ML15138A182

Radioactive Waste Process Control Program Manual

ML15138A182
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/28/2008
From:	Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15138A185	List: ML15138A176 ML15138A177 ML15138A182 MNS-15-028, Offsite Dose Calculation Manual (Odcm), Revision 55
References
MNS-15-028
Download: ML15138A182 (126)

Text

NEDL SDQA "C" RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM NEDL SDQA "C"

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM REVISION NUMBER 15 ISSUE DATE 1/30/08_ Reviews and Approvals Documented in PIP G-06-00560 & G-07-00841 Prepared by/ Date: DL Vaught/ 11/14/07_ Review by/ Date: GT Johnson / 11/16/07__

NGO Radwaste Staff NGO Radiation Protecti on CATAWBA MCGUIRE OCONEE Reviewed By/ Date BN Kimray/ 12/6/07___

Station Radiation Protection Reviewed By/ Date WK Carroll/ 11/14/07 Station Radwaste Chemistry Approved By/Date __RS Beagles/ _1/3/08______

Chemistry Manager Approved By/Date ___JA Pitesa/ _1/3/08____________

Station Manager Reviewed By/ Date: JR Litaker/_11/15/07_____

Station Radiation Protection Reviewed By/ Date ___OM Reid/12/7/07 __

Station Radwaste Chemistry Approved By/Date PA Hull/ 12/2/07_______

Chemistry Manager Approved By/Date __RT Repko/ _12/2/07_______

Station Manager Reviewed By/ Date: RA Bowser/ 12/1/07___

Station Radiation Protection Reviewed By/ Date _JA Cashion/ 11/19/07_____

Station Radwaste Chemistry Approved By/Date GM Barker/ 12/31/07__

Chemistry Manager Approved By/Date __DA Baxter/ 12/31/07__________

Station Manager Issued By: ____Dewey P Rochester/ 1/28/08____________

Technical Manager, Nuclear Chemistry

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP i NEDL SDQA "C" TABLE OF CONTENTS

1. INTRODUCTION.........................................................................................................................1 1.1 Purpose...................................................................................................................................1 1.2 Radioactive Waste Process Control Program Description.....................................................2 1.3 Radioactive Waste PCP Manual Contents.............................................................................2

2. APPLICABILITY.........................................................................................................................4 2.1 Liquid and Wet Radioactive Waste Disposal........................................................................4 2.2 Mixed Waste Disposal...........................................................................................................4 2.3 Radioactive Waste Oil Disposal............................................................................................5

2.4 Radioactive

Waste Interim Storage.......................................................................................6

3. REGULATORY REFERENCES................................................................................................6

3.1 Regulatory

Requirements.......................................................................................................6 3.2 Regulatory Guidance.............................................................................................................7 4. DUKE ENERGY PROGRAMMATIC REFERENCES...........................................................8

4.1 Oconee

Technical Specification 5.6.2 "Annual Radiological Environmental Operating Report"...................................................................................................................................8 4.2 Site-specific Selected Licensee Commitments......................................................................8

4.3 Oconee

UFSAR Chapter 11...................................................................................................8

4.4 Catawba

UFSAR Chapter 11.................................................................................................8 4.5 McGuire UFSAR Chapter 13.................................................................................................8 4.6 Duke Power Company QA Program "Topical Report".........................................................8 4.7 "CNS 10 CFR Part 61 Waste Classification and Waste Form Implementation Program"....8 4.8 "MNS 10 CFR Part 61 Waste Classification and Waste Form Implementation Program"...8 4.9 "ONS 10 CFR Part 61 Waste Classification and Waste Form Implementation Program"...8 4.10 Duke Energy Information Retention Policy..........................................................................8 4.11 NSD 701 "Records Management".........................................................................................9 4.12 NSD 703 "Administrative Instructions for Technical Procedures".......................................9 4.13 Catawba, McGuire & Oconee Environmental Work Practice (EWP) 2.8 "Used Oil"..........9 4.14 Catawba, McGuire & Oconee EWP 2.9 "Mixed Waste"......................................................9 RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP ii NEDL SDQA "C" 4.15 Supply Chain Document (SCD) 510 "Approved Suppliers List"..........................................9 4.16 SCD 520 "Audits of Suppliers".............................................................................................

9 4.17 SCD 285 "Procurement of QA Condition 2, 3, and 4 Items"................................................9 4.18 Operating Experience (OE) & Problem Investigation Process (PIP)....................................9

5. DEFINITIONS..............................................................................................................................9

5.1 Safety

Analysis Report (SAR)...............................................................................................

9 5.2 Selected Licensee Commitments (SLCs)...............................................................................9

5.3 10CFR

Part 61 "Licensing Requirements for Land Disposal of Radioactive Waste".........10 5.4 Free Standing Liquid (FSL).................................................................................................

10 5.5 Liquid Radioactive Wastes..................................................................................................

10 5.6 Wet Radioactive Wastes......................................................................................................10 5.7 Solidification........................................................................................................................10 5.8 High Integrity Container (HIC)...........................................................................................11 5.9 Dewatering...........................................................................................................................11 5.10 Unwatering (Gross Dewatering)..........................................................................................11 5.11 Mixed Waste........................................................................................................................11 5.12 QA Approved Supplier List.................................................................................................

12 5.13 Waste Batch.........................................................................................................................12 5.14 Waste Batch Mixing............................................................................................................12 5.15 Process Parameters...............................................................................................................12 5.16 Boundary Conditions/ Acceptance Criteria.........................................................................12 5.17 Topical Report (PIPs O-03-0624, M-03-2515, C-03-3385)................................................13

6. RESPONSIBILITIES.................................................................................................................13 6.1 Nuclear General Office........................................................................................................13 6.2 Nuclear Safety Review Board..............................................................................................14

6.3 Nuclear

Stations...................................................................................................................15

7. ADMINISTRATION OF THE PCP AND SUPPORT DOCUMENTS.................................16 7.1 PCP Manual Administration................................................................................................16 7.2 PCP Revision Reports to the NRC......................................................................................16 7.3 PCP Audit Process...............................................................................................................16 RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP iii NEDL SDQA "C" 7.4 PCP Manual Revision Record Retention Requirements......................................................16 7.5 Periodic cross-checks & comparisons (PIP O-03-0624 CAPR)..........................................17 7.6 PCP Implementing Procedure Requirements.......................................................................17

8. APPROVAL PROCESS FOR QA APPROVED SUPPLIERS..............................................18

8.1 Technical

Review and Approval..........................................................................................18 8.2 QA Supplier Evaluation.......................................................................................................18 8.3 QA Approved Supplier Program.........................................................................................18

9. PCP REQUIREMENTS FOR VENDOR PROCESSES AND SERVICES..........................19

9.1 Topical

Report (or equivalent).............................................................................................

19 9.2 10CFR61 Waste Form Compliance.....................................................................................19

9.3 10CFR61Waste

Classification Compliance.........................................................................19

9.4 Minimum

Requirements for Onsite Process Vendors.........................................................20 9.5 Minimum Requirements for Offsite PCP Process Vendors.................................................21

10. PCP SOLIDIFICATION PROCESS DESCRIPTION...........................................................21 10.1 Waste Characterization........................................................................................................21 10.2 Mixed Waste Characterization.............................................................................................2 1 10.3 Minimum Solidification Acceptance Criteria......................................................................22 10.4 Representative Waste Sample..............................................................................................2 2 10.5 Bench Scale Test Solidification...........................................................................................

23 10.6 Full Scale Solidification.......................................................................................................26 10.7 Product Verification of Full Scale Solidification.................................................................26 10.8 Inoperable Equipment (SLC Remedial Action Requirements)...........................................28 10.9 Solidification Document Retention......................................................................................28

11. PCP DEWATERING PROCESS DESCRIPTION.................................................................29 11.1 Dewatering Mechanical Filters (e.g., cartridge, bag, membrane)........................................29 11.2 Dewatering Slurries.............................................................................................................30 11.3 Additional Conservatism in Slurry Dewatering Procedures to Address Variation from the Topical Report (PIP O-03-0624, M-03-2515, C-03-3385)..................................................31 11.4 Dewatering Process Requirements......................................................................................33 11.5 Product Verification.............................................................................................................34 RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP iv NEDL SDQA "C" 11.6 Inoperable Equipment (SLC Remedial Action Requirements)...........................................36 11.7 Dewatering Document Retention.........................................................................................36

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 1 of 37 Rev.15 NEDL SDQA "C"

1. INTRODUCTION

1.1 Purpose

The Duke Energy Radioactive Waste Process Control Program Manual addresses all the requirements for the "Solid Radioactive Waste" section in Selected Licensing Commitment 16.11, "Radiological Effluent C ontrols" at each of the Duke Energy nuclear stations.

1.1.1 The Process Control Program (PCP) describes the administrative and operational controls used for the solidif ication of liquid or wet radioactive wastes and the dewatering of wet radioact ive wastes. Its purpose is to assure that the final disposal waste product meets applicable Federal, State and Disposal Site waste form requirement s for burial at a 10CFR61 licensed Low Level Waste (LLW) disposal site per the "Commitment" section of the Solid Radioactive Wastes section in SLC 16.11.

