1.64E+
02
8.25E+
04
U
238
92
0.00E+
00
8.62E­
09
3.40E­
07
U
239
92
0.00E+
00
1.69E+
05
3.35E+
07
U
240
92
0.00E+
00
1.17E+
03
9.26E+
05
Np
237
93
1.50E­
02
2.09E­
05
7.13E­
04
Np
238
93
0.00E+
00
1.49E+
03
2.59E+
05
Np
239
93
0.00E+
00
5.87E+
02
2.32E+
05
Np
240
93
0.00E+
00
8.52E+
04
1.27E+
07
Np
240m
93
0.00E+
00
9.98E+
05
1.08E+
08
Pu
236
94
0.00E+
00
1.87E+
01
5.37E+
02
Pu
238
94
1.13E­
01
5.73E­
01
1.73E+
01
Pu
239
94
1.00E+
00
1.95E­
03
6.29E­
02
Pu
240
94
2.25E­
02
7.16E­
03
2.30E­
01
Pu
241
94
2.25E+
00
3.31E­
03
1.04E+
02
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
232
Table
6­
1,
Pu­
239
Fissile
Gram
Equivalent,
Decay
Heat,
and
Specific
Activity
of
Many
Radionuclides
(
continued)

NUCLIDE
ATOMIC
NUMBER
Pu­
239FGEa
DECAY
HEATb
(
W/
g)
SPECIFIC
ACTIVITYc
(
Ci/
g)

Pu
242
94
7.50E­
03
1.17E­
04
3.97E­
03
Pu
243
94
0.00E+
00
5.38E+
03
2.60E+
06
Pu
244
94
0.00E+
00
5.22E­
07
1.79E­
05
Am
241
95
1.87E­
02
1.16E­
01
3.47E+
00
Am
242
95
0.00E+
00
9.38E+
02
8.08E+
05
Am
242m
95
3.46E+
01
4.32E­
03
9.83E+
00
Am
243
95
1.29E­
02
6.49E­
03
2.02E­
01
Am
245
95
0.00E+
00
2.12E+
04
6.24E+
06
Cm
240
96
0.00E+
00
7.48E+
02
2.01E+
04
Cm
242
96
0.00E+
00
1.23E+
02
3.35E+
03
Cm
243
96
5.00E+
00
1.90E+
00
5.22E+
01
Cm
244
96
9.00E­
02
2.86E+
00
8.18E+
01
Cm
245
96
1.50E+
01
5.77E­
03
1.74E­
01
Cm
246
96
0.00E+
00
1.02E­
02
3.11E­
01
Cm
247
96
5.00E­
01
2.98E­
06
9.38E­
05
Cm
248
96
0.00E+
00
5.53E­
04
4.30E­
03
Cm
250
96
0.00E+
00
1.59E­
01
2.10E­
01
Bk
247
97
0.00E+
00
3.69E­
02
1.06E+
00
Bk
249
97
0.00E+
00
3.24E­
01
1.66E+
03
Bk
250
97
0.00E+
00
3.34E+
04
3.90E+
06
Cf
249
98
4.50E+
01
1.54E­
01
4.14E+
00
Cf
250
98
0.00E+
00
4.12E+
00
1.11E+
02
Cf
251
98
9.00E+
01
5.89E­
02
1.60E+
00
Cf
252
98
0.00E+
00
4.06E+
01
5.44E+
02
Cf
254
98
0.00E+
00
9.10E­
01
8.50E+
03
Es
252
99
0.00E+
00
4.37E+
01
1.11E+
03
Es
253
99
0.00E+
00
9.91E+
02
2.52E+
04
Es
254
99
0.00E+
00
7.35E+
01
1.88E+
03
Es
254m
99
0.00E+
00
1.69E+
03
3.14E+
05
a
American
National
Standards
Institute/
American
Nuclear
Society
(
ANSI/
ANS),
1981,
"
Nuclear
Criticality
Control
of
Special
Actinide
Elements,"
ANSI/
ANS­
8.15­
1981,
American
National
Standards
Institute/
American
Nuclear
Society,
Washington,
D.
C.
bInternational
Commission
on
Radiological
Protection,
1983.
International
Commission
on
Radiological
Protection,
1983,
"
Radionuclide
Transformations:
Energy
and
Intensity
of
Emissions,"
Annals
of
the
International
Commission
on
Radiological
Protection­
38,
Volumes
11­
13,
Pergamon
Press,
Oxford.
cWalker,
F.
W.,
Kiravac,
G.
J.,
and
Rourke,
F.
M.,
1983,
Chart
of
the
Nuclides,
13th
Edition,
Knolls
Atomic
Power
Laboratories,
Schenectady,
NY.
dThese
isotopes
are
stable
and
thus
have
decay
heats
and
specific
activities
of
zero.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
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VERSION
7
02/
12/
2004
PAGE
233
Table
6­
2,
Allowable
Materials
 
Greater
Than
1
Weight
Percent
Allowable
Materials
for
Waste
Material
Type
I.
1a
Absorbed,
Adsorbed,
or
Solidified
Inorganic
Liquid
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Acids,
inorganic
Alumina
cement
Aquaset
®
products
(
for
aqueous
solutions)
Aqueous
sludges
Aqueous
solutions/
water
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete
Envirostone
®
(
no
organic
emulsifiers
allowed)
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,

and
crucible
heel)

Insulation,
inorganic
Magnesia
cement
(
e.
g.,
Ramcote
®
cement)

Metal
hydroxides
Metal
oxides
(
e.
g.,
slag)

Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,

tungsten,
zinc)

Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)

Petroset
®
products
(
for
aqueous
solutions)

Portland
cement
Sand/
soil,
inorganic
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)

Other
inorganic
materials
a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
met
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
234
Table
6­
2,
Allowable
Materials
 
Greater
Than
1
Weight
Percent
(
continued)

Allowable
Materials
for
Waste
Material
Type
I.
2a
Soils,
Solidified
Particulates,
or
Sludges
Formed
from
Precipitation
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Alumina
cement
Aquaset
®
products
(
for
aqueous
solutions)
Aqueous
sludges
Aqueous
solutions/
water
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,

and
crucible
heel)

Insulation,
inorganic
Magnesia
cement
(
e.
g.,
Ramcote
®
cement)

Metal
hydroxides
Metal
oxides
(
e.
g.,
slag)

Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,

tungsten,
zinc)

Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)

Petroset
®
products
(
for
aqueous
solutions)

Portland
cement
Sand/
soil,
inorganic
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)

Other
inorganic
materials
a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
met
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.

Allowable
Materials
for
Waste
Material
Type
I.
3a
Concreted
Inorganic
Particulate
Waste
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,

and
crucible
heel)

Insulation,
inorganic
Metal
hydroxides
Metal
oxides
(
e.
g.,
slag)

Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,

tungsten,
zinc)

Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)

Portland
cement
Sand/
soil,
inorganic
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)

Water
(
maximum
of
30
weight
percent
unbound
water)

Other
inorganic
materials
a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
met
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
235
Table
6­
2,
Allowable
Materials
 
Greater
Than
1
Weight
Percent
(
continued)

Allowable
Materials
for
Waste
Material
Types
II.
1
and
II.
2a
Solid
Inorganic
Materials
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete/
Portland
cement
(
surface
contaminated
only)
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,

and
crucible
heel)

Insulation,
inorganic
Magnesium
alloy
Metal
oxides
(
e.
g.,
slag)
Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,

tungsten,
zinc)

Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)

Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)

Sand/
soil,
inorganic
Other
inorganic
materials
a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
met
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.

b
Dry
absorbents/
adsorbents
and
other
dry
desiccants
are
allowed
if
they
contain
no
absorbed
or
adsorbed
liquids.

Allowable
Materials
for
Waste
Material
Type
II.
3a
Homogeneous
Solid
Inorganic
Materials
with
Unbound
Absorbed
Ambient
Moisture
( 
6%
by
weight)

Any
material
in
Waste
Material
Types
II.
1
and
II.
2
and
water
as
unbound
absorbed
ambient
moisture
( 
6%
by
weight).

a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
236
Table
6­
2,
Allowable
Materials
 
Greater
Than
1
Weight
Percent
(
continued)

Allowable
Materials
for
Waste
Material
Type
III.
1a
Solid
Organic
Materials
Any
material
in
Waste
Types
I
or
II
(
Tables
above)
Absorbent
polymers,
organic
Acids,
solid,
organic
Asphalt
Bakelite
®
b
Cellulose
(
e.
g.,
Benelex
®
,
cotton
Conwed
®
,
paper
rags,
rayon,
wood)
Cellulose
acetate
butyrate
Cellulose
propionate
Chlorinated
polyether
Detergent,
solid
(
e.
g.,
emulsifiers,
surfactants)
Fiberglass,
organic
Filter
media,
organic
Greases,
commercial
brands
Insulation,
organic
Leaded
rubber
(
e.
g.,
gloves,
aprons,
sheet
material)
Leather
Oil
(
e.
g.,
petroleum,
mineral)

Organophosphates
(
e.
g.,
tributyl
phosphate,
dibutyl
phosphate,
monobutyl
phosphite)

Paint,
dry
(
e.
g.,
floor/
wall
paint,
ALARA)

Plastics
(
e.
g.,
polycarbonate,
polyethylene,
polymethyl
methacrylate
[
Plexiglas
®
,
Lucite
®
]
,
polysulfone,

polytetrafluorethylene
[
Teflon
®
]
,
polyvinyl
acetate,

polyvinyl
chloride
[
PVC],
polyvinylidene
chloride
[
saran])

Polyamides
(
nylon)

Polychlorotrifluoroethylene
(
e.
g.,
Kel­
F
®
)

Polyesters
(
e.
g.,
Dacron
®
,
Mylar
®
)

Polyethylene
glycol
(
e.
g.,
Carbowax
®
)

Polyimides
Polyphenyl
methacrylate
Polypropylene
(
e.
g.,
Ful­
Flo
®
filters)

Polyurethane
Polyvinyl
alcohol
Resins
(
e.
g.,
aniline­
formaldehyde,

melamineformaldehyde
organic
resins,
phenol­
formaldehyde,

phenolic
resins,
urea­
formaldehyde)

Rubber,
natural
or
synthetic
(
e.
g.,
chlorosulfonated
polyethylene
[
Hypalon
®
]
,
ethylene­
propylene
rubber,

EPDM,
polybutadiene,
polychloroprene
[
neoprene],

polyisobutylene,
polyisoprene,
polystyrene,
rubber
hydrochloride
[
pliofilm
®
]
)

Sand/
Soil
Waxes,
commercial
brands
a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
met
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.

b
Bakelite
is
a
trademark
for
materials
that
can
be
composed
of
several
different
polymers,
including
polyethylene,
polypropylene,
epoxy,
phenolic,

polystyrene,
phenoxy,
perylene,
polysulfone,
ethylene
copolymers,
ABS,
acrylics,
and
vinyl
resins
and
compounds.

Allowable
Materials
for
Waste
Material
Types
III.
2
and
III.
3a
Homogeneous
Mixed
Organic
(
10%
by
weight)
and
Inorganic
(
90%
by
weight)
Materials
Any
material
in
Waste
Material
Types
I.
1,
I.
2,
I.
3,
II.
1,
II.
2,
II.
3,
or
III.
1,
provided
that
the
total
amount
of
solid
organic
material
and/
or
absorbed
or
adsorbed
water
is
less
than
or
equal
to
10
weight
percent
of
the
total
waste.

a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
237
Table
6­
2,
Allowable
Materials
 
Greater
Than
1
Weight
Percent
(
continued)

Allowable
Materials
for
Waste
Material
Type
IV.
1a
Solidified
Organics
Any
material
in
Waste
Types
I,
II,
or
III
Acids,
organic
Alcohols
(
e.
g.,
butanol,
ethanol,
isopropanol,
methanol)
Esters
(
e.
g.,
ethyl
acetate,
polyethylene
glycol
ester)
Ethers
(
e.
g.,
ethyl
ether)
Halogenated
organics
(
e.
g.,
bromoform;
carbon
tetrachloride
;
chlorobenzene;
chloroform;
1,1­
dichloroethane;
1,2­
dichloroethane;
1,1­
dichlorethylene;
cis­
1,2­
dichloroethylene;
methylene
chloride;
1,1,2,2­
tetrachloroethane;
tetrachloroethylene;
1,1,1­
trichloroethane;
1,1,2­
trichloroethane;
trichloroethylene;
1,1,2­
trichloro­
1,2,2­
trifluoroethane)
Hydrocarbons,
aliphatic
(
e.
g.,
cyclohexane,
n­
paraffin
hydrocarbons)
Hydrocarbons,
aromatic
(
e.
g.,
benzene;
ethyl
benzene;
toluene;
1,2,4­
trimethylbenzene;
1,3,5­
trimethylbenzene;
xylene)
Ketones
(
e.
g.,
acetone,
methyl
ethyl
ketone,
methyl
isobutyl
ketone)
Trioctyl
phosphine
oxide
a
Other
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
for
trace
constituents,
as
defined
in
Section
6.4.3.1.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
238
Table
6­
3,
Summary
of
Payload
Waste
Types
Waste
Typea
Waste
Typeb
(
XX)
Description
and
Examples
I
10
Solidified
Aqueous
or
Homogeneous
Inorganic
Solids
(<
1
percent
organics
­
not
including
packaging)
­
absorbed,
adsorbed
or
solidified
inorganic
liquid
­
soils,
solidified
particulates,
or
sludges
formed
from
precipitates
­
concreted
inorganic
particulate
waste
II
20
Solid
Inorganics
­
glass,
metal,
crucibles
­
other
solid
inorganics
III
30
Solid
Organics
­
plastics
(
e.
g.,
polyethylene,
polyvinyl
chloride)
­
cellulose
(
e.
g.,
paper,
cloth,
wood)
­
cemented
organic
solids
­
other
solid
organics
IV
40
Solidified
Organics
­
cemented
or
immobilized
organic
liquids
and
solids
a
Payload
shipping
category
notation
used
through
Revision
16
of
the
TRUPACT­
II
SAR.
b
Payload
shipping
category
notation
initiated
in
Revision
17
of
the
TRUPACT­
II
SAR.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
239
Table
6­
4,
CH­
TRU
Waste
Material
Types
and
G
Values
Waste
Material
Typea
Typical
Material
Description
G
Value
Numeric
Shipping
Category
Notationb
(
G
Value
x
102)
(
YYYY)

I.
1
Absorbed,
adsorbed,
or
solidified
inorganic
liquid
1.6
0160
I.
2
Soils,
solidified
particulates,
or
sludges
formed
from
precipitation
1.3
0130
I.
3
Concreted
inorganic
particulate
waste
0.4
0040
II.
1
Solid
inorganic
materials
in
plastic
bags
(
watt*
year
 
0.012)
1.7
0170
II.
1
Solid
inorganic
materials
in
plastic
bags
(
watt*
year
>
0.012)
0.32
0032
II.
2
Solid
inorganic
materials
in
metal
cans
0
0000
II.
3
Homogeneous
solid
inorganic
materials
with
unbound
absorbed
ambient
moisture
( 
6%
by
weight)
in
metal
cans
0.08
0008
III.
1
Solid
organic
materials
(
watt*
year
 
0.012)
3.4
0340
III.
1
Solid
organic
materials
(
watt*
year
>
0.012)
1.09
0109
III.
2
Homogeneous
mixed
organic
(
10%
by
weight)
and
inorganic
(
90%
by
weight)
materials
in
metal
cans
(
watt*
year
 
0.012)
0.34
0034
III.
2
Homogeneous
mixed
organic
(
10%
by
weight)
and
inorganic
(
90%
by
weight)
materials
in
metal
cans
(
watt*
year
>
0.012)
0.11
0011
III.
3
Homogeneous
mixed
organic
(
10%
by
weight)
and
inorganic
(
90%
by
weight)
materials
in
plastic
bags
(
watt*
year
 
0.012)
1.85
0185
III.
3
Homogeneous
mixed
organic
(
10%
by
weight)
and
inorganic
(
90%
by
weight)
materials
in
plastic
bags
(
watt*
year
>
0.012)
0.4
0040
IV.
1
Solidified
organics
Unknown
(
test)
9999
a
Payload
shipping
category
notation
used
through
Revision
16
of
the
TRUPACT­
II
SAR.
b
Payload
shipping
category
notation
initiated
in
Revision
17
of
the
TRUPACT­
II
SAR.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
240
Table
6­
5,
Alpha­
numeric
Shipping
Category
Notation
for
Payload
Package
Configurations
ALPHA
NOTATION
DESCRIPTION
A
55­
gallon
drums
with
materials
in
additional
layers
of
confinement
[
such
as
rigid
liner(
s),
bag(
s),
and
can(
s)]
(
includes
55­
gallon
drums
overpacked
in
a
TDOP)
B
Overpack
of
up
to
four
55­
gallon
drums
in
an
SWB
(
SWB
overpack)
C
SWB
with
materials
in
additional
layers
of
confinement
[
such
as
bag(
s)
and
can(
s)]
D
Overpack
of
one
experimental
bin
in
an
SWB
E
Overpack
of
one
pipe
component
in
a
55­
gallon
drum
(
standard
POC)

