ML17306A474
| ML17306A474 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/30/1991 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17306A472 | List: |
| References | |
| 76PR-9RW01, 76PR-9RW1, NUDOCS 9202250222 | |
| Download: ML17306A474 (54) | |
Text
ATTACHMENT3 SOLID RADWASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 REVISION 2 2Q PDR ADOCK 05000528 PDR
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL p><e g pf 25 Revts(on SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 RECORD OF REVISIONS REVISION DATE REASON FOR AND DESCRIPTION OF CHANGE 08/23/89 New Issue 05/08/90 Revised position titles and responsibilities to reflect organizational realignment 10/30/91 Relocation of procedural details from Technical Specifications to this Process Contxol Program per NUREG 1301 TECRWCAI. REVIEW SICRATVRE PATE LEAP hVVIACERREVIEW PATE OA CONCVRREIICE (PR, AC)
Effectiv DBIo:
PRBITRRC REVIEW SICIIATVRE, (IF REOVIREO) PATE APPROVED BY:
POC OIILY ASBIGNEO CCPY INCUMBER POCVhIEIVT APPROVER
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 2 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 'PURPOSE AND SCOPE
.1.1 Purpose 1.2 Scope 2.0 RESPONSIBILITIES 3.0 PROGRAM
- 3. 1 Solid'adwaste System 3.2 Precautions 3.3 Prerequisites 3.4 Waste Types 10 3.5 Process Parameters 10 3.6 Waste Classification 12 3.7 Waste Preconditioning 13 3.8 Verification of Solidification 13
- 3. 9 Stability Requirements 16 3.10 Data Sheets 16 3.11 Record Retention 17 4.0 DEPINXTIONS AND ABBREVIATIONS 17 4.1 Definitions 17 4.2 Abbreviations 20
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL pa f g 3 p 25 Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9'1 TABLE OF CONTENTS (con't)
SECTION PAGE NUMBER
5.0 REFERENCES
20 5.1 Implementing 20 5.2 Developmental 21 6.0 APPENDICES 23 Appendix A Schematic Flow Diagram 24 r
Appendix. B, Radwaste Cement Solidification System Diagram 25 PV21548NI t 84S1
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL pg e 4 Of 75 Revision SOLID RADWASTZ PROCESS CONTROL PROGRAM 76PR-9RW01 1.0 PURPOSE AND SCOPE 1.1 'urpose 1.1.1 The purpose of the Process Control Program (PCP) fox the Palo Verde Nuclear Generating Station (PVNGS),
Units 1, 2, and 3 is to establish a set of process parameters which will provide reasonable assuxance of complete solidification of various liquid radioactive "wet wastes" including resin slurries, evaporatox bottoms, filter sludges, and chemical
'drains in accordance with the xequirements of applicable portions of the PVNGS Quality Assurance Program, PVNGS Technical Specifications, PVNGS Final Safety Analysis Report, Department of Transportation (DOT) regulations, Arizona State Regulations, Nuclear Regulator Commission (NRC) regulations, and licensed burial facilities acceptance criteria for solidification, packaging and shipment to an approved offsite burial site.
1~1~2 Toward this purpose, the PCP ensures that the solidified substance is a monolith having no freestanding liquid and is within the limits as set forth in the above mentioned xegulations and acceptance criteria. This PCP will also ensure that solidification will be performed to maintain any potential radiation exposure to plant personnel to "as low as is reasonably achievable" (ALARA) levels, in accordance with the "ALARA Program" procedure.
(RCTS 032630 01I 032639 0 1 )
1~1~3 The program addresses dewatering and drying of resin in conformance with 10 CFR 61 and packaging of various class B and class C waste in High Integrity Containers to meet waste form stability requirements.
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL page 5 Of 25 Revtston 76PR-9RW01 l~ Scope
.1. 2~1 This program applies to operation of plant installed and plant portable processing systems and vendor provided portable processing syst:ems at PVNGS. It provides reasonable assurance of compliance with Low Level Radioactive Haste Regulations.
2.0 RESPONSIBILITIES 2.1 The Vice President:, Nuclear Production or designee, shall assure t:he performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM in accordance with this document.
22 The General Manager, Site Radiation Protection shall:
2.2.1 =Ensure a periodic review of the Process Control Program (PCP) is completed at a minimum of every two years subsequent to the latest revision to maintain compliance with applicable State and Federal Regulations, licensing commitments, and burial facility requirements in accordance with 75AC-ORP01, "Review of Radiological Protection and Chemistry Program Performance".