1.1.2 Waste

processing (solidification or dewatering as described below) equipment and services may be provided by Duke Energy or vendors. Any process used shall meet all applicable requirements of the Process Control Program.

1.1.3 This Corporate PCP section specifically describes the processes required to meet the Remedial Action requirements and Surveillance Requirements of ONS SLC 16.11.5, MNS SLC 16.11.11 a nd CNS SLC 16.11-11. These are summarized below:

1.1.3.1 Actions required prior to the next shipment for disposal of solidified or dewatered wastes if applicable regulatory requirements for solidified or dewa tered wastes are not satisfied (See Corporate PCP Sections 10 & 11).

1.1.3.2 Actions required prior to next solidification for shipment of waste for disposal at a 10CFR61 disposal site if a solidification test fails to verify solidification (See Corporate PCP Section 10).

1.1.3.3 Actions required whenever so lidification or dewatering for disposal is not performed in accordance with the PCP (See Corporate PCP Sections 10 & 11).

1.1.3.4 Actions required with the solid waste equipment incapable of meeting SLC 16.11 Solid Radioactive Waste requirements, or not in service (See Corporate PCP Sections 10 & 11).

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 2 of 37 Rev.15 NEDL SDQA "C" 1.1.3.5 The Surveillance Requirement pert ains only to solidification and is contained in section 10. "The Process Control Program shall be used to verify the Solidification of at least one representative test specimen from at least every tenth batch of each type of radioactive waste to be solidif ied for disposal at a 10CFR61 disposal site per the CO MMITMENT of this SLC."

1.1.4 It is the responsibility of the LLW generator to ensure that PCP requirements are met and that the condition of the wa ste is acceptable upon arrival at the disposal site.

1.2 Radioactive

Waste Process Control Program Description The Radioactive Waste PCP Manual meets NRC requirements for a Process Control Program. It is published as a manual and controlled copies are maintained in the following locations: Online PCP Manual: NEDL (Portal)/Licensing/ELL Document Nuclear General Office (NGO) Chemis try copy of the PCP Manual: NGO Chemistry Satellite File Archived film copies of revisions are maintained as described in APPENDIX F "Administration of the PCP and Support Documents"

1.3 Radioactive

Waste PCP Manual Contents The PCP manual is comprised of:

1.3.1 CORPORATE

PROCESS CONTROL PROGRAM The Corporate Process Control Program (PCP) describes the technical and operational requirements that shall be me t by each nuclear station to ensure final solidification or de watering radioactive waste products meet applicable federal and state disposal regulations. It also includes documentation of the required approvals for the current revision of the Corporate PCP. The requirements comprise a system wide program and are applicable to all of the nuclear stations as defined in their individual PCP program appendices described below.

1.3.2 APPENDIX

A "OCONEE NUCLEAR STATION PCP" Each station has a site specific PCP describing the Nuclear Generation documents used for implementing the requirements of the Corporate PCP. The station PCPs are contained in APPENDIX A, B and C. Each site PCP contains the following:

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 3 of 37 Rev.15 NEDL SDQA "C" Documentation of the required approvals for the current revision of the station PCP per APPENDIX E A list of Nuclear Generation procedures used to implement the Corporate PCP requirements A list of drawings showing plant radwaste systems interfaces with solidification and dewatering equipment used to meet the Corporate PCP Exceptions to the Corporate PCP

1.3.3 APPENDIX

B "Mc GUIRE NUCLEAR STATION PCP" (for content see 1.3.2) 1.3.4 APPENDIX C "CATAWBA NUCLEAR STATI ON PCP" (for content see 1.3.2) 1.3.5 APPENDIX D "APPROVED SUPPLIERS OF PCP SERVICES" This table contains the following: List of vendors approved for PCP services Describes approved services and specific requirements

1.3.6 APPENDIX

E "PCP MANUAL REVIEW AND APPROVAL REQUIREMENTS" This table describes who shall perform the reviews and approvals for each section of the PCP Manual.

1.3.7 APPENDIX

F "ADMINISTRATION OF THE PCP AND SUPPORT DOCUMENTS" This appendix is a comprehensive administrative guideline for control and distribution of the PCP manual and its supporting documents. Its contents are summarized below.

1.3.7.1 Administrative processes for the PCP manual Revisions, reviews and approvals Electronic publication 1.3.7.2 Administrative processes for Nuclear Generation implementing procedures Revisions Retention requirements RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 4 of 37 Rev.15 NEDL SDQA "C" 1.3.7.3 Administrative processes for use of vendor documents Revision review and evaluation for impact Control, distribution and retention of vendor documents

1.3.8 APPENDIX

G "WASTE PROCESSOR CHECKLIST" This is a template of technical re view criteria used by NGO Radiation Protection and Chemistry to pre-appr ove and renew radwaste vendors for inclusion in the QA Approved Supplier List.

1.3.9 APPENDIX

H "REVISION

SUMMARY

- LICENSEE INITIATED CHANGES" This appendix summarizes changes for current PCP manual revisions for reference during reviews and for record retention.

2. APPLICABILITY

2.1 Liquid

and Wet Radioacti ve Waste Disposal

2.1.1 Final

Safety Analysis Report Chapter 16, Selected Licensee Commitments, Section 11 requires that the Solid Radwaste System or an approved alternative process be used in accordance with a PCP for the solidification of liquid or wet radioactive wastes or the dewatering of wet radioactive wastes to be shipped for direct disposal at a 10CFR61 licensed disposal site such that the final product meets all applicable disposal site requirements.

2.1.2 These

"Process Control Program" requirements are applicable to all liquid or wet radioactive wastes that are being prepared for direct disposal at a 10CFR61 LLW disposal facility.

2.1.3 Radioactive

wastes shipped for off site processing in accordance with the processor's specifications and transportation requirements are not required to be solidified or dewatered to meet disposal requirements and are not subject to the solidification or dewatering requirements of this PCP.

2.2 Mixed

Waste Disposal

2.2.1 Environmental

Work Practice 2.9 "Mixed Waste" defines the Mixed Waste program at Duke Energy nuclear stations.

2.2.2 The PCP is only applicable when Mixed Waste is solidified for disposal at a 10CFR61 disposal site.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 5 of 37 Rev.15 NEDL SDQA "C" 2.2.3 NGO Chemistry shall approve the use of solidification for disposal of Mixed Waste. 2.2.4 If Mixed Waste is to be disposed of as LLW at a 10CFR 61 disposal site by rendering it non-hazardous using solidificat ion, the solidificati on shall be done according to PCP requirements.

2.2.5 Disposal

of Mixed Waste at a Low Level Radioactive Waste disposal site is prohibited except under the following conditions:

2.2.5.1 The waste shall meet the 40 CFR part 266 exemption criteria, 10 CFR part 61 disposal requirements and all applicable state and disposal site requirements.

2.2.5.2 Approval for disposal shall be obtained from the disposal site prior to disposal. (e.g., Barnwell):

A. No mixtures of radioactiv e waste and hazardous waste (Mixed Waste), as defined by 40CFR261 and S.C.

Management Registration 61-79.261, are acceptable for burial in Barnwell.

B. However, a Mixed Waste which was classified as hazardous solely because it exhibited one or more characteristics

defined in 40CFR261 Subpart C, but has been treated in a manner such that it no longer exhibits any of these characteristics, will be reviewed on a case-by-case basis for burial acceptance.

2.2.6 All vendors supplying solidification services for Mixed Waste shall meet the requirements of applicable PCP sect ions and be listed in Appendix D "Approved PCP Service Suppliers".

2.3 Radioactive

Waste Oil Disposal

2.3.1 Radioactively

contaminated oil is to be managed as described in the EWP 2.8 "Used Oil".

2.3.2 Each disposal site defines the acceptable threshold fo r incidental levels of waste petroleum-based oil (e.g., less than 1% by volume). Solidified waste

containing oil shipped to a 10CFR61 disposal site shall meet the applicable requirements of this Process Control Program and all applicable disposal site acceptance criteria.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 6 of 37 Rev.15 NEDL SDQA "C" 2.3.3 If a disposal site accepts greater than incidental concentrations of oil to be solidified for disposal, an oil-specific procedure that meets the requirements of this PCP and the acceptance criteria of that disposal site shall be used (e.g., on a case-by-case basis, SCDHEC may approve solidification of synthetic oils for burial at the Barnwell, SC LLW disposal site).

2.4 Radioactive

Waste Interim Storage Nuclear Generation procedures shall be established to ensure that all of the following interim storage requirements are met.

2.4.1 Any processed (i.e., solidified or dewatered) radioactive waste that is stored for an interim period in a disposal contai ner shall be packaged such that there is no interaction between th e waste and its container.

2.4.2 If applicable, Certificates of Compliance shall be maintained at each station for all waste disposal containe rs used for interim storage.

2.4.3 Vendor

supplied containers used for st orage shall be ha ndled and stored according to applicable guidance in vendor procedures, including chemical compatibility requirements.