Table
6­
6,
Alpha­
numeric
Shipping
Category
Notation
for
Layers
of
Confinement
in
Payload
Packages
NOTATION
DESCRIPTION
0
No
closed
bags
around
waste
1
Up
to
a
maximum
of
1
closed
bag
around
waste
2
Up
to
a
maximum
of
2
closed
layers
of
bags
around
waste
3
Up
to
a
maximum
of
3
closed
layers
of
bags
around
waste
4
Up
to
a
maximum
of
4
closed
layers
of
bags
around
waste
5
Up
to
a
maximum
of
5
closed
layers
of
bags
around
waste
6
Up
to
a
maximum
of
6
closed
layers
of
bags
around
waste
M
Metal
container(
s)
as
the
innermost
layer
of
confinement
a
For
Waste
Types
II
and
III
packaged
in
drums,
denotes
a
minimum
of
2
liner
bags
b
For
all
waste
types
packaged
in
SWBs,
denotes
a
minimum
of
1
SWB
liner
bag
f
All
layers
of
bags
around
waste
are
vented
with
a
minimum
of
one
filter
vent
T
Payload
package
qualified
for
shipment
under
the
test
category
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
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VERSION
7
02/
12/
2004
PAGE
241
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF111A
RF211A
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0046
10
0130
0154
10
0130
0190
10
0130
0215
10
0130
0250
0.8068
0.2410
0.1962
0.1726
0.1486
NA
NA
RF111B
RF211B
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0311
0.1193
NA
NA
RF111D
RF211D
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0175
0.2121
NA
NA
RF111DF
RF211DF
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0210
10
0130
0246
0.1767
0.1509
NA
NA
RF111E
RF211E
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0156
10
0130
0191
10
0130
0216
10
0130
0252
0.2379
0.1943
0.1718
0.1473
NA
NA
RF111H
RF211H
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0286
10
0130
0373
10
0130
0408
10
0130
0433
10
0130
0469
0.1298
0.0995
0.0910
0.0857
0.0791
NA
NA
RF111J
RF211J
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0221
10
0130
0257
10
0130
0282
10
0130
0318
0.1679
0.1444
0.1316
0.1167
NA
NA
RF111K
RF211K
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0197
10
0130
0232
10
0130
0257
10
0130
0293
0.1884
0.1600
0.1444
0.1267
NA
NA
RF111P
RF211P
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0212
0.1751
NA
NA
RF111PF
RF211PF
001,
002,
007,
053,
054,
054H,
057,
060,
061,
062,
065,
067,
080,
081,
087,
159,
289,
290,
291,
292,
299,
340,
559,
800,
802,
803,
807,
828,
829
10
0130
0283
10
0130
0319
0.1311
0.1163
NA
NA
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
242
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF112A
RF212A
003,
332,
531,
801,
808,
816,
827
40
9999
0144
40
9999
0169
40
9999
0184
40
9999
0209
NA
NA
NA
NA
NA
NA
RF112B
RF212B
003,
332,
531,
801,
808,
816,
827
40
9999
0481
40
9999
0506
40
9999
0521
40
9999
0546
NA
NA
NA
RF112D
RF212D
003,
332,
531,
801,
808,
816,
827
40
9999
0174
NA
NA
NA
RF112DF
RF212DF
003,
332,
531,
801,
808,
816,
827
40
9999
0225
40
9999
0250
NA
NA
NA
NA
RF112J
RF212J
003,
332,
531,
801,
808,
816,
827
40
9999
0153
40
9999
0179
40
9999
0193
40
9999
0219
NA
NA
NA
NA
NA
NA
RF112N
RF212N
003,
332,
531,
801,
808,
816,
827
40
9999
0481
40
9999
0506
40
9999
0521
40
9999
0546
NA
NA
NA
NA
NA
NA
RF113A
RF213A
40
9999
0144
40
9999
0169
40
9999
0184
40
9999
0209
NA
NA
NA
NA
NA
NA
RF114A
RF214A
536,
806,
823
10
0040
0613
10
0040
0648
10
0040
0673
10
0040
0709
0.1968
0.1863
0.1792
0.1703
NA
NA
RF114B
RF214B
536,
806,
823
10
0040
0634
10
0040
0669
10
0040
0695
10
0040
0730
0.1902
0.1803
0.1735
0.1652
NA
NA
RF114D
RF214D
536,
806,
823
10
0040
0629
0.1917
NA
NA
RF114DF
RF214DF
536,
806,
823
10
0040
0664
10
0040
0700
0.1816
0.1723
NA
NA
RF114E
RF214E
536,
806,
823
10
0040
0156
10
0040
0191
10
0040
0216
10
0040
0252
0.7731
0.6315
0.5584
0.4786
NA
NA
RF114F
RF214F
536,
806,
823
10
0040
0156
10
0040
0191
10
0040
0216
10
0040
0252
0.7731
0.6315
0.5584
0.4786
NA
NA
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
243
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF114G
RF214G
536,
806,
823
10
0040
0175
0.6892
NA
NA
RF114GF
RF214GF
536,
806,
823
10
0040
0210
10
0040
0246
0.5743
0.4903
NA
NA
RF114J
RF214J
536,
806,
823
10
0040
0231
10
0040
0266
10
0040
0291
10
0040
0327
0.5221
0.4534
0.4145
0.3688
NA
NA
RF114JF
RF214JF
536,
806,
823
10
0040
0302
10
0040
0337
10
0040
0362
10
0040
0398
0.3994
0.3579
0.3332
0.3030
NA
NA
RF114K
RF214K
536,
806,
823
10
0040
0154
10
0040
0190
10
0040
0215
10
0040
0250
0.7832
0.6375
0.5610
0.4828
NA
NA
RF114L
RF214L
536,
806,
823
10
0040
0130
10
0040
0166
10
0040
0191
10
0040
0226
0.9278
0.7266
0.6315
0.5337
NA
NA
RF114P
RF214P
536,
806,
823
10
0040
0212
0.5689
NA
NA
RF114PF
RF214PF
536,
806,
823
10
0040
0283
10
0040
0319
0.4262
0.3781
NA
NA
RF115A
RF215A
300,
301,
301U,
303,
310,
310P,
312
20
0170
0502
20
0170
0528
20
0170
0542
20
0170
0568
0.0565
0.0537
0.0524
0.0500
20
0032
0502
20
0032
0528
20
0032
0542
20
0032
0568
0.3003
0.2855
0.2782
0.2654
RF115B
RF215B
300,
301,
301U,
303,
310,
310P,
312
20
0000
0000
40.0000
NA
NA
RF115D
RF215D
300,
301,
301U,
303,
310,
310P,
312
20
0000
0000
40.0000
NA
NA
RF115E
RF215E
300,
301,
301U,
303,
310,
310P,
312
20
0170
0153
20
0170
0179
20
0170
0193
20
0170
0219
0.1855
0.1585
0.1470
0.1296
20
0032
0153
20
0032
0179
20
0032
0193
20
0032
0219
0.9854
0.8423
0.7812
0.6884
RF115F
RF215F
300,
301,
301U,
303,
310,
310P,
312
20
0170
0114
20
0170
0140
20
0170
0154
20
0170
0180
0.2489
0.2034
0.1843
0.1577
20
0032
0114
20
0032
0140
20
0032
0154
20
0032
0180
1.3225
1.0769
0.9790
0.8376
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
244
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF115N
RF215N
300,
301,
301U,
303,
310,
310P,
312
20
0170
0399
20
0170
0481
20
0170
0506
20
0170
0521
20
0170
0546
0.0711
0.0590
0.0561
0.0545
0.0520
20
0032
0399
20
0032
0481
20
0032
0506
20
0032
0521
20
0032
0546
0.3779
0.3134
0.2980
0.2894
0.2761
RF116A
RF216A
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0041
30
0340
0502
30
0340
0528
30
0340
0542
30
0340
0568
0.3515
0.0283
0.0269
0.0262
0.0250
30
0109
0041
30
0109
0502
30
0109
0528
30
0109
0542
30
0109
0568
1.0795
0.0882
0.0838
0.0817
0.0779
RF116C
RF216C
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0144
30
0340
0169
30
0340
0184
30
0340
0209
0.0985
0.0840
0.0771
0.0680
30
0109
0144
30
0109
0169
30
0109
0184
30
0109
0209
0.3074
0.2619
0.2405
0.2118
RF116D
RF216D
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0147
0.0965
30
0109
0147
0.3011
RF116DF
RF216DF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216,
30
0340
0172
30
0340
0198
0.0825
0.0717
30
0109
0172
30
0109
0198
0.2573
0.2235
RF116E
RF216E
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216,
30
0340
0079
30
0340
0153
30
0340
0179
30
0340
0193
30
0340
0219
0.1796
0.0927
0.0793
0.0735
0.0648
30
0109
0079
30
0109
0153
30
0109
0179
30
0109
0193
30
0109
0219
0.5603
0.2893
0.2473
0.2293
0.2021
RF116EF
RF216EF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216,
30
0340
0105
30
0340
0179
30
0340
0205
30
0340
0219
30
0340
0244
0.1351
0.0793
0.0692
0.0648
0.0582
30
0109
0105
30
0109
0179
30
0109
0205
30
0109
0219
30
0109
0244
0.4215
0.2473
0.2159
0.2021
0.1814
RF116F
RF216F
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0034
30
0340
0114
30
0340
0140
30
0340
0154
30
0340
0180
0.4173
0.1245
0.1017
0.0921
0.0788
30
0109
0034
30
0109
0114
30
0109
0140
30
0109
0154
30
0109
0180
1.3018
0.3883
0.3161
0.2874
0.2459
RF116G
RF216G
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0070
30
0340
0144
30
0340
0170
30
0340
0184
30
0340
0209
0.2027
0.0985
0.0835
0.0771
0.0680
30
0109
0070
30
0109
0144
30
0109
0170
30
0109
0184
30
0109
0209
0.6323
0.3074
0.2604
0.2405
0.2118
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
245
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF116GF
RF216GF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0096
30
0340
0170
30
0340
0195
30
0340
0209
30
0340
0235
0.1478
0.0835
0.0728
0.0680
0.0604
30
0109
0096
30
0109
0170
30
0109
0195
30
0109
0209
30
0109
0235
0.4610
0.2604
0.2270
0.2118
0.1883
RF116H
RF216H
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0220
0.0646
30
0109
0220
0.2012
RF116I
RF216I
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0052
30
0340
0126
30
0340
0152
30
0340
0166
30
0340
0192
0.2729
0.1126
0.0937
0.0856
0.0739
30
0109
0052
30
0109
0126
30
0109
0152
30
0109
0166
30
0109
0192
0.8512
0.3513
0.2912
0.2666
0.2305
RF116J
RF216J
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0660
30
0340
0686
30
0340
0700
30
0340
0725
0.0215
0.0207
0.0203
0.0196
30
0109
0660
30
0109
0686
30
0109
0700
30
0109
0725
0.0671
0.0645
0.0632
0.0610
RF116K
RF216K
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0163
30
0340
0188
30
0340
0202
30
0340
0228
0.0871
0.0758
0.0702
0.0622
30
0109
0163
30
0109
0188
30
0109
0202
30
0109
0228
0.2715
0.2354
0.2191
0.1941
RF116KF
RF216KF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0188
30
0340
0214
30
0340
0228
30
0340
0254
0.0758
0.0663
0.0622
0.0559
30
0109
0188
30
0109
0214
30
0109
0228
30
0109
0254
0.2354
0.2068
0.1941
0.1743
RF116L
RF216L
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0839
30
0340
0865
30
0340
0879
30
0340
0905
0.0169
0.0164
0.0161
0.0157
30
0109
0839
30
0109
0865
30
0109
0879
30
0109
0905
0.0528
0.0512
0.0504
0.0489
RF116M
RF216M
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0172
30
0340
0198
30
0340
0212
30
0340
0237
0.0825
0.0717
0.0669
0.0599
30
0109
0172
30
0109
0198
30
0109
0212
30
0109
0237
0.2573
0.2235
0.2088
0.1868
RF116MF
RF216MF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0198
30
0340
0223
30
0340
0237
30
0340
0263
0.0717
0.0636
0.0599
0.0540
30
0109
0198
30
0109
0223
30
0109
0237
30
0109
0263
0.2235
0.1985
0.1868
0.1683
RF116N
RF216N
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0399
30
0340
0481
30
0340
0506
30
0340
0521
30
0340
0546
0.0356
0.0295
0.0280
0.0272
0.0260
30
0109
0399
30
0109
0481
30
0109
0506
30
0109
0521
30
0109
0546
0.1109
0.0920
0.0875
0.0850
0.0811
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
246
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF116P
RF216P
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0174
0.0815
30
0109
0174
0.2544
RF116PF
RF216PF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0225
30
0340
0250
0.0631
0.0568
30
0109
0225
30
0109
0250
0.1967
0.1770
RF116Q
RF216Q
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0459
30
0340
0485
30
0340
0499
30
0340
0525
0.0309
0.0293
0.0284
0.0270
30
0109
0459
30
0109
0485
30
0109
0499
30
0109
0525
0.0964
0.0913
0.0887
0.0843
RF116R
RF216R
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0687
30
0340
0713
30
0340
0727
30
0340
0752
0.0207
0.0199
0.0195
0.0189
30
0109
0687
30
0109
0713
30
0109
0727
30
0109
0752
0.0644
0.0621
0.0609
0.0589
RF116RF
RF216RF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0713
30
0340
0738
30
0340
0752
30
0340
0778
0.0199
0.0192
0.0189
0.0182
30
0109
0713
30
0109
0738
30
0109
0752
30
0109
0778
0.0621
0.0600
0.0589
0.0569
RF116S
RF216S
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0866
30
0340
0892
30
0340
0906
30
0340
0932
0.0164
0.0159
0.0157
0.0152
30
0109
0866
30
0109
0892
30
0109
0906
30
0109
0932
0.0511
0.0496
0.0489
0.0475
RF116SF
RF216SF
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0892
30
0340
0918
30
0340
0932
30
0340
0957
0.0159
0.0155
0.0152
0.0148
30
0109
0892
30
0109
0918
30
0109
0932
30
0109
0957
0.0496
0.0482
0.0475
0.0462
RF116T
RF216T
330,
336,
337,
487,
821,
822,
822X,
825,
831,
832,
832X,
833,
861,
862,
863,
2116,
2216
30
0340
0043
0.3329
30
0109
0043
1.0293
RF117A
RF217A
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0041
20
0170
0372
20
0170
0502
20
0170
0528
20
0170
0542
20
0170
0568
0.7029
0.0763
0.0565
0.0537
0.0524
0.0500
20
0032
0041
20
0032
0372
20
0032
0502
20
0032
0528
20
0032
0542
20
0032
0568
3.6771
0.4053
0.3003
0.2855
0.2782
0.2654
RF117B
RF217B
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0000
0000
40.0000
NA
NA
RF117C
RF217C
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0144
20
0170
0169
20
0170
0184
20
0170
0209
0.1971
0.1680
0.1542
0.1360
20
0032
0144
20
0032
0169
20
0032
0184
20
0032
0209
1.0470
0.8921
0.8194
0.7214
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
247
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF117D
RF217D
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0000
0000
40.0000
NA
NA
RF117E
RF217E
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0079
20
0170
0153
20
0170
0179
20
0170
0193
20
0170
0219
0.3592
0.1855
0.1585
0.1470
0.1296
20
0032
0079
20
0032
0153
20
0032
0179
20
0032
0193
20
0032
0219
1.9084
0.9854
0.8423
0.7812
0.6884
RF117F
RF217F
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0034
20
0170
0114
20
0170
0140
20
0170
0154
20
0170
0180
0.8518
0.2489
0.2034
0.1843
0.1577
20
0032
0034
20
0032
0114
20
0032
0140
20
0032
0154
20
0032
0180
4.4342
1.3225
1.0769
0.9790
0.8376
RF117H
RF217H
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0220
0.1292
20
0032
0220
0.6853
RF117I
RF217I
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0032
20
0170
0052
20
0170
0126
20
0170
0152
20
0170
0166
20
0170
0192
0.8868
0.5457
0.2252
0.1875
0.1711
0.1478
20
0032
0032
20
0032
0052
20
0032
0126
20
0032
0152
20
0032
0166
20
0032
0192
4.7113
2.8993
1.1965
0.9919
0.9082
0.7852
RF117K
RF217K
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
489,
824,
854,
2117
20
0170
0062
0.4577
20
0032
0062
2.4317
RF117N
RF217N
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0399
20
0170
0481
20
0170
0506
20
0170
0521
20
0170
0546
0.0711
0.0590
0.0561
0.0545
0.0520
20
0032
0399
20
0032
0481
20
0032
0506
20
0032
0521
20
0032
0546
0.3779
0.3134
0.2980
0.2894
0.2761
RF117T
RF217T
197W,
320,
321,
416,
479,
480,
481,
483,
484,
485,
486,
488,
824,
2117
20
0170
0043
0.6659
20
0032
0043
3.5061
RF118A
RF218A
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0041
20
0170
0502
20
0170
0528
20
0170
0542
20
0170
0568
0.7029
0.0565
0.0537
0.0524
0.0500
20
0032
0041
20
0032
0502
20
0032
0528
20
0032
0542
20
0032
0568
3.6771
0.3003
0.2855
0.2782
0.2654
RF118B
RF218B
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0000
0000
40.0000
NA
NA
RF118C
RF218C
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0144
20
0170
0169
20
0170
0184
20
0170
0209
0.1971
0.1680
0.1542
0.1360
20
0032
0144
20
0032
0169
20
0032
0184
20
0032
0209
1.0470
0.8921
0.8194
0.7214
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
248
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF118D
RF218D
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0000
0000
40.0000
NA
NA
RF118E
RF218E
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0079
20
0170
0153
20
0170
0179
20
0170
0193
20
0170
0219
0.3592
0.1855
0.1585
0.1470
0.1296
20
0032
0079
20
0032
0153
20
0032
0179
20
0032
0193
20
0032
0219
1.9084
0.9854
0.8423
0.7812
0.6884
RF118F
RF218F
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0034
20
0170
0114
20
0170
0140
20
0170
0154
20
0170
0180
0.8518
0.2489
0.2034
0.1843
0.1577
20
0032
0034
20
0032
0114
20
0032
0140
20
0032
0154
20
0032
0180
4.4342
1.3225
1.0769
0.9790
0.8376
RF118H
RF218H
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0220
0.1292
20
0032
0220
0.6853
RF118I
RF218I
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0052
20
0170
0126
20
0170
0152
20
0170
0166
20
0170
0192
0.5457
0.2252
0.1875
0.1711
0.1478
20
0032
0052
20
0032
0126
20
0032
0152
20
0032
0166
20
0032
0192
2.8993
1.1965
0.9919
0.9082
0.7852
RF118N
RF218N
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0399
20
0170
0481
20
0170
0506
20
0170
0521
20
0170
0546
0.0711
0.0590
0.0561
0.0545
0.0520
20
0032
0399
20
0032
0481
20
0032
0506
20
0032
0521
20
0032
0546
0.3779
0.3134
0.2980
0.2894
0.2761
RF118T
RF218T
360,
368,
370,
440,
441,
442,
443,
444,
601,
655,
855,
856,
859,
2118,
2218
20
0170
0043
0.6659
20
0032
0043
3.5061
RF119A
RF219A
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0041
30
0340
0502
30
0340
0528
30
0340
0542
30
0340
0568
0.3515
0.0283
0.0269
0.0262
0.0250
30
0109
0041
30
0109
0502
30
0109
0528
30
0109
0542
30
0109
0568
1.0795
0.0882
0.0838
0.0817
0.0779
RF119BA
RF219BA
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0508
30
0340
0533
30
0340
0548
30
0340
0573
0.0279
0.0266
0.0259
0.0248
30
0109
0508
30
0109
0533
30
0109
0548
30
0109
0573
0.0871
0.0830
0.0808
0.0772
RF119BAF
RF219BAF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0533
30
0340
0559
30
0340
0573
30
0340
0599
0.0266
0.0254
0.0248
0.0237
30
0109
0533
30
0109
0559
30
0109
0573
30
0109
0599
0.0830
0.0792
0.0772
0.0739
RF119C
RF219C
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0144
30
0340
0169
30
0340
0184
30
0340
0209
0.0985
0.0840
0.0771
0.0680
30
0109
0144
30
0109
0169
30
0109
0184
30
0109
0209
0.3074
0.2619
0.2405
0.2118
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
249
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
250
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF119D
RF219D
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0147
0.0965
30
0109
0147
0.3011
RF119DF
RF219DF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0172
30
0340
0198
0.0825
0.0717
30
0109
0172
30
0109
0198
0.2573
0.2235
RF119E
RF219E
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0079
30
0340
0153
30
0340
0179
30
0340
0193
30
0340
0219
0.1796
0.0927
0.0793
0.0735
0.0648
30
0109
0079
30
0109
0153
30
0109
0179
30
0109
0193
30
0109
0219
0.5603
0.2893
0.2473
0.2293
0.2021
RF119EF
RF219EF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0105
30
0340
0179
30
0340
0205
30
0340
0219
30
0340
0244
0.1351
0.0793
0.0692
0.0648
0.0582
30
0109
0105
30
0109
0179
30
0109
0205
30
0109
0219
30
0109
0244
0.4215
0.2473
0.2159
0.2021
0.1814
RF119F
RF219F
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0034
30
0340
0114
30
0340
0140
30
0340
0154
30
0340
0180
0.4259
0.1245
0.1017
0.0921
0.0788
30
0109
0034
30
0109
0114
30
0109
0140
30
0109
0154
30
0109
0180
1.3018
0.3883
0.3161
0.2874
0.2459
RF119G
RF219G
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0070
30
0340
0144
30
0340
0170
30
0340
0184
30
0340
0209
0.2027
0.0985
0.0835
0.0771
0.0680
30
0109
0070
30
0109
0144
30
0109
0170
30
0109
0184
30
0109
0209
0.6323
0.3074
0.2604
0.2405
0.2118
RF119GF
RF219GF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0096
30
0340
0170
30
0340
0195
30
0340
0209
30
0340
0235
0.1478
0.0835
0.0728
0.0680
0.0604
30
0109
0096
30
0109
0170
30
0109
0195
30
0109
0209
30
0109
0235
0.4610
0.2604
0.2270
0.2118
0.1883
RF119H
RF219H
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0220
0.0646
30
0109
0220
0.2012
RF119I
RF219I
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0052
30
0340
0126
30
0340
0152
30
0340
0166
30
0340
0192
0.2729
0.1126
0.0937
0.0856
0.0739
30
0109
0052
30
0109
0126
30
0109
0152
30
0109
0166
30
0109
0192
0.8512
0.3513
0.2912
0.2666
0.2305
RF119J
RF219J
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0660
30
0340
0686
30
0340
0700
30
0340
0725
0.0215
0.0207
0.0203
0.0196
30
0109
0660
30
0109
0686
30
0109
0700
30
0109
0725
0.0671
0.0645
0.0632
0.0610
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
251
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF119K
RF219K
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0163
30
0340
0188
30
0340
0202
30
0340
0228
0.0871
0.0758
0.0702
0.0622
30
0109
0163
30
0109
0188
30
0109
0202
30
0109
0228
0.2715
0.2354
0.2191
0.1941
RF119KF
RF219KF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0188
30
0340
0214
30
0340
0228
30
0340
0254
0.0758
0.0663
0.0622
0.0559
30
0109
0188
30
0109
0214
30
0109
0228
30
0109
0254
0.2354
0.2068
0.1941
0.1743
RF119L
RF219L
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0839
30
0340
0865
30
0340
0879
30
0340
0905
0.0169
0.0164
0.0161
0.0157
30
0109
0839
30
0109
0865
30
0109
0879
30
0109
0905
0.0528
0.0512
0.0504
0.0489
RF119M
RF219M
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0172
30
0340
0198
30
0340
0212
30
0340
0237
0.0825
0.0717
0.0669
0.0599
30
0109
0172
30
0109
0198
30
0109
0212
30
0109
0237
0.2573
0.2235
0.2088
0.1868
RF119MF
RF219MF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0198
30
0340
0223
30
0340
0237
30
0340
0263
0.0717
0.0636
0.0599
0.0540
30
0109
0198
30
0109
0223
30
0109
0237
30
0109
0263
0.2235
0.1985
0.1868
0.1683
RF119N
RF219N
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0399
30
0340
0481
30
0340
0506
30
0340
0521
30
0340
0546
0.0356
0.0295
0.0280
0.0272
0.0260
30
0109
0399
30
0109
0481
30
0109
0506
30
0109
0521
30
0109
0546
0.1109
0.0920
0.0875
0.0850
0.0811
RF119P
RF219P
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0174
0.0815
30
0109
0174
0.2544
RF119PF
RF219PF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0225
30
0340
0250
0.0631
0.0568
30
0109
0225
30
0109
0250
0.1967
0.1770
RF119Q
RF219Q
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0459
30
0340
0485
30
0340
0499
30
0340
0525
0.0309
0.0293
0.0284
0.0270
30
0109
0459
30
0109
0485
30
0109
0499
30
0109
0525
0.0964
0.0913
0.0887
0.0843
RF119R
RF219R
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0687
30
0340
0713
30
0340
0727
30
0340
0752
0.0207
0.0199
0.0195
0.0189
30
0109
0687
30
0109
0713
30
0109
0727
30
0109
0752
0.0644
0.0621
0.0609
0.0589
RF119RF
RF219RF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0713
30
0340
0738
30
0340
0752
30
0340
0778
0.0199
0.0192
0.0189
0.0182
30
0109
0713
30
0109
0738
30
0109
0752
30
0109
0778
0.0621
0.0600
0.0589
0.0569
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
252
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF119S
RF219S
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0866
30
0340
0892
30
0340
0906
30
0340
0932
0.0164
0.0159
0.0157
0.0152
30
0109
0866
30
0109
0892
30
0109
0906
30
0109
0932
0.0511
0.0496
0.0489
0.0475
RF119SF
RF219SF
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0892
30
0340
0918
30
0340
0932
30
0340
0957
0.0159
0.0155
0.0152
0.0148
30
0109
0892
30
0109
0918
30
0109
0932
30
0109
0957
0.0496
0.0482
0.0475
0.0462
RF119T
RF219T
328,
331,
335,
342,
490,
491,
492,
2219
30
0340
0043
0.3329
30
0109
0043
1.0293
RF121A
RF221A
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0041
30
0340
0372
30
0340
0502
30
0340
0528
30
0340
0542
30
0340
0568
0.3515
0.0381
0.0283
0.0269
0.0262
0.0250
30
0109
0041
30
0109
0372
30
0109
0502
30
0109
0528
30
0109
0542
30
0109
0568
1.0795
0.1190
0.0882
0.0838
0.0817
0.0779
RF121D
RF221D
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0486
30
0340
0512
0.0292
0.0277
30
0109
0486
30
0109
0512
0.0911
0.0864
RF121DA
RF221DA
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0147
0.0965
30
0109
0147
0.3011
RF121DAF
RF221DAF
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0172
30
0340
0198
0.0825
0.0717
30
0109
0172
30
0109
0198
0.2573
0.2235
RF121DF
RF221DF
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0512
30
0340
0538
0.0277
0.0264
30
0109
0512
30
0109
0538
0.0864
0.0823
RF121E
RF221E
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0079
30
0340
0153
30
0340
0179
30
0340
0193
30
0340
0219
0.1796
0.0927
0.0793
0.0735
0.0648
30
0109
0079
30
0109
0153
30
0109
0179
30
0109
0193
30
0109
0219
0.5603
0.2893
0.2473
0.2293
0.2021
RF121F
RF221F
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0034
30
0340
0114
30
0340
0140
30
0340
0154
30
0340
0180
0.4259
0.1245
0.1017
0.0921
0.0788
30
0109
0034
30
0109
0114
30
0109
0140
30
0109
0154
30
0109
0180
1.3018
0.3883
0.3161
0.2874
0.2459
RF121H
RF221H
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0220
0.0646
30
0109
0220
0.2012
RF121I
RF221I
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0032
30
0340
0052
30
0340
0126
30
0340
0152
30
0340
0166
30
0340
0192
0.4434
0.2729
0.1126
0.0937
0.0856
0.0739
30
0109
0032
30
0109
0052
30
0109
0126
30
0109
0152
30
0109
0166
30
0109
0192
1.3831
0.8512
0.3513
0.2912
0.2666
0.2305
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
253
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF121K
RF221K
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0062
0.2289
30
0109
0062
0.7139
RF121N
RF221N
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0399
30
0340
0481
30
0340
0506
30
0340
0521
30
0340
0546
0.0356
0.0295
0.0280
0.0272
0.0260
30
0109
0399
30
0109
0481
30
0109
0506
30
0109
0521
30
0109
0546
0.1109
0.0920
0.0875
0.0850
0.0811
RF121T
RF221T
000,
200,
302,
338S,
350,
374,
420F,
430,
431,
523,
545,
998,
3011
30
0340
0043
0.3329
30
0109
0043
1.0293
RF122A
RF222A
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0041
20
0170
0502
20
0170
0528
20
0170
0542
20
0170
0568
0.7029
0.0565
0.0537
0.0524
0.0500
20
0032
0041
20
0032
0502
20
0032
0528
20
0032
0542
20
0032
0568
3.6771
0.3003
0.2855
0.2782
0.2654
RF122B
RF222B
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0000
0000
40.0000
NA
NA
RF122D
RF222D
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0000
0000
40.0000
NA
NA
RF122E
RF222E
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0079
20
0170
0153
20
0170
0179
20
0170
0193
20
0170
0219
0.3592
0.1855
0.1585
0.1470
0.1296
20
0032
0079
20
0032
0153
20
0032
0179
20
0032
0193
20
0032
0219
1.9084
0.9854
0.8423
0.7812
0.6884
RF122F
RF222F
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0034
20
0170
0114
20
0170
0140
20
0170
0154
20
0170
0180
0.8518
0.2489
0.2034
0.1843
0.1577
20
0032
0034
20
0032
0114
20
0032
0140
20
0032
0154
20
0032
0180
4.4342
1.3225
1.0769
0.9790
0.8376
RF122H
RF222H
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0220
0.1292
20
0032
0220
0.6853
RF122I
RF222I
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0052
20
0170
0126
20
0170
0152
20
0170
0166
20
0170
0192
0.5457
0.2252
0.1875
0.1711
0.1478
20
0032
0052
20
0032
0126
20
0032
0152
20
0032
0166
20
0032
0192
2.8993
1.1965
0.9919
0.9082
0.7852
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
254
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF122N
RF222N
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0399
20
0170
0481
20
0170
0506
20
0170
0521
20
0170
0546
0.0711
0.0590
0.0561
0.0545
0.0520
20
0032
0399
20
0032
0481
20
0032
0506
20
0032
0521
20
0032
0546
0.3779
0.3134
0.2980
0.2894
0.2761
RF122T
RF222T
044,
317,
334,
344,
371,
372,
375,
377,
378,
379,
387,
390,
390P,
391,
391P,
392,
392P,
394,
394P,
395,
395P,
396,
396P,
398,
398P,
398R,
438,
532,
869
20
0170
0043
0.6659
20
0032
0043
3.5061
RF123A
RF223A
339
30
0340
0502
30
0340
0528
30
0340
0542
30
0340
0568
0.0283
0.0269
0.0262
0.0250
30
0109
0502
30
0109
0528
30
0109
0542
30
0109
0568
0.0882
0.0838
0.0817
0.0779
RF123E
RF223E
339
30
0340
0144
30
0340
0169
30
0340
0184
30
0340
0209
0.0985
0.0840
0.0771
0.0680
30
0109
0144
30
0109
0169
30
0109
0184
30
0109
0209
0.3074
0.2619
0.2405
0.2118
RF123F
RF223F
339
30
0340
0034
30
0340
0114
30
0340
0140
30
0340
0154
30
0340
0180
0.4259
0.1245
0.1017
0.0921
0.0788
30
0109
0034
30
0109
0114
30
0109
0140
30
0109
0154
30
0109
0180
1.3018
0.3883
0.3161
0.2874
0.2459
RF123I
RF223I
339
30
0340
0052
30
0340
0126
30
0340
0152
30
0340
0166
30
0340
0192
0.2729
0.1126
0.0937
0.0856
0.0739
30
0109
0052
30
0109
0126
30
0109
0152
30
0109
0166
30
0109
0192
0.8512
0.3513
0.2912
0.2666
0.2305
RF123N
RF223N
339
30
0340
0399
30
0340
0481
30
0340
0506
30
0340
0521
30
0340
0546
0.0356
0.0295
0.0280
0.0272
0.0260
30
0109
0399
30
0109
0481
30
0109
0506
30
0109
0521
30
0109
0546
0.1109
0.0920
0.0875
0.0850
0.0811
RF124B
RF224B
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0000
0000
40.0000
NA
NA
RF124D
RF224D
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0000
0000
40.0000
NA
NA
RF124E
RF224E
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0193
20
0008
0229
20
0008
0254
20
0008
0289
3.1246
2.6334
2.3742
2.0867
NA
NA
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
255
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF124F
RF224F
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0212
2.8446
NA
NA
RF124FF
RF224FF
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0283
20
0008
0319
2.1309
1.8904
NA
NA
RF124G
RF224G
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0175
3.4460
NA
NA
RF124GF
RF224GF
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0210
20
0008
0246
2.8717
2.4514
NA
NA
RF124H
RF224H
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0629
0.9587
NA
NA
RF124HF
RF224HF
409,
411R,
411X,
412,
414,
429R,
429X,
433R,
433X,
436R,
436X,
454R,
454X
20
0008
0664
20
0008
0700
0.9082
0.8615
NA
NA
RF126A
RF226A
089,
099,
340,
531,
537,
809
30
0340
0481
30
0340
0506
30
0340
0521
30
0340
0546
0.0295
0.0280
0.0272
0.0260
30
0109
0481
30
0109
0506
30
0109
0521
30
0109
0546
0.0920
0.0875
0.0850
0.0811
RF126D
RF226D
089,
099,
340,
531,
537,
809
30
0340
0486
0.0292
30
0109
0486
0.0911
RF126DA
RF226DA
089,
099,
340,
531,
537,
809
30
0340
0147
0.0965
30
0109
0147
0.3011
RF126DAF
RF226DAF
089,
099,
340,
531,
537,
809
30
0340
0172
30
0340
0198
0.0825
0.0717
30
0109
0172
30
0109
0198
0.2573
0.2235
RF126DF
RF226DF
089,
099,
340,
531,
537,
809
30
0340
0512
30
0340
0538
0.0277
0.0264
30
0109
0512
30
0109
0538
0.0864
0.0823
RF126E
RF226E
089,
099,
340,
531,
537,
809
30
0340
0126
30
0340
0152
30
0340
0166
30
0340
0192
0.1126
0.0937
0.0856
0.0739
30
0109
0126
30
0109
0152
30
0109
0166
30
0109
0192
0.3513
0.2912
0.2666
0.2305
RF126J
RF226J
089,
099,
340,
531,
537,
809
30
0340
0180
30
0340
0206
30
0340
0220
30
0340
0246
0.0788
0.0689
0.0646
0.0577
30
0109
0180
30
0109
0206
30
0109
0220
30
0109
0246
0.2459
0.2149
0.2012
0.1799
RF126K
RF226K
089,
099,
340,
531,
537,
809
30
0340
0144
30
0340
0169
30
0340
0184
30
0340
0209
0.0985
0.0840
0.0771
0.0680
30
0109
0144
30
0109
0169
30
0109
0184
30
0109
0209
0.3074
0.2619
0.2405
0.2118
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
256
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF126L
RF226L
089,
099,
340,
531,
537,
809
30
0340
0114
30
0340
0140
30
0340
0154
30
0340
0180
0.1245
0.1017
0.0921
0.0788
30
0109
0114
30
0109
0140
30
0109
0154
30
0109
0180
0.3883
0.3161
0.2874
0.2459
RF126P
RF226P
089,
099,
340,
531,
537,
809
30
0340
0174
0.0815
30
0109
0174
0.2544
RF126PF
RF226PF
089,
099,
340,
531,
537,
809
30
0340
0225
30
0340
0250
0.0631
0.0568
30
0109
0225
30
0109
0250
0.1967
0.1770
RF127A
RF227A
480A,
828,
829
30
0340
0041
30
0340
0144
30
0340
0169
30
0340
0184
30
0340
0209
0.3460
0.0985
0.0839
0.0771
0.0678
NA
NA
RF127D
RF227D
480A,
828,
829
30
0340
0147
0.0965
NA
NA
RF127DF
RF227DF
480A,
828,
829
30
0340
0172
30
0340
0198
0.0824
0.0716
NA
NA
RF127E
RF227E
480A,
828,
829
30
0340
0133
30
0340
0159
30
0340
0173
30
0340
0198
0.1066
0.0892
0.0820
0.0716
NA
NA
RF127F
RF227F
480A,
828,
829
30
0340
0034
30
0340
0114
30
0340
0140
30
0340
0154
30
0340
0180
0.4173
0.1244
0.1013
0.0921
0.0788
NA
NA
RF127J
RF227J
480A,
828,
829
30
0340
0180
30
0340
0206
30
0340
0220
30
0340
0246
0.0788
0.0688
0.0644
0.0576
NA
NA
RF127K
RF227K
480A,
828,
829
30
0340
0163
30
0340
0188
30
0340
0202
30
0340
0228
0.0870
0.0754
0.0702
0.0622
NA
NA
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
257
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF127N
RF227N
480A,
828,
829
30
0340
0122
30
0340
0148
30
0340
0162
30
0340
0188
30
0340
0399
0.1163
0.0958
0.0875
0.0754
0.0355
NA
NA
RF127P
RF227P
480A,
828,
829
30
0340
0174
0.0815
NA
NA
RF127PF
RF227PF
480A,
828,
829
30
0340
0225
30
0340
0250
0.0630
0.0567
NA
NA
RF130A
RF230A
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0041
30
0185
0372
30
0185
0502
30
0185
0528
30
0185
0542
30
0185
0568
0.6360
0.0701
0.0519
0.0494
0.0481
0.0459
30
0040
0041
30
0040
0372
30
0040
0502
30
0040
0528
30
0040
0542
30
0040
0568
2.9417
0.3242
0.2403
0.2284
0.2225
0.2123
RF130B
RF230B
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0502
30
0034
0528
30
0034
0542
30
0034
0568
0.2827
0.2687
0.2618
0.2498
30
0011
0502
30
0011
0528
30
0011
0542
30
0011
0568
0.8737
0.8307
0.8092
0.7722
RF130BA
RF230BA
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0508
30
0034
0533
30
0034
0548
30
0034
0573
0.2793
0.2662
0.2589
0.2476
30
0011
0508
30
0011
0533
30
0011
0548
30
0011
0573
0.8634
0.8229
0.8003
0.7654
RF130D
RF230D
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0486
30
0034
0512
0.2920
0.2771
30
0011
0486
30
0011
0512
0.9024
0.8566
RF130DF
RF230DF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0512
30
0034
0538
0.2771
0.2637
30
0011
0512
30
0011
0538
0.8566
0.8152
RF130E
RF230E
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0133
30
0034
0159
30
0034
0173
30
0034
0198
1.0669
0.8924
0.8202
0.7166
30
0011
0133
30
0011
0159
30
0011
0173
30
0011
0198
3.2976
2.7584
2.5352
2.2151
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
258
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
259
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF130F
RF230F
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0034
30
0185
0133
30
0185
0159
30
0185
0173
30
0185
0198
0.7670
0.1961
0.1640
0.1507
0.1317
30
0040
0034
30
0040
0133
30
0040
0159
30
0040
0173
30
0040
0198
3.5474
0.9068
0.7586
0.6972
0.6091
RF130G
RF230G
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0147
30
0034
0172
0.9653
0.8250
30
0011
0147
30
0011
0172
2.9836
2.5499
RF130GF
RF230GF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0172
30
0034
0198
0.8250
0.7166
30
0011
0172
30
0011
0198
2.5499
2.2151
RF130H
RF230H
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0220
0.1185
30
0040
0220
0.5482
RF130I
RF230I
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0032
30
0185
0052
30
0185
0126
30
0185
0152
30
0185
0166
30
0185
0192
0.8149
0.5015
0.2070
0.1716
0.1571
0.1358
30
0040
0032
30
0040
0052
30
0040
0126
30
0040
0152
30
0040
0166
30
0040
0192
3.7691
2.3194
0.9572
0.7935
0.7266
0.6282
RF130J
RF230J
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0180
30
0034
0206
30
0034
0220
30
0034
0246
0.7883
0.6888
0.6450
0.5768
30
0011
0180
30
0011
0206
30
0011
0220
30
0011
0246
2.4366
2.1290
1.9936
1.7829
RF130K
RF230K
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0062
30
0185
0687
30
0185
0713
30
0185
0727
30
0185
0752
0.4206
0.0380
0.0366
0.0359
0.0347
30
0040
0062
30
0040
0687
30
0040
0713
30
0040
0727
30
0040
0752
1.9453
0.1756
0.1692
0.1659
0.1604
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
260
Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF130N
RF230N
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0399
0.0654
30
0040
0399
0.3023
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
261
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF130P
RF230P
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0174
0.8155
30
0011
0174
2.5206
RF130PA
RF230PA
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0513
0.2766
30
0011
0513
0.8549
RF130PAF
RF230PAF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0565
30
0034
0590
0.2511
0.2405
30
0011
0565
30
0011
0590
0.7763
0.7434
RF130PF
RF230PF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0034
0225
30
0034
0250
0.6306
0.5676
30
0011
0225
30
0011
0250
1.9493
1.7543
RF130Q
RF230Q
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0660
30
0185
0686
30
0185
0700
30
0185
0725
0.0395
0.0380
0.0373
0.0360
30
0040
0660
30
0040
0686
30
0040
0700
30
0040
0725
0.1827
0.1758
0.1723
0.1664
RF130R
RF230R
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0163
30
0185
0188
30
0185
0202
30
0185
0228
0.1600
0.1387
0.1291
0.1144
30
0040
0163
30
0040
0188
30
0040
0202
30
0040
0228
0.7399
0.6415
0.5971
0.5290
RF130RF
RF230RF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0188
30
0185
0214
30
0185
0228
30
0185
0254
0.1387
0.1219
0.1144
0.1027
30
0040
0188
30
0040
0214
30
0040
0228
30
0040
0254
0.6415
0.5636
0.5290
0.4748
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
262
Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF130S
RF230S
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0866
30
0185
0892
30
0185
0906
30
0185
0932
0.0301
0.0292
0.0288
0.0280
30
0040
0866
30
0040
0892
30
0040
0906
30
0040
0932
0.1393
0.1352
0.1331
0.1294
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
263
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF130SF
RF230SF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0892
30
0185
0918
30
0185
0932
30
0185
0957
0.0292
0.0284
0.0280
0.0272
30
0040
0892
30
0040
0918
30
0040
0932
30
0040
0957
0.1352
0.1314
0.1294
0.1260
RF130T
RF230T
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0043
0.6065
30
0040
0043
2.8049
RF130U
RF230U
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0839
30
0185
0865
30
0185
0879
30
0185
0905
0.0311
0.0301
0.0297
0.0288
30
0040
0839
30
0040
0865
30
0040
0879
30
0040
0905
0.1438
0.1394
0.1372
0.1333
RF130V
RF230V
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0172
30
0185
0198
30
0185
0212
30
0185
0237
0.1516
0.1317
0.1230
0.1100
30
0040
0172
30
0040
0198
30
0040
0212
30
0040
0237
0.7012
0.6091
0.5689
0.5089
RF130VF
RF230VF
090,
091,
092,
093,
097,
338,
373,
376,
393,
393R,
394C,
396C,
398C,
411,
419,
420,
420P,
421,
422,
423,
424,
425,
428,
429,
433,
436,
454,
532,
532A,
532B,
532C,
532D,
3010,
H61
30
0185
0198
30
0185
0223
30
0185
0237
30
0185
0263
0.1317
0.1169
0.1100
0.0992
30
0040
0198
30
0040
0223
30
0040
0237
30
0040
0263
0.6091
0.5409
0.5089
0.4586
RF131A
RF231A
489,
854
20
0170
0041
20
0170
0502
20
0170
0528
20
0170
0542
20
0170
0568
0.7029
0.0565
0.0537
0.0524
0.0500
20
0032
0041
20
0032
0502
20
0032
0528
20
0032
0542
20
0032
0568
3.6771
0.3003
0.2855
0.2782
0.2654
RF131B
RF231B
489,
854
20
0000
0000
40.0000
NA
NA
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
264
Table
6­
7,
RFETS
TRUCON
Content
Codes,
Correlating
IDCs,
Shipping
Categories,
and
Decay
Heat
Limits
(
continued)

Watt*
year
Criteria
>
0.012
TRUCON
Content
Code
RFETS
Correlating
IDCs
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
Numeric
Shipping
Category
 
Decay
Heat
Limit
(
Watts/
pkg)
RF131D
RF231D
489,
854
20
0000
0000
40.0000
NA
NA
RF131E
RF231E
489,
854
20
0170
0079
20
0170
0153
20
0170
0179
20
0170
0193
20
0170
0219
0.3592
0.1855
0.1585
0.1470
0.1296
20
0032
0079
20
0032
0153
20
0032
0179
20
0032
0193
20
0032
0219
1.9084
0.9854
0.8423
0.7812
0.6884
RF131F
RF231F
489,
854
20
0170
0034
20
0170
0114
20
0170
0140
20
0170
0154
20
0170
0180
0.8518
0.2489
0.2034
0.1843
0.1577
20
0032
0034
20
0032
0114
20
0032
0140
20
0032
0154
20
0032
0180
4.4342
1.3225
1.0769
0.9790
0.8376
RF131H
RF231H
489,
854
20
0170
0220
0.1292
20
0032
0220
0.6853
RF131I
RF231I
489,
854
20
0170
0052
20
0170
0126
20
0170
0152
20
0170
0166
20
0170
0192
0.5457
0.2252
0.1875
0.1711
0.1478
20
0032
0052
20
0032
0126
20
0032
0152
20
0032
0166
20
0032
0192
2.8993
1.1965
0.9919
0.9082
0.7852
RF131K
RF231K
489,
854
20
0170
0062
0.4577
20
0032
0062
2.4317
RF131N
RF231N
489,
854
20
0170
0399
20
0170
0481
20
0170
0506
20
0170
0521
20
0170
0546
0.0711
0.0590
0.0561
0.0545
0.0520
20
0032
0399
20
0032
0481
20
0032
0506
20
0032
0521
20
0032
0546
0.3779
0.3134
0.2980
0.2894
0.2761
RF131T
RF231T
489,
854
20
0170
0043
0.6659
20
0032
0043
3.5061
*
Packaging
specific
information
(
container
type,
confinement
layers,
etc.)
for
each
shipping
category
is
located
in
Table
2
of
the
TRUCON.

Note:
An
IDC
that
is
not
listed
in
this
table
may
still
be
shipped
in
the
TRUPACT­
II
provided
all
the
applicable
requirements
for
the
assigned
TRUCON
code
are
met.

NA
=
Not
applicable.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
265
Table
6­
8,
Decay
Heat
Criteria
for
Drum
Selection
Shipping
Category
Maximum
Decay
Heat
per
TRUPACT­
II
(
watts)
Test
Temperature
All
shipping
categories
for
drums
in
Waste
Type
I
34
RT
All
shipping
categories
for
drums
in
Waste
Type
II
37
RT
All
shipping
categories
for
drums
overpacked
in
SWBs
in
Waste
Type
I
10
RT
All
shipping
categories
for
drums
overpacked
in
SWBs
in
Waste
Type
II
11
RT
All
shipping
categories
for
drums
in
Waste
Type
III
less
than
or
equal
to
7
watts
per
TRUPACT­
II
7
RT
All
shipping
categories
for
drums
in
Waste
Type
III
greater
than
7
watts
per
TRUPACT­
II
20
146
°
F
All
shipping
categories
for
drums
overpacked
in
SWBs
in
Waste
Type
III
5
RT
All
shipping
categories
in
Waste
Type
IV
7
135
°
F
RT
=
Room
temperature.

