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 <IP_ADDRESS> CH4   1,250 ppm Section <IP_ADDRESS>.1 Flammable ( Gas/ VOC) Concentration  MLEL Section <IP_ADDRESS>.1 Flammable ( Gas/ VOC) Concentration  MLEL Section <IP_ADDRESS>.2 All Payload Same Shipping Section <IP_ADDRESS> Yes No No IV Test Category Section <IP_ADDRESS> Measurement Section <IP_ADDRESS>.1 O. K. to Ship Section 6.6 Cannot Ship Mitigate ( Repackage or Full Drum Testing Section <IP_ADDRESS>.2 Mixing Section <IP_ADDRESS> Reconfigure Payload Section <IP_ADDRESS> or Go to Test Category Section <IP_ADDRESS> Analytical Section <IP_ADDRESS> I, II, III I, II, III Total Gas Generation Rate Limit Section <IP_ADDRESS>.2 CH4 1,250 ppm Section <IP_ADDRESS>.2 Flammability Index  50,000 for each Container Section <IP_ADDRESS> Decay Heat  Analytical Limit Section <IP_ADDRESS> 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 <IP_ADDRESS> All Payload Packages Same Shipping Section <IP_ADDRESS> <

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 VERSION 7 02/ 12/ 2004 PAGE 293 This page is intentionally blank TRANSURANIC ( TRU) WASTE 1 MAN 008 WM 001 MANAGEMENT MANUAL VERSION 7 02/ 12/ 2004 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/ 12/ 2004 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 MAN 008 WM 001 MANAGEMENT MANUAL VERSION 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 VERSION 7 02/ 12/ 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 MAN 008 WM 001 MANAGEMENT MANUAL 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 MAN 008 WM 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 1 MAN 008 WM 001 MANAGEMENT MANUAL VERSION 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 A<IP_ADDRESS>.

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 A<IP_ADDRESS> 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 A<IP_ADDRESS> 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.

A<IP_ADDRESS> 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 ( TRU) WASTE 1 MAN 008 WM 001 MANAGEMENT MANUAL VERSION 7 02/ 12/ 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 MAN 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 ( TRU) WASTE 1 MAN 008 WM 001 MANAGEMENT MANUAL VERSION 7 02/ 12/ 2004 PAGE 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 ( TRU) WASTE 1 MAN 008 WM 001 MANAGEMENT MANUAL VERSION 7 02/ 12/ 2004 PAGE 344 A4.5 Data Management ( continued)

RFETS Pre DOE/ WIPP 02 3122 Data Management ( continued)