3. REGULATORY REFERENCES

3.1 Regulatory

Requirements The use of and content of the PCP addresses requirements found in the following regulations:

3.1.1 10CFR20, "Standards for Protec tion Against Radiation" 3.1.2 10CFR50, "Domestic Licensing of Production and Utilization Facilities" 3.1.3 10CFR61, "Licensing Requirements for Land Disposal of Radioactive Waste" 3.1.4 l0CFR7l, "Packaging and Transporta tion of Radioactive Materials" 3.1.5 40CFR, "Protection of Environment" 3.1.6 40 CFR Part 266 "Storage, Treatment, Tr ansportation, and Disposal of Mixed Waste" 3.1.7 Licensed radioactive wast e burial site criteria RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 7 of 37 Rev.15 NEDL SDQA "C"

3.1.8 State

hazardous waste regulations

3.2 Regulatory

Guidance In order to assure compli ance with the above regula tions, the NRC has provided guidance in the following documents:

3.2.1 NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" 3.2.2 NUREG-0452, "Standard Technical Specifications for Westinghouse PWR's" (Superseded by NUREG 1431) 3.2.3 NUREG-1431 "Standard Technical Specifications Westinghouse Plants" 3.2.4 NUREG-1430 "Standard Technical Specifications Babcock and Wilcox Plants" 3.2.5 NUREG-800 "Standard Review Plan

", Section 11.4 "Solid Waste Management Systems"

3.2.6 NUREG

800, Section 11.4, Appendix -A, "Design Guidance for Temporary Onsite Storage of Low Level Radioactive Waste"

3.2.7 Branch

Technical Position - ETSB 11-3, "Design Guidance of Solid Radioactive Waste Management Systems" 3.2.8 NRC Review Criteria for Solid Waste Management Systems

3.2.9 Regulatory

Guide 1.143, "Design Gu idance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Plants" 3.2.10 NRC "TECHNICAL POSITION ON WAS TE FORM" Revision 1 (January 1991) 3.2.11 ANSI/ANS-40.37-1993 "mobile radioactive waste processing systems" RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 8 of 37 Rev.15 NEDL SDQA "C"

4. DUKE ENERGY PROGRAMMATIC REFERENCES

4.1 Oconee

Technical Specification 5.6.2 "Annual Radiological Environmental Operating Report" 4.2 Site-specific Selected Licensee Commitments

4.2.1 Catawba

SLC 16.11-11 "Solid Radioactive Waste"

4.2.2 Catawba

SLC 16.11-16 "Annual Radiological Environmental Operating Report and Radioactive E ffluent Release Report"

4.2.3 McGuire

SLC 16.11.11 "Solid Radioactive Waste"

4.2.4 McGuire

SLC 16.11.17 "Radioactive Effluent Release Report"

4.2.5 Oconee

SLC 16.11.5 "Solid Radioactive Waste"

4.3 Oconee

UFSAR Chapter 11

4.4 Catawba

UFSAR Chapter 11

4.5 McGuire

UFSAR Chapter 13 4.6 Duke Power Company QA Program "Topical Report" 4.7 "CNS 10 CFR Part 61 Waste Classifica tion and Waste Form Implementation Program" 4.8 "MNS 10 CFR Part 61 Waste Classificati on and Waste Form Implementation Program" 4.9 "ONS 10 CFR Part 61 Waste Classificati on and Waste Form Implementation Program" 4.10 Duke Energy Information Retention Policy Ref: (Legal 109, 10CFR20 Appe ndix G (III.A.3), 10CFR61.80)

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 9 of 37 Rev.15 NEDL SDQA "C" 4.11 NSD 701 "Records Management" 4.12 NSD 703 "Administrative Instructions for Technical Procedures" 4.13 Catawba, McGuire & Oconee Environmental Work Practice (EWP) 2.8 "Used Oil" 4.14 Catawba, McGuire & Oconee EWP 2.9 "Mixed Waste" 4.15 Supply Chain Document (SCD) 510 "Approved Suppliers List" 4.16 SCD 520 "Audits of Suppliers" 4.17 SCD 285 "Procurement of QA Co ndition 2, 3, and 4 Items" 4.18 Operating Experience (OE) & Problem Investigation Process (PIP) 4.18.1 G-99-00349 (NGO Radwaste Support PCP evaluation) 4.18.2 C-99-05094 (SLC 16.11 Issues related to PCP requirements) 4.18.3 G-00-401 (QA Audit -General Office Assessment SA-00-29(GO) (RA))

4.18.4 O-00-4680 (ONS filter dewatering procedure use) 4.18.5 C-01-02522 (2001 CNS NRC Audit) 4.18.6 O-01-01067 (Filter HIC dewa tering clarification) 4.18.7 G-02-00272 (QA Audit -Assessment GO-02-31(NPA) NSD) 4.18.8 O-03-0624, M-03-2515, C-03-3385 (ONS FS L Failure Root Cause)

5. DEFINITIONS

5.1 Safety

Analysis Report (SAR)

The station's Technical Specifi cations (Tech Specs) updated fi nal safety analysis report, licensee commitments, safety evaluation reports and the facility operating license.

5.2 Selected

Licensee Commitments (SLCs) Commitments to control important plant equipment and operating conditions not controlled elsewhere. Operational commitments which are to be removed from existing station Tech Specs may be included in the SLC program. Also included in this program can be selected NRC commitments contained in licensing documents such as the RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 10 of 37 Rev.15 NEDL SDQA "C" station's SERs, LERs, violation responses , generic letter and bulletin responses, submittal documents and other Duke letters to the NRC.

5.3 10CFR

Part 61 "Licensing Requirements fo r Land Disposal of Radioactive Waste" This NRC regulation requires that low-level radioactive waste (LLW) meet certain waste form acceptance criteria in order to be received for disposal at NRC and Agreement State licensed radioactive waste disposal sites.

5.4 Free Standing Liquid (FSL)

FSL is liquid that is in a disposal co ntainer but is not bound by the waste in the container. FSL is the liquid available for rele ase if disposal container integrity is lost (e.g., punctured). The amount of FSL in a radioa ctive waste disposal container shall be less than a specified threshold in order to meet 10CFR61, state and disposal site requirements for disposal.

5.5 Liquid

Radioactive Wastes Radioactive wastes comprised primarily of water containing a combination of dissolved and suspended solids (e.g., evaporator concentrates, lab wastes, floor and equipment drain water, laundry, wet waste decant or drainage, etc.).

5.6 Wet Radioactive Wastes Wet radioactive wastes are solid radioactive wastes containing l oosely bound liquid that can collect in the disposal container as FSL (e.g., slurry wastes are comprised primarily of solid particles suspended in loosely bound in terstitial water, spent mechanical filters are solid materials that are adsorb ent or porous and retain liquid).

5.7 Solidification

Solidification is a pr ocess that converts radioactive waste into a product meeting 10CFR61, State and disposal site requiremen ts for waste-form stability and FSL. Solidification is accomplished by mixing measured amounts of liquid or wet radioactive waste, binder and required additives that, after sufficient curing time, produce a solid homogeneous, freestanding monolith. At the end of the curing period, the absence of excessive FSL is verified either by confirmation that the PCP was followed or by physical verification/testing.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 11 of 37 Rev.15 NEDL SDQA "C" 5.8 High Integrity Container (HIC)

Disposal containers that have been a pproved by the NRC for disposal of Class A unstable, Class B or Class C LLW and meet the long term stability requirements of 10CFR61 and the disposal site.

5.9 Dewatering

Dewatering as used in this document is the removal of liquid using a process that is required to meet the requirements of th is PCP. Dewatering removes the loosely bound liquid from a wet radioactive waste such that accumulation of Fr ee Standing Liquid in the disposal container is un likely to approach the disposal limit threshold values as defined by applicable regulations and disposal site criteria. NRC regulations require that the process used to dewater radioactive wastes to meet disposal criteria shall be governed by a PCP.

5.9.1 10CFR61

FSL criteria requires less than 0.5% FSL by waste volume per container or less than 1.0% FSL if a hi gh integrity container (HIC) is used.

5.9.2 Typically, liquid and wet wastes are pre-st aged in vented tanks or containers and are therefore degassed prior to th e dewatering process. However, all vendor-required venting practi ces should be adhered to.

5.10 Unwatering (Gross Dewatering) Unwatering as used in this document is the removal of water using a process that is not required to meet the requirements of this PCP. Unwatering removes loosely bound excess or freeboard water from wet radioactive wastes such that only the requirements for transportation set forth in 49CFR are satisfied (e.g., unwatering may be used to prepare waste for shipment to an approved offsite processor who will perform additional processing that will meet the final disposal requirements).

5.11 Mixed Waste Defined in Resource Conservation Recovery Act (RCRA) as amended by the Federal Facility Compliance Act of 1992, a Mixed Waste contains both RCRA hazardous waste and source, special nuclear, or byproduct material subject to the Atomic Energy Act of 1954, as amended. The use of solidifica tion to render Mixed Wastes non-hazardous shall ensure that the final product meets all waste form requirements applicable to radioactive waste disposal at a 10CFR61 disposal site (R ef: 3.1.6. "40 CFR Part 266").