Table
6­
9,
Maximum
Total
Gas
Release
Rates
for
Test
Categories
55­
Gallon
Drums
Drums
Overpacked
in
an
SWB
Payload
Shipping
Category
Maximum
Gas
Release
Rate
(
moles/
sec/
container)
a
Payload
Shipping
Category
Maximum
Gas
Release
Rate
(
moles/
sec/
container)
a
Payload
shipping
categories
belonging
to
Waste
Type
III
greater
than
7
watts
per
TRUPACT­
II
6.36E­
07
Payload
shipping
categories
belonging
to
Waste
Type
IV
3.26E­
06
Payload
shipping
categories
belonging
to
Waste
Type
IV
6.51E­
07
N/
A
N/
A
a
The
maximum
gas
release
rates
were
determined
from
analysis
as
described
in
the
TRUPACT­
II
SAR,
Section
3.4.4.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
266
Table
6­
10,
Flammable
Volatile
Organic
Compounds
Flammable
VOCs
Acetone
Benzene
Butanol
Chlorobenzene
Cyclohexane
1,1­
Dichloroethane
1,2­
Dichloroethane
1,1­
Dichloroethylene
cis­
1,2­
Dichloroethylene
Ethyl
benzene
Ethyl
ether
Methanol
Methyl
ethyl
ketone
Methyl
isobutyl
ketone
Toluene
1,2,4­
Trimethylbenzene
1,3,5­
Trimethylbenzene
Xylenes
Carbon
Disulfide
a
a
This
compound
has
been
added
to
the
RFETS
target
analyte
list
due
to
the
frequency
of
detection
as
a
Tentatively
Identified
Compound
(
TIC)
in
at
least
one
waste
stream
(
refer
to
the
TWCP
QAPjP,
Table
B3­
2).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
267
Waste
Type
Waste
Type
Flammable
VOCs 
500
ppm
Section
6.5.2.1
CH4
 
1,250
ppm
Section
6.5.2.3.1
Flammable
(
Gas/
VOC)
Concentration 
MLEL
Section
6.5.2.3.1
Flammable
(
Gas/
VOC)
Concentration 
MLEL
Section
6.5.2.3.2
All
Payload
Same
Shipping
Section
6.5.2.2
Yes
No
No
IV
Test
Category
Section
6.5.2.3
Measurement
Section
6.5.2.3.1
O.
K.
to
Ship
Section
6.6
Cannot
Ship
Mitigate
(
Repackage
or
Full­
Drum
Testing
Section
6.5.2.3.2
Mixing
Section
6.6.2.5
Reconfigure
Payload
Section
6.6.2.5
or
Go
to
Test
Category
Section
6.5.2.3
Analytical
Section
6.5.2.2
I,
II,
III
I,
II,
III
Total
Gas
Generation
Rate
Limit
Section
6.5.2.3.2
CH4
1,250
ppm
Section
6.5.2.3.2
Flammability
Index 
50,000
for
each
Container
Section
6.6.2.5
Decay
Heat 
Analytical
Limit
Section
6.5.2.2
IV
No
No
No
No
(
Option
1)
No
(
Option
2)

No
No
(
Option
2)
No
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
No
No
No
(
Option
1)
All
Payload
Packages
Same
Shipping
Section
6.5.2.4
All
Payload
Packages
Same
Shipping
Section
6.5.2.4
<

Figure
6­
1,
TRUPACT­
II
Gas
Generation
Requirements
 
RFETS
Compliance
Logic
Flow
Diagram
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
268
Select
Payload
Package
with
Approved
Shipping
Category
and
Content
Code
and
Obtain
Package
Data/
Identification
Information
Meet
Prohibited/
Restricted
Item
Limits?

Payload
Package
Rejected
for
Transport
(
Subject
to
Mitigation
or
Repackaging)

Pass
Unified
Flammable
Gas
Test
Procedure?
Physical/
Chemical
Properties
Nuclear
Properties
Gas
Generation
Properties
Meet
Payload
Package
Weight
Limit?

Meet
Payload
Package
Dose
Rate
Limit?

Meet
Payload
Package
Decay
Heat
Limit?

Approval
of
Payload
Package
by
Transportation
Certification
Official.
Payload
Package
Authorized
for
Transport.
Meet
Payload
Package
FGE
Limit?

Meet
Payload
Package
Curie
Limit?
(
S100
and
S200
Pipe
Overpacks
only)

Meet
Payload
Package
Aspiration
Requirement
(
if
applicable)?

Concentration
of
Flammable
Volatile
Organic
Compounds
in
Payload
Package
Headspace
 
500
ppm?
Meet
All
Packaging
Confinement
Layer
and
Filter
Transportation
Requirements?
Reevaluate
Payload
Package
Based
on
Mitigation
or
Repackaging
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
Yes
No
No
No
No
No
No
No
No
No
No
Note:
Compliance
determinations
illustrated
by
this
figure
may
occur
in
any
sequence.

Figure
6­
2,
Payload
Selection
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
269
Figure
6­
3,
TRUPACT­
II
Payload
Assembly
Criteria
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
270
Figure
6­
4,
Assignment
of
Shipping
Categories
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
271
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
272
7.
RECORDS
PROCESSING
The
following
documents
are
initiated,
processed
or
maintained
as
a
result
of
this
document
and
SHALL
be
processed
as
follows:

Records
Identification
Record
Type
Determination
Protection
/
Storage
Methods
Processing
Instructions
NONE
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
273
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
274
8.
REFERENCES
8.1
External
References
10
CFR
71,
Packaging
and
Transportation
of
Radioactive
Material,
Subpart
G,
Operating
Controls
and
Procedures,
and
Subpart
H,
Quality
Assurance
10
CFR
Part
830
Part
A,
Quality
Assurance
40
CFR
Part
191,
December
1993,
Environmental
Radiation
Protection
Standards
for
the
Management
and
Disposal
of
Spent
Nuclear
Fuel,
High
Level
Waste
and
Transuranic
Wastes,
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register,
National
Archives
and
Records
Administration
40
CFR
Part
194,
February
1994,
Criteria
for
the
Certification
&
Re­
Certification
of
the
Waste
Isolation
Pilot
Plant's
(
WIPP)
Compliance
with
the
40
CFR
Part
191
 
Disposal
Regulations,
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register,
National
Archives
and
Records
Administration
40
CFR
Parts
100­
173,
September
1994,
Hazardous
Materials
Transportation,
Code
of
Federal
Regulations,
Washington
D.
C.,
Office
of
the
Federal
Register,
National
Archives
and
Records
Administration
40
CFR
Parts
178­
199,
Transportation,
Title
49,
Code
of
Federal
Regulations
(
Parts
178­
199)

40
CFR
Parts
260­
270,
July
1994,
Protection
of
the
Environment,
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register,
National
Archives
and
Records
Administration
49
CFR
Parts
100­
180
and
350­
399,
Transportation,
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register,
National
Archives
and
Records
Administration
American
National
Standards
Institute.
Nondestructive
Assay
Measurement
Control
and
Assurance,
ANSI
N15.36,
American
National
Standards
Institute,
Inc.,
1430
Broadway,
New
York,
NY
10018
American
National
Standards
Institute.
Nuclear
Criticality
Control
of
Special
Actinide
Elements,
ANSI/
ANS­
8.15­
1981,
American
National
Standards
Institute,
Inc.,
1430
Broadway,
New
York,
NY
10018
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
275
8.1
External
References
(
continued)

American
National
Standards
Institute.
Plutonium­
Bearing
Solids
Calibration
Techniques
for
Calorimetric
Assay,
ANSI
N15.22­
1987,
American
National
Standards
Institute,
Inc.,
1430
Broadway,
New
York,
NY
10018
American
National
Standards
Institute.
Radioactive
Materials
 
Leakage
Tests
on
Packages
for
Shipment,
ANSI
N14.5­
1997,
American
National
Standards
Institute,
Inc.,
1430
Broadway,
New
York,
NY
10018
American
National
Standards
Institute.
Radiometric
Calorimeters
 
Measurement
Control
Program,
ANSI
N15.54,
American
National
Standards
Institute,
Inc.,
1430
Broadway,
New
York,
NY
10018
American
Society
of
Mechanical
Engineers
ASME,
NQA­
1­
1989,
Quality
Assurance
Program
Requirements
for
Nuclear
Facilities
American
Society
of
Mechanical
Engineers
ASME,
NQA­
2a­
1990
Addenda,
part
2.7,
Quality
Assurance
Requirements
of
Computer
Software
for
Nuclear
Facility
Applications
American
Society
for
Testing
and
Materials
ASTM.
1979.
Methods
for
Chemical,
Mass
Spectrometric,
and
Spectrochemical,
Nuclear,
and
Radiochemical
Analysis
of
Nuclear­
Grade
Plutonium
Nitrate
Solutions.
ASTM
C
696­
80,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
1980.
Methods
for
Chemical,
Mass
Spectrometric,
and
Spectrochemical
Analysis
of
Nuclear­
Grade
Uranium
Dioxide
Powders
and
Pellets.
ASTM
C
696­
80,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
1982.
Standard
Test
Methods
for
Nondestructive
Assay
of
Special
Nuclear
Materials
Contained
in
Scrap
and
Waste.
ASTM
C
853­
82,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
276
8.1
External
References
(
continued)

American
Society
for
Testing
and
Materials
ASTM.
1986.
Methods
for
Chemical,
Mass
Spectrometric,
and
Spectrochemical
Analysis
of
Nuclear­
Grade
Plutonium
Dioxide
Powders
and
Pellets.
ASTM
C
697­
86,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
1989.
Standard
Test
Method
for
Determination
of
Plutonium
Isotopic
Composition
by
Gamma­
Ray
Spectrometry.
ASTM
C1030­
89,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
1991.
Standard
Test
Method
for
Nondestructive
Assay
of
Plutonium
in
Scrap
and
Waste
by
Passive
Neutron
Coincidence
Counting.
ASTM
C1207­
91,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
1992.
Standard
Test
Method
for
Nondestructive
Analysis
of
Special
Nuclear
Materials
in
Homogeneous
Solutions
by
Gamma­
Ray
Spectrometry.
ASTM
C1221­
92,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
1995.
Standard
Test
Method
for
Determination
of
Plutonium
Isotopic
Composition
by
Gamma­
Ray
Spectrometry,
ASTM
C1030­
95,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
of
Testing
and
Materials
American
Society
for
Testing
and
Materials
ASTM.
2000.
Standard
Test
Method
for
Nondestructive
Assay
of
Plutonium,
Tritium,
and
241­
Am
by
Calorimetric
Assay.
ASTM
C1458­
01,
Annual
Book
of
ASTM
Standards,
Philadelphia,
Pennsylvania,
American
Society
for
Testing
and
Materials
Currie,
Lloyd
A.,
1968.
Limits
for
Qualitative
Detection
and
Quantitative
Determination.
Analytical
Chemistry,
40:
586­
93
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
277
8.1
External
References
(
continued)

CBFO:
NTP:
RMK:
GS:
02­
2558:
UFC
5822.00,
Memorandum
from
Kerry
W.
Watson,
Assistant
Manager
Office
of
National
TRU
Program,
to
Lam
Xuan,
DOE­
RFFO,
CBFO
Review
of
the
Dented
55­
Gallon
Drums
Stress
Analysis,
May
2002.

CBFO:
NTP:
RMK:
VW:
02­
2734:
UFC:
5822,
Memorandum
from
Kerry
W.
Watson,
Assistant
Manager
Office
of
National
TRU
Program,
CBFO
Review
and
Approval
of
NDA
and
Radiochemistry
Plans,
Procedures,
and
Related
Technical
Documents
Dragnev,
T.
N.,
1977.
Intrinsic
Self
Calibration
of
Non­
destructive
Gamma
Spectrometric
Measurements­
Determination
of
U,
Pu,
and
Am­
241
Isotopic
Ratios.
Journal
of
Radioanalytical
Chemistry,
36:
pp.
491­
508
Environmental
Protection
Agency
EPA,
1980.
Upgrading
Environmental
Radiation
Data.
EPA
5201/
1­
80­
012,
Washington
D.
C.,
Office
of
Radiation
Programs,
U.
S.
Environmental
Protection
Agency
Fisenne,
I.
M.,
et.
al.
1973.
Least
Squares
Analysis
and
Minimum
Detection
Levels
Applied
to
Multi­
component
Alpha
Emitting
Samples.
Radiochem.
Radioanal.
Letters,
16,
No.
1:
pp.
5­
16.

FPMR
101­
11.4,
National
Archives
and
Records
Service
General
Record
Schedules
Gunnink,
R.,
1980.
Use
of
Isotope
Correlation
Techniques
to
Determine
Pu­
242
Abundance.
Nuclear
Materials
Management,
9,
No.
2:
pp.
83­
93
Nuclear
Regulatory
Commission
NRC,
Nondestructive
Assay
of
Special
Nuclear
Material
Contained
in
Scrap
and
Waste.
Regulatory
Guide
5.11
Nuclear
Regulatory
Commission
NRC,
Establishing
Quality
Assurance
Programs
for
Packaging
used
in
the
Transport
of
Radioactive
Material,
Regulatory
Guide
7.10,
Annex
2
Nuclear
Regulatory
Commission
NRC,
Certificate
of
Compliance,
USA/
9218/
B(
U)
F,
Model
No:
TRUPACT­
II
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
278
8.1
External
References
(
continued)

Pasternack,
B.
S.
and
Harley,
N.
H.
1971.
Detection
Limits
for
Radionuclides
in
the
Analysis
of
Multi­
Component
Gamma­
spectrometric
Data.
Nucl.
Instr.
And
Meth,
No.
91:
pp.
533­
40
Sampson,
T.
E.,
and
Gunnink,
R.
1983,
The
Propagation
of
Errors
in
the
Measurement
of
Plutonium
Isotopic
Composition
by
Gamma­
Ray
Spectroscopy,
Journal
of
the
Institute
of
Nuclear
Materials
Management,
Vol.
XII,
No.
2,
Summer
1983
Smith,
K.
C.,
R.
A.
Stroud,
K.
L.
Coop,
and
J.
F.
Bresson.
1998.
"
Total
measurement
uncertainty
assessment
for
transuranic
waste
shipments
to
the
Waste
Isolation
Pilot
Plant."
Proceedings
of
the
6th
Nondestructive
Assay
Waste
Characterization
Conference,
Salt
Lake
City,
Nov.
17­
19,
1998,
pp.
21­
37
U.
S.
Department
of
Energy,
Waste
Isolation
Pilot
Plant,
TRUPACT­
II
Content
Codes
(
TRUCON).
DOE/
WIPP
89­
004,
Current
Revision
U.
S.
Department
of
Energy,
Carlsbad
Area
Office,
Performance
Demonstration
Program
Plan
Nondestructive
Assay
for
the
TRU
Waste
Characterization
Program.
DOE/
CAO­
95­
1045,
Current
Revision.

U.
S.
Department
of
Energy,
Carlsbad
Field
Office,
Quality
Assurance
Program
Document,
DOE/
CBFO­
94­
1012,
Revision
5,
May
2003
U.
S.
Department
of
Energy,
Carlsbad
Area
Office,
Waste
Isolation
Pilot
Plant
Transportation
Plan,
DOE/
CAO
98­
3103
U.
S.
Department
of
Energy,
DOE/
RL
96­
57,
Test
and
Evaluation
Document
for
DOT
Specification
7A
Type
A
Certification
Packaging
U.
S.
Department
of
Energy,
Order
414.1,
Quality
Assurance
U.
S.
Department
of
Energy,
Order
435.1,
Radioactive
Waste
Management
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
279
8.1
External
References
(
continued)

U.
S.
Department
of
Energy,
Order
460.2,
Transportation
Management
U.
S.
Department
of
Energy,
Order
5480.3
(
460.1)
Transportation
and
Packaging
Safety
U.
S.
Department
of
Energy,
Carlsbad
Field
Office.
Performance
Demonstration
Program
Plan
for
Nondestructive
Assay
of
Boxed
Wastes
for
the
TRU
Waste
Characterization
Program.
DOE/
CBFO­
01­
1006,
Current
Revision.
Carlsbad,
New
Mexico,
Carlsbad
Field
Office
U.
S.
Department
of
Energy.
Performance
Demonstration
Program
Plan
for
Nondestructive
Assay
of
Drummed
Wastes
for
the
TRU
Waste
Characterization
Program.
DOE/
CBFO­
01­
1005,
Current
Revision.
Carlsbad,
New
Mexico,
Carlsbad
Field
Office
U.
S.
Department
of
Energy,
TRUPACT­
II
Operating
and
Maintenance
Instructions,
DOE/
WIPP
93­
1001,
Revision
1,
1997
U.
S.
Department
of
Energy,
CH
Packaging
Program
Guidance,
DOE/
WIPP
02­
3183,
Current
Revision
U.
S.
Department
of
Energy,
CH
Packaging
Operations
Manual,
DOE/
WIPP
02­
3184,
Current
Revision
U.
S.
Department
of
Energy,
CH
Packaging
Maintenance
Manual,
DOE/
WIPP
02­
3185,
Current
Revision
U.
S.
Department
of
Energy,
Contact­
Handled
Transuranic
Waste
Acceptance
Criteria
for
the
Waste
Isolation
Pilot
Plant,
DOE/
WIPP­
02­
3122,
Current
Revision
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
280
8.1
External
References
(
continued)

U.
S.
Nuclear
Regulatory
Commission.
Peer
Review
for
High­
Level
Nuclear
Waste
Repositories.
NUREG­
1297
U.
S.
Nuclear
Regulatory
Commission,
Safety
Analysis
Report
for
the
TRUPACT­
II
Shipping
Container
(
SARP),
Docket
No.
71­
9218,
Current
Revision
U.
S.
Nuclear
Regulatory
Commission.
TRUPACT­
II
Authorized
Methods
for
Payload
Control
(
TRAMPAC).
Current
Revision
WIPP­
WAP,
Attachment
B
of
the
WIPP
Hazardous
Waste
Facility
Permit
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
281
8.2
RFETS
References
00­
NDA­
TGS­
001,
Qualification
Plan
for
the
Skid
Mounted
Tomographic
Gamma
Scanner
(
TGS)
[
This
document
is
inactive
and
as
of
October
30,
2002
this
counter
is
no
longer
in
service.]

00­
NDA­
TGS­
002,
Qualification
Plan
for
the
371TGS02
Tomographic
Gamma
Scanner
(
TGS)
Building
371
[
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.]

00­
NDA­
TGS­
003,
Qualification
Plan
for
the
569TGS04
Tomographic
Gamma
Scanner
(
TGS)
Building
569
[
This
counter
has
been
moved
to
Building
664,
and
this
document
is
replaced
by
KH­
NDA2002­
CAL/
QUAL­
664­
TGS04
as
of
August
1,
2002.]

00­
NDA­
TGS­
004,
Qualification
Plan
for
the
371TGS05
Tomographic
Gamma
Scanner
(
TGS)
Building
371
[
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.]

1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items
1­
A67­
QAP­
08.01,
Identification
and
Control
of
Items
1­
C20­
QAP­
09.01,
Control
of
Processes
1­
C80­
WO­
1102­
W/
RT,
Waste/
Residue
Traveler
Instructions
1­
J55­
ADM­
08.10,
Subcontractor
Quality
Evaluations
1­
M12­
WO­
4034,
Solid
Radioactive
Waste
Packaging
Requirements
Manual
1­
M60­
WPC­
001,
Waste
Process
Control
1­
MAN­
004­
CSMM,
Computer
Software
Management
Manual
1­
N92­
ADM­
02.03,
Training
and
Qualification
of
Assessment
and
Surveillance
Personnel
1­
PRO­
072­
001,
Inspection
and
Acceptance
Test
Program
1­
PRO­
079­
WGI­
001,
Waste
Characterization,
Generation
and
Packaging
1­
PRO­
087­
WEMS­
WP­
1201,
WEMS
Waste
Package
Inventory,
Tracking,
and
Control
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
282
8.2
RFETS
References
(
continued)

1­
PRO­
110­
WP­
1212,
WIPP
Waste
Information
System
(
WWIS)
Data
Entry
1­
PRO­
Q11­
WO­
1221,
Controls
for
Updating
Waste
Package
Information
in
WEMS
1­
V10­
ADM­
15.02,
Stop
Work
Action
1­
V41­
RM­
001,
Records
Management
Manual
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure
1­
W37­
IA­
002,
Integrated
Planning
and
Scheduling
of
Assessment
Activities
3­
B52­
IA­
003,
Conduct
of
Independent
Assessment
Activities
3­
PRO­
165­
RSP­
07.02,
Contamination
Monitoring
Requirements
3­
W24­
MA­
002,
Kaiser­
Hill
Management
Assessment
Program
3­
X31­
CAP­
001,
Corrective
Action
Process
4­
D99­
WO­
1100,
Solid
Radioactive
Waste
Packaging
Procedure
4­
F72­
WEM­
WP1205,
WEMS
and
WSRIC
Software
Quality
Assurance
Compliance
4­
G83­
WEM­
WP­
1209,
WEMS
Waste
Package
Verification
and
Certification
4­
H19­
WSRIC­
001,
WSRIC
Characterization
and
Reverification
4­
H80­
776­
ASRF­
007,
Visual
Examination
for
Confirmation
of
RTR
[
This
procedure
is
inactive
as
of
November
6,
2001.]

4­
K47­
WEM­
WP1210,
WEMS
Offsite
Shipping
Module
4­
P16­
SA­
TID­
001,
Tamper­
Indicating
Devices
(
TIDs)

5­
NDT­
TC­
1A,
Training,
Qualification,
and
Certification
of
Nondestructive
Testing
Personnel
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
283
8.2
RFETS
References
(
continued)

95­
QAPjP­
0050,
RFETS
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
95­
WP/
SAP­
001,
Transuranic
(
TRU/
TRM)
Waste
Sampling
Plan
Analytical
Laboratories
L
Procedures
(
A
relevant
list
is
included
in
the
RFETS
TWCP
QAPjP)

BII­
8215­
C&
VP­
001,
Building
569
Passive/
Active
Drum
Counter
Calibration
and
Validation
Plan,
Instrument
Control
Number
569PADC001
CALC­
000­
NA­
000672,
Dented
55
Gal.
Drum
Stress
Analysis
CALG­
PD­
00005,
Calorimeter/
Gamma
Spec
Lower
Limit
of
Detection
[
This
document
is
inactive
as
of
November
12,
2003.
Equipment
taken
out
of
service.]

Calibration
and
Qualification
Report
Package
for
the
SuperHENC
Mobile
Assay
Trailer,
Instrument
Identification
Number
440SHENC01
Determination
of
the
Total
Measurement
Uncertainty
for
the
RFETS
Skid
Mounted
TGS
and
Can
TGS
[
cancelled
as
of
July
15,
2003,
counters
out
of
service]

KH
Procurement
System
Manual
KH­
NDA2001­
CAL­
371TGS02,
Calibration
and
Qualification
Report
for
the
ANTECH
Tomographic
Gamma
Scanning
(
TGS)
Can
Counter
371TGS02
After
Installation
of
ANTECH
MasterScan
and
MasterAnalysis
Software
[
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.]

KH­
NDA2001­
CAL­
371TGS05,
Calibration
and
Qualification
Report
for
the
ANTECH
Tomographic
Gamma
Scanning
(
TGS)
Can
Counter
371TGS05
[
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.]
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
284
8.2
RFETS
References
(
continued)

KH­
NDA2001­
RECAL­
371TGS03,
Calibration
and
Qualification
Report
for
the
Conversion
of
the
ANTECH
TGS
Can
Counter
371TGS03
from
DAC.
TGS
Data
Aquisition
to
MasterScan
Data
Collection
Software
[
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.]

KH­
NDA2002­
CAL/
QUAL­
664TGS04,
Calibration
and
Qualification
Plan
for
the
Newly
Relocated
Building
664
Tomographic
Gamma
Scanning
(
TGS)
Drum
Counter,
Instrument
Control
Number
664TGS04
KH­
NDA2002­
LLD,
Technical
Report
for
the
Determination
of
Lower
Limit
of
Detection
(
LLDs)
for
WIPP
and
Other
Reported
Isotopes
for
NDA
Measurement
Systems
KH­
NDA2002­
QUAL­
440SHENC001(
DRUM),
Supplemental
Qualification
Report
for
the
Radioassay
of
Waste
Packaged
in
55­
Gallon
Drums
Using
the
Super
High
Efficiency
Neutron
Counter
(
SuperHENC)
440SHENC001
KH­
NDA2002­
QUAL­
569PADC01,
Revised
WIPP­
Related
Calibration
and
Qualification
Report
for
Extension
of
the
Qualified
Plutonium
Mass
and
Matrix
Ranges
for
the
Building
569
Passive­
Active
Neutron
Drum
Counter,
569PADC01
KH­
NDA2002­
QUALR­
664MPCC01,
Calibration
and
Qualification
Report
for
the
Multi­
Purpose
Crate
Counter
(
MPCC)
Imaging
Passive­
Active
Neutron
and
Gamma
Energy
Analysis
(
IPAN/
GEA)
System,
Instrument
Control
Number
664MPCC01
KH­
NDA2003­
CAL/
QUAL­
664TGS04,
Calibration
and
Qualification
Report
for
the
ANTECH
TGS
Drum
Counter
664TGS04
KH­
NDA2003­
CAL/
QUALP­
440FRAM01,
Calibration
and
Confirmation
Plan
for
the
Building
440
FRAM
Gamma
Spectroscopy
System,
Instrument
Control
Number
440FRAM01
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
285
8.2
RFETS
References
(
continued)

KH­
NDA2003­
CALVER­
440PADC01,
Calibration
Verification
Plan
for
the
Newly
Relocated
Building
440
Imaging
Passive/
Active
Neutron
Drum
Counter
(
PADC),
Instrument
Control
Number
440PADC01
KH­
NDA2003­
CALVER­
RPT­
440PADC01,
Calibration
Verification
Report
for
the
Newly
Relocated
Building
440
Imaging
Passive/
Active
Neutron
Drum
Counter
(
PADC),
Instrument
Control
Number
440PADC01
KH­
NDA2003­
QUAL­
440FRAM01,
Calibration
and
Qualification
Report
for
the
Building
440
FRAM
Gamma
Spectroscopy
System,
Instrument
Control
Number
440FRAM01
L­
4031,
Software
Quality
Assurance
[
This
document
will
be
deactivated
in
February
2004.]

L­
4111,
GC/
MS
Determination
of
Volatile
Organics
For
Waste
Characterization
[
This
procedure
is
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.]

L­
4146,
Headspace
Gas
Sampling
of
Waste
Containers
[
This
procedure
is
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.]

L­
4231,
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold
[
This
procedure
has
been
cancelled
as
of
June
18,
2003,
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.]

MAN­
001­
SDRM,
Site
Document
Requirements
Manual
MAN­
010­
MCA,
Materials
Control
&
Accountability
Manual
MAN­
027­
SERM,
Site
Engineering
Requirements
Manual
MAN­
062­
CAUSEANALYSIS,
Cause
Analysis
Requirements
Manual
MAN­
066­
COOP,
Site
Conduct
of
Operations
Manual
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
286
8.2
RFETS
References
(
continued)

MAN­
071­
IWCP,
Integrated
Work
Control
Program
Manual
MAN­
072­
OS&
IH
PM,
Occupational
Safety
&
Industrial
Hygiene
Program
Manual
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management
MAN­
094­
TPM,
Training
Program
Manual
MAN­
131­
QAPM,
Quality
Assurance
Program
Manual
MAN­
134­
PPM,
Procurement
Program
Manual
MAN­
955­
099,
Waste
Requirements
Group
Operations
Manual
MAN­
T91­
STSM­
001,
Site
Transportation
Safety
Manual
PLN­
97­
007,
TRU
Waste
Characterization
Program
Training
Implementation
Plan
PRO­
015­
NMT­
003,
On­
Site
Transfer
Procedure
PRO­
077­
WIPP­
005,
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center
PRO­
108­
PREP­
01,
Preparation
of
Nondestructive
Assay
(
NDA)
Performance
Demonstration
Program
Samples
PRO­
284­
POC­
001,
Pipe
Overpack
Component
Initial
Assembly
Process
PRO­
484­
WIPP­
003,
Collection,
Review,
and
Confirmation
of
Acceptable
Knowledge
Documentation
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
287
8.2
RFETS
References
(
continued)

PRO­
486­
WIPP­
006,
TRU
Waste
Characterization
Project
QA
Grading
PRO­
497­
RSP­
09.07,
TRUPACT­
II
Contamination
and
Radiation
Survey
Requirements
PRO­
548­
SSOC­
SQA,
Software
Management
for
Nondestructive
Assay
Systems
PRO­
666­
PADC440,
Operating
Building
440
Passive/
Active
Drum
Counter
PRO­
666­
PADC569,
Operating
Building
569
Passive/
Active
Drum
Counter
[
Cancelled
as
of
March
10,
2003
 
replaced
by
PRO­
666­
PADC440,
Operating
Building
440
Passive/
Active
Drum
Counter]

PRO­
697­
MLC­
00013,
Preparation
and
Certification
of
Nondestructive
Assay
Standards
and
Sources
[
cancelled
 
replaced
by
PRO­
1566­
NDA­
STD]

PRO­
717­
HDGAS­
371,
Headspace
Gas
Sampling,
Building
371
[
This
procedure
is
inactive
as
of
May
12,
2003.
Headspace
gas
sampling
in
Building
371
has
been
discontinued.]

PRO­
731­
MC­
002,
NDA
Measurement
Control
Program
PRO­
767­
WIPP­
001,
Waste
Records
Center
Processing
PRO­
815­
DM­
01,
Developing
and
Maintaining
Documents
PRO­
845­
NDA­
008,
Data
Review,
Verification,
and
Validation
for
Nondestructive
Assay
(
NDA)
Measurement
Systems
PRO­
940­
WIPP­
010,
WIPP
TRU
Waste
Characterization
Project
Level
Data
Review
and
Reporting
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
288
8.2
RFETS
References
(
continued)

PRO­
943­
WIPP­
007,
TRU
Waste
Characterization
Program
Trending
and
Analysis
of
Quality­
Affecting
Problems
PRO­
944­
WIPP­
008,
Completion
of
Waste
Stream
Profile
Form
for
Waste
to
be
Disposed
of
at
WIPP
PRO­
957­
SuperHENC,
Operating
the
Super
High
Efficiency
Neutron
Coincidence
(
SuperHENC)
Counter
Mobile
Assay
System
PRO­
985­
SURV,
Performance
of
Surveillances
PRO­
1003­
WSRIC­
ADMIN,
WSRIC
Administration
Guidance
PRO­
1031­
WIPP­
1112,
TRU/
TRM
Waste
Visual
Verification
(
VV)
and
Data
Review
PRO­
1034­
PEQA,
Procurement
Engineering
and
Quality
Assurance
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection
PRO­
1072­
NDA­
MSQ,
Matrix­
Specific
Qualification
for
NDA
Can
Counters
[
This
procedure
is
inactive
and
as
of
July
25,
2003
all
can
counters
are
out
of
service.]

PRO­
1092­
FRAM­
440,
Operating
Building
440
FRAM
Gamma
Spectroscopy
System
PRO­
1092­
FRAM­
569,
Operating
the
Building
569
FRAM
Gamma
Spectroscopy
System
[
Cancelled
as
of
March
10,
2003
 
replaced
by
PRO­
1092­
FRAM­
440,
Operating
Building
440
FRAM
Gamma
Spectroscopy
System]

PRO­
1132­
WIPP­
012,
Preparation
of
an
Interface
Document
for
Vendor
Owned
or
Operated
Systems
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
289
8.2
RFETS
References
(
continued)

PRO­
1141­
WP­
4701,
Waste
Characterization
Gas
Sampling
[
This
procedure
is
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.]

PRO­
1205­
MLA­
008,
Metrology
Control
of
Measuring
and
Test
Equipment
[
Inactive
as
of
October
30,
2003,
superseded
by
MAN­
092­
M&
TEM,
Measuring
and
Test
Equipment
Management.]

PRO­
1247­
MS­
POC,
POC
Operations
PRO­
1290­
TRIFID­
371,
TRIFID
Gamma­
Ray
Isotopic
Analysis
System
Qualification
[
This
procedure
is
inactive
as
of
November
12,
2003.
These
systems
are
no
longer
in
service.]

PRO­
1297­
CLC&
RPT­
371,
Calorimetry/
Gamma­
Ray
Assay
Calculation
and
Reporting
of
Results
[
This
procedure
is
to
be
deactivated
in
March
2004.
These
systems
are
no
longer
in
service.]

PRO­
1298­
ISOAN­
371,
Gamma­
Ray
Isotopic
Analysis
of
Plutonium­
Bearing
Solids
in
Building
371
Cal/
Gamma
Laboratory
[
This
procedure
is
inactive
as
of
November
12,
2003.
These
systems
are
no
longer
in
service.]

PRO­
1299­
AIRBATH­
371,
Calorimetry
Using
the
ANTECH
Airbath
System
in
Building
371
Cal/
Gamma
Laboratory
[
This
procedure
is
inactive
as
of
November
12,
2003.
This
system
is
no
longer
in
service.]

PRO­
1302­
WIPPDATA­
371,
Data
Review
and
Validation
for
Calorimetric
Assay
for
WIPP­
TRU
Waste
Characterization
Program
in
Building
371
Cal/
Gamma
Laboratory
[
This
procedure
is
to
be
deactivated
in
March
2004.
These
systems
are
no
longer
in
service.]

PRO­
1306­
ARIBA,
Ariba
Buyer
Users
Guide
PRO­
1329­
DM­
03,
Site
Document
Control
PRO­
1351­
440­
SWB,
Room
113
Perma­
Con
Operations
PRO­
1358­
440­
VERP,
Glovebox
and
C­
Cell
Waste
Operations
PRO­
1386­
TGS­
371,
Setup
and
Calibration
of
Building
371
Can
Tomographic
Gamma
Scanner
(
TGS)
[
This
procedure
is
inactive
as
of
August
13,
2003.
Can
counters
are
no
longer
in
service.]
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
290
8.2
RFETS
References
(
continued)

PRO­
1392­
TGS­
371,
Operating
Building
371
Tomographic
Gamma
Scanning
(
TGS)
Can
Counters
[
This
procedure
is
inactive
as
of
August
13,
2003.
Can
counters
are
no
longer
in
service.]

PRO­
1405­
PREP­
02,
Preparation
of
Boxed
Waste
Performance
Demonstration
Program
(
PDP)
Samples
for
Nondestructive
Assay
PRO­
1406­
SWB,
Standard
Waste
Box
Repair/
Replacement
Operations
PRO­
1411­
WO­
Waste,
Waste
Receiving,
Transfer,
&
Handling
PRO­
1418­
WO­
TRUOP,
TRUPACT­
II
Operations
PRO­
1419­
WO­
LKTST,
TRUPACT­
II
Shipping
Leak
Test
PRO­
1433­
MPCC­
664,
Operating
the
Multipurpose
Crate
Counter
(
MPCC)
at
Building
664
PRO­
1471­
VE­
771,
Visual
Examination
for
Confirmation
of
RTR
[
This
procedure
is
inactive
as
of
November
14,
2003.]

PRO­
1566­
NDA­
STD,
Evaluating
NDA
Standards
for
Continued
Use
PRO­
1569­
SAP­
001,
Polymerized
Organic
and
Inorganic
Liquid
Process
 
Sampling
and
Analysis
Plan
PRO­
1570­
NDA­
QUAL,
Qualification
Requirements
for
NDA
Large
Package
Counters
PRO­
1608­
VECRTR­
371,
RTR
Visual
Examination
Confirmation,
Building
371
[
This
procedure
is
inactive
as
of
August
12,
2003.]

PRO­
1631­
TGS­
01,
Setup
and
Calibration
of
Building
664
Drum
Tomographic
Gamma
Scanner
(
TGS)

PRO­
1632­
TGS­
02,
Operating
Building
664
Drum
Tomographic
Gamma
Scanner
(
TGS)

PRO­
1668­
SQA,
TRU
Waste
Characterization
Program
(
TWCP)
Software
Quality
Assurance
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
291
8.2
RFETS
References
(
continued)

PRO­
1730­
903­
001,
903
Pad
Soil
Removal/
Repack
and
Characterization
Plan
PRO­
J44­
RC&
I­
6600,
Procured
Items
Inspection
and
Certification
PRO­
Q49­
PKG­
4040,
Warehouse
Waste
Packaging
Operations
PRO­
T13­
Traffic­
306,
Labeling
and
Marking
TRUPACT
Packages
PRO­
T30­
Traffic­
515,
Preparation
and
Retention
of
Hazardous
Materials
Shipping
Documents
PRO­
T43­
Traffic­
528,
TRUPACT­
II
Operations
PRO­
T95­
OSTP­
002,
Off­
Site
Transportation
Procedure
PRO­
U76­
WC­
4030,
Control
of
Waste
Nonconformances
PRO­
X05­
WC­
4018,
Transuranic
(
TRU)
Waste
Certification
Qualification
Plan
for
Building
664
Multipurpose
Crate
Counter
(
MPCC)
Instrument
Identification
Number
664MPCC01
Radiation
Instrumentation
Manual
Radiological
Safety
Practices
(
RSPs)

RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information
Rocky
Flats
Environmental
Technology
Site
Non­
Destructive
Assay
Calorimetry
and
Gamma
Spectrometry
Laboratories
Calorimeter
Qualification
Plan
[
This
plan
is
inactive
as
of
November
12,
2003.
These
systems
are
no
longer
in
service.]

Rocky
Flats
Site
Quality
Assurance
Program
Procedures
Manual
(
SQAPP)

RS­
012­
004,
Grid
Method
­
Solid
Sampling
and
Analysis
Plan
RS­
012­
005,
Cone
and
Quartering
Method
­
Solid
Sampling
and
Analysis
Plan
[
This
document
is
inactive
as
of
December
2003.]

RS­
020­
001,
Gas
Generation
Testing
Program
Quality
Assurance
Project
Plan
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
292
8.2
RFETS
References
(
continued)

RS­
020­
006,
Salt
Residue
Stabilization,
Building
707
Process
Control/
Qualification
Plan
[
The
Salt
Residue
stabilization/
repack
activity
that
utilized
this
PCP
was
completed
in
June
2000.]

RS­
020­
012,
Ash
Residue
Repack
Process
Control
Plan
RS­
020­
013,
Dry
Residue
Repackaging
Process
Control
Plan
RS­
020­
018,
Combustible
Residue
Repackaging
Process
Control
Plan
RS­
020­
021,
Salt
Residue
Repack,
Buildings
371
and
707
Process
Control
Plan
Site
Radiological
Control
Manual
Super
High
Efficiency
Neutron
Counter
Calibration
and
Validation
Plan,
Instrument
Control
Number
984SHENC01
Super
High
Efficiency
Neutron
Counter
Calibration
and
Validation
Report,
LA­
CP­
00­
427
TWCP­
QP­
1.1­
015,
Design
Control
WSRIC
Building
Books
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
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7
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12/
2004
PAGE
293
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
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PAGE
294
9.
GLOSSARY
9.1
Definitions
Acceptable
Knowledge
(
AK).
An
EPA
term
which
includes
process
knowledge
and
results
from
previous
testing,
sampling,
and
analysis
associated
with
the
waste.
Acceptable
knowledge
(
AK)
includes
information
regarding
the
raw
materials
used
in
a
process
or
operation,
process
description,
products
produced,
and
associated
wastes.
AK
documentation
includes
the
site
history
and
mission,
site­
specific
processes
or
operations,
administrative
building
controls,
and
all
previous
and
current
activities
that
generate
a
specific
waste.
The
term
"
acceptable
knowledge"
is
used
interchangeably
with
the
term
"
process
knowledge"
in
this
document.

As
Low
As
Reasonably
Achievable
(
ALARA).
A
philosophy
of
protection
that
controls
and
maintains
radiation,
radioactive
contamination
and
hazardous
material
exposures
to
individuals
and
to
the
work
force
and
general
public
as
low
as
technically
and
economically
feasible
below
the
regulatory
limits.

Becquerel.
The
International
System
unit
of
activity
of
a
radionuclide
equal
to
the
activity
of
a
quantity
of
a
radionuclide
having
one
spontaneous
nuclear
transition
per
second.
37
Becquerels
equals
one
nCi.

Box.
TRUPACT
II
standard
waste
box
(
SWB).

Calibration.
(
A)
The
process
of
establishing
the
accuracy
of
measurement
and
test
equipment;
(
B)
the
check
or
correction
of
accuracy
of
a
measuring
instrument
to
ensure
proper
operational
characteristics;
(
C)
the
comparison
of
a
measurement
standard
or
item
of
test
and
measurement
and
test
equipment
of
unknown
accuracy
to
a
standard
or
instrument
of
known
accuracy
in
order
to
detect,
correlate,
report,
or
eliminate
by
adjustment,
any
variation
(
deviation)
in
the
accuracy
of
the
item
being
compared;
(
D)
the
establishment
of
a
curve
relating
the
measurement
and
test
equipment
response
to
analyte
amount
or
concentration
based
on
analyses
with
analytes
of
known
amount
or
concentration.

Calorimetry.
An
NDA
measurement
device
used
to
measure
the
heat
flow
caused
by
the
radioactive
decay
in
materials.

Carbon
Composite
Filter.
A
high­
efficiency
particulate
air
filter
designed
to
fit
CH­
TRU
payload
packages
to
prevent
buildup
of
gases
and
pressure.

Certificate
of
Compliance
(
C
of
C).
Authorizes
use
of
a
package
for
shipment
of
radioactive
material
in
accordance
with
the
provisions
of
49
CFR
173.471,
subject
to
the
conditions
listed
in
the
certificate.
The
C
of
C
is
issued
by
the
NRC
to
the
Department
of
Energy,
Albuquerque
Operations
Office.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
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PAGE
295
9.1
Definitions
(
continued)

Certification
Authority.
Authorization
to
certify
TRU
waste
to
the
WIPP
Waste
Acceptance
Criteria
which
is
granted
by
the
CBFO
to
those
TRU
waste
generator/
storage
sites
whose
TRU
Waste
Characterization
Programs
have
been
evaluated
and
found
to
be
acceptable.

Certified
Waste.
Payload
packages,
loaded
with
waste,
that
have
been
verified
to
meet
the
criteria
of
the
WIPP­
WAC.

Chemical
Compatibility
Testing.
Assessing
the
properties
of
all
potential
chemicals
in
a
payload
package
(>
1
weight
percent),
to
ensure
that
there
will
not
be
adverse
safety
or
health
hazards
produced
as
a
result
of
any
mixtures
that
could
occur.

Chemical
Constituent
Code
(
CCC).
A
two
character
alpha
or
numeric
designator
used
to
identify
chemical
constituents
associated
with
a
particular
waste
stream.

Combustibles.
Organic
materials
that
are
dominantly
cellulosics
(
e.
g.,
cotton,
paper,
cloth,
wood,
etc.),
but
also
includes
plastics.

Completeness.
The
percentage
of
measurements
made
which
are
judged
to
be
valid
measurements.
The
completeness
goal
is
to
generate
a
sufficient
amount
of
valid
data
based
on
Program
needs.
Valid
results
for
analytical
and
radioassay
data
are
those
that
were
obtained
when
the
laboratory
or
testing
facility
demonstrated
that
the
instrumentation
and
method
were
in
control.
That
is,
that
all
calibration,
verification,
interference,
and
non­
matrix
checks
met
acceptance
criteria.
Valid
samples
are
those
collected
and
submitted
for
analysis
that
were
representative
and
met
all
preservation
requirements
upon
arrival
at
the
laboratory.

Compressed
Gas.
Any
material
or
mixture
having
in
the
package
an
absolute
pressure
exceeding
40
psi
at
70
°
F,
or
regardless
of
the
pressure
at
70
°
F,
having
an
absolute
pressure
exceeding
104
psi
at
130
°
F;
or
any
liquid
flammable
material
having
a
vapor
pressure
exceeding
40
psi
absolute
at
100
°
F,
as
determined
by
the
ASTM
Test
D­
323.
Compressed
gases
are
those
materials
defined
as
such
by
49
CFR
173.300(
a).

Contact­
Handled
(
CH)
TRU
Waste.
Transuranic
waste
with
a
surface
radiation
dose
equivalent
rate
not
greater
than
200
mrem/
hr.

Container.
Serialized
white
drum
or
SWB
for
shipping
radioactive
or
mixed
waste.
Note:
The
term
"
package"
used
in
DOT
requirements
documents
has
replaced
the
use
of
container.
This
document
now
follows
the
DOT
terminology
except
where
DOE
and
WIPP
requirements
are
being
directly
listed.

Content
Code.
A
uniform
system
applied
to
waste
forms
to
group
those
with
similar
characteristics
for
purposes
of
shipment
in
the
TRUPACT­
II.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
296
9.1
Definitions
(
continued)

Corrosive
Materials.
A
corrosive
material
has
a
pH
less
than
or
equal
to
2,
or
greater
than
or
equal
to
12.5.
Corrosive
materials
are
those
defined
as
such
by
40
CFR
261.22(
a)(
1).
Also
refer
to
49
CFR
173.240
for
an
expanded
definition.

Counts
per
minute
(
cpm).
Related
to
the
specific
nuclear
event
being
measured,
i.
e.,
a
rate
of
decay
(
if
measuring
gamma
radiation,
the
number
of
gamma
rays
detected
in
a
minute.
This
number
is
usually
less
than
but
directly
proportional
to
the
decay
rate.).

Crate
Counter.
An
instrument
used
to
measure
radioactivity
and
help
perform
TRU
or
low­
level
waste
(
LLW)
sorting
of
crates.

Curie
(
Ci).
A
unit
of
radioactivity
equal
to
3.7
x
1010
disintegrations
per
second
(
dps).
A
nCi
is
10­
9
Ci,
or
37
dps.
One
nCi
equals
37
Bq.

Decay
Heat.
Heat
produced
by
radioactive
emissions
absorbed
in
the
surrounding
materials.

Dose
Equivalent
Rate.
The
radiation
dose
equivalent
delivered
per
unit
time
(
e.
g.,
rem
per
hour).

D
O
T
7A
Type
A.
A
Department
of
Transportation
(
DOT)
packaging
specification
for
shipping
Type
A
quantities
of
radioactive
materials.

Environmental
Coordinator/
Environmental
Program
Manager.
Individuals
with
technical
expertise
in
environmental
regulations
and
requirements
who
assist
operations
management
and
personnel
with
decisions
and
actions
on
wastes.

Explosive.
An
explosive
material
is
any
compound,
mixture,
or
device,
which
produces
a
substantial
release
of
gas
and
heat,
spontaneously
or
by
contact
with
sparks
or
flame.
Also
refer
to
49
CFR
173.50.

Fissile
Gram
Equivalent
(
FGE).
(
See
definition
under
Pu­
239
Fissile
Gram
Equivalent).

Fissile
Material.
Any
material
consisting
of
or
containing
one
or
more
radionuclides
that
can
undergo
neutron­
induced
fission
with
neutrons
of
essentially
zero
kinetic
energy
(
e.
g.,
thermal
neutrons)
such
as
233U,
235U,
and
239Pu.

Flammable
VOC.
A
headspace
gas
volatile
organic
component
(
VOC)
that
has
a
National
Fire
Protection
Association
Flammability
Hazard
Degree
of
3
or
4
and
a
flashpoint
of
less
than
100
°
F
or
considered,
by
EPA,
to
be
a
significant
fire
hazard
under
WIPP
repository
conditions.
Flammable
headspace
gas
VOCs
that
are
evaluated
for
the
TWCP
are
listed
in
Table
B­
3
of
the
WIPP­
WAP.
TRANSURANIC
(
TRU)
WASTE
1­
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008­
WM­
001
MANAGEMENT
MANUAL
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7
02/
12/
2004
PAGE
297
9.1
Definitions
(
continued)

Generator.
This
term
is
interchangeable
with
Originator.
Any
person
whose
act
or
process
produces
a
waste
or
whose
act
causes
a
waste
to
become
subject
to
regulation
or
DOE
order.
This
includes
RFETS's
subcontractors
and
DOE
prime
contractors
who
create
wastes.

Glovebox.
A
sealed
box
with
windows
and
rubber
gloves
attached
to
access
ports
such
that
an
operator's
hands
and
arms
are
protected
as
he/
she
works
inside
the
box.

Hazardous
Waste.
Those
wastes
that
exhibit
the
characteristics
of
being
corrosive,
ignitable,
reactive,
toxic,
or
are
listed
in
40
CFR
261
or
the
Code
of
Colorado
Regulations
(
CCR),
6
CCR
1007­
3,
Colorado
Hazardous
Waste
Regulations.

Hazardous
Waste
Requirements
Manual.
The
governing
document
stating
how
RFETS
identifies,
treats,
packages,
and
stores
hazardous
and
mixed
wastes.

Headspace.
That
volume
of
any
containment
that
is
not
occupied
by
the
volume
of
waste
material.
Headspace
is
also
used
to
refer
to
the
gases
contained
in
this
volume.

Item
Description
Code
(
IDC).
A
three
or
four
digit
number
assigned
to
a
waste
form
type,
such
as
plastics,
dry
combustibles,
light
metals,
etc.

Land
Disposal
Restricted
(
LDR).
Those
RCRA­
regulated
hazardous
wastes
that
require
treatment
or
applied
waste
constituent
standards
to
comply
with
the
RCRA
regulations
before
land
burial.

Layer
of
Confinement.
Any
closed
plastic
bag
containing
waste.
Punctured
bags
or
liners,
bags
open
at
the
end,
or
pieces
of
plastic
sheet
wrapped
around
the
waste
for
handling
are
not
considered
as
layers
of
confinement.

Line
Generated.
Items
that
are
removed
from
a
glovebox
or
items
generated
from
the
cleanup
of
a
contamination
incident
with
direct
count
radioactivity
levels
greater
than
500,000
cpm
of
alpha
contamination
when
measured
using
a
Ludlum­
12­
1A
are
categorized
and
packaged
as
TRU
waste.

Low
Specific
Activity
LSA.
[
as
defined
by
49
CFR
173.403].

Lower
Limit
of
Detection
(
LLD).
The
level
of
radioactivity
which,
if
present,
will
yield
a
measured
value
greater
than
the
critical
limit
with
a
95%
probability.
The
critical
limit
is
defined
as
that
value
which
measurements
of
background
will
exceed
with
a
5%
probability.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
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02/
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2004
PAGE
298
9.1
Definitions
(
continued)

Neutron
Multiplicity
Counter
(
NMC).
An
NDA
measurement
device
used
to
measure
neutron
radiation
in
packages.

Newly
Generated
Waste.
There
are
two
definitions
for
newly
generated
waste
based
on
WIPPrequirement
documents.
One
definition
is
derived
from
the
WIPP­
WAP
and
the
other
from
TRAMPAC.
Each
definition
is
presented
below:

 
WIPP­
WAP
Definition.
Newly
generated
waste
is
defined
as
TRU
waste
generated
after
the
New
Mexico
Environmental
Department
approves
the
final
audit
report
for
RFETS.

 
TRAMPAC
Definition.
Newly
generated
waste
is
defined
as
waste
generated
after
a
formal
certification
program
has
been
established
at
the
site.

Nondestructive
Assay
(
NDA).
The
measurement
of
radioactivity
and/
or
radionuclide
specific
activity
without
destroying
the
material.

Nondestructive
Examination
(
NDE).
Methods
that
allow
examination
of
items
without
affecting
the
chemical
or
physical
forms
of
these
items.
An
example
is
real­
time
radiography
(
RTR)
which
provides
visible
evidence
of
the
contents
of
payload
packages.

Nondestructive
Testing
(
NDT).
Those
groups
of
tests,
such
as
Real­
time
Radiography
(
RTR),
that
evaluate
an
item's
conformance
without
affecting
the
physical
or
chemical
form
of
the
material.

Non­
line
Generated.
Radioactive
waste
excluding
radioactive
medical
waste,
that
does
not
meet
the
definition
of
Line
Generated;
i.
e.,
items
which
are
not
removed
from
a
glovebox
and
display
less
than
500,000
cpm
of
alpha
contamination
when
measured
using
a
Ludlum
12­
1A.
This
waste
is
packaged
and
characterized
as
LLW.

NQA­
1.
American
Society
of
Mechanical
Engineers
(
ASME)
Quality
Assurance
Program
Requirements,
as
specified
in
ASME
NQA­
1­
1989,
Quality
Assurance
Program
Requirements
for
Nuclear
Facilities.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
299
9.1
Definitions
(
continued)

Originator.
This
term
is
interchangeable
with
Generator.
A
person
or
persons
who
assemble
and
package
waste
or
any
person
whose
act
or
process
produces
a
waste,
or
whose
act
causes
a
waste
to
become
subject
to
regulation
or
DOE
order.
This
includes
RFETS
subcontractors
and
DOE
prime
contractors
who
create
wastes.

Overpack.
Except
when
referenced
to
a
packaging
specified
in
49
CFR
178,
means
an
enclosure
that
is
used
by
a
consignor
to
provide
protection
or
convenience
in
handling
of
a
package,
or
to
consolidate
two
or
more
packages.
Overpack
does
not
include
a
freight
package.
Also
refer
to
49
CFR
171.80.

Package.
The
packaging
together
with
its
radioactive
contents
as
presented
for
transport
(
49
CFR
173.403).

Packaging.
The
assembly
of
components
necessary
to
ensure
compliance
with
the
packaging
requirements
of
49
CFR.
For
radioactive
materials,
refer
to
49
CFR
173.403.

Passive/
Active
Drum
Counter
(
PADC).
An
instrument
used
to
measure
radionuclide
content
and
perform
TRU
or
LLW
sorting
of
waste
drums.
Measures
both
spontaneous
and
stimulated
neutrons
using
differential
die­
away
technique
to
determine
nuclear
material
content
of
drummed
material.
Capable
of
measuring
materials
that
are
too
dense
for
gamma
measurements.

Payload
Container
Assembly.
The
outermost
container,
such
as
a
seven­
pack
of
drums,
that
is
intended
to
be
handled
and
emplaced
in
the
WIPP
as
a
single
unit.

Payload
Package
Assembly.
An
assembly
of
payload
packages,
such
as
a
seven­
pack
of
drums,
that
is
intended
to
be
handled
as
a
single
unit.

Payload
Packages.
Fifty­
five
gallon
drums
and
Standard
Waste
Boxes
that
are
filled
with
wastes.
They
may
also
be
called
waste
packages
or
payload
packages.

Pipe
Overpack
Component
(
POC).
This
DOT
7A
package
is
used
primarily
for
TRU
waste
derived
from
the
processing
of
residues,
although
other
TRU
wastes
may
also
be
packaged
in
POCs
in
accordance
with
specific
project
requirements.
The
POC
packages
are
also
known
as
Pipe
Component
Assemblies
with
55­
Gallon
Drums
or
Pipe
Components,
but
are
referred
to
as
POCs
throughout
this
document.
The
POC
is
NRC­
licensed
and
is
an
authorized
configuration
within
the
scope
of
the
TRUPACT­
II
Package
Certificate
of
Compliance
(
C
of
C
No.
9218).
Design
configuration
for
the
POC
is
maintained
through
the
application
of
1­
V51­
COEM­
DES­
210,
Site
Engineering
Process
Procedure.
Supporting
processes
and
procedures
are
discussed
in
this
document.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
300
9.1
Definitions
(
continued)

Pressurized
Vessels
(
Containers).
Items
in
a
payload
package,
such
as
aerosol
cans,
that
may
hold
compressed
gas.

Process
Knowledge.
Knowledge
of
the
material
used
in
a
process
that
provides
information
for
characterization
of
waste
from
that
process.

Protected
Area
(
PA).
An
area
encompassed
by
physical
barriers
(
such
as,
walls
or
fences),
subject
to
access
controls,
surrounding
a
Material
Access
Area,
and
meeting
the
standards
of
DOE
Order
5632.2A.
The
area
of
RFETS
that
is
located
within
several
physical
security
boundaries
and
in
which
most
of
the
Special
Nuclear
Material
is
used,
processed,
and
stored.

Pu­
239
Fissile
Gram
Equivalent.
The
amount
of
Pu­
239
that
would
produce
the
equivalent
Keff
as
that
determined
for
the
fissile
material
in
the
package
(
assuming
all
packages
are
in
an
optimally
moderated
infinite
array)
is
called
the
Pu­
239
fissile
gram
equivalent.
U­
235
and
U­
233
and
other
radionuclides
shall
be
calculated
as
Pu­
239
fissile
equivalents
using
Table
6.1
in
the
TRUPACT­
II
TRAMPAC.

Pyrophoric
Materials.
Materials
that
may
ignite
spontaneously
under
ambient
conditions,
or
are
strong
oxidizers
(
Refer
to
49
CFR
173.115).

Radiochemical
Assay.
Process
employing
instrumentation
capable
of
detecting
and
quantifying
radioactive
decay
(
e.
g.
alpha,
beta,
gamma)
usually
involving
sample
preparation
techniques
(
e.
g.
separations
which
alter
the
original
sample).

Radiological
Control
Technician
(
RCT).
The
job
title
of
personnel
who
provide
radiation
protection
through
controls
and
monitoring
of
areas,
items,
and
personnel.

RCRA
Custodian.
Designated
individuals
who
are
RCRA
qualified
to
manage
the
operation(
s)
of
a
RCRA
Hazardous
Unit
and
whose
actions
or
failure
to
act
may
result
in
noncompliance
with
the
requirements
of
the
Colorado
Hazardous
Waste
Regulations,
6
CCR
1007­
3,
or
the
Custodian
officially
"
on
record"
as
the
responsible
RCRA
Qualified
Personnel
for
a
given
RCRA
Hazardous
Waste
Unit.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
301
9.1
Definitions
(
continued)

Reactive
Material.
Material
which
is
normally
unstable
and
readily
undergoes
a
violent
change
without
detonating,
reacts
violently
with
water,
forms
potentially
explosive
mixtures
with
water,
and/
or
generates
gases,
vapors
or
fumes
when
mixed
with
water.

Real­
time
Radiography
(
RTR).
A
radiographic
method
that
allows
simultaneous
remote
imaging
for
the
viewing
of
waste
package
contents.

rem.
Roentgen
equivalent
man,
a
unit
of
ionizing
radiation
dose
equivalent.

Residual
Liquid.
Liquids
in
quantities
of
less
than
1
volume
percent
of
the
waste
package
that
result
from
liquid
residues
remaining
in
well­
drained
internal
containers,
condensation
of
moisture,
and
liquid
separation
resulting
from
sludge/
resin
setting.

Residue.
As
a
result
of
production
activities
at
RFETS,
a
variety
of
materials
became
contaminated
with
plutonium.
If
the
level
of
plutonium
contamination
for
specific
materials
exceeded
the
economic
discard
limit
(
EDL),
the
plutonium
contaminated
materials
were
originally
categorized
as
"
residue"
rather
than
"
waste"
and
were
stored
for
later
recovery
of
plutonium.
These
residues
have
now
been
declared
to
be
waste.

Retrievably
Stored
Waste.
Retrievably
stored
waste
is
defined
as
TRU
waste
generated
after
1970
and
before
New
Mexico
Environmental
Department
notifies
the
WIPP
facility,
by
approval
of
the
final
audit
report,
that
the
characterization
requirements
of
the
WIPP­
WAP
have
been
implemented
appropriately
at
RFETS.

Segmented
Gamma
Scanner
(
SGS).
An
NDA
measurement
device
used
to
measure
gamma
radiation
in
packages.

Segregate.
To
isolate,
separate,
or
sort
according
to
contamination
level,
IDC,
and
hazardous
or
nonhazardous
constituency.

Shipper.
A
TRU
waste
site
that
releases
a
TRUPACT­
II
to
a
carrier
for
shipment.

Shipping
Category.
A
grouping
system
for
CH­
TRU
waste
payload
packages
intended
to
prevent
mixing
of
incompatible
groups
in
the
same
TRUPACT­
II.
Refer
to
Section
6.5.1
of
this
document.

Standard
Waste
Box
(
SWB).
A
metal
payload
container
authorized
for
use
within
the
TRUPACT­
II
packaging,
that
has
been
tested
by
DOE
to
meet
DOT
Specification
7A,
Type
A
requirements.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
302
9.1
Definitions
(
continued)

Tamper­
Indicating
Device
(
TID).
A
device
that
may
be
used
on
packages
to
reveal
violations
of
containment
integrity.

Ten
Drum
Overpack
(
TDOP).
A
specialized
payload
package
authorized
for
use
within
the
TRUPACT­
II
packaging
that
meets
DOT
specification
7A
Type
A.

Test
Category.
Payload
containers
that
do
not
meet
the
analytical
category
limits
are
classified
as
test
category.
(
TRAMPAC,
revision
19,
section
5.2).

Tomographic
Gamma
Scanner
(
TGS).
An
NDA
measurement
device
used
to
measure
gamma
radiation
in
packages
and
drums.

Trace
chemicals/
materials.
Chemicals/
materials
that
occur
individually
in
the
waste
in
quantities
less
than
1
weight
percent.
The
total
quantity
of
trace
chemicals/
materials
not
listed
as
allowed
materials
for
a
given
waste
material
type
in
any
payload
containers
is
restricted
to
less
than
5
weight
percent.
(
TRAMPAC,
revision
19,
section
4.3.1).

TRAMPAC.
TRUPACT­
II
Authorized
Methods
for
Payload
Control.
Documentation
describing
allowable
methods
for
payload
control
to
assure
TRUPACT­
II
payloads
meet
all
of
the
TRUPACT­
II
shipping
requirements
and
limits.
For
each
of
the
limits
and
requirements,
sites
must
select
and
implement
one
or
more
of
the
allowable
methods.
This
information
is
documented
in
Section
6.0
of
this
document.

Transportation
Certification
Official
(
TCO).
The
person
(
In
Traffic
Management
organization)
who
affirms
by
signature
that
the
Bill
of
Lading
and
Uniform
Hazardous
Waste
Manifest
are
accurate
according
to
DOE
regulations.
Certifies
that
the
shipment
meets
transportation
requirements
of
EPA,
WIPP­
WAC,
WIPP­
WAP,
and
DOE.

Transuranic
Waste
(
TRU
Waste).
Radioactive
waste
containing
alpha­
emitting
radionuclides
having
atomic
numbers
greater
than
92
and
half­
lives
greater
than
20
years
in
concentrations
greater
than
100
nCi/
g
at
the
time
of
assay.

TRU
isotope.
An
isotope
of
any
element
having
an
atomic
number
greater
than
uranium
(
i.
e.,
92).

TRU
Mixed
Waste.
TRU
waste
containing
both
radioactive
and
hazardous
components
as
defined
by
the
Atomic
Energy
Act
and
RCRA,
respectively.
For
the
purposes
of
this
document,
TRU
waste
is
used
to
collectively
reference
mixed
(
RCRA)
and
non
mixed
wastes
when
controls
for
both
waste
types
are
the
same.
When
it
is
necessary
to
discriminate,
the
wastes
are
specifically
referenced
as
"
mixed"
or
"
straight"
TRU
waste.

TRUCON.
TRUPACT­
II
Content
Codes
document
developed
to
show
wastes
characterized
and
grouped
together
for
controlling
the
payload
(
authorized
contents)
in
a
TRUPACT­
II,
(
refer
to
DOE
WIPP
89­
004).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
303
9.1
Definitions
(
continued)

TRUPACT­
II
Authorized
Method
for
Payload
Control
(
TRAMPAC).
The
TRAMPAC
is
the
governing
document
for
payload
shipments
in
the
TRUPACT­
II.
(
TRAMPAC,
section
1.0).

TRUPACT­
II
Package.
NRC
approved
Type
B
package
loaded
with
TRUPACT­
II
standard
waste
boxes
(
SWB),
55­
gallon
drums
or
ten
drum
overpack.

TRUPACT­
II
Payload.
55­
gallon
drums,
SWBs,
or
ten
drum
overpack
loaded
into
the
TRUPACT­
II.

TRUPACT­
II
Trailer.
The
trailer
used
to
ship
TRU
waste
in
TRUPACT
II
packages
to
the
designated
disposal
facility.