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 12 of 37 Rev.15 NEDL SDQA "C" 5.12 QA Approved Supplier List Radwaste vendors approved to provid e PCP processing are included on the QA Approved Supplier List and are subject to the requirements and audits of that program.

5.13 Waste Batch A "batch" shall be defined as an isolated quantity of waste to be processed having essentially consistent physical and chemical characteristics.

5.14 Waste Batch Mixing A Waste Batch shall be adequately mixed using a proceduralized process such as agitation via mixers, air spargi ng or recirculating flow which meets a specified minimum rate that has been determined to provide a representative sample for the vessel.

5.15 Process Parameters Those conditions measured or observed during a solidification or de watering process to ensure an acceptable product. These are determined for each waste type and are specific to the process method used.

5.16 Boundary Conditions/ Acceptance Criteria 5.16.1 Solidification Boundary Conditions or Acceptance Criteria are defined as, the bounding numerical values for solidification process parameters that produce an acceptable product.

5.16.1.1 The Boundary Conditions are verified by using a Bench Scale Test Solidification.

5.16.1.2 A Bench Scale Test Solidification is performed on a small representative sample of the Waste Batch using the prescribed formulation and conditions that model those parameters critical to the full scale solidification process 5.16.1.3 The Bench Scale Test product is then verified to meet the acceptance criteria for that waste form.

5.16.1.4 For Mixed Waste solidification, the Boundary Condition values also ensure that the final so lidified product is rendered non-hazardous and are verified through lab testing of the Bench Scale Test product.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 13 of 37 Rev.15 NEDL SDQA "C" 5.16.2 Dewatering Boundary Conditions or Acceptance Criteria are defined as the bounding numerical values for process parameters that ensure free standing liquid requirements are met.

5.16.2.1 Media: Acceptance Criteria for dewatering process media in disposal containers (e.g., HICs) have been determined by vendor tests using real or simulated waste to demonstrate the adequacy of the dewatering process for each combination of waste type and container. These tests are documented in dewatering Topical

Reports, or equivalent, that sha ll be approved by the NRC before the containers are certified for use. The Acceptance Criteria are then incorporated into the dewatering procedures for each combination of waste type and container.

5.16.2.2 Filters: Acceptance criteria for mechanical filters (e.g., cartridge, bag, membranes, etc.) are derived from tests performed on the various types of filters in use. Tests performed by Duke Energy should be documented in a retrievable manner (e.g., PIP, Memo in Master file, etc.). Acceptance criteria are then incorporated into the applicable procedure for each filter type (e.g., drainage time, drainage conditions, etc.).

5.17 Topical Report (PIPs O-03-0624, M-03-2515, C-03-3385)

A Topical Report provides the basis for a PCP technology & process. It documents test results that demonstrate regulatory requirements were met during the regulatory required testing for solidification or dewatering t echnologies and processes. All currently approved processes developed to dewater or solidify waste have been approved by the NRC based their review of the Topical Report for that process. T opical report testing was designed to envelope the worst case de watering scenarios given the industry's then current practices. As with any topical based program, the critical conditions and parameters identified during testing are incorporated into the implementing process with enough conservative margin to ensure success if you operate within the enveloping conditions and assumptions of the tests performed. When actual conditions vary from the conditions in the specific tests performed for the Topical Report, the correlation with the Topical testing is diminished and degree of conservatism must increase to compensate.

6. RESPONSIBILITIES

6.1 Nuclear

General Office 6.1.1 NGO Chemistry is the owner, sponsor and administrator for the PCP including the following activities:

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 14 of 37 Rev.15 NEDL SDQA "C" 6.1.1.1 Revises and publishes PCP Manual per APPENDIX F "Administration of the PCP and Support Documents" 6.1.1.2 Technical contact for PCP issues 6.1.1.3 Ensures corporate Chemistry program complies with applicable PCP requirements 6.1.1.4 Supports nuclear site Chemistry programs in complying with applicable PCP requirements 6.1.1.5 Provides review and approval of PCP service providers 6.1.1.6 Authors and approves PCP Manua l revisions per APPENDIX E "PCP Manual Review and Approval Requirements"

6.1.2 Nuclear

General Office Radiation Protection (RP) 6.1.2.1 Ensures corporate RP program complies with applicable PCP requirements 6.1.2.2 Supports nuclear site RP programs in complying with applicable PCP requirements 6.1.2.3 Provides review and approval of radioactive waste processors 6.1.2.4 Reviews PCP revisions per APPE NDIX E "PCP Manual Review and Approval Requirements"

6.1.3 Nuclear

Supply Chain 6.1.3.1 Maintains PCP vendors in Approved QA supplier list 6.1.3.2 Communicates NUPIC QA audits and issues related to PCP vendors to NGO Chemistry Radwaste support staff

6.2 Nuclear

Safety Review Board Audits of the Process Control Program and implementing procedures for Solidification of radioactive wastes shall be performed under the cogni zance of the NSRB per Duke Power Company QA Program "Topical Report".

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6.3 Nuclear

Stations The PCP applies to all liquid or wet radioactive waste generate d at the nuclear site when it is solidified or dewatere d for direct disposal at a 10CFR61 disposal site. Any group that has responsibility for activities that generate or manage these wastes shall ensure their programs and processes comply with and support compliance with the applicable portions of the PCP. The following responsib ilities are currently identified within specific groups or positions, but will be applicable to any group that has the responsibility. Any changes in these responsibilities and the groups to whom they are assigned should be evaluated for impact and potential incorporation into the PCP Manual.

6.3.1 Station

Manager approves PCP revisions per APPENDIX E "PCP Manual Review and Approval Requirements"

6.3.2 Station

Line Management responsible for programs impacting the PCP ensures those programs comply with the site PCP. Currently identified program owners:

6.3.2.1 Station Chemistry Manager approves PCP revisions per APPENDIX E "PCP Manual Review and Approval Requirements" 6.3.2.2 Station Chemistry General Supervisors ensure Chemistry programs and resources comply with and support the PCP

Manual, (e.g., site PCP, dewatering procedures) 6.3.2.3 Station RP Management ensures RP programs and resources comply with and support the PCP Manual, (e.g., site PCP, filter

dewatering, shipping process inte rface with PCP activities)

6.3.3 Station

Staff and Line Supervisors ensure applicable area-specific procedures and activities comply with the PCP 6.3.3.1 Station Chemistry Staff A. Ensures site PCP complies with the Corporate PCP B. Ensures Chemistry dewatering or solidification procedures comply with the Corporate PCP C. Serves as Subject Matter Expert on Chemistry PCP processes at the site RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 16 of 37 Rev.15 NEDL SDQA "C" D. Reviews PCP revisions per APPENDIX E "PCP Manual Review and Approval Requirements" 6.3.3.2 Station Radiation Protection Sta ff and/or RM&C Supervision A. Ensure RP procedures comply with applicable PCP Manual requirements (e.g., filter de watering/disposal, shipping procedures, shipping and disposal paperwork)

B. Reviews PCP revisions per APPENDIX E "PCP Manual Review and Approval Requirements"

6.3.4 Station

Technicians ensure current documents are used to implement PCP-related activities 6.3.4.1 Station Chemistry Technicians implement applicable portions of the site PCP, (e.g., dewatering process media) 6.3.4.2 Station Radiation Protection Technicians implement applicable portions of the site PCP, (e.g., dewatering mechanical filters)

6.3.5 Regulatory

Compliance incorporates the PCP revision summary report into the site Annual Effluent report.

7. ADMINISTRATION OF THE PCP AND SUPPORT DOCUMENTS 7.1 PCP Manual Administration See APPENDIX F "Administration of the PCP and Support Documents" 7.2 PCP Revision Reports to the NRC Revisions to the PCP shall be reported to the NRC each year as described in APPENDIX F "Administration of the PCP and Support Documents".

7.3 PCP Audit Process The Duke Power Company QA Program "Topical Report" describes the internal auditing requirements for the Corporate PCP and Nuclear Generation implementing procedures under the cognizance of the NSRB at each station and the General Office.

7.4 PCP Manual Revision Reco rd Retention Requirements See APPENDIX F "Administration of the PCP and Support Documents" RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 17 of 37 Rev.15 NEDL SDQA "C"

7.5 Periodic

cross-checks & comp arisons (PIP O-03-0624 CAPR) Periodic cross-checks & comparisons of each nuclear site's dewatering process guidance, dewatering techniques and equipment will be performed as part of the following activities:

7.5.1 Every

other year during the annual Chem istry Functional Area Evaluation as part of section 8.4 "Implementation of Process Control Program" of the Performance Attributes Matrix

7.5.2 Other

benchmarking opportunities (e.g., benchmark trips by Radwaste personnel, annual Radwaste workshop discussion groups identify current industry practices and site contacts for comparison of practices 7.6 PCP Implementing Procedure Requirements

7.6.1 Nuclear

Generation procedures shall be established to ensure that all requirements for solidification or dewatering are met when performed by site-assigned personnel.

7.6.2 The administrative requirements for PCP implementing procedures are described in APPENDIX F "Admin istration of the PCP and Support Documents".