Twist
and
Tape.
A
method
of
bag
closure
for
waste
consisting
of
gathering
the
neck
of
the
bag,
twisting
tightly,
and
wrapping
tightly
with
plastic
tape.
Often
called
"
pigtail."

Validation.
An
activity
that
demonstrates
or
confirms
that
a
process,
item,
data
set,
or
service
satisfies
the
requirements
defined
by
the
user.
Data
validation
requirements
for
the
TWCP
include
signature
release
and
are
described
in
the
WIPP­
WAP
and
WIPP­
WAC.

Verification.
The
act
of
authenticating
or
formally
asserting
the
truth
that
a
process,
item,
data
set
or
service
is,
in
fact,
that
which
is
claimed.
Data
verification
is
the
process
used
to
confirm
that
all
review
and
validation
procedures
have
been
completed.
Data
verification
requirements
for
the
TWCP
are
described
in
the
WIPP­
WAP.

Volatile
Organic
Compounds
(
VOCs).
For
the
purposes
of
the
TWCP,
those
gas
VOCs
listed
in
the
WIPP­
WAP
(
Table
B3­
2
and
the
target
VOCs
listed
in
Table
B3­
4
)
and
any
additional
compounds
tentatively
identified
by
the
VOC
analytical
procedures
used
to
satisfy
WIPP­
WAP
requirements.

Waste
Acceptance
Criteria.
Waste
acceptance
criteria
ensure
that
CH­
TRU
waste
is
managed
and
disposed
of
in
a
manner
that
protects
human
health
and
safety
and
the
environment.

Waste
Analysis
Plan.
Sites
are
required
to
implement
the
applicable
requirements
of
the
WIPPWAP

Waste
and
Environmental
Management
System
(
WEMS).
A
computer
database
used
to
perform
waste
package
inventory,
tracking,
and
control
functions.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
304
9.1
Definitions
(
continued)

Waste
Certification.
Activities
associated
with
waste
characterization
and
records
required
to
certify
that
the
waste
meets
the
WIPP­
WAC.

Waste
Certification
Official
(
WCO).
The
person(
s)
who
affirms
by
signature
that
waste
meets
all
WIPP­
WAC
criteria
for
off­
site
shipment.
Ensures
independent
oversight
is
conducted
to
verify
that
quality
assurance
requirements
and
waste
disposal
site
waste
acceptance
criteria
are
satisfied.

Waste
Characterization.
The
process
of
determining
that
TRU
waste
meets
the
requirements
of
the
WIPP­
WAC
by
the
acceptable
performance
of
the
activities
defined
by
the
CBFO­
approved
site­
specific
plans.

Waste
Inspection
(
WI).
An
RFETS
function
that
provides
inspection
services.
Waste
Inspection
ensures
conformance
to
applicable
waste
acceptance
and
certification
criteria.
The
Waste
Inspector
assesses
package
integrity,
drum
or
box
contents
conformance,
and
package
documentation,
labeling,
and
marking.

Waste
Item.
Waste
that
is
placed
or
packaged
for
placement
into
a
waste
package.

Waste
Material
Type.
Further
divisions
of
Waste
Types
based
on
G
values
(
flammable
gas
generation
potential),
bagging,
and
packaging
configurations.

Waste
Package.
The
waste,
the
waste
container,
and
any
absorbent
that
is
intended
for
disposal
as
a
unit.

Waste
Stream.
Material
from
a
waste
generating
process
whose
known
or
measured
characteristics
fall
within
a
pre­
established
range
of
specific
chemical
and
physical
characteristics.

Waste
Stream
and
Residue
Identification
and
Characterization
(
WSRIC).
A
program
designed
to
verify
waste
streams
at
RFETS
through
the
collection
of
process
knowledge,
analytical
data,
data
management,
and
WSRIC
Building
Book
production.
These
books
are
reference
documents
for
operating
personnel
and
are
used
as
aids
in
the
characterization
of
RFETS
wastes.

Waste
Type.
Physical
types
of
waste
such
as
solidified
inorganics,
solid
inorganics,
solidified
organics
or
solid
organics.

WIPP
Waste
Acceptance
Criteria
(
WIPP­
WAC).
Criteria
developed
for
the
safe
handling,
packaging,
and
acceptance
of
TRU
waste
at
the
WIPP.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
305
9.2
Acronyms
AFGC
Allowable
flammable
gas
concentration
AK
Acceptable
Knowledge
ALARA
As
Low
As
Reasonably
Achievable
ANSI
American
National
Standard
Institute
ASTM
American
Society
for
Testing
and
Materials
Bq
Becquerel
BWRBB
Backlog
Waste
Reassessment
Baseline
Book
C
of
C
Certificate
of
Compliance
C&
I
Certification
and
Inspection
CAP
Corrective
Action
Plan
CAQ
Condition
Adverse
to
Quality
CBFO
Carlsbad
Field
Office
(
current
abbreviation)
CC
Component
Checkout
CCA
Compliance
Certification
Application
CCC
Chemical
Constituent
Code
CCR
Code
of
Colorado
Regulations.
CDPHE
Colorado
Department
of
Public
Health
&
Environment
CFR
Code
of
Federal
Regulations
CH­
TRU
Contact
Handled
Transuranic
Ci
Curie
cpm
Counts
per
minute
CPR
Combustibles,
plastics,
and
rubber
CVSA
Commercial
Vehicle
Safety
Alliance
DAC
Drum
age
criteria
DCF
Document
Change
Form
DH
Decay
Heat
DOE
United
States
Department
of
Energy
DOT
United
States
Department
of
Transportation
dpm
Disintegration(
s)
per
minute
DQO
Data
Quality
Objective
DU
Depleted
Uranium
EPA
Environmental
Protection
Agency
EPA
HWN
EPA
Hazardous
Waste
Number
e­
TRAMPAC
Electronic­
TRAMPAC
EU
Enriched
Uranium
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
306
9.2
Acronyms
(
continued)

FGE
Fissile
Gram
Equivalent
FI
Flammability
index
FRAM
Fixed
Energy
Response
Function
Analysis
with
Multiple
Efficiencies
GC/
MS
Gas
Chromatography/
Mass
Spectroscopy
GGTP
QAPjP
Gas
Generation
Testing
Program
Quality
Assurance
Project
Plan
HWN
Hazardous
waste
number
HWRM
Hazardous
Waste
Requirements
Manual
ICV
Inner
Containment
Vessel
ID
Identification
IDC
Item
Description
Code
KH
Kaiser­
Hill
LANL
Los
Alamos
National
Laboratory
LDR
Land
Disposal
Restriction
LLD
Lower
Limit
of
Detection
LLW
Low­
Level
Waste
LSA
Low
Specific
Activity
(
as
defined
by
49
CFR
173.403[
n])

M&
O
Management
and
Operation
M&
TE
Measuring
and
test
equipment
MDC
Minimum
Detectable
Concentration
MDL
Minimum
Detection
Limit
MLEL
Mixture
Lower
Explosive
Limit
MPCC
Multi­
purpose
passive/
active
neutron
crate
counter
mrem/
hr
milliroentgen(
s)
equivalent
man
per
hour
MS
Mass
Spectrometry,
or
Matrix
Spike
m/
s/
mf
Moles
per
second
per
mole
fraction
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
307
9.2
Acronyms
(
continued)

NA
Not
applicable
NBL
New
Brunswick
Laboratory
nCi/
g
NanoCuries
per
gram
NCR
Nonconformance
Report
NDA
Nondestructive
Assay
NDE
Nondestructive
Examination
NDT
Nondestructive
Testing
NIST
National
Institute
of
Standards
and
Technology.
NMC
Neutron
Multiplicity
Counter
NMED
New
Mexico
Environmental
Department
NMMA
Nuclear
Material
Management
Area
NRC
U.
S.
Nuclear
Regulatory
Commission
OCA
Outer
Containment
Assembly
OPCTCD
Overpack
Payload
Container
Transportation
Certification
Document
PA
Protected
Area
PADC
Passive/
Active
Drum
Counter
PAN
Passive
Active
Neutron
PATCD
Payload
Assembly
Transportation
Certification
Document
PCP
Process
Control
Plan
PCTCD
Payload
Container
Transportation
Certification
Document
PM
Project
Manager
PNCC
Passive
neutron
coincidence
counting
POC
Pipe
Overpack
Component
ppm
Parts
per
million
PQAO
Project
Quality
Assurance
Officer
PQPs
Process
Qualification
Plans
QA
Quality
Assurance
QAO
Quality
Assurance
Objective
QAPD
Quality
Assurance
Program
Document
QC
Quality
Control
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
308
9.2
Acronyms
(
continued)

RCRA
Resource
Conservation
and
Recovery
Act
RCT
Radiological
Control
Technician
rem
Roentgen
equivalent
man
RFETS
Rocky
Flats
Environmental
Technology
Site
RFFO
Rocky
Flats
Field
Office
RIDS
Records
Inventory
Disposition
Schedule
RMS
Root
Mean
Square
RSD
Relative
standard
deviation
RSP
Radiological
Safety
Practices
RT
Room
temperature
RTR
Real­
Time
Radiography
SAR
Safety
Analysis
Report
SCAQ
Significant
Condition
Adverse
to
Quality
SDRM
Site
Document
Requirements
Manual
SGS
Segmented
Gamma
Scanner
SME
Subject
Matter
Expert
SNM
Special
Nuclear
Material
SO
Systems
Operability
SOP
Standard
Operating
Procedure
SQA
Software
Quality
Assurance
STP
Standard
temperature
and
pressure
SuperHENC
Super
High
Efficiency
Neutron
drum
and
box
counter
SWB
Standard
Waste
Box
for
the
TRUPACT­
II.
SVOC
Semivolatile
Organic
Compound
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
309
9.2
Acronyms
(
continued)

TCO
Transportation
Certification
Official
TDOP
Ten
Drum
Overpack
TGS
Tomographic
Gamma
Scanner
TIC
Tentatively
identified
compound
TID
Tamper
Indicating
Device
TIP
Training
Implementation
Plan
(
see
PLN­
97­
007)
TMU
Total
Measurement
Uncertainty
TPM
Training
Program
Manual
(
see
MAN­
094­
TPM)
TRAMPAC
TRUPACT­
II
Authorized
Methods
for
Payload
Control
TRIFID
Transuranic
Isotopic
Fraction
Interrogation
Device
TRU
Transuranic
Waste
TRUCON
TRUPACT­
II
Content
Codes
TRUPACT­
II
Transuranic
Package
Transporter­
II
TSCA
Toxic
Substances
Control
Act
TSDF
Treatment,
Storage,
and
Disposal
Facility
TWCP
QAPjP
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
see
95­
QAPjP­
0050)
TWMM
TRU
Waste
Management
Manual
(
1­
MAN­
008­
WM­
001)

UCL
Upper
confidence
limit
VE
Visual
Examination
VOC
Volatile
Organic
Compound
VV
Visual
Verification
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
310
9.2
Acronyms
(
continued)

WAC
Waste
Acceptance
Criteria
WCF
WSRIC
Change
Form
WCL
Waste
Component
Limits
WCO
Waste
Certification
Official
WCR
WSRIC
Change
Request
WEMS
Waste
and
Environmental
Management
System
WG
Weapons
Grade
WGI
Waste
Generating
Instruction
WI
Waste
Inspection
WIPP
Waste
Isolation
Pilot
Plant
WIPP­
WAC
Waste
Isolation
Pilot
Plant
Waste
Acceptance
Criteria
WIPP­
WAP
Waste
Isolation
Pilot
Plant
Waste
Analysis
Plan
WNCR
Waste
Nonconformance
Report
WRG
Waste
Requirements
Group
WSPFs
Waste
Stream
Profile
Forms
W/
RT
Waste/
Residue
Traveler
(
form
number
RF­
47386)
WSRIC
Waste
Stream
and
Residue
Identification
and
Characterization
WWIS
WIPP
Waste
Information
System
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
311
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
312
APPENDIX
1
Page
1
of
2
RFETS
ORGANIZATIONAL
CHARTS
Rocky
Flats
Environmental
Technology
Site
NOTES:
­
The
RFETS
organization
presented
here
is
simplified
to
illustrate
TWCP­
related
functions
­
The
organizational
structure
here
is
subject
to
change.
Updates
are
made
commensurate
with
changes
to
the
TWMM.
Department
of
Energy
Rocky
Flats
Field
Office
Kaiser­
Hill
Executive
Office
Administration
General
Counsel
&
Audit
Environmental
Systems
&
Stewardship
Metrology
Remediation,
Industrial
D&
D,
and
Site
Services
Information
Resource
Management
Analytical
Laboratory
Strategic
Planning
&
Integration
Waste
Certification
&
Oversight
Waste
Certification
Official
(
WCO)
Environmental
Compliance
Procurement
Systems
771/
774
Closure
Project
776/
777/
707
Closure
Project
371/
374
Closure
Project
Material
Stewardship
D&
D
Project
QA
Nuclear
Operations
D&
D
D&
D
See
next
page
Project
QA
Project
QA
Safety,
Engineering,
&
Quality
Programs
Quality
Program/
PATS
Analytical
Lab
Project
Quality
Assurance
Officer
(
LPQAO)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
313
APPENDIX
1
Page
2
of
2
RFETS
ORGANIZATIONAL
CHARTS
(
continued)

Material
Stewardship
NOTES:
­
The
RFETS
organization
presented
here
is
simplified
to
illustrate
TWCP­
related
functions
­
The
organizational
structure
here
is
subject
to
change.
Updates
are
made
commensurate
with
changes
to
the
TWMM.
VP
Project
Manager
Environmental,
Safety,
Health
&
Quality
Protected
Area
Closure
TWCP
Site
Quality
Assurance
Officer
(
TWCP
Site
PQAO)

Strategic
Planning
&
Administration
Material
Stewardship
Quality
Assurance
Waste
Operations
Traffic
&
Transportation
Measurements
Waste
Inspectors
Traffic
Management
Transportation
Certification
Officer
(
TCO)
Facility
Managers
NDA
Quality
Assurance
Technical
Operations
TRU
Waste
Project
(
TWCP
Site
PM)

Waste
Requirements
Project
Data
Control
Officer
(
PDCO)
Material
Control
&
Accountability
NDA
Operations
Nondestructive
Testing
(
NDT)
Waste
Systems
Headspace
Analytical
Services
Quality
Assurance
Officer
(
HASQAO)

Headspace
Analytical
Services
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
314
APPENDIX
2
Page
1
of
3
WASTE
CERTIFICATION
FLOW
DIAGRAM
WASTE
PACKAGE
CERTIFICATION
B440
/
B664
OPERATIONS
TRU
WASTE
PROGRAMS
WASTE
CERTIFICATION
AND
OVERSIGHT
(
WC&
O)
TRAFFIC
MANAGEMENT
Drums
selected
from
storage
(
PRO­
1411­
WO­
WASTE)
WIPP/
WEMS
Verification
(
4­
G83­
WEM­
WP­
1209)

Labeling
and
marking
completed
(
PRO­
T13­
Traffic­
306)

Radiological
smears
performed
(
PRO­
497­
RSP­
09.07)

Final
drum
inspection
(
PRO­
1045­
WI­
001)

NCR
if
unacceptable
(
PRO­
U76­
WC­
4030)
WEMS
Radiological
Verification
and
documentation
review
(
4­
G83­
WEM­
WP­
1209
&
RF/
RMRS­
97­
018)
Electronic
transmission
of
package
characterization
data
to
WWIS
(
no
profile
established)
(
4­
K47­
WEM­
WP1210)
1­
PRO­
110­
WP­
1212)

Electronic
transmission
of
Certification
data
from
WEMS
to
WWIS
(
4­
K47­
WEM­
WP1210)
(
1­
PRO­
110­
WP­
1212)

WIPP
APPROVAL
WIPP
Package
Certification
and
visual
inspection
(
PRO­
X05­
WC­
4018)
Package
Certification
(
4­
G83­
WEM­
WP­
1209)

Continued
on
Page
2
of
3
WIPP
APPROVAL
of
Profile
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
315
APPENDIX
2
Page
2
of
3
WASTE
CERTIFICATION
FLOW
DIAGRAM
(
continued)

PAYLOAD
SHIPMENT
CERTIFICATION
B440
/
B664
OPERATIONS
TRU
WASTE
PROGRAMS
WASTE
CERTIFICATION
AND
OVERSIGHT
(
WC&
O)
TRAFFIC
MANAGEMENT
Continued
on
Page
3
of
3
Generate
payload
PCTCDs
and
preliminary
PATCD
reports
in
eTRAMPAC.
Preliminary
PATCD
to
Ops.
(
4­
K47­
WEM­
WP1210)

Assign
payloads
to
shipment
and
enter
shipment
data
into
eTRAMPAC
(
excluding
ICV
closure
dates,
TRUPACT­
II
dose
rates,
certification
date,
Transporter
name
and
send
date).
Submit
eTRAMPAC
shipment
data
to
WWIS.
(
4­
K47­
WEM­
WP1210)

Generate
Shipment
report
from
WEMS
and
shipment
PATCD
reports
from
eTRAMPAC.
(
PRO­
T43­
Traffic­
528)
(
4­
K47­
WEM­
WP1210)
Payload
staged
(
PRO­
1418­
WO­
TRUOP)
(
DOE/
WIPP
02­
3184)

Ensure
filters
torqued
(
PRO­
1045­
WI­
001)

Payload
assembly
prepared
(
PRO­
1418­
WO­
TRUOP)
(
DOE/
WIPP
02­
3184)
Payload
staging
verification
(
PRO­
X05­
WC­
4018)

WIPP
Approval
Review
&
Approval
of
PCTCD
reports
(
PRO­
T43­
Traffic­
528)
Vessel
Inspection
and
preparation
(
PRO­
1418­
WO­
TRUOP)
(
DOE/
WIPP
02­
3184)
Assign
packages
to
assemblies,
and
assemblies
to
payloads
in
eTRAMPAC.
(
4­
K47­
WEM­
WP1210)
Receiving
CVSA
Inspection
of
incoming
vessel
(
PRO­
T43­
Traffic­
528)

Continued
on
Page
3
of
3
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
316
APPENDIX
2
Page
3
of
3
WASTE
CERTIFICATION
FLOW
DIAGRAM
(
continued)

PAYLOAD
SHIPMENT
CERTIFICATION
(
Cont'd)

B440
/
B664
OPERATIONS
TRU
WASTE
PROGRAMS
WASTE
CERTIFICATION
AND
OVERSIGHT
(
WC&
O)
TRAFFIC
MANAGEMENT
TRUPACT­
II
loading
operations
(
PRO­
1418­
WO­
TRUOP)
(
DOE/
WIPP
02­
3184)

Closure
of
TRUPACT­
II
vessel
(
PRO­
1418­
WO­
TRUOP)
(
DOE/
WIPP
02­
3184)

Leak
Test
verification
(
PRO­
1419­
WO­
LKTST)

Radiological
surveys
of
TRUPACT­
II
vessels
(
PRO­
497­
RSP­
09.07)
TRUPACT­
II
vessel
loading
and
closure
verification
(
PROX05
WC­
4018)

Certify
Shipment.
Enter
Certification
date
and
send
date
into
eTRAMPAC.
Finalize
eTRAMPAC
shipment
to
WWIS.
(
4­
K47­
WEMEnter
ICV
closure
dates,
TRUPACT­
II
dose
rates,
and
Transporter
Name
to
eTRAMPAC.
(
4­
K47­
WEMWP
1210)

TRUPACT­
II
vessel
labeling
and
marking
inspection
(
PRO­
T43­
Traffic­
528)
Generate
final
shipment
PATCD
reports
from
eTRAMPAC.
(
4­
K47­
WEM­
WP­
1210)

Review
and
approval
of
final
PATCD
report
(
PRO­
T43­
Traffic­
528)
Complete
Bill
of
Lading
and/
or
Uniform
Hazardous
Waste
Manifest
(
PRO­
T30­
Traffic­

Perform
enhanced
CVSA
Inspection
with
CSP,
Transporter
&
Trans.
Personnel.
(
PRO­
T43­
Traffic­
528)
Execute
Bill
of
Lading
(
PRO­
T30­
Traffic­
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
317
APPENDIX
3
Page
1
of
4
A3.0
Payload
Package
Visual
Examination
Visual
examination
of
100%
of
the
payload
package
exterior
is
conducted
to
determine
if
the
payload
package
meets
the
criteria
of
Section
5.2.1.
RFETS
incorporates
the
questions
and
criteria
contained
in
the
following
checklist
into
PRO­
1045­
WI­
001,
Solid
Radioactive
Waste
Inspection.
This
payload
package
inspection
is
performed
and
documented
as
a
part
of
the
TRUPACT­
II
loading
process.
Any
YES
answer
on
the
inspection
checklist
will
result
in
the
inspector
discontinuing
the
inspection,
marking
the
payload
package
as
unacceptable
for
shipment,
and
removal
of
the
payload
package
from
the
shippable
inventory.
Before
the
rejected
package
can
be
shipped,
it
must
undergo
appropriate
corrective
actions
(
e.
g.,
evaluation,
repackaging,
overpacking,
etc.),
as
applicable.
All
packages
must
have
an
acceptable
and
complete
inspection
checklist
documenting
that
it
meets
the
DOT
7A
criteria.

PAYLOAD
PACKAGE
INTEGRITY
CHECKLIST
PACKAGE
EXAMINATION
DISCUSSION
OF
CRITERIA
COMPLIANCE
1.
Is
the
payload
package
obviously
degraded?
Obviously
degraded
means
clearly
visible
and
potentially
significant
defects
in
the
payload
package
or
payload
package
surface.
YES
NO
2.
Is
there
evidence
that
the
payload
package
is,
or
has
been,
pressurized?
Pressurization
can
be
indicated
by
a
fairly
uniform
expansion
of
the
sidewalls,
bottom
or
top.
Past
pressurization
can
be
indicated
by
a
notable
outward
deflection
of
the
bottom
or
top.
Verify
that
the
drum
is
not
warped.
YES
NO
3.
Is
there
any
potentially
significant
rust
or
corrosion
such
that
wall
thinning,
pin
holes,
or
breaches
are
likely
or
the
load
bearing
capacity
is
suspect?
Rust
shall
be
assessed
in
terms
of
its
type,
extent,
and
location.
Pitting,
pocking,
flaking,
or
dark
coloration
characterizes
potentially
significant
rust
or
corrosion.
This
includes
the
extent
of
the
payload
package
surface
area
covered,
thickness,
and,
if
it
occurs
in
large
flakes
or
builtup
(
caked)
areas.
Rusted
payload
packages
may
not
be
accepted
if:
 
Rust
is
present
in
caked
layers
or
deposits
 
Rust
is
present
in
the
form
of
deep
metal
flaking,
or
built­
up
areas
of
corrosion
products.

In
addition,
the
location
of
rust
should
be
noted;
for
example
on
a
drum:
top
lid;
filter
region;
locking
chime;
top
one­
third,
above
the
second
rolling
hoop;
middle
onethird
between
the
first
and
second
rolling
hoops;
bottom
one­
third,
below
the
second
rolling
hoop;
and
on
the
bottom.

Payload
packages
may
still
be
considered
acceptable
if
the
signs
of
rust
show
up
as:
 
Some
discoloration
on
the
payload
package
 
If
rubbed
would
produce
fine
grit
or
dust
or
minor
flaking
(
such
that
wall
thinning
does
not
occur).
YES
NO
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
318
APPENDIX
3
Page
2
of
4
PAYLOAD
PACKAGE
INTEGRITY
CHECKLIST
(
continued)

PACKAGE
EXAMINATION
DISCUSSION
OF
CRITERIA
COMPLIANCE
4.
Are
any
of
the
following
apparent?
 
wall
thinning
 
pin
holes
 
breaches
Wall
thinning,
pin
holes,
and
breaches
can
be
a
result
of
rust/
corrosion
(
see
discussion
for
#
3).
YES
NO
5.
Are
there
any
split
seams,
tears,
obvious
holes,
punctures
(
of
any
size),
creases,
broken
welds,
or
cracks?
Payload
packages
with
obvious
leaks,
holes
or
openings,
cracks,
deep
crevices,
creases,
tears,
broken
welds,
sharp
edges
or
pits,
are
either
breached
or
on
the
verge
of
being
breached.
Verify
that
there
is
no
warpage
that
could
cause
the
package
to
be
unstable
or
prevent
it
from
fitting
properly
in
the
TRUPACT­
II.
YES
NO
6.
Is
the
load­
bearing
capacity
suspect?
The
load­
bearing
capacity
could
be
reduced
for
excessive
rust
(
see
discussion
for
#
3),
wall
thinning
(
see
discussion
for
#
4),
breaches,
cracks,
creases,
broken
welds,
etc.
(
see
discussion
for
#
5).
YES
NO
7.
Is
the
payload
package
improperly
closed?
Inspect
the
fastener
and
fastener
ring
(
chime)
if
applicable
for
damage
or
excessive
corrosion.
Check
the
alignment
of
the
fastener
to
ensure
that
it
is
in
firm
contact
around
the
entire
lid
and
the
payload
package
will
not
open
during
transportation.
YES
NO
8.
Are
there
any
dents,
scrapes,
or
scratches
that
make
the
payload
package's
structural
integrity
questionable
or
prevent
the
top
and
bottom
surfaces
from
being
parallel?
Deep
gouges,
scratches,
or
abrasions
over
wide
areas
are
not
acceptable.
If
top
and
bottom
surfaces
are
not
parallel,
this
would
indicate
that
the
package
is
warped.
Dents
should
be
less
than
¼
inch
deep
by
3
inches
long
and
between
½
inch
to
6
inches
wide.
All
other
dents
must
be
examined
to
determine
impact
of
structural
integrity.

Note:
Based
on
an
engineering
evaluation
performed
at
RFETS
it
has
been
determined
that
larger
dents
on
55­
gallon
drums
are
acceptable,
see
Section
A3.1.
YES
NO
9.
Is
there
discoloration
which
would
indicate
leakage
or
other
evidence
of
leakage
of
material
from
the
payload
package?
Examine
the
payload
package
regions
near
vents,
top
lid
fittings,
bottom
fittings,
welds,
seams
and
intersections
of
one
or
more
metal
sheets
or
plates.
Payload
packages
must
be
rejected
if
evidence
of
leakage
is
present.
YES
NO
10.
Is
the
payload
package
bulged?
For
the
purposes
of
this
examination,
bulging
is
indicated
by:
 
A
fairly
uniform
expansion
of
the
sidewalls,
bottom,
or
top
(
e.
g.,
in
the
case
of
a
drum,
either
the
top
or
bottom
surface
protrudes
beyond
the
planar
surface
of
the
top
or
bottom
ring,
 
A
protrusion
of
the
side
wall
(
e.
g.,
in
the
case
of
a
drum,
beyond
a
line
connecting
the
peaks
of
the
surrounding
rolling
hoops
or
a
line
between
a
surrounding
rolling
hoop
and
the
bottom
or
top
ring),
or
 
Expansion
of
the
sidewall
(
e.
g.,
in
the
case
of
a
drum,
such
that
it
deforms
any
portion
of
a
rolling
hoop).
YES
NO
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
319
APPENDIX
3
Page
3
of
4
A3.1
Allowable
Drum
Dents
RFETS
evaluation
of
structural
integrity
impacts
of
dents
in
55­
gallon
drums
is
documented
by
CALC­
000­
NA­
000672,
Dented
55
Gal.
Drum
Stress
Analysis;
as
concurred
with
by
CBFO
in
CBFO:
NTP:
RMK:
GS:
02­
2558:
UFC
5822.00,
CBFO
Review
of
the
Dented
55­
Gallon
Drums
Stress
Analysis.
Based
on
this
evaluation,
drums
with
dents
smaller
than
the
following
meet
DOT
7A
structural
integrity
criteria:

 
Drums
with
dents
¼
inch
deep
by
3
inches
long
and
between
½
inch
to
6
inches
wide
located
on
the
lid,
top
chime,
bottom,
bottom
chime,
or
side
of
the
drum
above
the
top
rolling
hoop
(
including
the
top
rolling
hoop
and
the
top
chime).
See
Area
1
as
shown
in
Figure
A3.1­
1.

 
Drums
with
a
single
dent
of
dimensions
8
inches
by
6
inches
by
2­
inches
deep,
or
less,
and
located
on
the
side
of
the
drum,
anywhere
below
the
top
rolling
hoop
(
including
the
two
lower
rolling
hoops
and
the
drum
seam)
and
above
the
bottom
chime.
See
Area
2
as
shown
in
Figure
A3.1­
1.

 
Drums
with
multiple
dents
that
are
grouped
together
such
that
the
outer
dimensions
of
the
group
of
dents
are
less
than
8
inches
by
6
inches
by
2
inches
deep,
and
located
on
the
side
of
the
drum,
anywhere
below
the
top
rolling
hoop
(
including
the
two
lower
rolling
hoops
and
the
drum
seam)
and
above
the
bottom
chime.
See
Area
2
as
shown
in
Figure
A3.1­
1.

 
Drums
with
multiple
dents
and
sizes
located
on
the
side
of
the
drum,
anywhere
below
the
top
rolling
hoop
(
including
the
two
lower
rolling
hoops
and
the
drum
seam)
and
above
the
bottom
chime,
with
a
combined
area
of
dents
less
than
50
square
inches,
and
each
dent
less
than
1
inch
deep.
See
Area
2
as
shown
in
Figure
A3.1­
1.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
320
APPENDIX
3
Page
4
of
4
Figure
A3.1­
1,
55­
Gallon
Drum
Side
View
55­
Gallon
Drum
Lid
(
Area
1)

Drum
Seam
Weld
(
Hidden)
Top
Rolling
Hoop
Bottom
Chime
(
Area
1)
Top
Chime
(
Area
1)

Lower
Rolling
Hoops
Area
1
Area
2
55­
Gallon
Drum
Bottom
(
Area
1)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
321
This
page
is
intentionally
blank
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
322
APPENDIX
4
NONDESTRUCTIVE
ASSAY
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
323
Appendix
4:
Table
of
Contents
Section
Page
APPENDIX
4:
TITLE
PAGE..................................................................................................
317
APPENDIX
4:
TABLE
OF
CONTENTS................................................................................
318
A4.0
NONDESTRUCTIVE
ASSAY....................................................................................
324
A4.1
Introduction
.....................................................................................................
324
A4.2
Radionuclide
Isotopic
Ratios
............................................................................
329
A4.2.1
Methods
for
Confirmation
of
Isotopic
Ratio
AK
................................
329
A4.2.2
AK
Documentation............................................................................
330
A4.3
Data
Quality
Objectives....................................................................................
334
A4.4
Quality
Control
................................................................................................
340
A4.4.1
General
Requirements
........................................................................
340
A4.4.2
NDA
QC
Requirements
.....................................................................
341
A4.5
Data
Management
............................................................................................
343
A4.5.1
Data
Review
and
Validation...............................................................
345
A4.5.2
Data
Reporting
..................................................................................
345
A4.5.3
Data
and
Records
Retention...............................................................
346
A4.6
Quality
Characteristics
Assessment
...................................................................
347
A4.6.1
Data
Accuracy...................................................................................
347
A4.6.2
Data
Precision....................................................................................
347
A4.6.3
Data
Representativeness.....................................................................
347
A4.6.4
Data
Completeness
............................................................................
347
A4.6.5
Data
Comparability............................................................................
348
A4.7
Document
Review,
Approval
and
Control
........................................................
314
TABLE
Table
A4.1­
1,
WIPP
Isotopes
......................................................................................
327
Table
A4.1­
2,
RFETS
NDA
Instrument
Qualification...................................................
327
Table
A4.1­
3,
RFETS
NDA
Operating
and
Data
Management
Procedures...................
328
Table
A4.2­
1,
Determination
of
Radionuclide
Isotopic
Ratios
......................................
333
Table
A4.3­
1,
Data
Quality
Objectives
for
Radioassay..................................................
338
Table
A4.3­
2,
RFETS
NDA
Qualification
Documents..................................................
338
Table
A4.3­
3,
Upper
Limits
for
%
RSD
vs.
Number
of
Replicates.................................
339
Table
A4.4­
1,
Range
of
Applicability
...........................................................................
342
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
324
A4.0
NONDESTRUCTIVE
ASSAY
A4.1
Introduction
RFETS
implements
a
variety
of
nondestructive
assay
(
NDA)
techniques
to
assay
TRU
waste
consisting
of
a
broad
range
of
waste
matrices
packaged
in
numerous
packaging
configurations.
RFETS
NDA
systems
include:

 
Tomographic
Gamma­
Ray
Scanner
(
TGS)
drum
counter
and
associated
Fixed
Energy
Response
Function
Analysis
with
Multiple
Efficiencies
(
FRAM)
gamma
isotopic
system
 
Passive/
active
neutron
drum
counter
and
associated
FRAM
gamma
isotopic
systems
 
Super
High
Efficiency
Neutron
drum
and
box
counter
(
SuperHENC)
and
SGEAS
gamma
isotopic
system
 
Multi­
purpose
passive/
active
neutron
crate
counter
(
MPCC)
and
GEAS
gamma
isotopic
system
The
FRAM01
gamma
isotopic
system
associated
with
the
passive/
active
neutron
drum
counter
(
PADC)
has
been
calibrated
and
qualified
to
measure
sludge
drum
85­
gallon
overpacks
in
a
stand­
alone
mode.
A
second
FRAM
system
is
also
associated
with
the
PADC,
however,
it
does
not
operate
in
a
stand­
alone
mode.

Several
NDA
systems
have
been
de­
activated
since
the
March
2003
WIPP
recertification
audit.
They
are:

 
Calorimeters
and
TRIFIDs
(
designated
as
AR02
[
deactivated
7/
21/
03],
AR03
[
deactivated
8/
20/
03],
AR06
[
deactivated
8/
20/
03],
AR07
[
deactivated
11/
20/
03],
P2
[
deactivated
10/
02/
03],
P3
[
deactivated
11/
12/
03],
P4
[
deactivated
8/
20/
03],
P5
[
deactivated
8/
20/
03],
P6
[
deactivated
10/
02/
03],
P8
[
deactivated
8/
20/
03],
and
P9
[
deactivated
7/
31/
03],
GPC1
[
deactivated
8/
20/
03],
T4
[
deactivated
9/
29/
03],
and
T5
[
deactivated
11/
12/
03])

 
TGS
can
counters
(
designated
as
371TGS02
,
371TGS03,
and
371TGS05
[
all
deactivated
7/
15/
03])

Other
NDA
systems
that
were
de­
activated
prior
to
the
March
2003
WIPP
recertification
audit,
but
after
the
May
17,
2002
certification
to
DOE/
WIPP­
02­
3122
are:

 
Calorimeters
(
designated
as
AR04,
P7,
and
P10)

 
Skid
mounted
TGS
Can
and
Drum
Counter
(
designated
as
371TGS01)
TRANSURANIC
(
TRU)
WASTE
1­
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VERSION
7
02/
12/
2004
PAGE
325
A4.1
Introduction
(
continued)

 
Building
569
TGS
Drum
Counter
(
designated
569TGS04)
(
this
counter
has
been
modified,
relocated,
re­
calibrated,
and
re­
qualified
as
a
new
NDA
system
designated
664TGS04).

RFETS
also
has
NDA
data
generated
from
several
other
NDA
systems,
that
are
no
longer
in
operation.
These
NDA
systems
are
certified
to
DOE/
WIPP­
069,
Revision
7,
Change
Notice
2
and
include:

 
Canberra
IQ3
Drum
Counter
 
Canberra
Passive
Neutron
Drum
Counter
 
Segmented
Gamma­
Ray
Scanner
(
SGS)
Drum
Counter
 
SGS
Can
Counters
 
Neutron
Multiplicity
Can
Counters
 
LANL
Mobile
TGS
Drum
Counter
 
Calorimeters
and
TRIFIDs
(
AR05,
AR08,
AR09,
and
P1).

The
Waste
Isolation
Pilot
Plant
(
WIPP)
requires
radiological
characterization
data
to:

 
track
the
WIPP
radionuclide
inventory,
by
isotopic
activity
and
mass,
for
those
radionuclides
listed
in
Section
3.3.1
of
the
WIPP­
WAC
(
i.
e.,
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs),

 
demonstrate
that
each
payload
package
disposed
of
at
the
WIPP
contains
TRU
waste
as
specified
in
Section
3.3.3
of
the
WIPP­
WAC
(
i.
e.,
waste
contains
greater
than
100
nCi/
g
of
TRU
radionuclides),
and
 
verify
that
applicable
transportation
and
facility
limits
on
individual
payload
packages
and
assemblies
for
FGE,
PE­
Ci,
and
decay
heat
are
not
exceeded,
as
specified
in
Sections
3.3.2,
3.3.4
and
3.3.6
of
the
WIPP­
WAC.

The
radioassay
process
quantifies
at
least
one
of
the
more
prevalent
radionuclides
known
to
be
present
in
the
waste.
The
remaining
listed
radionuclides
present
in
the
waste
in
significant
quantities
are
identified
by
direct
measurement
of
isotopic
ratios
as
discussed
in
Section
A4.2.
The
isotopic
ratios
are
then
used
to
quantify
radionuclides
based
on
the
assay
value.
Table
A4.1­
1,
WIPP
Isotopes,
lists
the
RFETS
NDA
systems
that
are
used
to
assay
TRU
waste
and
describes
how
each
of
the
WIPP­
tracked
radionuclides
will
be
quantified.
TRANSURANIC
(
TRU)
WASTE
1­
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008­
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001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
326
A4.1
Introduction
(
continued)

The
requisite
data
on
isotopic
ratios
and
quantities
are
derived
from
AK
(
see
Section
A4.2),
radioassay
or
both
using
CBFO
approved
NDA
techniques,
instruments
and
procedures.
RFETS
has
technically
justified
that
the
AK
and/
or
radioassay
techniques,
instruments
and
procedures
used:

 
are
appropriate
for
the
specific
waste
stream
and
waste
content
code
descriptions
being
assayed,
and
 
result
in
unbiased
values
for
the
cumulative
activity
and
mass
of
the
WIPP
radionuclide
inventory.

This
justification
is
contained
in
the
instrument­
specific
qualification
plans
listed
in
Table
A4.1­
2,
RFETS
NDA
Instrument
Qualification
NDA
equipment
is
operated
and
data
managed
in
accordance
with
approved
written
operating
procedures.
Table
A4.1­
3,
RFETS
NDA
Operating
and
Data
Management
Procedures,
lists
the
operating
and
data
management
procedures
for
RFETS
NDA
systems.

Existing
radioassay
data
collected
prior
to
the
implementation
of
a
quality
assurance
program
pursuant
to
40
CFR
§
194.22(
a)(
1)
may
only
be
qualified
in
accordance
with
an
alternate
methodology
that
is
approved
by
CBFO
and
employs
one
or
more
of
the
following
methods:

 
peer
review
in
accordance
with
NRC
NUREG­
1297,
Peer
Review
for
High­
Level
Nuclear
Waste
Repositories,

 
corroborating
data,

 
confirmatory
testing
(
i.
e.,
testing
made
on
a
representative
sub­
population
of
payload
packages
within
a
waste
stream),
or
 
demonstrating
the
equivalence
of
an
alternate
QA
program
as
described
in
the
QAPD,
Section
5.4.

Proposals
for
alternative
approaches
to
identification
and
quantification
of
radioisotopes
(
e.
g.,
qualification
of
isotopic
ratio
AK
on
a
waste
stream
basis)
must
be
submitted
to
CBFO
for
review
and
approval.
CBFO
will
report
such
proposals
to
EPA
for
consideration
prior
to
issuing
approval.
TRANSURANIC
(
TRU)
WASTE
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001
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7
02/
12/
2004
PAGE
327
Table
A4.1­
1,
WIPP
Isotopes
NDA
SYSTEMS
241Am
238Pu
239Pu
240Pu
242Pu
233U
234Ua
238U
90Srb
137Cs
440
PADC
Meas.
Calc.
Meas.
Meas.
Calc.
Meas
Calc.
Meas.
Calc
Meas
SuperHENC
Meas.
Calc.
Meas.
Meas.
Calc.
Meas
Calc.
Meas.
Calc
Meas
TGS
Meas.
Meas.
Meas.
Meas.
Calc.
Meas
Calc.
Meas.
Calc
Meas
MPCC
Meas.
Calc.
Meas.
Meas.
Calc.
Meas
Calc.
Meas.
Calc
Meas
FRAM
Meas.
Meas.
Meas.
Meas.
Calc.
Meas
Calc.
Meas.
Calc
Meas
a.
As
described
in
RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information,
234U
was
not
processed
at
RFETS,
however,
it
is
present
in
small
quantities
in
enriched
uranium
(
EU)
and
depleted
uranium
(
DU).
Since
none
of
the
counters
are
able
to
detect
234U
in
small
quantities,
234U
is
calculated
by
a
controlled
spreadsheet
based
upon
the
estimated
percent
of
234U
present
in
each
measurement,
with
the
ITR
having
first
determined
whether
the
uranium
is
present
as
enriched
(
EU)
or
depleted
(
DU).
The
ITR
determination
is
reviewed
by
the
Technical
Supervisor
to
ensure
accuracy
and
technical
defensibility.
b.
The
RFETS
NDA
systems
are
not
capable
of
directly
measuring
the
amount
of
90Sr
that
may
be
present
in
a
waste
package.
Instead,
RFETS
has
developed
a
scaling
factor
that
allows
the
amount
of
90Sr
to
be
calculated
based
on
a
measured
137Cs
value.
The
derivation
and
application
of
this
scaling
factor
is
described
in
KHNDA2002
LLD,
Technical
Report
for
the
Determination
of
Lower
Limit
of
Detection
(
LLDs)
for
WIPP
and
Other
Reported
Isotopes
for
NDA
Measurement
Systems.

Table
A4.1­
2,
RFETS
NDA
Instrument
Qualification
NDA
SYSTEMS
Qualification
Plans
Cal/
Gamma
Rocky
Flats
Environmental
Technology
Site
Non­
Destructive
Assay
Calorimetry
and
Gamma
Spectrometry
Laboratories
Calorimeter
Qualification
Plan
(
cancelled
as
of
November
12,
2003,
these
systems
are
no
longer
active.)
440
PADC
BII­
8215­
C&
VP­
001,
Building
569
Passive/
Active
Drum
Counter
Calibration
and
Validation
Plan,
Instrument
Control
Number
569PADC001
(
this
counter
has
been
moved
to
Building
440;
calibration
verification
has
been
performed)
KH­
NDA2003­
CALVER­
440PADC01,
Calibration
Verification
Plan
for
the
Newly
Relocated
Building
440
Imaging
Passive/
Active
Neutron
Drum
Counter
(
PADC),
Instrument
Control
Number
440PADC01
SuperHENC
Super
High
Efficiency
Neutron
Counter
Calibration
and
Validation
Plan,
Instrument
Control
Number
984SHENC01
TGS
00­
NDA­
TGS­
001,
Qualification
Plan
for
the
Skid
Mounted
Tomographic
Gamma
Scanner
(
TGS)
(
cancelled,
as
of
October
30,
2002,
this
counter
is
no
longer
active)
00­
NDA­
TGS­
002,
Qualification
Plan
for
the
371TGS02
Tomographic
Gamma
Scanner
(
TGS)
Building
371
(
cancelled,
as
of
July
15,
2003
this
counter
is
no
longer
active.)
00­
NDA­
TGS­
003,
Qualification
Plan
for
the
569TGS04
Tomographic
Gamma
Scanner
(
TGS)
Building
569
(
cancelled
as
of
August
1,
2002,
replaced
by
KH­
NDA2002­
CAL/
QUAL­
664TGS04,
see
below)
00­
NDA­
TGS­
004,
Qualification
Plan
for
the
371TGS05
Tomographic
Gamma
Scanner
(
TGS)
Building
371
(
cancelled,
as
of
July
15,
2003
this
counter
is
no
longer
in
service.)
KH­
NDA2002­
CAL/
QUAL­
664TGS04,
Calibration
and
Qualification
Plan
for
the
Newly
Relocated
Building
664
Tomographic
Gamma
Scanning
(
TGS)
Drum
Counter,
Instrument
Control
Number
664TGS04
MPCC
Qualification
Plan
for
Building
664
Multipurpose
Crate
Counter
(
MPCC)
Instrument
Identification
Number
664MPCC01
FRAM
KH­
NDA2003­
CAL/
QUALP­
440FRAM01,
Calibration
and
Confirmation
Plan
for
the
Building
440
FRAM
Gamma
Spectroscopy
System,
Instrument
Control
Number
440FRAM01
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
328
Table
A4.1­
3,
RFETS
NDA
Operating
and
Data
Management
Procedures
NDA
SYSTEMS
Operating
Procedures
Cal/
Gamma
PRO­
1298­
ISOAN­
371,
Gamma­
Ray
Isotopic
Analysis
of
Plutonium­
Bearing
Solids
in
Building
371
Cal/
Gamma
Laboratory
(
procedure
cancelled
and
the
systems
inactive
as
of
November
12,
2003.)
PRO­
1299­
AIRBATH­
371,
Calorimetry
Using
the
ANTECH
Airbath
System
in
Building
371
Cal/
Gamma
Laboratory
(
procedure
cancelled
and
the
systems
inactive
as
of
November
12,
2003.)
440
PADC
PRO­
666­
PADC440,
Operating
Building
440
Passive/
Active
Drum
Counter
PRO­
666­
PADC569,
Operating
Building
569
Passive/
Active
Drum
Counter
(
cancelled
as
of
March
10,
2003
 
replaced
by
PRO­
666­
PADC440,
Operating
Building
440
Passive/
Active
Drum
Counter)
PRO­
1092­
FRAM­
440,
Operating
Building
440
FRAM
Gamma
Spectroscopy
System
PRO­
1092­
FRAM­
569,
Operating
Building
569
FRAM
Gamma
Spectroscopy
System
(
cancelled
as
of
March
10,
2003
 
replaced
by
PRO­
1092­
FRAM­
440,
Operating
Building
440
FRAM
Gamma
Spectroscopy
System)
SuperHENC
PRO­
957­
SuperHENC,
Operating
the
Super
High
Efficiency
Neutron
Coincidence
(
SuperHENC)
Counter
Mobile
Assay
System
TGS
PRO­
1631­
TGS­
01,
Setup
and
Calibration
of
Building
664
Drum
Tomographic
Gamma
Scanner
(
TGS)
PRO­
1632­
TGS­
02,
Operating
Building
664
Drum
Tomographic
Gamma
Scanner
(
TGS)
PRO­
1386­
TGS­
371,
Setup
&
Calibration
of
Building
371
Can
Tomographic
Gamma
Scanner
(
TGS)
(
procedure
cancelled
and
the
can
counters
inactive
as
of
August
13,
2003.)
PRO­
1392­
TGS­
371,
Operating
Building
371
Tomographic
Gamma
Scanning
(
TGS)
Can
Counters
(
procedure
cancelled
and
the
can
counters
inactive
as
of
August
13,
2003.)

MPCC
PRO­
1433­
MPCC­
664,
Operating
the
Multipurpose
Crate
Counter
(
MPCC)
at
Building
664
FRAM
PRO­
1092­
FRAM­
440,
Operating
the
Building
440
FRAM
Gamma
Spectroscopy
System
REVIEW
LEVEL
NDA
Data
Management
Procedures
Data
Generation
PRO­
845­
NDA­
008,
Data
Review,
Verification,
and
Validation
for
Nondestructive
Assay
(
NDA)
Measurement
Systems
Data
Generation
PRO­
1302­
WIPPDATA­
371,
Data
Review
and
Validation
for
Calorimetric
Assay
for
WIPP­
TRU
Waste
Characterization
Program
in
Building
371
Cal/
Gamma
Laboratory
(
procedure
to
be
deactivated
in
March
2004,
systems
inactive
as
of
November
12,
2003.)
Project
PRO­
940­
WIPP­
010,
WIPP
TRU
Waste
Characterization
Project
Level
Data
Review
and
Reporting
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
329
A4.2
Radionuclide
Isotopic
Ratios
Establishing
isotopic
ratios
for
use
in
quantifying
radionuclides
is
performed
by
direct
measurement
of
the
packages
using
WIPP­
certified
systems.
RFETS
may
opt
to
qualify
AK
as
permitted
by
40
CFR
§
194.22(
b)
by
performing
confirmatory
testing
using
WIPP­
certified
radioassay
systems.
When
RFETS
performs
direct
measurements
of
isotopic
ratios,
it
is
expected
that
all
packages
in
the
waste
stream
are
measured,
with
the
understanding
that,
in
some
cases,
valid
data
may
not
be
obtainable
for
given
packages
for
technical
reasons
(
e.
g.,
lack
of
sufficient
signal
or
poor
counting
statistics).
All
such
instances
are
documented
and
appropriately
dispositioned
by
the
Measurements
organization.
For
those
few
waste
packages
for
which
direct
measurement
does
not
yield
useable
isotopic
ratio
information,
AK
may
be
used.
Table
A4.2­
1
displays
which
RFETS
NDA
systems
routinely
measure
the
isotopic
ratios
for
each
package
and
which
use
confirmatory
testing.
Confirmatory
testing
is
performed
by
comparing
the
ratio
of
the
measured
240Pu
results
to
the
measured
239Pu
results
to
a
pre­
established
acceptance
criteria.
Cases
where
confirmatory
testing
fails
to
confirm
AK
isotopic
ratios
are
documented
in
a
nonconformance
report
(
NCR)
in
accordance
with
1­
A65­
ADM­
15.01,
Control
of
Nonconforming
Items.

A4.2.1
Methods
for
Confirmation
of
Isotopic
Ratio
AK
Coincident
with
the
May
17,
2002
effective
date
of
the
CH­
WAC
(
DOE/
WIPP­
02­
3122,
Revision
0),
RFETS
has
implemented
an
enhanced
program
to
measure
and/
or
perform
confirmation
measurements
of
the
10
radionuclides
listed
in
Section
3.3.1
of
the
CH­
WAC
(
DOE/
WIPP­
02­
3122,
Revision
0).
RFETS
no
longer
relies
on
acceptable
knowledge
as
the
sole
mechanism
to
determine
that
certain
radionuclides
are
not
present
in
RFETS
TRU
waste.
RFETS
now
measures
233U
and
137Cs
to
confirm
that
these
radionuclides
and
90Sr
are
not
present
in
its
TRU
waste
streams.
Any
reported
results
for
these
isotopes
will
be
handled
as
a
discrepancy
in
accordance
with
Section
A4.2.2.3.

As
a
minimum,
to
confirm
existing
AK
data,
it
is
necessary
to
compare
ratios
of
the
two
most
prevalent
radionuclides
in
the
isotopic
mix.
For
weapons
grade
plutonium,
these
are
typically
239Pu
and
240Pu.

Because
RFETS
has
performed
chemical
operations
to
separate
241Am
from
plutonium,
it
is
not
possible
to
use
AK
to
relate
241Am
to
a
measurement
of
a
plutonium
isotope.
Consequently,
every
RFETS
NDA
technique
directly
measures
the
241Am
content
in
each
waste
package.

For
weapons
grade
waste,
isotopic
ratio
values
for
238Pu
can
be
assumed
to
be
valid
in
AK
data
if
the
values
for
239Pu
and
240Pu
have
been
confirmed.
Because
242Pu
cannot
be
measured
using
NDA
methods,
the
contribution
of
242Pu
isotopic
ratio
is
calculated
by
correlation
techniques.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
330
A4.2.1
Methods
for
Confirmation
of
Isotopic
Ratio
AK
(
continued)

Every
RFETS
NDA
system
used
to
assay
TRU
waste
directly
measures
the
235U
content
of
each
waste
package.
If
235U
is
measured
in
a
waste
package,
then
PRO­
845­
NDA­
008,
Data
Review
and
Validation
for
Nondestructive
Assay
Measurement
Systems,
directs
the
Independent
Technical
Reviewer
to
determine
whether
the
measured
235U
is
part
of
Enriched
Uranium
(
EU)
or
Depleted
Uranium
(
DU).
Once
the
uranium
is
determined
to
be
either
EU
or
DU,
then
AK
information
regarding
the
relative
abundance
of
234U,
235U,
and
238U
in
EU
and
DU
is
used
to
calculate
both
234U
and
238U
concentrations
based
on
the
measured
235U
results;
however,
all
relevant
information
must
be
included
in
the
AK
record.

All
currently
operating
RFETS
NDA
systems
directly
measure
233U
and
137Cs.
RFETS
NDA
systems
are
not
capable
of
directly
measuring
90Sr.
Instead,
RFETS
has
developed
a
scaling
factor
that
allows
the
amount
of
90Sr
to
be
calculated
based
on
a
measured
137Cs
value.
The
derivation
and
application
of
this
scaling
factor
is
described
in
KH­
NDA2002­
LLD,
Technical
Report
for
the
Determination
of
Lower
Limit
of
Detection
(
LLDs)
for
WIPP
and
Other
Reported
Isotopes
for
NDA
Measurement
Systems.

A4.2.2
AK
Documentation
The
use
of
AK
information
concerning
the
radiological
composition
of
a
waste
stream
will
be
documented
either
in
the
AK
summary
report
for
the
waste
characterization
of
the
waste
stream
or
in
another
controlled
document
approved
by
the
TWCP
Site
PM.
Should
this
information
be
contained
in
AK
package(
s)
prepared
to
meet
other
general
waste
characterization
requirements,
it
need
not
be
duplicated
in
other
controlled
documents
that
address
the
radiological
properties
of
the
waste
stream.
RFETS
AK
information
is
assembled
and
maintained
in
accordance
with
PRO­
484­
WIPP­
003,
Collection,
Review,
and
Confirmation
of
Acceptable
Knowledge
Documentation.
The
following
discussion
is
included
for
the
sake
of
completeness.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
331
A4.2.2.1
Required
Elements
This
section
identifies
the
required
radiological
information
that
RFETS
must
maintain
for
a
waste
stream.
RFETS
may
use
AK
to
delineate
the
distribution
of
the
10
WIPP­
tracked
radioisotopes
within
a
TRU
waste
stream
and
the
presence
or
absence
of
isotopes.
The
type
and
quantity
of
supporting
documentation
may
vary
by
waste
stream
and
shall
be
compiled
in
a
written
record
that
shall
include
a
summary
identifying
all
sources
of
information
used
to
delineate
the
waste
stream's
isotopic
distribution.
The
basis
and
rationale
for
the
delineation
shall
be
clearly
summarized
in
an
AK
report
and
traceable
to
referenced
documents.
Assumptions
made
in
this
delineation
shall
be
identified.
The
following
information
shall
be
included
as
part
of
the
AK
written
record:

 
map
of
the
site
with
the
areas
and
facilities
involved
in
TRU
mixed
waste
generation,
treatment,
and
storage
identified;

 
facility
mission
description
as
related
to
radionuclide­
bearing
materials
and
their
management,
e.
g.,
routine
weapons
production,
fuel
research
&
development
and
experimental
processes;

 
description
of
the
specific
site
locations
(
such
as
the
area
or
building)
and
operations
relative
to
the
isotopic
composition
of
the
TRU
wastes
they
generated,
e.
g.,
plutonium
recovery,
weapons
fabrication,
pyrochemical
operations
and
waste
incineration;

 
waste
identification
or
categorization
schemes
used
at
the
facility
relevant
to
the
waste
material's
isotopic
distribution,
e.
g.,
the
use
of
codes
that
correlate
to
a
specific
isotopic
distribution,
and
a
description
of
the
isotopic
composition
of
each
waste
stream;

 
information
regarding
the
waste's
physical
and
chemical
composition
that
could
affect
the
isotopic
distribution,
e.
g.,
processes
used
to
remove
ingrown
241Am
or
alter
its
expected
contribution
based
solely
on
radioactive
decay
kinetics;

 
statement
of
all
numerical
adjustments
applied
to
derive
the
material's
isotopic
distribution,
e.
g.,
scaling
factors,
decay/
ingrowth
corrections
and
secular
equilibrium
considerations;
and
 
specification
of
the
isotopic
ratios
for
the
10
WIPP­
tracked
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
and,
if
applicable,
the
radionuclides
that
comprise
95%
of
the
radiological
hazard
on
a
waste
stream,
waste
stream
subpopulation,
or
package
basis.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
332
A4.2.2.2
Supplemental
AK
Information
RFETS
shall
obtain
supplemental
AK
information,
dependent
on
availability.
The
amount
and
type
of
this
information
cannot
be
mandated,
but
RFETS
shall
collect
information
as
appropriate
to
support
the
Site's
contention
regarding
the
waste's
isotopic
distribution.
This
information
will
be
documented
in
RF/
RMRS­
97­
018,
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information.

A4.2.2.3
Discrepancy
Resolution
If
there
is
a
discrepancy
between
AK
information
related
to
isotopic
ratios
or
composition,
RFETS
will
evaluate
the
sources
of
the
discrepancy
to
determine
if
the
discrepant
information
is
credible.
Discrepancies
between
AK
information
related
to
isotopic
ratios
or
composition
will
be
evaluated
by
the
Measurements
organization
and
reported
to
the
TRU
Waste
project
office
in
accordance
with
PRO­
845­
NDA­
008.
Information
that
is
not
credible
or
information
that
is
limited
in
its
applicability
to
WIPP
characterization
will
be
identified
as
such
and
the
reasons
for
dismissing
it
will
be
justified
in
writing.
Limitations
concerning
the
information
will
be
documented
in
the
AK
record
and
summarized
in
the
AK
report.
In
the
event
that
the
discrepancy
cannot
be
resolved,
RFETS
will
perform
direct
measurements
for
the
impacted
population
of
packages.

If
discrepancies
result
in
a
change
to
the
original
determinations,
the
AK
will
be
updated
in
accordance
with
PRO­
484­
WIPP­
003,
Collection,
Review,
and
Confirmation
of
Acceptable
Knowledge
Documentation.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
333
Table
A4.2­
1,
Determination
of
Radionuclide
Isotopic
Ratios
NDA
Systems
Method
for
Determining
Radionuclide
Isotopic
Ratios
440
PADC
Confirmation
Testing
SuperHENC
Confirmation
Testing
TGS
Measurement
MPCC
Confirmation
Testing
FRAM
Measurement
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
334
A4.3
Data
Quality
Objectives
The
data
quality
objectives
for
WIPP
certifiable
radiological
characterization
data
are
established
in
Section
3.3
of
the
WIPP­
WAC.
They
are
summarized
in
Table
A4.3­
1
as
they
apply
to
individual
payload
packages.

There
are
no
stipulated
data
quality
objectives
for
PE­
Ci
or
individual
isotope
activities
(
except
as
they
impact
the
requirements
listed
above).
However,
at
a
minimum,
radioassay
programs
must
be
capable
of
identifying
and
reporting
the
presence
or
absence
of:

 
the
ten
radionuclides
identified
in
WIPP­
WAC
Section
3.3.1
for
tracking
of
the
WIPP
radionuclide
inventory,

 
235U,
in
order
to
calculate
FGE,
as
required
in
WIPP­
WAC
Section
3.3.2
for
compliance
with
transportation
requirements,
and
 
other
radionuclides
whose
presence
contribute
to
95%
of
the
radioactive
hazard,
as
specified
in
WIPP­
WAC
Section
3.3.1,
for
compliance
with
transportation
requirements.

In
support
of
the
above
requirements,
RFETS
must
evaluate,
document
and
technically
justify
the
following
determinations.

Lower
Limit
of
Detection:
The
LLD
for
each
radioassay
system
must
be
determined.
Instruments
performing
TRU/
low­
level
waste
discrimination
measurements
must
have
an
LLD
of
100
nCi/
g
or
less.
RFETS
specific
environmental
background
and
package
specific
interferences
must
be
factored
into
LLD
determinations.
The
LLD
is
that
level
of
radioactivity
which,
if
present,
yields
a
measured
value
greater
than
the
critical
level
with
a
95%
probability,
where
the
critical
level
is
defined
as
that
value
which
measurements
of
the
background
will
exceed
with
5%
probability.
Because
the
LLD
is
a
measurement­
based
parameter,
it
is
not
feasible
to
calculate
LLDs
for
radionuclides
that
are
not
determined
primarily
by
measurement
(
e.
g.,
90Sr).
In
such
cases,
RFETS
shall
derive
the
equivalent
of
an
LLD,
(
i.
e.,
a
reporting
threshold
for
a
radionuclide(
s),
when
it
is
technically
justified).
This
value
may
be
based
on
decay
kinetics,
scaling
factors
or
other
scientifically
based
relationships
and
must
be
adequately
documented
in
site
records.
For
purposes
of
reporting
radionuclide
data
in
the
WWIS,
this
value
will
be
the
equivalent
of
an
LLD.
The
description
of
the
methodology
used
to
determine
the
LLD
for
each
radionuclide,
or
a
discussion
of
why
a
LLD
is
not
technically
justified
for
a
specific
radionuclide
is
contained
in
KH­
NDA2002­
LLD,
Technical
Report
for
the
Determination
of
Lower
Limit
of
Detection
(
LLDs)
for
WIPP
and
Other
Reported
Isotopes
for
NDA
Measurement
Systems.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
335
A4.3
Data
Quality
Objectives
(
continued)

Total
Measurement
Uncertainty:
The
method
used
to
calculate
the
TMU
for
the
quantities
in
Table
A4.3­
1
must
be
documented
and
technically
justified
for
each
CBFO
certified
radioassay
system.
Compliance
with
this
requirement
will
be
evaluated
in
reviews
of
the
TMU
documentation
package
for
each
assay
system
by
CBFO.
The
discussions
of
TMU
are
presented
in
either
a
stand
alone
TMU
Report
or
included
in
the
Qualification
Report
for
each
assay
system.
Table
A4.3­
2,
RFETS
NDA
Qualification
Documents,
list
the
Calibration,
Validation,
Qualification,
and
TMU
Reports
for
each
system.

Calibration
Procedures
and
Frequencies:
Each
radioassay
measurement
system
shall
be
calibrated
before
initial
use.
During
calibration
or
re­
calibration,
system
correction
factors
shall
be
established
and
algorithms
adjusted
such
that
the
value
of
%
R
is
set
equal
to
100%,
i.
e.,
the
system
is
calibrated
to
100%
R.
The
range
of
applicability
of
system
calibrations
is
specified
in
system­
specific
qualification
reports
(
See
Table
A4­
3.2,
RFETS
NDA
Qualification
Documents).
The
matrix/
source
surrogate
waste
combination(
s)
used
for
calibration
shall
be
representative
of
the
 
activity
range(
s)
or
gram
loading(
s),
and
 
relevant
waste
matrix
characteristics
(
e.
g.,
densities,
moderator
content,
container
size)
planned
for
measurement
by
the
system.

Calibration(
s)
are
performed
in
accordance
with
consensus
standards,
when
such
standards
exist.
If
consensus
standards
are
not
used,
full
documentation
of
the
calibration
technique
must
be
provided
to
and
approved
by
CBFO
prior
to
performing
WIPP
related
assays.
Primary
calibration
standards
are
obtained
from
suppliers
maintaining
a
nationally
accredited
measurement
program.
When
primary
standards
are
not
available,
the
standards
used
are
correlated
with
primary
standards
obtained
from
a
nationally
accredited
measurement
program.

NDA
system
calibration
is
documented
in
the
system­
specific
Qualification
Plan
(
See
Table
A4.1­
2,
RFETS
NDA
Instrument
Qualification)
and
Qualification
Report
(
See
Table
A4.3­
2
RFETS
NDA
Qualification
Documents).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
336
A4.3
Data
Quality
Objectives
(
continued)

Calibration
Verification:
Notwithstanding
the
need
to
calibrate
individual
components
for
replacement,
changes
or
adjustments
(
e.
g.,
energy
calibration
of
a
detector),
verification
of
the
radioassay
measurement
system's
calibration
shall
be
performed
after
any
one
of
the
following
occurs:

 
major
system
repairs
and/
or
modifications
 
replacement
of
the
measurement
system's
components,
(
e.
g.,
detector,
neutron
generator
or
supporting
electronic
components)
that
have
the
capacity
to
affect
data
 
significant
changes
to
the
system's
software
 
relocation
of
the
system.

Calibration
verification
shall
consist
of
demonstrating
that
the
system
is
within
the
range
of
acceptable
operation.
Secondary
standards
can
be
used
for
the
calibration
verification
if
their
performance
has
been
correlated
with
calibration
standards.
If
a
verification
of
the
measurement
system's
calibration
or
other
test
demonstrates
that
the
system's
response
has
significantly
changed,
a
re­
calibration
of
the
system
shall
be
performed.