7.6.2.1 Completed procedures documenting the solidification verification records described in section 10 shall be maintained by Duke Power Company on each vessel of solidified waste as described in section 5.5 of APPENDIX F.

7.6.2.2 Documentation of the dewatering verification records described in section 11 shall be maintained by Duke Power Company on each vessel of dewatered waste as described in section 5.5 of APPENDIX F.

7.6.3 Vendors

providing onsite PCP services may use their own vendor procedures to perform PCP services using non-installed equipment as described in NSD 703 provided they meet the applicable requirements of the PCP Manual.

7.6.4 Vendor

documents directing solidification or dewateri ng activities of site assigned personnel shall be incorporated into site implementing procedures as described in APPENDIX F.

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8. APPROVAL PROCESS FOR QA APPROVED SUPPLIERS Any supplier shall be approved and incorporated into the QA Approved Supplier Program prior to being contracted for PCP services.

8.1 Technical

Review and Approval Before vendors can provide PCP related servic es, they shall be evaluated against the Duke Energy Radioactive Waste PCP Manual and approved by the Technical Manager, Nuclear Chemistry or his designee.

8.1.1 Prior

to awarding a contract to a supplier for processing site radioactive waste, vendors are subjected to a review using criteria outlined in APPENDIX G "Waste Processor Checklist" 8.1.2 If the vendor provides PCP related serv ices, the vendor PCP and other related program documents are evaluated to ensure they meet the applicable requirements of the Duke Energy Radioactive Waste PCP Manual as

described in section 9 below.

8.1.3 The results of these reviews should be documented in a PIP for future reference.

8.2 QA Supplier Evaluation Upon meeting the requirements of the techni cal review, the supplie r is evaluated for incorporation into the QA Supplier program in accordance with the requirements of Duke Energy Nuclear Quality Assurance Program.

8.3 QA Approved Supplier Program All vendors approved to provide PCP related services are included in the QA Approved Suppliers List. The QA processes that apply are described in the following Supply Chain documents 8.3.1 SCD 510 "Approved Suppliers List" 8.3.2 SCD 520 "Audits of Suppliers" 8.3.3 SCD 285 "Procurement of QA Condition 2, 3, and 4 Items" RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 19 of 37 Rev.15 NEDL SDQA "C"

9. PCP REQUIREMENTS FOR VENDOR PROCESSES AND SERVICES

9.1 Topical

Report (or equivalent)

Any vendor service or vendor supplied processe s utilized for solidif ication or dewatering by Duke Energy shall have a Topical Report or other form of certification documenting appropriate regulatory approval of the process and associated containers, or shall supply to Duke Energy sufficient documentation of the process and test results to demonstrate that an acceptable product will be produced using the described solidification or dewatering process.

9.2 10CFR61

Waste Form Compliance 9.2.1 The vendor(s) approved for solidification or dewatering services shall have regulatory certification documenting compliance with waste form requirements in the final product, or shall supply Duke Energy sufficient documentation to demonstrate waste form compliance.

9.2.2 Any vendor providing High Integrity Containers (HIC's) to Duke Energy shall provide proof of regulatory approval documenting compliance with waste form requirements, or shall supply Duke Energy sufficient documentation to demonstrate waste form compliance.

9.2.3 All vendor Topical Reports or equivalent shall certif y that the final product conforms to the appropriate waste form for Class A, B, or C waste.

9.2.4 Vendor

PCP Service Quality Requirements QA Approved PCP Service Suppliers shall meet the applicable quality requirements set forth in their Purchase Order. Examples of such requirements are described in APPENDIX D "Approved PCP Service Suppliers".

9.3 10CFR61Waste

Classification Compliance 9.3.1 Each container of processed (i.e., solidified or dewatered) waste shall be classified as Class A, B, or C waste using the "10 CFR Part 61 Waste Classification and Waste Form Implementation Program" for the applicable station.

9.3.2 Each container of processed waste shall be certified to the appropriate waste form for Class A, B or C waste. Greater-than-Class C waste may be approved for disposal on a case-by-case basis with appropriate approval from the disposal site and agreement state.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 20 of 37 Rev.15 NEDL SDQA "C" 9.3.3 Each container of processed Mixed Waste shall be certified to be non-hazardous.

9.4 Minimum

Requirements for Onsite Process Vendors

9.4.1 Vendors

providing PCP services onsite sh all fulfill all of the applicable requirements in the Radioactive Waste PCP Manual and the a pplicable quality requirements set forth in the Purchase Order prior to shipment of the solidified or dewatered waste offsite for disposal.

9.4.2 Onsite

Vendor System/Equipment Interface Requirements:

9.4.2.1 The vendor Topical Report or documentation supplied to Duke Energy shall include a detailed sy stem or process description of all vendor interfaces with installed plant equipment.

9.4.2.2 Drawings or diagrams shall be included detailing all solidification and dewatering system interfaces with installed plant systems and equipment.

9.4.2.3 Solidification system ventilation discharge is treated or routed to the plant's auxiliary building or radwaste facility ventilation system to meet effluent discharge requirements.

9.4.2.4 Decanted radioactive liquid is processed as required or routed to the station liquid radwaste systems.

9.4.2.5 This information may be included as part of a Topical Report furnished by the equipment manufactu rer or supplier or as part of the station specific Final Safety Analysis Report.

9.4.3 Onsite

Vendor System Design Requirements 9.4.3.1 The vendor Topical Report or equivalent documentation supplied to the Duke Energy shall include a statement that the design, construction, operation and quality assurance provisions are in accordance with NRC ETSB Branch Technical Position 11-3 and Regulatory Guide 1.143.

9.4.3.2 Permanent or portable solidification and dewatering systems used at nuclear sites shall meet the design, construction, operation and quality assurance provisions of NRC ETSB Branch Technical Position 11-3 and Regulatory Guide 1.143.

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9.5 Minimum

Requirements for Offsite PCP Process Vendors Vendors providing PCP services offsite shall meet the requirements of their PCP process and the applicable quality requirements set forth in the Nuclear Supply Chain Purchase Order prior to disposal of the final product.

10. PCP SOLIDIFICATION PROCESS DESCRIPTION Waste solidification at Duke Ener gy nuclear stations shall be performed in a manner equivalent to the process described below using approved procedures in a controlled and quality fashion which ensures that all applicable regulatory and disposal site criteria are met. Procedures used to direct solidification shall include the adequate detail to implem ent a process equivalent to that described below.

NOTE: Whenever a solidification process is used to meet 10CFR61 disposal site requirements, "Surveillance Requirements" in ONS SLC 16.11.5, MNS SLC 16.11.11 and CNS SLC 16.11-11 shall be fulfilled by using procedures that meet or surpass the Bench Scale Test solidification verification and frequency requirements below or by verifying these requirements are met by the vendor program/process being used.

10.1 Waste Characterization The waste sample shall be characterized chemically, physically and radiologically. Sample analyses such as the following shall be performed as outlined in site-specific procedures for the applicable waste form and solidification media to be used.

10.1.1 Waste pH 10.1.2 Waste density 10.1.3 Waste boron concentration 10.1.4 Waste oil content 10.1.5 Gamma Analysis 10.2 Mixed Waste Characterization 10.2.1 Process knowledge may be used for hazardous waste characterization with approval by the appropriate knowledgeable individual.

10.2.2 If process knowledge cannot be used, th e hazardous characte ristics shall be determined before solidification using an approved method.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 22 of 37 Rev.15 NEDL SDQA "C" 10.2.3 The disposal site shall be notified to obtain pre-approval for disposal whenever a waste determined to be a Mixed Waste is being rendered non- hazardous by solidification.

10.3 Minimum Solidification Acceptance Criteria Minimum Solidification Acceptance criteria are listed below, but additional criteria may be added by the disposal site and shall be included in the verification process:

10.3.1 FSL Criteria: Liquid wastes , or wastes containing li quid, shall be converted into a form that contains as little free standing and non-corro sive liquid as is reasonably achievable, but in no case shall the liquid exceed 1% of the volume of the waste when the waste is in a disposal container designed to ensure stability, or 0.5% of the volume of the waste for waste in a disposal container not designed to meet stability requirements and/or waste processed to meet waste form stability requirements independent of the disposal container.

10.3.2 Physical Criteria: the solidified prod uct shall be a free-standing, non-friable and homogeneous monolith.

10.3.3 Chemical Criteria: The solidified product of a Mixed Waste shall be rendered non-hazardous.

10.4 Representative Waste Sample A representative sample of the waste to be solidified shall be obtained by a process equivalent to the following as outlined in a pproved procedures for the applicable waste form and solidification media.

10.4.1 A representative waste sample shall include the characteristics of the waste that are critical to the soli dification process being used 10.4.2 The contents of the container to be sampled shall be adequately mixed to achieve a homogeneous mixture 10.4.3 During the mixing and sampling period, the vessel shall not be placed in a transfer mode nor shall additional waste be received 10.4.4 Vessel level readings or input isolation shall be documented at the time of mixing initiation, sampling, and process initiation 10.4.5 Recirculation or mixing time shall be uninterrupted until sample collection RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 23 of 37 Rev.15 NEDL SDQA "C" 10.5 Bench Scale Test Solidification The boundary conditions are demonstrated by pr oducing a solidified product during the Bench Scale Test that meets the minimum acceptance criteria described above. The test-proven boundary conditions will then be used to perform a full scale solidification that meets these same criteria. A Bench Scale Test Solidification shall be performed using a process similar to the following:

10.5.1 Frequency of Bench Scale Testing (Ref: Solid Waste SLC Surveillance Requirement) 10.5.1.1 The minimum frequency for performing Bench Scale Testing shall be as described in the Solid Waste SLC Surveillance requirement: The PCP shall be used to verify at least one test specimen from at least every tenth batch of each type of waste to be solidified for disposal at a 10CFR61 disposal site.

10.5.1.2 Where variability of critical waste parameters is known to be great or is uncertain, the follo wing more conservative frequency shall be followed:

A. An initial Bench Scale Test solidification shall be performed prior to the full-scale solidification of each distinct batch of waste. B. Where multiple solidifications of the same batch of waste occur after the successful initial Bench Scale Test, a Bench Scale Test shall be repeated at a frequency of no less than once per ten solidificatio ns of that batch.

10.5.2 Establish process parameters and boundary conditions Process parameters and boundary conditions (or a method by-which to establish them) are usually given in vendor procedures which have already been certified for a given radioactive waste type. Process parameters should include any of the followi ng that are applicable: Waste form Waste to solidification agent ratio Amount of each solidification additive Waste pH Waste boron concentration Waste density RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 24 of 37 Rev.15 NEDL SDQA "C" Waste oil content Mixer speed Mixing time Curing time Specific activity Pre-solidification hazardous waste characterization 10.5.3 Mixed Waste (additional requirements) 10.5.3.1 Vendor procedures used to solidify Mixed Waste shall be certified to be applicable to the specific waste stream being

processed.

10.5.3.2 For Mixed Waste solidified by D uke Energy personnel, a Nuclear Generation procedure shall be de veloped based on an approved demonstrated process for each specific Mixed Waste stream.

10.5.4 Bench Scale Test Solidificat ion product verification:

Physical testing and laboratory analysis, as described below, shall be utilized to determine if the Bench Scale Test solidified waste sample is a free-standing monolith with the % FSL volume within the acceptance criteria. This testing shall consist of:

10.5.4.1 The % by volume FSL criteria sh all be verified by visual inspection or by physical measurement of any visible FSL 10.5.4.2 Physical testing to determine if a solidified waste is a free-standing monolith shall consist of:

A. Visual inspection AND B. Probe penetration testing to demonstrate non-friability 10.5.5 Mixed Waste Bench Scale Test Solidif ication product verification:

10.5.5.1 In addition to the physical tests listed above, laboratory analysis using approved EPA methods shall be performed to determine if a solidified Mixed Waste has b een rendered non-hazardous.

10.5.5.2 Note that the solidified Mixed Wa ste need only be analyzed for those hazardous properties it exhibited prior to solidification or those that may have been introduced by the solidification process.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 25 of 37 Rev.15 NEDL SDQA "C" 10.5.6 Bench Scale Test Solidification failures (Ref: SLC Remedial Action Requirements) 10.5.6.1 Full Scale Solidification for disposal shall not be performed unless the Bench Scale Test Solidification is acceptable.

10.5.6.2 If any Bench Scale Test Solidification fails to meet the acceptance criteria set forth in section 10.3 "Minimum Solidification Acceptance Criteria", the following actions shall be taken prior to the next solidification for disposal at a 10CFR61 disposal site:

A. Suspend solidification of the batch under test B. Obtain additional representative samples from the current waste batch of waste C. Perform additional test solidifications until alternate solidification parameters are determined and solidification

verified D. Modify the PCP and or procedures as required to assure successful solidification of subsequent batches of waste 10.5.6.3 If the initial Bench Scale Test solidification fails SLC Remedial Actions requires that:

A. Representative test sampling solidifications from each consecutive batch of the same type of waste shall be performed using alternate solidification parameters until at least 3 consecutive initial test solidifications meet the minimum solidification acceptance criteria.

B. Modify the PCP and or procedures as required to assure successful solidification of subsequent batches of waste.

10.5.7 Bench Scale Test Solidification results performed onsite shall be submitted to Station Chemistry for review and authorization prior to initiating full scale waste solidification including the following:

10.5.7.1 Sample analysis 10.5.7.2 Test solidification results RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 26 of 37 Rev.15 NEDL SDQA "C" 10.5.7.3 Prescribed boundary conditions 10.5.7.4 Specific activity to ensure packaging limits of the disposal container will not be exceeded 10.5.8 Bench Scale Test Solidification results performed by an offsite processor shall be handled as follows:

10.5.8.1 Bench Scale Test Solidification failures shall be communicated to the originating site Chemistry supervision prior to performing full scale solidification for disposal.

10.5.8.2 Successful Bench Scale Test Solidification documentation shall be sent to the originating site in the completed PCP documentation for record retention.

10.6 Full Scale Solidification Actual full scale solidification shall be performed using approved procedures which ensure that the solidifica tion process is operated with in the established boundary conditions.

10.6.1 Full scale solidification pro cedures should contain step wise instructions with documentation of completion for the following activities:

10.6.1.1 The Bench Scale Test Solidific ation process described above 10.6.1.2 The full scale formulation of waste additives including mixing requirements 10.6.1.3 The verification described below 10.6.1.4 Documentation of verification that PCP requirements were met 10.6.2 Full Scale Solidification performed in drums shall use new drums (not reconditioned) that meet the requirements of 49CFR.

10.7 Product Verification of Full Scale Solidification Product verification shall be performed to ensu re the acceptance criteria have been met.

10.7.1 Documentation that the Process Control Program was followed and successfully completed may serve as verification of the final solidified

product.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 27 of 37 Rev.15 NEDL SDQA "C" 10.7.2 Non PCP verification (Ref: SLC Remedial Action Requirements) If the Process Control Program was no t followed or if any unusual condition existed during processing that inva lidates the PCP boundary conditions the following actions shall be taken:

10.7.2.1 Reprocess the waste in accordance with PCP requirements, OR 10.7.2.2 Physical testing may be used to verify that disposal site requirements are met:

A. Visual inspection for FSL on top of the waste B. Probe penetration testing and C. Puncturing the bottom of the vessel D. Visual inspection shall be utilized to determine if a solidified waste is a free-standing monolith.

10.7.2.3 Mixed Waste Additional Testing A. In addition to the above physical testing, laboratory analysis using approved EPA methods shall be performed to determine if a solidified Mixed Waste has been rendered non-hazardous.

B. The solidified Mixed Waste need only be analyzed for those hazardous properties it exhibited prior to solidification or

those that may have been introduced by the solidification

process. 10.7.2.4 Make programmatic changes as necessary to address any problems identified.

10.7.3 Full scale solidification does not meet the PCP Acceptance Criteria requirements or physical tests described above.

Any full scale solidification vessel that does not pass the verification requirements described above shall not be shipped to a burial site until reprocessing or repackagi ng has resulted in an acc eptable product (Ref: SLC Remedial Action Requirements). Prior to next shipment for disposal of solidified wastes:

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 28 of 37 Rev.15 NEDL SDQA "C" 10.7.3.1 Suspend shipments of the defectively packaged/inadequately processed solid radioactive wastes from the site AND 10.7.3.2 Initiate action to correct the PC P, procedures, or solid waste equipment as necessary to prevent recurrence 10.7.4 Mixed Waste Pre-approval:

Any solidified Mixed Waste that passes these tests shall not be shipped to a burial site until that burial site has given approval.

10.8 Inoperable Equipment (SLC Remedial Action Requirements) With the waste solidification equipment incapable of meeting PCP requirements or not in service:

10.8.1 Restore the equipment to operable status, OR 10.8.2 Provide alternative capability as necessary to process wastes per this PCP 10.9 Solidification Document Retention Solidification records shall be maintained on each vessel of solidified waste as described in section 7.4 of the Corporate PCP and s ection 5.5 of APPENDIX F "Administration of the PCP and Support Documents". All of the following records that are applicable should be included:

10.9.1 Representative sampling documentation 10.9.2 Sample analysis results 10.9.3 Test solidification results a nd prescribed boundary conditions.

10.9.4 Documentation of Acceptance Criteria verification from completed Nuclear Generation or vendor solidifica tion procedures such as:

10.9.4.1 FSL verification 10.9.4.2 Free-standing monolith verification 10.9.4.3 If applicable, verification that solidified Mixed Waste is non-hazardous.

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11. PCP DEWATERING PROCESS DESCRIPTION The methods used for removal of liquid from wet wa stes for final disposal shall comply with the specific requirements of the disposal site at which the waste is being disposed. Dewatering of wet wastes shall be performed in a manner equi valent to the process described below using approved procedures in a controlled and quality fashion which ensures that all applicable Selected Licensee Commitments and disposal site criteria are met. Procedures used to direct dewatering shall include enough detail to implemen t a process that addresses the applicable requirements described below.

11.1 Dewatering Mechanical Filters (e.g., cartridge, bag, membrane) The guidance below addresses dewatering methods and PCP issues unique to disposal of mechanical filters.