NDA
system
calibration
verification
at
RFETS
is
performed
using
a
graded
approach.
For
minor
changes
to
the
system
(
i.
e.,
replacement
of
components,
minor
repairs,
changes
to
the
system
software),
calibration
verification
generally
consists
of
performing
measurement
control
activities
such
as
measuring
daily
working
standards
several
times
and
documenting
in
the
MC&
A
monthly
measurement
control
report.
For
more
significant
changes
to
the
system
(
i.
e.,
system
relocation,
or
major
modifications
to
the
system),
calibration
verification
is
documented
in
both
a
calibration
verification
plan
and
a
calibration
verification
report.
These
plans
and
reports
are
subjected
to
the
same
type
of
review
and
oversight
as
is
done
for
instrument
qualification.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
337
A4.3
Data
Quality
Objectives
(
continued)

Calibration
Confirmation:
In
order
to
confirm
that
the
calibration
of
the
NDA
system
was
correctly
established,
the
accuracy
and
precision
of
the
system
are
determined
after
each
calibration
or
re­
calibration
by
performing
replicate
measurements
of
a
non­
interfering
matrix.
Calibration
confirmation
replicate
measurements
are
performed
on
containers
of
the
same
nominal
size
as
those
in
which
actual
waste
is
assayed
and
according
to
approved
waste
assay
procedures.
The
number
of
replicate
measurements
performed
shall
be
documented
and
technically
justified.
The
replicate
measurements
are
performed
using
nationally
recognized
standards,
or
certified
standards
derived
from
nationally
recognized
standards
that
span
the
range
of
use;
meaning
confirmation,
at
a
minimum,
the
lower
and
upper
thirds
of
the
range
of
operation.
The
standards
used
to
calculate
accuracy
are
not
the
same
as
those
used
for
the
system
calibration.
Accuracy
is
reported
as
percent
recovery
(%
R).
The
applicable
range
for
accuracy
shall
not
exceed
±
30%
on
a
non­
interfering
matrix.
Precision
is
reported
as
percent
relative
standard
deviation
(%
RSD).
The
%
RSD
shall
not
exceed
the
values
listed
in
Table
A4.3­
3
for
the
corresponding
number
of
replicate
measurements
in
a
non­
interfering
matrix.

Measurement
facilities
may
develop
alternate
limits
for
accuracy
and
precision
subject
to
approval
by
CBFO
prior
to
certification
of
waste.

NDA
system
calibration
confirmation
is
documented
in
the
system­
specific
Qualification
Plan
(
See
Table
A4.1­
2,
RFETS
NDA
Instrument
Qualification)
and
the
Qualification
Report
(
See
Table
A4.3­
2
RFETS
NDA
Qualification
Documents).
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
338
Table
A4.3­
1,
Data
Quality
Objectives
for
Radioassay
REQUIREMENT
DQO
CONFIDENCEa
TRU
 ­
activity
concentration
>
100
nCi/
g
A
>
LLD
NA%

Fissile
mass
<
200
FGE
(
55­
gallon
drums)
FGE
+
2 TMU(
FGE)
<
200
97.5
%

Fissile
mass
<
325
FGE
(
SWBs
and
TDOPs)
FGE
+
2 TMU(
FGE)
<
325
97.5
%

Decay
heat
<
TRAMPAC
limit
DH
+
1 TMU(
DH)
<
LTRAMPAC
84
%

a
Confidence
means
the
statistical
level
of
confidence
that
the
limit
is
exceeded
or
not
exceeded
depending
on
the
requirements
of
the
individual
data
quality
objectives.
The
confidence
is
derived
from
the
specified
DQOs
which
assume
contributions
to
TMU
are
normally
distributed.

Table
A4.3­
2,
RFETS
NDA
Qualification
Documents
NDA
SYSTEMS
Qualification
Documents
Cal/
Gamma
Calorimeter­
specific
Qualification
Reports
(
Instrument
numbers
AR02
through
AR09,
P2
through
P10)
(
cancelled
as
of
deactivation
dates,
as
listed
in
Section
A4.0)
Calorimetric
Assay
Total
Measurement
Uncertainty
and
Total
Bias
(
cancelled
as
of
November
12,
2003;
systems
no
longer
active.)
440
PADC
KH­
NDA2002­
QUAL­
569PADC01,
Revised
WIPP­
Related
Calibration
and
Qualification
Report
for
Extension
of
the
Qualified
Plutonium
Mass
and
Matrix
Ranges
for
the
Building
569
Passive­
Active
Neutron
Drum
Counter,
569PADC01
(
includes
TMU
report)
(
this
counter
has
been
moved
to
Building
440;
calibration
verification
has
been
performed)
KH­
NDA2003­
CALVER­
RPT­
440PADC01,
Calibration
Verification
Report
for
the
Newly
Relocated
Building
440
Imaging
Passive/
Active
Neutron
Drum
Counter
(
PADC),
Instrument
Control
Number
440PADC01
SuperHENC
Calibration
and
Qualification
Report
Package
for
SuperHENC
Mobile
Assay
Trailer,
Instrument
Identification
Number
440SHENC01
(
includes
TMU
Report)
KH­
NDA2002­
QUAL­
440SHENC001(
DRUM),
Supplemental
Qualification
Report
for
the
Radioassay
of
Waste
Packaged
in
55­
Gallon
Drums
Using
the
Super
High
Efficiency
Neutron
Counter
(
SuperHENC)
440SHENC001
FRAM
KH­
NDA2003­
QUAL­
440FRAM01,
Calibration
and
Qualification
Report
for
the
Building
440
FRAM
Gamma
Spectroscopy
System,
Instrument
Control
Number
440FRAM01
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
339
Table
A4.3­
2,
RFETS
NDA
Qualification
Documents
(
continued)

NDA
SYSTEMS
Qualification
Documents
TGS
KH­
NDA2001­
CAL­
371TGS02,
Calibration
and
Qualification
Report
for
the
ANTECH
Tomographic
Gamma
Scanning
(
TGS)
Can
Counter
371TGS02
After
Installation
of
ANTECH
MasterScan
and
MasterAnalysis
Software
(
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.)
KH­
NDA2001­
RECAL­
371TGS03,
Calibration
and
Qualification
Report
for
the
Conversion
of
the
ANTECH
TGS
Can
Counter
371TGS03
from
DAC.
TGS
Data
Acquisition
to
MasterScan
Data
Collection
Software
(
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.)
Determination
of
the
Total
Measurement
Uncertainty
for
the
RFETS
Skid
Mounted
TGS
and
Can
TGS
(
cancelled
as
of
July
15,
2003,
counters
out
of
service)
KH­
NDA2003­
CAL/
QUALR­
664TGS04,
Calibration
and
Qualification
Report
for
the
ANTECH
TGS
Drum
Counter
664TGS04
(
includes
TMU)
KH­
NDA2001­
CAL­
371TGS05,
Calibration
and
Qualification
Report
for
the
ANTECH
Tomographic
Gamma
Scanning
(
TGS)
Can
Counter
371TGS05
(
This
document
is
inactive
and
as
of
July
15,
2003
this
counter
is
no
longer
in
service.)
MPCC
KH­
NDA2002­
QUALR­
664MPCC01,
Calibration
and
Qualification
Report
for
the
Multi­
Purpose
Crate
Counter
(
MPCC)
Imaging
Passive­
Active
Neutron
and
Gamma
Energy
Analysis
(
IPAN/
GEA)
System,
Instrument
Control
Number
664MPCC01
(
includes
calibration
and
TMU)

Table
A4.3­
3,
Upper
Limits
for
%
RSD
vs.
Number
of
Replicates
NUMBER
OF
REPLICATES
2
3
4
5
6
7
8
9
10
11
12
13
14
15
Max
%
RSD
1.8
6.6
10.0
12.3
14.0
15.2
16.2
17.1
17.7
18.3
18.8
19.3
19.7
20.0
Note:
The
values
listed
are
derived
from
the
measured
standard
deviation
of
the
replicate
measurements
using
*
100%
<
*
100%
where
s
is
the
measured
standard
deviation,
n
is
the
number
of
replicates,
µ
is
the
true
value,
 2
0.05,
n­
1
is
the
critical
value
for
the
upper
5%
tail
of
a
one
sided
chi­
squared
distribution
with
n­
1
degrees
of
freedom,
and
0.292
corresponds
to
a
95%
upper
confidence
bound
on
the
true
system
precision
limit
of
29.2%.
s
µ
(
0.292)*
 2
0.05,
n­
1
n­
1
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
340
A4.4
Quality
Control
To
ensure
that
data
of
known
and
documented
quality
are
generated
RFETS
implements
a
documented
QA
program.
Any
radioassay
technique
used
for
TRU
waste
must
be
performed
in
accordance
with
calibration
and
operating
procedures
that
have
been
written,
approved,
and
controlled
by
the
site.
The
NDA
operating
procedures
are
listed
in
Table
A4.1­
3,
RFETS
NDA
Operating
and
Data
management
Procedures.
The
RFETS
QA
program
specifies
qualitative
and
quantitative
acceptance
criteria
for
the
QC
checks
of
this
program
and
corrective
action
measures
to
be
taken
when
these
criteria
are
not
satisfied.

A4.4.1
General
Requirements
Radioassay
Training:
Only
appropriately
trained
and
qualified
personnel
are
allowed
to
perform
radioassay
and
data
validation/
review.
Standardized
training
requirements
for
radioassay
personnel
are
based
upon
existing
industry
standardized
training
requirements
(
e.
g.,
ASTM
C1490,
Standard
Guide
for
Selection,
Training
and
Qualification
of
Nondestructive
Assay
(
NDA)
Personnel;
ANSI
N15.54,
Radiometric
Calorimeters
 
Measurement
Control
Program)
and
meet
the
specifications
in
the
QAPD.
Requalification
of
radioassay
personnel
is
based
upon
evidence
of
continued
satisfactory
performance
and
must
be
performed
at
least
every
two
years.
Personnel
training
and
qualification
is
performed
in
accordance
with
PLN­
97­
007,
TWCP
Training
Implementation
Plan
(
TWCP
TIP).

Software
QC
Requirements:
All
computer
programs
and
revisions
thereof
used
for
radioassay
meet
the
applicable
requirements
in
the
QAPD,
Section
6.0.
Compliance
with
the
QAPD,
Section
6.0
is
performed
in
accordance
with
PRO­
548­
SSOC­
SQA,
Software
Management
for
Nondestructive
Assay
Systems.

Comparison
Programs:
RFETS
participates
in
any
relevant
measurement
comparison
program(
s)
sponsored
or
approved
by
the
CBFO.
Such
programs
may
be
conducted
as
part
of
the
NDA
PDP
or
through
other
third
parties.
RFETS
calorimetric
assay
systems
participate
in
the
Calorimetry
Exchange
Program
sponsored
by
New
Brunswick
Laboratory.
PDP
participation
at
RFETS
is
done
in
accordance
with
PRO­
108­
PREP­
01,
Preparation
of
NDA
Performance
Demonstration
Program
Samples,
and
PRO­
1405­
PREP­
02,
Preparation
of
Boxed
Waste
Performance
Demonstration
Program
(
PDP)
Samples
for
Nondestructive
Assay.
TRANSURANIC
(
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7
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2004
PAGE
341
A4.4.2
NDA
QC
Requirements
RFETS
implements,
qualifies
and
operates
NDA
systems
using
standard
operating
procedures
that
implement
assay
procedures
cited
in
various
ASTM
and
ANSI
standards
and
NRC
standard
practices
and
guidelines
as
referenced
in
the
WIPPWAC
Appendix
A.

Background
Measurements:
Background
measurements
are
to
be
performed
daily,
unless
otherwise
approved
by
CBFO.
Contributions
to
background
due
to
radiation
from
nearby
radiation
producing
equipment,
standards
or
wastes
must
be
carefully
controlled
or
more
frequent
background
checks
must
be
performed.
For
calorimeters,
basepower
or
baseline
measurements
shall
be
conducted
at
a
frequency
determined
by
RFETS
and
approved
by
CBFO.

Instrument
Performance
Measurements:
Performance
checks
on
calibrated
and
operable
gamma
and
neutron
NDA
instruments
are
be
performed
once
per
operational
day.
Performance
checks
include
efficiency
checks
(
when
applicable),
matrix
correction
checks
and,
for
spectrometric
instruments,
peak
position
and
resolution
checks.

Both
radioactive
sources
and
surrogate
waste
matrix
containers
(
both
noninterfering
and
interfering)
are
used.
At
least
once
per
operational
week
an
interfering
matrix
is
used
to
assess
the
long­
term
stability
of
the
NDA
instrument's
matrix
correction.
Surrogate
waste
containers
reflect
the
type
of
waste
(
e.
g.,
debris,
sludge,
etc.)
currently
being
assayed.
To
verify
calibration,
radioactivity
standards
are
selected
such
that,
over
a
six
month
period,
the
operating
range
of
the
assay
system
is
tested
in
each
applicable
surrogate
waste
matrix.
The
use
of
interfering
and
non­
interfering
matrices
provides
a
realistic
assessment
of
the
assay
system's
performance
over
time,
and
will
assist
measurement
personnel
in
detecting
potential
problems
relative
to
the
matrices
currently
assayed
by
the
measurement
system.
Interfering
matrix
measurement
control
checks
are
performed
in
accordance
with
PRO­
731­
MC­
002,
Measurement
Control
for
NDA.

Interfering
surrogate
matrix
containers
are
constructed
in
such
a
way
that
the
waste
characteristics
do
not
change
over
time.

Radioactive
sources
are
long­
lived,
easy
to
position
relative
to
the
detector(
s),
and
of
sufficient
radioactivity
to
obtain
good
results
with
relatively
short
count
times.

Performance
checks
for
calorimetry
are
performed
with
electrical
and/
or
heat
standards
traceable
to
a
nationally
accredited
measurement
program
at
a
frequency
determined
by
RFETS,
consistent
with
ANSI
N15.22­
1987,
Plutonium­
Bearing
Solids
Calibration
Techniques
for
Calorimetric
Assay.
This
information
is
specified
in
site
operating
procedures
and
approved
by
CBFO.
TRANSURANIC
(
TRU)
WASTE
1­
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008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
342
A4.4.2
NDA
QC
Requirements
(
continued)

Data
Checks:
Background
(
for
calorimetry:
baseline
or
base
power)
and
performance
measurements
are
reviewed
and
evaluated
at
least
weekly
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
performance
trends.
If
daily
performance
checks
result
in
data
that
are
outside
the
acceptable
range,
the
required
responses
in
Table
A4.4­
1
is
followed.

A4.4.3
Radiochemistry
QC
Requirements
RFETS
does
not
plan
to
implement
any
radiochemistry
methods
to
characterize
TRU
waste.
Therefore,
no
QC
requirements
for
radiochemistry
are
presented.

Table
A4.4­
1,
Range
of
Applicability
ACCEPTABILITY
RANGEa
REQUIRED
RESPONSE
Acceptable
Range
|
Data|
c
<
2 b
No
action
required.
Warning
Range
2 b
<
|
Data|
<
3 b
The
performance
check
standard
shall
be
rerun
no
more
than
two
times.
If
the
rerun
performance
check(
s)
result
in
data
within
±
2 ,
then
the
additional
performance
checks
shall
be
documented
and
work
may
continue.
If
the
system
does
not
fall
within
±
2 
after
two
rerun
performance
checks,
then
the
required
response
for
the
Action
Range
shall
be
followed.
Action
Range
|
Data|
>
3 b
Work
shall
stop
and
the
occurrence
shall
be
documented
and
appropriately
dispositioned
(
e.
g.,
initiating
a
nonconformance
report).
The
radioassay
system
shall
be
removed
from
service
pending
successful
resolution
of
all
necessary
actions,
and
all
assays
performed
since
the
last
acceptable
performance
check
are
suspect,
pending
satisfactory
resolution.
Recalibration
or
calibration
verification
is
required
prior
to
returning
the
system
back
to
service.

a
ANSI
N15.36,
Nondestructive
Assay
Measurement
Control
and
Assurance.

b
"
 "
 
the
standard
deviation
is
only
based
on
the
reproducibility
of
the
data
check
measurements
themselves.
This
is
not
TMU.

c
Absolute
value.
TRANSURANIC
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343
A4.5
Data
Management
RFETS
Pre­
DOE/
WIPP­
02­
3122
Data
Management
The
following
describes
data
management
at
RFETS
conducted
as
described
in
Revision
4
of
this
document,
written
to
the
requirements
specified
in
DOE/
WIPP­
069,
Revision
7,
Change
Notice
2.

Separate
testing
report
sheet(
s)
are
generated
for
each
sample
in
the
testing
batch
that
includes:

 
Title
Radioassay
Data
Sheet
 
Method
used
for
NDA
(
i.
e.,
procedure
identification)

 
TRUCON,
content
code,
Item
Description
Code,
matrix
parameter
category,
as
applicable
 
Date
of
NDA
examination
Note:
IF
isotopic
information
is
measured,
THEN
individual
isotopic
information
(
grams)
is
reported.

IF
default
isotopic
information
is
used,
THEN
weapons
grade
plutonium
(
grams)
is
reported.

 
Listing
of
weapons
grade
plutonium
(
grams)
or
individual
radioisotopes
present
(
grams)
and
associated
uncertainty
(
grams)
reported
at
the
95­
percent
confidence
level
 
QC
replicate
(
yes/
no)

 
Operator
signature/
date
 
Reviewer
signature/
date
The
following
items
are
not
required
to
be
included
on
the
testing
report
sheet(
s)
because
they
are
calculated
by
the
WEMS
database
and
reported
to
CBFO
through
the
WWIS.

 
Total
Pu­
239
FGEs
(
g)
and
associated
uncertainty
 
Total
alpha
activity
and
associated
uncertainty
(
Curies)

 
Listing
of
individual
radioisotopes
present
(
Curies)
and
associated
uncertainty
(
Curies)

 
TRU
alpha
activity
concentration
and
associated
uncertainty
(
nCi/
g)

 
Thermal
power
and
associated
uncertainty
(
W)
TRANSURANIC
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A4.5
Data
Management
(
continued)

RFETS
Pre­
DOE/
WIPP­
02­
3122
Data
Management
(
continued)

These
reporting
items
are
calculated
by
the
Waste
Environmental
Management
System
(
WEMS)
waste
management
computer
database
system
from
data
reported
and
input
for
the
mass
(
in
grams)
and
uncertainty
of
radioactive
material
or
isotopes
present
that
is
reported
on
individual
radioassay
data
sheets.
Consequently,
from
the
listing
of
individual
radioisotopes
present
(
grams)
and
associated
uncertainty
(
grams),
as
reported
on
radioassay
data
sheets,
WEMS
calculates
total
Pu­
239
FGE
and
uncertainty,
total
alpha
activity
and
uncertainty
(
curies),
activity
(
in
curies)
of
individual
radioisotopes
present
and
uncertainty,
and
thermal
power
and
associated
uncertainty
(
in
watts).

Data
Management
Guidance
RFETS
has
generated
data
under
the
requirements
of
TWMM
Revision
4,
which
largely
implemented
DOE/
WIPP­
069,
Revision
7,
Change
Notice
2.
This
data
may
have
been
in
various
stages
of
the
data
review,
verification,
validation,
and
reporting
process
on
May
17,
2002,
the
date
the
CH­
WAC
(
DOE/
WIPP­
02­
3122,
Revision
0)
became
effective.

Data
that
was
completely
through
the
data
review,
verification,
validation,
and
reporting
process
on
May
17,
2002,
was
accepted
as
having
met
the
requirements
of
the
WAC
(
DOE/
WIPP­
069,
Revision
7,
Change
Notice
2).
No
reconciliation
with
the
requirements
of
the
CH­
WAC
(
DOE/
WIPP­
02­
3122,
Revision
0)
was
performed.

For
data
that
was
collected
and
part
way
through
the
data
review,
verification,
validation,
and
reporting
process
prior
to
May
17,
2002,
the
requirement
for
a
replicate
measurement
was
in
effect,
and
weekly
interfering
matrix
measurements
were
not
required.
Consequently,
the
site
program
office
in
reviewing
and
approving
the
data
package
on
or
after
May
17,
2002,
indicated
on
the
batch
report
and/
or
batch
review
checklist
the
use
of
replicates
(
required
in
DOE/
WIPP­
069,
Revision
7,
Change
Notice
2)
in
lieu
of
the
use
of
a
weekly
interfering
surrogate
waste
matrix
(
required
in
DOE/
WIPP­
02­
3122,
Revision
0).
Also,
the
associated
radionuclides
reported
to
the
WWIS
on
or
after
May
17,
2002,
only
included
those
radionuclides
that
were
quantified
by
the
NDA
system.
RFETS
identified
in
the
Batch
Data
Report
(
such
as
in
a
case
narrative
or
batch
review
checklist)
the
rationale
for
addressing
these
allowed
variances
from
the
requirements
of
the
CHWAC

Data
collected
after
May
17,
2002
is
managed
in
full
compliance
with
the
CH­
WAC
(
DOE/
WIPP­
02­
3122).
TRANSURANIC
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PAGE
345
A4.5.1
Data
Review
and
Validation
All
radioassay
data
is
reviewed
and
approved
by
qualified
personnel
prior
to
being
reported.
At
a
minimum,
the
data
must
be
reviewed
by
a
technical
reviewer
and
approved
by
the
TWCP
Site
PM
or
designee(
s).
The
validation
process
includes
verification
that
the
applicable
quality
controls
specified
in
Section
A4.4
have
been
met.
Data
validation
procedures
are
listed
in
Table
A4.1­
3,
RFETS
NDA
Operating
and
Data
Management
Procedures.

A4.5.2
Data
Reporting
Radioassay
data
is
reported
to
the
TWCP
Project
Office
on
a
testing
batch
basis.
Batches
are
defined,
for
the
purpose
of
the
program,
as
a
suite
of
waste
containers
undergoing
radioassay
using
the
same
testing
equipment.
For
NDA,
RFETS
shall
specify
the
size
of
the
testing
batch
as
needed,
without
regard
to
waste
matrix.

The
RFETS
Measurements
Organization
is
required
to
submit
testing
batch
data
reports
for
each
testing
batch
to
the
TWCP
Project
Office
on
standard
forms
(
either
hard
copy
or
electronic
equivalent),
as
provided
in
approved
site
specific
documentation.
Radioassay
testing
batch
data
reports
consist
of
the
following:

 
Testing
facility
name,
testing
batch
number,
container
numbers
included
in
that
testing
batch,
and
signature
release
by
the
TWCP
Site
PM
or
designee(
s).

 
Table
of
contents.

 
Background
and
performance
data
or
control
charts
for
the
relevant
time
period.

 
Data
validation
per
Section
5.3.2
of
the
QAPD
and
as
described
in
RFETS
procedures.

 
Separate
testing
report
sheet(
s)
for
each
container
in
the
testing
batch
that
includes:

 
title
"
Radioassay
Data
Sheet"

 
method
used
for
radioassay
(
i.
e.,
procedure
identification)

 
date
of
radioassay
 
item
description
code
(
IDC)

 
masses
of
individual
radioisotopes
present
and
their
associated
TMUs
grams)
reported
at
the
Upper
95%
Confidence
Level
(
UCL95).
The
radioassay
data
sheet
will
specify
that
the
TMUs
are
reported
as
UCL95.

 
operator
signature/
date
 
reviewer
signature/
date.
TRANSURANIC
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2004
PAGE
346
A4.5.2
Data
Reporting
(
continued)

Other
radiological
properties
to
be
documented
for
each
container
include:

 
decay
heat
expressed
in
Watts
(
W)
and
its
associated
TMU,

 
total
239Pu
FGE
expressed
in
grams
(
g)
and
its
associated
TMU,

 
TRU
alpha
activity
concentration
expressed
in
curies/
gram
(
Ci/
g)
and
its
associated
TMU,
and
 
total
239Pu
equivalent
activity
expressed
in
curies
(
Ci).

These
calculated
quantities
are
calculated
by
and
presented
in
the
Waste
and
Environmental
Management
System
(
WEMS).

A4.5.3
Data
and
Records
Retention
The
following
nonpermanent
records
are
maintained
by
the
Measurements
organization
or
are
forwarded
to
the
site
project
office
for
maintenance,
and
are
documented
and
retrievable
by
testing
batch
number,
in
accordance
with
the
QAPD:

 
testing
batch
reports
 
all
raw
data,
including
instrument
readouts,
calculation
records,
and
radioassay
QC
results
 
all
instrument
calibration
reports,
as
applicable.
TRANSURANIC
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347
A4.6
Quality
Characteristics
Assessment
Per
40
CFR
§
194.22(
c),
there
are
five
"
quality
characteristics"
that
have
to
be
assessed.
These
quality
characteristics
and
the
method
by
which
they
are
assessed
are
described
in
the
following
sections.

A4.6.1
Data
Accuracy
Per
40
CFR
§
194.22(
c)(
1),
Data
Accuracy
is
defined
as
"
the
degree
to
which
data
agree
with
an
acceptable
reference
or
true
value."
For
NDA
methods,
this
quality
characteristic
is
met
and
maintained
as
described
in
Section
A4.4.2.

A4.6.2
Data
Precision
Per
40
CFR
§
194.22(
c)(
2),
Data
Precision
is
defined
as
"
a
measure
of
the
mutual
agreement
between
comparable
data
gathered
or
developed
under
similar
conditions
expressed
in
terms
of
standard
deviation."
For
NDA
methods,
this
quality
characteristic
is
met
and
maintained
as
described
in
Section
A4.4.2.

A4.6.3
Data
Representativeness
Per
40
CFR
§
194.22(
c)(
3),
Data
Representativeness
is
defined
as
"
the
degree
to
which
data
can
accurately
and
precisely
represent
a
characteristic
of
a
population,
a
parameter,
variations
at
a
sampling
point,
or
environmental
conditions."
For
NDA,
this
quality
characteristic
for
the
waste
stream
is
met
and
maintained
through
100%
measurement
confirmation
on
a
payload
package
basis.
For
NDA,
since
the
entire
waste
package
is
subjected
to
measurement,
representativeness
pertaining
to
the
actual
measurement
is
not
applicable.

A4.6.4
Data
Completeness
Per
40
CFR
§
194.22(
c)(
4),
Data
Completeness
is
defined
as
"
a
measure
of
the
amount
of
valid
data
obtained
compared
to
the
amount
that
was
expected."
For
NDA
methods,
this
quality
characteristic
is
met
and
maintained
by
requiring
100%
valid
results.
Any
results
indicating
the
NDA
measurement
was
invalid
require
remeasurement
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
348
A4.6.5
Data
Comparability
Per
40
CFR
§
194.22(
c)(
5),
Data
Comparability
is
defined
as
"
a
measure
of
confidence
with
which
one
data
set
can
be
compared
to
another."
For
NDA,
this
quality
characteristic
is
addressed
by
ensuring
that
all
data
are
produced
under
the
same
system
of
controls.
These
controls
apply
to
all
aspects
of
the
data
generation
process,
including:
procurement
of
analytical
instruments;
calibration
and
operation
of
assay
equipment
according
to
industry
standards;
preparation
and
use
of
standardized
instrument
and
data
review
procedures;
and,
training
of
equipment
operators
and
technical/
data
review
personnel
to
the
QAPD,
as
specified
in
Section
A4.4.1.
All
NDA
systems
and
methods
are
approved
by
CBFO
prior
to
use
in
generating
waste
characterization
data.
Additionally,
comparison
of
measured
data
with
AK
derived
or
based
values,
as
applicable,
provides
a
means
to
assess
comparability
on
a
waste
stream
basis.
Although
no
specific
confidence
level
is
specified,
these
controls
provide
comparability
among
all
data
generated
under
this
program.
RFETS
shall
participate
in
applicable
measurement
comparison
programs
as
specified
in
Section
A4.4.1.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
349
A4.7
Document
Review,
Approval,
and
Control
The
following
describes
required
reviews
and
approvals
of
controlled
changes
to
NDA
related
plans
or
procedures
at
RFETS
as
required
in
CBFO:
NTP:
RMK:
VW:
02­
2734:
UFC
5822,
CBFO
Review
and
Approval
of
NDA
and
Radiochemistry
Plans,
Procedures,
and
Related
Technical
Documents.

TRU
waste
radioassay
(
NDA
or
radiochemistry)
related
plans
(
e.
g.,
calibration
plans,
qualification
plans,
qualification
reports)
shall
be
developed
and
managed
in
accordance
with
PRO­
1570­
NDA­
QUAL,
Qualification
Requirements
for
NDA
Large
Package
Counters.
TRU
waste
radioassay
related
procedures
shall
be
developed
and
managed
as
WIPP­
related
documents
through
the
document
control
process
described
in
Section
3.1.4
of
this
TWMM
(
describes
RFETS
document
control
for
compliance
with
QAPD).
The
TWCP
Site
PM
and
the
TWCP
Site
PQAO
shall
review
all
such
documents,
revisions,
and
major
changes
and
report
to
the
CBFO
those
that
could
impact
compliance
with
the
criteria
in
the
WIPP­
WAC.
The
TWCP
Site
PM
shall
ensure
that
RFETS
approved
changes
to
radioassay
related
plans,
reports,
or
procedures
affecting
either
the
performance
criteria
or
data
quality
of
certified
systems/
processes
are
not
used
in
the
collection
of
waste
certification
data
prior
to
CBFO
review
and
approval.
The
TWCP
Site
PM
determines
when
such
review
is
necessary
and
coordinates
such
review.
Documentation
of
such
review/
concurrence
is
placed
in
the
Document
History
File,
but
not
reflected
on
the
document
cover
page
or
Document
Change
Form.
Related
testing,
calibration,
and
training
performed
in
accordance
with
these
RFETS
approved
changes,
however,
are
not
precluded
from
being
conducted
prior
to
CBFO
review
and
approval.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
350
APPENDIX
5
Page
1
of
4
NUMERIC
PAYLOAD
SHIPPING
CATEGORY
WORKSHEET
Container
ID
Number:

Two
Digit
Waste
Type
Notation
(
XX)
from
Table
6­
3
G
Value
for
Waste
Material
Type
from
Table
6­
4
Four
Digit
G
Value
Notation
(
YYYY)
from
Table
6­
4
Resistance
Factor
(
Use
One
Column
Only)
a
Packaging
Type
Number
of
Layers
Column
1
Column
2
Total
Resistance
Factorb
Filtered
From
Table
A5­
2
Inner
Bag
Layers
Twist
and
Tape
23,989
17,922
Slip­
Top/
Unsealed
0
0
Metal
Can
Layers
Filtered
From
Table
A5­
2
Filtered
Drum
Liner
Bag
From
Table
A5­
2
Twist
and
Tape
Drum
Liner
Bag
2,142
2,142
Filtered
SWB/
Bin/
TDOP
Liner
Bag
From
Table
A5­
2
Liner
Bag
Layers
Fold
and
Tape
SWB/
Bin/
TDOP
Liner
Bag
1,257
1,257
Confinement
Layers
Rigid
Drum
Liner
Rigid
Liner
From
Table
A5­
2
Pipe
Component
From
Table
A5­
3
55­
Gallon
Drum
(
or
Pipe
Overpack)
From
Table
A5­
3
100­
Gallon
Drum
From
Table
A5­
3
Bin
Overpack
From
Table
A5­
3
85­
Gallon
Drum
Overpack
­
One
55­
Gallon
Drum
From
Table
A5­
3
SWB
­
Direct
Load
From
Table
A5­
3
SWB
Overpack
­
Four
55­
Gallon
Drums
From
Table
A5­
3
Payload
Container
TDOP
­
Direct
Load
From
Table
A5­
3
55­
Gallon
Drums
or
Pipe
Overpacks
7,147
100­
Gallon
Drums
2,764
Direct
Loaded
SWBs
or
Bin
Overpacks
1,430
SWB
Overpacks
Containing
Up
To
Four
55­
Gallon
Drums
per
SWB;
or
85­
Gallon
Overpacks
of
55­
Gallon
Drums
5,718
Choose
Those
That
Apply
Load
Typec
Direct
Loaded
TDOP
980
Total
Resistance
Factor
Sum
Divide
Total
Resistance
Factor
Sum
by
100
and
Round
Up
to
Whole
Number
÷
100
Total
Resistance
Notation
(
ZZZZ)
Report
as
Four
Digits
If
Waste
Type
20
and
a
metal
can
is
the
innermost
layer
of
confinement,
enter
0000.