11.1.1 Dewatering is required so subsequent accumulation of free standing liquid in the disposal container is not likely to approach disposal site limits.

11.1.2 Wet spent mechanical filters can be dewatered by allowing liquid to drain freely from the filter, blowing the filter down with air, compacting the filter, etc. 11.1.3 The method of dewatering shall be in accordance with a previously defined, evaluated, and documented process.

11.1.4 The parameters of the process, referred to as boundary conditions, shall be defined and used to ensure quality in the process, which in turn serves to ensure an acceptable characteristic of the waste. An example of a boundary condition is the specified period of time for which a mechanical filter shall be allowed to drain freely to ensure FSL will be less than disposal requirements.

NOTE: Removal of free standing liquid fr om a disposal container shall not be considered the PCP method for dewatering mechanical filters.

11.1.5 Filters placed in a filter disposal container designed for removal of FSL shall meet the PCP boundary conditions for dewatering independent of removal of FSL from the container. If PCP boundary conditions are met after placing the filter in the disposal container, the container shall be unwatered to ensure FSL meets disposal requirements.

11.1.5.1 If the PCP boundary conditions have been met prior to placing the filters in the disposal contai ner, dewatering the container to remove incidental FSL is optional.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 30 of 37 Rev.15 NEDL SDQA "C" 11.1.5.2 Case-by case circumstances, such as the following, should be considered in the determining the appropriateness of performing additional filter disposal container dewatering: The time interval between removal of the filters from wet service and placement into the disposal container Size of the disposal container relative to the moisture content in the filters The number of filters The variety of filter types in a single container The environmental conditions of filter staging and interim storage 11.1.6 Use of absorbent package material in mechanical filter disposal containers is subject to the requirements of the disposal site acceptance criteria.

11.2 Dewatering Slurries The guidance below addresses dewatering issues associated with slurry wastes.

11.2.1 Dewatering of "slurried" wet wastes (e.g., resin, carbon, Zeolite, filter precoat, filter backwash solids) removes the loosely bound interstitial liquid from solids such that the disposal container meets applicable regulatory and burial site FSL criteria for disposal.

11.2.2 Wet spent process media dewatering shall be performed using processes, containers and procedures that have met the requirements described in section 9, "Process Control Program Requirements".

11.2.3 Typical container dewatering processes use a vacuum pump that takes suction from the vessel through a filter system in the vessel. The water is returned to a station liquid radwaste system and the waste solids are retained in the vessel

by the container filter(s).

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 31 of 37 Rev.15 NEDL SDQA "C" 11.3 Additional Conservatism in Slurry Dewatering Procedures to Address Variation from the Topical Report (P IP O-03-0624, M-03-2515, C-03-3385)

Dewatering processes based on Topical Reports are applied to actual conditions that can vary from the conditions of the Topical Re port testing. The results of a Root Cause investigation at ONS (O-03-0624) identified several i ssues and resolutions that should be incorporated into future revisions of dewatering implementing procedures. Vendor procedures applicable to the technologies and processe s used by Duke Energy in implementing the PCP provide the basis for minimal requirements in PCP implementing

procedures. In addition the guidelines below have been ad ded based on the Root Cause findings at ONS:

11.3.1 All PCP dewatering procedures shall include flexibility/ guidance for Chemistry to add conservatism to the dewa tering process if waste content and/

or process conditions are atypical in a non conservative manner relative to the testing performed for the Topical report (e.g., greater than normal non media solids, dewatering boundary parameters are not easily met, higher than normal volume of FSL is collected during the final dewatering cycle, etc.)

11.3.1.1 Additional conservatism can include but is not limited to the following examples:

A. Additional dewatering cycles B. Additional settling time between pumping periods C. Additional processing by an approved offsite vendor to verify FSL prior to disposal 11.3.2 Guidance for dewatering all liners using a PCP for direct disposal at Barnwell (PIP O-03-0624 CAPR) 11.3.2.1 Require liner functional testing prior to filling liner with waste to ensure there are no leaks in the liner dewatering system. This testing should include:

A. filling the liner with water B. testing each level of the liner dewatering laterals using the dewatering procedure to unwater the liner, C. verifying that vacuum is not broken prior to exposing the filters for each set of laterals as described in the procedure RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 32 of 37 Rev.15 NEDL SDQA "C" 11.3.2.2 Ensure ambient temperature guidance for dewatering will preclude localized freezing c onditions during the dewatering sequence. After most of the water is removed during the first

dewatering cycle, subsequent cycles pull air through the interstitial spaces of the medi a and the loss of heat due to evaporation can depress the temperature on surface of the media and dewatering filters below ambient temperature.

A. Follow guidance in the vendor documentation for the process in use B. If no other guidance is provided, dewatering should not be performed unless ambient temperature of air entering the liner is 40 degrees Fahrenhe it or higher (FO-OP-022) 11.3.2.3 Ensure final water collection samp le point is representative (e.g., as close as possible to the pump discharge) 11.3.3 Mixed Media: Additional guidance for dewatering liners containing Mixed Media with significant non media solids using a PCP for direct disposal at Barnwell (PIP O-03-0624 CAPR)

The guidance below applies to liners containing combinations of different media with significant quantities of non media so lids (e.g., spent zeolite, carbon, resin, etc. containing filtered particulate) 11.3.3.1 Require Ecodex filter system in all liners that contain mixed media with significant non-media solids 11.3.3.2 Clearly specify media loading sequence if media is not homogeneously mixed to minimi ze potential blinding of the lowest level of filters. (e.g., for layered media, largest diameter media in the bottom of the liner) 11.3.3.3 Require additional dewatering Cycles (e.g. minimum of 3 additional cycles after the acceptance criteria in the vendor procedure have been met) 11.3.3.4 Require longer settling periods during the additional dewatering cycles (e.g., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> instead of the 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> required in the vendor procedure)

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 33 of 37 Rev.15 NEDL SDQA "C" 11.3.3.5 Require dewatering through bottom 2 laterals during liner filling (Topical Report requirement to establish proper media compaction and capillary conditions) 11.4 Dewatering Process Requirements The procedures directing dewatering processes shall address all of the following activities that apply to the specific waste type being dewatered.

11.4.1 Waste Characterization Dewatering procedures shall describe how each type of waste is characterized. The characterization information determ ines what disposal and container requirements apply and may also be utilized to determine shipment packaging requirements (e.g., shielding). Much of the required information for slurried waste is obtained using a representative sample of the waste media. Characterization requires the following types of information:

11.4.1.1 Radioactivity content A. To determine 10CFR61 waste class, form and container requirements B. To provide waste content char acterization for packaging and disposal requirements 11.4.1.2 Waste compatibility with disposal container and process method A. Chemical Compatibility: Proce ss knowledge can be applied to determine chemical compatibility with the container.

B. Hazardous Characteristics:

Process knowledge can be applied to determine if the waste is a Mixed Waste.

C. If process knowledge is uncertain due to a potential input of incompatible or hazardous materials, then chemical analysis using an approved method shall be performed to determine chemical compatibility or hazardous characteristics.

11.4.2 PCP process parameters shall be identified in implementing procedures. Typical parameters are:

11.4.2.1 Waste form RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 34 of 37 Rev.15 NEDL SDQA "C" 11.4.2.2 Settling time 11.4.2.3 Drain (or pump) time 11.4.2.4 Drying time 11.4.2.5 Specific activity 11.4.3 PCP boundary conditions shall be established for applicable process parameters to verify FSL threshold limits are met.

11.4.4 Sample analysis results and boundary conditions shall be reviewed by the appropriate knowledgeable individual re sponsible for the dewatering process.

11.4.5 Actual dewatering shall be performed us ing approved procedures that ensure the process is performed within the established boundary conditions.

11.5 Product Verification The amount of free-standing liquid shall be verifi ed to be within dis posal site criteria for each container of dewatered waste prior to disposal (e.g., 10CFR61 requires that each

container shall have less than 0.5% free-standing liquids by waste volume or less than 1.0% free-standing liquid if a High Inte grity Container (HIC) is used).

11.5.1 PCP Verification Verification may be accomplished by documenting that the Process Control Program was followed.

11.5.2 Non PCP Verification (SLC Remedial Action Requirements, PIP O-02-7159)

If the PCP was not followed or a non process control method is used:

11.5.2.1 Reprocess the waste in accordance with PCP requirements using an onsite process or approved offsite vendor process, OR 11.5.2.2 Use physical testing of the final dewatered product container to verify that the free-standing liquid content meets disposal site requirements. Physical testi ng shall be based on a process approved by the appropriate regulat or, disposal site operator, or applicable disposal site requirements document.

A. A disposal site may define a product verification testing method approved for use in lieu of a process control method.

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 35 of 37 Rev.15 NEDL SDQA "C"

1. That approved product verification process may be used for that category of disposal on a case-by-case basis, (e.g., bulk waste non-containerized disposal).