Payload
Shipping
Category
(
XX
YYYY
ZZZZ)
___
___
___
___
___
___
___
___
___
___

a
Use
Column
1
for
the
following
six­
digit
notations
(
XX
YYYY):
10
0160,
10
0130,
10
0040,
and
20
0008.
Use
Column
2
for
all
other
six­
digit
notations.
b
Multiply
the
"
Number"
by
the
appropriate
"
Resistance
Factor"
to
obtain
the
"
Total
Resistance
Factor."
c
See
Appendix
3.6.13
of
the
TRUPACT­
II
Safety
Analysis
Report
regarding
the
selection
of
the
appropriate
Load
Type
for
overpacked
configurations.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
351
APPENDIX
5
Page
2
of
4
NUMERIC
PAYLOAD
SHIPPING
CATEGORY
WORKSHEET
(
continued)

Filtered/
Punctured
Confinement
Layers
Resistance
Worksheet
Resistance
Factora
(
Use
One
Column
Only)

Packaging/
Type
Minimum
Filter
Hydrogen
Diffusivity/
Minimum
Puncture
Diameter
Number
of
Layers
Column
1
Column
2
Number
of
Filters/
Punctures
Total
Resistance
Factorb
1.075
x
10­
5
m/
s/
mf
Filter
1,290
931
2.150
x
10­
5
m/
s/
mf
Filter
645
466
5.375
x
10­
5
m/
s/
mf
Filter
258
187
2.688
x
10­
4
m/
s/
mf
Filter
52
38
Inner
Bag
Layers:
Filtered
1.075
x
10­
3
m/
s/
mf
Filter
13
10
1.9
x
10­
6
m/
s/
mf
Filter
7,294
5,264
3.7
x
10­
6
m/
s/
mf
Filter
3,746
2,703
7.4
x
10­
6
m/
s/
mf
Filter
1,873
1,352
1.85
x
10­
5
m/
s/
mf
Filter
750
541
9.25
x
10­
5
m/
s/
mf
Filter
150
109
Metal
Can
Layers:
Filtered
3.7
x
10­
4
m/
s/
mf
Filter
38
28
1.075
x
10­
5
m/
s/
mf
Filter
933
673
2.150
x
10­
5
m/
s/
mf
Filter
542
391
5.375
x
10­
5
m/
s/
mf
Filter
240
173
2.688
x
10­
4
m/
s/
mf
Filter
51
37
Liner
Bag
Layers:
Filtered
Drum
Liner
Bag
1.075
x
10­
3
m/
s/
mf
Filter
13
10
1.075
x
10­
5
m/
s/
mf
Filter
764
551
2.150
x
10­
5
m/
s/
mf
Filter
480
347
5.375
x
10­
5
m/
s/
mf
Filter
227
164
2.688
x
10­
4
m/
s/
mf
Filter
51
37
Liner
Bag
Layers:
Filtered
SWB/
Bin/
TDOP
Liner
Bag
1.075
x
10­
3
m/
s/
mf
Filter
13
10
0.3"
Diameter
Hole
197
197
0.375"
Diameter
Hole
126
126
0.75"
Diameter
Hole
32
32
1"
Diameter
Hole
18
18
Rigid
Drum
Liner:

2"
Diameter
Hole
5
5
a
Use
Column
1
for
the
following
six­
digit
notations
(
XX
YYYY):
10
0160,
10
0130,
10
0040,
and
20
0008.
Use
Column
2
for
all
other
six­
digit
notations.
b
Multiply
the
"
Number
of
Layers"
by
the
appropriate
"
Resistance
Factor"
and
divide
by
the
"
Number
of
Filters/
Punctures"
to
obtain
the
"
Total
Resistance
Factor."
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
352
m/
s/
mf
=
Moles/
second/
mole
fraction.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
353
APPENDIX
5
Page
3
of
4
NUMERIC
PAYLOAD
SHIPPING
CATEGORY
WORKSHEET
(
continued)

Payload
Container
Resistance
Worksheeta
Resistance
Factorb
(
Use
One
Column
Only)

Payload
Container
Filter
Type
Number
of
Filters
on
Container
Column
1
Column
2
Total
Resistance
Factorc
1.9
x
10­
6
m/
s/
mf
Filter
7,294
5,264
3.7
x
10­
6
m/
s/
mf
Filter
3,746
2,703
7.4
x
10­
6
m/
s/
mf
Filter
1,873
1,352
1.85
x
10­
5
m/
s/
mf
Filter
750
541
9.25
x
10­
5
m/
s/
mf
Filter
150
109
Pipe
Component
3.7
x
10­
4
m/
s/
mf
Filter
38
28
1.9
x
10­
6
m/
s/
mf
Filter
7,294
5,264
3.7
x
10­
6
m/
s/
mf
Filter
3,746
2,703
7.4
x
10­
6
m/
s/
mf
Filter
1,873
1,352
1.85
x
10­
5
m/
s/
mf
Filter
750
541
9.25
x
10­
5
m/
s/
mf
Filter
150
109
55­
Gallon
Drum
(
or
Pipe
Overpack)

3.7
x
10­
4
m/
s/
mf
Filter
38
28
3.7
x
10­
6
m/
s/
mf
Filter
3,746
2,703
7.4
x
10­
6
m/
s/
mf
Filter
1,873
1,352
1.85
x
10­
5
m/
s/
mf
Filter
750
541
9.25
x
10­
5
m/
s/
mf
Filter
150
109
100­
Gallon
Drum
3.7
x
10­
4
m/
s/
mf
Filter
38
28
3.7
x
10­
6
m/
s/
mf
Filter
3,746
2,703
7.4
x
10­
6
m/
s/
mf
Filter
1,873
1,352
1.85
x
10­
5
m/
s/
mf
Filter
750
541
9.25
x
10­
5
m/
s/
mf
Filter
150
109
Bin
Overpackd
(
SWB
Containing
One
Experimental
Bin)

3.7
x
10­
4
m/
s/
mf
Filter
38
28
3.7
x
10­
6
m/
s/
mf
Filter
7,490
5,406
7.4
x
10­
6
m/
s/
mf
Filter
3,746
2,703
1.85
x
10­
5
m/
s/
mf
Filter
1,499
1,082
9.25
x
10­
5
m/
s/
mf
Filter
300
217
85­
Gallon
Drum
Overpack
Containing
One
55­
Gallon
Drum
3.7
x
10­
4
m/
s/
mf
Filter
75
55
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
354
APPENDIX
5
Page
4
of
4
NUMERIC
PAYLOAD
SHIPPING
CATEGORY
WORKSHEET
(
continued)

Payload
Container
Resistance
Worksheet
(
continued)
a
Resistance
Factorb
(
Use
One
Column
Only)
Payload
Container
Filter
Type
Number
of
Filters
on
Container
Column
1
Column
2
Total
Resistance
Factorc
3.7
x
10­
6
m/
s/
mf
Filter
1,873
1,352
7.4
x
10­
6
m/
s/
mf
Filter
937
676
1.85
x
10­
5
m/
s/
mf
Filter
375
271
9.25
x
10­
5
m/
s/
mf
Filter
75
55
SWB
 
Direct
Loadd
3.7
x
10­
4
m/
s/
mf
Filter
19
14
3.7
x
10­
6
m/
s/
mf
Filter
7,490
5,406
7.4
x
10­
6
m/
s/
mf
Filter
3,746
2,703
1.85
x
10­
5
m/
s/
mf
Filter
1,499
1,082
9.25
x
10­
5
m/
s/
mf
Filter
300
217
SWB
Overpack
Containing
Up
To
Four
55­
Gallon
Drums
3.7
x
10­
4
m/
s/
mf
Filter
75
55
3.7
x
10­
6
m/
s/
mf
Filter
417
301
7.4
x
10­
6
m/
s/
mf
Filter
209
151
1.85
x
10­
5
m/
s/
mf
Filter
84
61
9.25
x
10­
5
m/
s/
mf
Filter
17
13
TDOP
 
Direct
Load
3.7
x
10­
4
m/
s/
mf
Filter
5
4
a
See
Appendix
3.6.13
of
the
TRUPACT­
II
Safety
Analysis
Report
regarding
the
selection
of
payload
packages
for
overpacked
configurations.
b
Use
Column
1
for
the
following
six­
digit
notations
(
XX
YYYY):
10
0160,
10
0130,
10
0040,
and
20
0008.
Use
Column
2
for
all
other
six­
digit
notations.
c
Divide
the
appropriate
"
Resistance
Factor"
by
the
"
Number
of
Filters
on
Container"
to
obtain
the
"
Total
Resistance
Factor."
d
Bin
Overpack
and
SWB
(
direct
load)
configurations
assume
two
filters
on
the
payload
package
as
the
baseline
(
as
described
in
Section
6.2.5.1
of
the
RFETS
TRAMPAC
Compliance
Plan).
The
"
Number
of
Filters
on
Container"
for
these
configurations
should
be
entered
as
the
ratio
of
the
total
number
of
filters
on
the
payload
package
divided
by
the
baseline
number
of
filters
(
2).
For
example,
for
an
SWB
(
direct
load)
with
3
filters,
the
"
Number
of
Filters
on
Container"
would
be
3
/
2.

m/
s/
mf
=
Moles/
second/
mole
fraction.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
355
APPENDIX
6
Page
1
of
2
PAYLOAD
ASSEMBLY
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PATCD)
a
IDENTIFICATION
PARAMETERS
Shipment
#:_________________________
Packaging
OCA
Body/
Lid
#:
_____________________

Governing
Payload
Shipping
Category:

Governing
Payload
Shipping
Category
Decay
Heat
Limit:

Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit:

Type
of
Payload:

55­
Gallon
Drums

Standard
Pipe
Overpacks

S100
Pipe
Overpacks

S200
Pipe
Overpacks

100­
Gallon
Drums

SWBs

SWB
Overpacks

Bin
Overpacks

TDOP
Date
ICV
Closed:
________________________________

BOTTOM
PAYLOAD
ASSEMBLY
COMPOSITION
Container
ID
Weight
(
lbs)
Error
(
lbs)
Decay
Heat
(
watts)
Error
(
watts)
Fissile
Mass
(
FGE)
2x
Error
(
FGE)
Hydrogen/
Flammable
Gas
Generation
Rate
Flammability
Index
Subtotal
(
A)

Subtotal
RMS
Error
(
C)

TOP
PAYLOAD
ASSEMBLY
COMPOSITION
Container
ID
Weight
(
lbs)
Error
(
lbs)
Decay
Heat
(
watts)
Error
(
watts)
Fissile
Mass
(
FGE)
2x
Error
(
FGE)
Hydrogen/
Flammable
Gas
Generation
Rate
Flammability
Index
Subtotal
(
B)

Subtotal
RMS
Error
(
D)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
356
APPENDIX
6
Page
2
of
2
PAYLOAD
ASSEMBLY
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PATCD)
a
PAYLOAD
TOTALS
Weight
of
Pallets,
Reinforcing
Plates,
Slip
Sheets,
Guide
Tubes,
Adjustable
Slings,
etc.
(
E)

Total
(
A+
B+
E)
Weight:
lbs
Total
RMS
Weight
Error:
lbs
Total
(
A+
B)
Decay
Heat:
Watts
Total
RMS
Decay
Heat
Error:
Watts
Total
(
A+
B)
Fissile
Mass:
FGE
Total
RMS
Fissile
Mass
Error:
FGE
Bottom
Assembly
Weight
plus
Subtotal
RMS
Error
(
A+
C)
lbs
Top
Assembly
Weight
plus
Subtotal
RMS
Error
(
B+
D)
lbs
Total
Weight
plus
Total
RMS
Error
lbs
Total
Fissile
Mass
plus
Total
RMS
Error
FGE
Total
Decay
Heat
plus
Total
RMS
Error
Watts
PAYLOAD
CERTIFICATION
PARAMETERS
Decay
Heat
+
Error
of
Each
Analytical
Category
Payload
Container
 
Governing
Limit
Hydrogen/
Flammable
Gas
Generation
Rate
of
Each
Test
Category
Payload
Container
 
Governing
Limit
Flammability
Index
of
Each
Payload
Container
 
50,000
Bottom
Weight
 
Top
Weight
Total
Weight
plus
RMS
Error
 
7,265
lbs
Decay
Heat
plus
RMS
Error
 
40
Watts
Fissile
Mass
(
Pu­
239
FGE)
plus
RMS
Error
 
FGE
Initials
I
certify
that
the
above
payload
assembly
meets
all
the
requirements
for
shipment
as
stated
in
the
TRAMPAC,
current
revision.
The
payload
assembly
is
approved
for
shipment.

_______________________________________________________/
_________________
TRANSPORTATION
CERTIFICATION
OFFICIAL
/
DATE
a
Follow
instructions
in
Section
6.6.2.4
or
6.6.2.5
of
the
RFETS
TRAMPAC
Compliance
Plan.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
357
APPENDIX
7
Page
1
of
1
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PCTCD)
(
ANALYTICAL
PAYLOAD
SHIPPING
CATEGORYa)
IDENTIFICATION
PARAMETERS
Container
ID
#
Container
Bar
Code
#___________________________

Shipping
Category
Content
Code__________________________________

Direct
Load
Configurations

55­
Gallon
Drum

100­
Gallon
Drum

SWB

TDOP
Fixed
Configurations

Standard
Pipe
Overpack

S100
Pipe
Overpack

S200
Pipe
Overpack

Bin
Overpack

85­
Gallon
Drum
Overpack
Overpacked
Configurations

SWB
with
55­
Gallon
Drum(
s)
(
SWB
Overpack)

TDOP
with
55­
Gallon
Drum(
s)


TDOP
with
SWB
Overpack

TDOP
with
85­
Gallon
Drum
Overpack(
s)


TDOP
with
SWB

TDOP
with
Bin
Overpack
Certification
Site
TRAMPAC
TRANSPORTATION
PARAMETERS
Parameter
Initials
Filter(
s)
Identification
Free
liquids
are
<
1%
of
payload
container
volume
Nonradioactive
pyrophorics
are
not
present
Radioactive
pyrophorics
are
<
1%
(
weight)
Explosives
are
not
present
Corrosives
are
not
present
Pressurized
containers
are
not
present
Sealed
containers
>
4
liters
are
not
present
55­
Gallon
drum
liner
(
if
present)
is
punctured/
vented
Flammable
VOCs
are
<
500
ppm
Radiation
Dose
Rate
is
<
200
mrem/
hour
__________
__________
__________
__________
__________
__________
__________
__________
__________
__________
1.
2.

3.
4.

5.
6.

7.
8.

9.
10.

MEASURED
PARAMETERS
Container
Parameter
Value
Error
Value
+
1x
Error
Value
+
2x
Error
Limit
Weight
(
lbs.)

Decay
Heat
(
watts)

Fissile
Mass
(
FGE)
Curie
Limits
(
Ci)
S100
Value
+
error
meets
limits
for
radionuclides
listed
in
Pipe
Overpack
or
S200
Appendix
2.3
(
S100)
or
Appendix
2.4
(
S200)
of
TRAMPAC
Yes/
No
Pipe
Overpack
only
UNVENTED
WASTE
PARAMETERS
ONLY
Aspiration
Method

Option
1

Option
2A

Option
2B

Option
3
Aspiration
Period
(
if
applicable)
days
Option
1
Container
closed
time
months
Aspiration
Table
No.
(
if
applicable)

Options
2A,
2B,
or
3
Headspace
H2
Concentration
mol%
Time
Container
Vented
I
certify
that
the
above
container
meets
all
the
requirements
for
shipment
as
stated
the
TRAMPAC,
current
revision.
The
container
is
approved
for
shipment
or
overpacking.

_______________________________________________________/
_________________
TRANSPORTATION
CERTIFICATION
OFFICIAL
/
DATE
aFollow
instructions
in
Section
6.6.2.1
of
the
RFETS
TRAMPAC
Compliance
Plan.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
358
APPENDIX
8
Page
1
of
1
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PCTCD)
(
TEST
PAYLOAD
SHIPPING
CATEGORYa)

IDENTIFICATION
PARAMETERS
Container
ID
#
Container
Bar
Code
#___________________________

Shipping
Category
Content
Code__________________________________

Direct
Load
Configurations

55­
Gallon
Drum

100­
Gallon
Drum

SWB

TDOP
Fixed
Configurations

Standard
Pipe
Overpack

S100
Pipe
Overpack

S200
Pipe
Overpack

Bin
Overpack

85­
Gallon
Drum
Overpack
Overpacked
Configurations

SWB
with
55­
Gallon
Drum(
s)
(
SWB
Overpack)

TDOP
with
55­
Gallon
Drum(
s)


TDOP
with
SWB
Overpack

TDOP
with
85­
Gallon
Drum
Overpack(
s)


TDOP
with
SWB

TDOP
with
Bin
Overpack
Certification
Site
TRAMPAC
TRANSPORTATION
PARAMETERS
Parameter
Initials
Filter(
s)
Identification
Free
liquids
are
<
1%
of
payload
container
volume
Nonradioactive
pyrophorics
are
not
present
Radioactive
pyrophorics
are
<
1%
(
weight)

Explosives
are
not
present
Corrosives
are
not
present
Pressurized
containers
are
not
present
Sealed
containers
>
4
liters
are
not
present
55­
Gallon
drum
liner
(
if
present)
is
punctured/
vented
Flammable
VOCs
are
<
500
ppm
Radiation
Dose
Rate
is
<
200
mrem/
hour
__________

__________

__________

__________

__________

__________

__________

__________

__________

__________
1.
2.

3.
4.

5.
6.

7.
8.

9.
10.

MEASURED
PARAMETERS
Container
Parameter
Value
Error
Value
+
1x
Error
Value
+
2x
Error
Limit
Weight
(
lbs.)

Fissile
Mass
(
FGE)

Curie
Limits
(
Ci)
S100
Value
+
error
meets
limits
for
radionuclides
listed
in
Pipe
Overpack
or
S200
Appendix
2.3
(
S100)
or
Appendix
2.4
(
S200)
of
the
TRAMPAC
Yes/
No
Pipe
Overpack
only
TEST
CRITERIA
UFGTP
requirements
met
as
documented
in
Attachment
A
of
Appendix
5.7
of
the
TRAMPAC
Yes/
No
I
certify
that
the
above
container
meets
all
the
requirements
for
shipment
as
stated
in
the
TRAMPAC,
current
revision.
The
container
is
approved
for
shipment
or
overpacking.

_______________________________________________________/
_________________
TRANSPORTATION
CERTIFICATION
OFFICIAL
/
DATE
aFollow
instructions
in
Section
6.6.2.2
of
the
RFETS
TRAMPAC
Compliance
Plan.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
359
APPENDIX
9
Page
1
of
2
OVERPACK
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
OPCTCD)
a
IDENTIFICATION
PARAMETERS
Overpack
Container
ID
#
Overpack
Container
Bar
Code
#

Governing
Payload
Shipping
Category
Number
Governing
Decay
Heat
Limit
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
Overpack
Container
Type

SWB

TDOP
Overpacked
Container
Type(
s):

55­
Gallon
Drum

SWB

SWB
Overpack

85­
Gallon
Drum
Overpack

Bin
Overpack
Weight
Limit
(
lbs)
Fissile
Mass
Limit
FGE
Certification
Site
Content
Code
TRAMPAC
TRANSPORTATION
PARAMETERS
Radiation
Dose
Rate
 
200
mrem/
hour
INITIALS
Filter
Identification
1.
2.
3.
4.
5.

6.
7.
8.
9.
10.

OVERPACKED
CONTAINER
MEASURED
PARAMETERS
Overpacked
Container
ID
Number
Weight
(
lbs)
Error
(
lbs)
Decay
Heat
(
watts)
Error
(
watts)
Decay
Heat
Limit
(
watts)
Fissile
Mass
(
FGE)
2x
Error
(
FGE)
Hydrogen/

Flammable
Gas
Generation
Rate
(
mol/
s)
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
(
mol/
s)

 
Weight
and
error
of
empty
overpack
payload
container
(
if
applicable).

Total
(
A)

Total
RMS
Error
Total
+
RMS
Error
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
360
APPENDIX
9
Page
2
of
2
OVERPACK
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
OPCTCD)
a
CERTIFICATION
OF
COMPLIANCE
INITIALS
Total
weight
+
weight
error
 
limit
_____________

Total
fissile
mass
+
2x
fissile
mass
error
 
limit
_____________

Decay
heat
+
decay
heat
error
 
decay
heat
limit
of
governing
payload
shipping
category
for
each
analytical
category
payload
container
_____________

Hydrogen/
flammable
gas
generation
rate
 
hydrogen/
flammable
gas
generation
rate
limit
of
governing
payload
shipping
category
for
each
test
category
payload
container
_____________

I
certify
that
the
above
container
meets
all
the
requirements
for
shipment
as
stated
in
the
TRAMPAC,
current
revision.
The
overpack
is
approved
for
shipment
or
overpacking.

_______________________________________________________/
_________________
TRANSPORTATION
CERTIFICATION
OFFICIAL
/
DATE
a
Follow
instructions
in
Section
6.6.2.3
of
the
RFETS
TRAMPAC
Compliance
Plan.

*
Use
Column
1
for
the
following
six­
digit
notations
(
XX
YYYY):
10
0160,
10
0130,
10
0040,
and
20
0008.
Use
Column
2
for
all
other
six­
digit
notations.
m/
s/
mf
=
Moles/
second/
mole
fraction
(
see
the
TRUPACT­
II
SAR,
Appendix
1.3.5).
APPENDIX
10
Page
1
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
RFETS
Controlling
Procedure/
Document
TRAMPAC
Requirement
(
Section
Number)
RFETS
TRU
Waste
Management
Manual
Section
Title
and
Number
Procedure/
Document
Number
Title
2.0
CONTAINER
AND
PHYSICAL
PROPERTIES
2.1
Container
Description
Container
Descriptions
(
6.2.1)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
PRO­
J44­
RC&
I­
6600
Procured
Items
Inspection
and
Certification
MAN­
134­
PPM
Procurement
Program
Manual
1­
V51­
COEM­
DES­
210
Site
Engineering
Process
Procedure
PRO­
1034­
PEQA
Procurement
Engineering
and
Quality
Assurance
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
PRO­
1045­
WI­
001
Solid
Radioactive
Waste
Inspection
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
2.2
Dunnage
Dunnage
(
6.2.2)
4­
K47­
WEM­
WP1210
WEMS
Offsite
Shipping
Module
2.3
Container/
Assembly
Weight
and
Center
of
Gravity
Container/
Assembly
Weight
(
6.2.3)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
PRO­
1045­
WI­
001
Solid
Radioactive
Waste
Inspection
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
MAN­
092­
M&
TEM
Measuring
and
Test
Equipment
Management
4­
K47­
WEM­
WP1210
WEMS
Offsite
Shipping
Module
Container/
Assembly
Center
of
Gravity
(
6.2.3)
4­
K14­
TPO­
WO­
5032
Preparing
the
TRUPACT­
II
Drum
and
Standard
Box
Shipment
in
Building
664
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
355
APPENDIX
10
Page
2
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
2.4
Container
Marking
Container
Marking
(
6.2.4)
PRO­
T13­
Traffic­
306
Labeling
and
Marking
TRUPACT
Packages
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
2.5
Filter
Vents
Filter
Vents
(
6.2.5)
MAN­
134­
PPM
Procurement
Program
Manual
1­
V51­
COEM­
DES­
210
Site
Engineering
Process
Procedure
PRO­
1034­
PEQA
Procurement
Engineering
and
Quality
Assurance
PRO­
1045­
WI­
001
Solid
Radioactive
Waste
Inspection
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
2.6
Liquids
Liquids
(
6.2.6)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
D99­
WO­
1100
Radioactive
Waste
Packaging
Procedure
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
PRO­
1031­
WIPP­
1112
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review
PRO­
U76­
WC­
4030
Control
of
Waste
Nonconformances
5­
NDT­
TC­
1A
Training,
Qualification,
and
Certification
of
Nondestructive
Testing
Personnel
4­
H80­
776­
ASRF­
007
Visual
Examination
for
Confirmation
of
RTR1
PRO­
1358­
440­
VERP
Glovebox
and
C­
Cell
Waste
Operations
PRO­
1471­
VE­
771
Visual
Examination
for
Confirmation
of
RTR2
PRO­
1608­
VECRTR­
371
RTR
Visual
Examination
Confirmation,
Building
3713
95­
QAPjP­
0050
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
QAPjP)

2.7
Sharp
or
Heavy
Objects
Sharp
or
Heavy
Objects
(
6.2.7)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
1
This
procedure
is
inactive
as
of
November
6,
2001.

2
This
procedure
is
inactive
as
of
November
14,
2003.

3
This
procedure
is
inactive
as
of
August
12,
2003.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
356
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
APPENDIX
10
Page
3
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
2.8
Sealed
Containers
Sealed
Containers
(
6.2.8)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
PRO­
1031­
WIPP­
1112
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review
95­
QAPjP­
0050
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
QAPjP)

3.0
NUCLEAR
PROPERTIES
REQUIREMENTS
3.1
Nuclear
Criticality
Nuclear
Criticality
(
6.3.1)
RF/
RMRS­
97­
018
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
1­
MAN­
008­
WM­
001
Transuranic
(
TRU)
Waste
Management
Manual
3.2
Radiation
Dose
Rates
Radiation
Dose
Rates
(
6.3.2)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
1­
C80­
WO­
1102­
W/
RT
Waste/
Residue
Traveler
Instructions
4.0
CHEMICAL
PROPERTIES
REQUIREMENTS
4.1
Pyrophoric
Materials
Pyrophorics
(
6.4.1)
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
PRO­
1031­
WIPP­
1112
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Reporting
RF/
RMRS­
97­
018
RFETS
TRU
Waste
Acceptable
Knowledge
Supplemental
Information
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
357
APPENDIX
10
Page
4
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
4.2
Explosives,
Corrosives,

and
Compressed
Gases
Explosives,
Corrosives,
and
Compressed
Gases
(
6.4.2)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
MAN­
071­
IWCP
Integrated
Work
Control
Program
Manual
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
PRO­
1031­
WIPP­
1112
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review
95­
QAPjP­
0050
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
QAPjP)

4.3
Chemical
Composition
Chemical
Composition
(
6.4.3)
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
95­
QAPjP­
0050
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
QAPjP)

4.4
Chemical
Compatibility
Chemical
Compatibility
(
6.4.4)
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
5.0
GAS
GENERATION
REQUIREMENTS
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
5.1
Payload
Shipping
Category
Assignment
of
Shipping
Category
to
an
Individual
Payload
Package
(
6.5.1.2.1)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
PRO­
1031­
WIPP­
1112
TRU/
TRM
Waste
Visual
Verification
(
V2)
and
Data
Review
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
95­
QAPjP­
0050
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
QAPjP)
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
358
APPENDIX
10
Page
5
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
1­
PRO­
079­
WGI­
001
Waste
Characterization,
Generation,
and
Packaging
5.1
Payload
Shipping
Category
(
continued)
4­
D99­
WO­
1100
Solid
Radioactive
Waste
Packaging
Procedure
Compliance
With
Specific
Requirements
for
Total
Resistance
(
6.5.1.2.3)
1­
M12­
WO­
4034
Solid
Radioactive
Waste
Packaging
Requirements
Manual
4­
H80­
776­
ASRF­
007
Visual
Examination
for
Confirmation
of
RTR1
PRO­
1358­
440­
VERP
Glovebox
and
C­
Cell
Waste
Operations
PRO­
1471­
VE­
771
Visual
Examination
for
Confirmation
of
RTR2
PRO­
1608­
VECRTR­
371
RTR
Visual
Examination
Confirmation,
Building
3713
1­
C80­
WO­
1102­
W/
RT
Waste/
Residue
Traveler
Instructions
PRO­
1045­
WI­
001
Solid
Radioactive
Waste
Inspection
95­
QAPjP­
0050
Rocky
Flats
Environmental
Technology
Site
TRU
Waste
Characterization
Program
Quality
Assurance
Project
Plan
(
QAPjP)

L­
4146­
O
Headspace
Gas
Sampling
of
Waste
Containers4
L­
4231­
D
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold5
PRO­
1676­
HGAS­
S&
A
Headspace
Gas
Sampling
and
Analysis
Using
an
On­

Line
Integrated
System
5.2
Compliance
with
Flammable
(
Gas/
VOC)

Concentration
Limits
(
Analytical/
Test
Category)
Determination
of
Flammable
Volatile
Organic
Compounds
Concentration
(
6.5.2.1)
L­
4111­
X
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization4
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
Analytical
Category
Compliance
(
6.5.2.2)
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
1
This
procedure
is
inactive
as
of
November
6,
2001.

2
This
procedure
is
inactive
as
of
November
14,
2003.

3
This
procedure
is
inactive
as
of
August
12,
2003.

4
These
procedures
are
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.

5
This
procedure
has
been
cancelled
as
of
June
18,
2003,
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
359
PRO­
T43­
Traffic­
528
TRUACT­
II
Operations
APPENDIX
10
Page
6
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
L­
4146­
O
Headspace
Gas
Sampling
of
Waste
Containers1
Test
Category
Compliance
 
Measurement
(
6.5.2.3.1)
L­
4231­
D
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold2
PRO­
1676­
HGAS­
S&
A
Headspace
Gas
Sampling
and
Analysis
Using
an
On­

Line
Integrated
System
5.2
Compliance
with
Flammable
(
Gas/
VOC)

Concentration
Limits
(
Analytical/
Test
Category)

(
continued)
L­
4111­
X
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization1
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
Test
Category
Compliance
 
Full­

Drum
Testing
(
6.5.2.3.2)
RS­
020­
001
Gas
Generation
Testing
Program
Quality
Assurance
Project
Plan
L­
4146­
O
Headspace
Gas
Sampling
of
Waste
Containers1
L­
4231­
D
Headspace
Gas
Sampling
and
Analysis
Using
an
Automated
Manifold2
PRO­
1676­
HGAS­
S&
A
Headspace
Gas
Sampling
and
Analysis
Using
an
On­

Line
Integrated
System
L­
4111­
X
GC/
MS
Determination
of
Volatile
Organics
Waste
Characterization1
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
5.3
Venting
and
Aspiration
Venting
and
Aspiration
(
6.5.3)
PRO­
1141­
WP­
4701
Waste
Characterization
Gas
Sampling1
4­
G83­
WEM­
WP­
1209
WEMS
Waste
Package
Verification
and
Certification
6.0
PAYLOAD
ASSEMBLY
REQUIREMENTS
6.1
Requirements
Payload
Assembly
Requirements
(
6.6.1)
PRO­
077­
WIPP­
005
Management
of
Waste
Information
Prior
to
Transmittal
to
the
Waste
Records
Center
1
These
procedures
are
inactive
as
of
October
22,
2002.
Headspace
gas
sampling
with
SUMMA

canisters
has
been
discontinued
at
RFETS.

2
This
procedure
has
been
cancelled
as
of
June
18,
2003,
superseded
by
PRO­
1676­
HGAS­
S&
A,
Headspace
Gas
Sampling
and
Analysis
Using
an
On­
Line
Integrated
System.
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
360
APPENDIX
10
Page
7
of
7
TRUPACT­
II
TRANSPORTATION
REQUIREMENTS
MATRIX
FOR
RFETS
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
Procedure
for
Qualifying
Individual
Payload
Packages
(
Analytical)

(
6.6.2.1)
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
Appendix
6.1,
Procedure
for
Certification
of
Individual
Payload
Containers
Procedure
for
Qualifying
Individual
Payload
Packages
(
Test)
(
6.6.2.2)
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
Procedure
for
Certification
of
Overpack
Payload
Packages
(
6.6.2.3)
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
Appendix
6.2,
Procedure
for
Assembly
and
Certification
of
a
CH­
TRU
Payload
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Same
Shipping
Category
(
6.6.2.4)
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
PRO­
X05­
WC­
4018
Transuranic
(
TRU)
Waste
Certification
Appendix
6.3,
Mixing
of
Shipping
Categories
and
Determination
of
Flammability
Index
Procedure
for
Assembly
and
Certification
of
a
TRUPACT­
II
Payload
of
Different
Shipping
Categories
(
6.6.2.5)
PRO­
T43­
Traffic­
528
TRUPACT­
II
Operations
TRANSURANIC
(
TRU)
WASTE
1­
MAN­
008­
WM­
001
MANAGEMENT
MANUAL
VERSION
7
02/
12/
2004
PAGE
361