2. Any such product verification process shall be approved by the Nuclear GO Chemistry and Radiation Protection

groups. B. Physical testing may include actual measurement of the volume of FSL in each container as follows:

1. Puncture the bottom of the de watered disposal container and collect the FSL.

2. Measure the collected FSL and verify it meets the disposal site requirements.

3. Punctured containers shall be repaired in order to meet all applicable regulatory and disposal site requirements prior to disposal.

11.5.2.3 Documentation of the method us ed for product verification and the results shall be included in the dewatering record as described

in the Dewatering Record Retention section below.

11.5.2.4 Make programmatic changes as necessary to address any problems identified.

11.5.3 Off-normal process or container conditions If any off-normal condition existed du ring processing that could invalidate boundary conditions the following guidance applies:

11.5.3.1 Reprocess the waste in accordance with PCP requirements using an onsite process or approved offsite vendor process, OR 11.5.3.2 Contact the process vendor for technical guidance. The vendor may be able to provide a contingency process to meet disposal requirements. The following examples may be considered:

A. If a dewatering lateral in a container fails to meet the process variable boundary requirement in the dewatering procedure, the vendor may be able to pr ovide procedural guidance to successfully complete the dewatering RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 36 of 37 Rev.15 NEDL SDQA "C" B. If a contingency dewatering process cannot be successfully completed refer to the dewatering failures guidance below 11.5.3.3 Make programmatic changes as necessary to address any problems identified 11.5.4 Dewatering verification failures (SLC Remedial Action Requirements) 11.5.4.1 Any dewatered vessel failing the product verification requirements shall not be shipped to a burial site until

reprocessing or repackaging has resulted in an acceptable product. 11.5.4.2 If applicable regulatory requirements for a dewatered waste container are not satisfied, the following actions shall be taken prior to next shipment of dewatered wastes for disposal:

A. Suspend shipments of defectively packaged/inadequately processed radioactive wastes from the site AND B. Initiate action to correct the PC P, procedures, or solid waste equipment as necessary to prevent recurrence.

C. If the process is a vendor pro cess, obtain technical guidance from the vendor in resolving the problem D. The reprocessing of a failed dewatering may be accomplished using an onsite process or approved offsite

vendor process 11.6 Inoperable Equipment (SLC Remedial Action Requirements) With the waste dewatering equipment incapable of meeting PCP requirements or not in service: 11.6.1 Restore the equipment to operable status, OR 11.6.2 Provide alternative capability as necessa ry to process wastes per this PCP 11.7 Dewatering Document Retention Dewatering records shall be maintained on each vessel of dewatered waste as described in section 7.4 of the Corporate PCP and s ection 5.5 of APPENDIX F "Administration of RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL CORPORATE PROCESS CONTROL PROGRAM CORP PCP Page 37 of 37 Rev.15 NEDL SDQA "C" the PCP and Support Documents". All of the following records that are applicable should be included:

11.7.1 Sample analysis and boundary conditions 11.7.2 Dewatering record from completed Nu clear Generation or vendor dewatering procedures 11.7.3 Free-standing liquid verification

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NEDL SDQA "C" RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUAL APPENDIX G Rev 1 WASTE PROCESSOR CHECKLIST

REVIEWED BY/ DATE: __GT Johnson/ 8/22/05_____ _ _DL Vaught/ 8/16/05________

NGO Radiation Protection NGO Chemistry

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUALAPPENDIX G Rev 1 WASTE PROCESSOR CHECKLIST PCP APP G 1 (Revision 8-22-05)

NEDL SDQA "C" NOTE: (This Checklist is a template and should be edited, as appropriate, for each individual company's Review)

Process Control Program (For Vendors who use a PCP to process wet wastes for disposal at a 10CFR61 licensed disposal site) 1. Verify that the vendor's Process Control Program (PCP), Quality Assurance program and other Dewatering or Solidification process related documents as described in the Radioactive Waste PCP for Duke Energy meet the requirements of the PCP. This is a PCP requirement.

Site License 1. Review the Vendor's Radioactive Material License and ensure that the specific license requirements are being meet.

State Regulations 1. Review the applicable State Regulations and ensure that any specific requirements are being met.

DOT Regulations 1. Does the Vendor meet the requirements of 49 CFR 172 Subpart H-Training? Requirement: Each employer is required to provide general awareness, function specific, and safety awareness training for each Hazmat employee. Training record keeping is required.

2. Does the Vendor meet the requirements of 49 CFR 172 Subpart I-Radiation Protection Program? Requirement: Each employer is required to develop, implement, and maintain a written Radiation protection program. The Vendor should perform and document an audit of the RP program annually.

Pre-planning 1. Has the shipper been trained in D.O.T. hazardous materials requirements? 2. Has the shipper or other site designee been trained to sign a waste manifest? 3. Has the waste been characterized and a profile approved with the Treatment, Storage or Disposal Facility (TSDF)? 4. Are there State-specific ID numbers that must be obtained by the shipper or carrier? 5. Is the release criteria for low-level radioactive waste documented? 6. Can it be demonstrated that instruments used to determine release criteria have been calibrated?

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUALAPPENDIX G Rev 1 WASTE PROCESSOR CHECKLIST PCP APP G 2 (Revision 8-22-05)

NEDL SDQA "C"

7. Does the carrier have a hazardous waste/radioactive waste transporter permit valid in all states that will be traveled? 8. Insurance coverage in the amounts required by DOT and the relevant states? 9. Has the route to the TSDF from the site been planned in advance with the carrier? 10. Does this route cross any states that require a shippers permit (Examples: Mississippi, Colorado) or a carriers temporary trip permit (Examples: Georgia, Maryland) for hazardous or radioactive materials/wastes? 11. If yes to # 9, has the shipper or carrier obtained these permits in advance of the ship date (allow at least 30 days lead- time for a shippers permit)? 12. In South Carolina, has a specific route been documented for low-level radioactive waste? Packaging 1. Does the package meet D.O.T. specifications? 2. Is the package in good condition (no signs of weakness, deterioration or staining)? 3. Is the package securely closed/sealed? 4. Is there a package inspection process/documentation?

• The D.O.T. proper shipping name?

• The D.O.T. hazard class and corresponding labels?

• The UN/NA number?

• To and From addresses?

• EPA hazardous waste or Non-hazardous waste label?

• Manifest number?

• EPA Waste I.D. Number

• TSDF's Waste profile/approval code?

Manifest and Attachments 1. Are State or supplier-specific data provided in the state manifest block? 2. Is the generator identification complete and correct including phone number? 3. Are the page numbers clearly marked? 4. If photocopies are used, is the original identified as such in contrasting color? 5. Is the transporter's ID and correct phone number provided? 6. Are the D.O.T. descriptions correct and do they match the packaging? 7. Is the package count and weight correct? 8. Are waste codes and profile/approval codes entered?

9. Is a 24-hour emergency contact phone number provided? Is information truly available through this contact during off-hours? Are drills conducted? 10. Is the generator's printed name, signature, and date entered correctly? 11. Is the driver's printed name, signature, and date entered correctly? 12. Is a land disposal restriction (LDR) form attached for hazardous waste? If applicable:

• Does the LDR have the correct generator name/location?

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUALAPPENDIX G Rev 1 WASTE PROCESSOR CHECKLIST PCP APP G 3 (Revision 8-22-05)

NEDL SDQA "C"

• The EPA ID number?

• The manifest number?

• The waste profile/approval number and corresponding description, treatability group, waste constituents, and universal treatment standards?

• Generator's printed name, title, signature, and date? 13. For low-level radioactive waste in South Carolina, is the Drivers Instruction Sheet attached? 14. Has it been confirmed with the TSDF that the third-signature manifest is returned to the generator within 20 days for low-level radioactive waste or 30 days for hazardous waste? Transporter 1. Is there a vehicle inspection documented prior to departure? 2. Does the driver have a Commercial Drivers License with Hazardous Materials endorsement? 3. Does the driver keep the manifest and other shipping documents within reach in the truck? 4. Has the driver been instructed on the route for low-level radioactive waste? 5. Does the driver have copies of any shipper or temporary carrier permits needed for this route/trip?

Radiological Conditions 1. Are all radiological postings legible/consistent? 2. Are all radiological labels is legible/consistent? 3. Are RWP's posted? 4. Do workers read/understand the RWP? 5. Are workers dressed IAW the RWP? 6. Do the workers know the dose limits of their RWP? 7. Are workers properly wearing/reading/recording their dosimetry?

Waste Tracking 1. How does the vendor track each customers waste through the different waste processes? 2. How does the vendor account for the waste activity through each process/disposal site? 3. How does the vendor determine Type Quantity/Waste Class on a package with several customer's waste?

4. Does the vendor consider (and document compliance with) requirements of the BTP on Concentration Averaging?

RADIOACTIVE WASTE PROCESS CONTROL PROGRAM MANUALAPPENDIX G Rev 1 WASTE PROCESSOR CHECKLIST PCP APP G 4 (Revision 8-22-05)

NEDL SDQA "C" Security (Ref: PIP C-04-06442) 1. Discuss Duke security requirements with Vendor 2. Discuss the Duke package search requirements with the Vendor 3. If possible, make arrangements for the use of Duke approved package seals on the vendor packages 4. If practical, make arrangements for Duke security personnel to observe and seal packages at the vendor site

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