- 2. 2. 2 Ensure that the Pex iodic Review Control Form is forwarded to NRM-DDC and copies are distxibuted to the following:
- 1) Vice President, Nuclear Production and,
- 2) General Manager, Site Radiation Protection
- 3) Nuclear Safety Group.
2.2.3 Initiate any required changes to the Process Control Program identified during the review.
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Rcvh joe SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9R%'01 2.2.4 Report changes to the Process Contxol Program to the NRC in the Semi-annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:
2.2.4.1 Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; and 2.2.4.2 A determination that the change did not reduce the, overall conf ormance of the solidified waste product to existing criteria for solid wastes.
2.2.5 Provide an independent review of Process Control Program Related ."Instruction Change Request" received to evaluate the impact of the proposed change upon the program. Make changes to the program as necessary to maintain compliance with applicable state and federal regulation.
2.2.6 Develop Station procedures or make necessary changes to existing procedures,to maintain compliance with the Process Control Program subsequent to any chang'e to the program.
2.2.7 Review and process Vendor solidification procedures through the PVNGS procedure approval process.
Z3 Manager, Radiation Protection Support Services is responsible for:
2.3.1 Implementation of the Solid Radwaste Process Control Program.
2.3.2 Assuring that personnel under his control are fully aware of, and operate equipment in compliance with the Process Control Program.
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NUCLEAR ADMINISTRATIYE-ANDTECHNICAL MANUAL Pg~e 7 pf 25 Rcvtston SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RWOl
- 2. 3. 3 Monitoring the activities of Vendor personnel to, assure Vendor compliance with the Process Control Program.
2.3.4 Communicating to the appropriate department, any apparent need for change to the PCP to maintain compliance with State and Fedexal Regulations, Licensing commitments and burial site requirements.
2.3.5 Communicating, to the appropriate department, the need for proceduxe changes, or new procedures to
'maintain compliance with the Process Control P'rogram.
3.0 PROGRAM 3.1 Solid Radwaste System 3 ~ 1-1 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with this PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of xadioactive wastes from the site.
3.1.2 Step 3.1.1 above is applicable at all times.
F 1-3 The solid radwaste system(s) shall be demonstrated OPERABLE at. least once per 92 days by:
(a) Operating the solid radwaste system(s) at least once in the previous 92 days in accordance this PROCESS CONTROL PROGRAM, or (b) Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM
l NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Page 3 of zs Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01
- 3. 1.4 Step 3.1.3 (a) & (b) above shall be documented by completion of 76ST-XSR01,. Solid Radwaste System Surveillance Test Procedure.
3.1.5 If operability is not demonstrated as directed is step 3.1.-3 above and:
(a) With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part'1 not satisfied, suspend shipments of defectively packaged solid radioactive waste from the site.
(b) With the solid radwaste system inoperable for more than 31 days, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which includes. the following information:
Identification of the inoperable equipment or subsystems and the reason for inoperability.
Action(s) taken to restore the inoperable
'equipment,to OPERABLE status.
A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and Summary description of action(s) taken to prevent a recurrence.
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NUCLEAR ADIVIINISTRATIVEAND TECHNICAL MANUAL P><e 9 pf 25 Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RWOl 2 32 Precautions 3 '.1 When the radiation level of a waste batch is determined to be excessive by ALARA standards, a waste substitute shall be prepared and used for performance of the prequalification bench test in accordance with 76RH-9SR01, "Solidification Process Control procedure".
3.2.2 Radiological Precautions; The radiological precautions necessary for implementing the Process Control Program shall be followed and are covered in the "Radiation Protection Program". (RCTS 032648-01) 3.2.3 Sited State Acceptance; Haste generators are allowed to stabilize class. B I(' waste utilizing topical reports "Approved by" or "Under Review" by the NRC provided the burial site State agrees to accept the waste so stabilized.
33 Prerequisites 3.3. 1 Typical and atypical wet waste types shall be identified by the "Solidification Process Control" procedure, or appropriate vendor procedure which shall provide a record of waste formulations.
3.3.2 All Radioactive wet waste processing will be accomplished in accordance with an approved procedure.
3.3.3 Vendor operating procedures will undergo the same review process as PVNGS procedures.
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NUCLEAR ADMINISTRATIVEAND,TECHNICAL MANUAL Revtsion SOLID RADWASTE< PROCESS CONTROL PROGRAiVl 76PR-9RW01 2 3A Waste Types
~ 3.4. 1 Appendix A, "Schematic Flow Diagram," and Appendix B, "Radwaste Cement Solidification. System Diagram,"
illustrate the different waste types to be processed by the solidification system. They are listed as follows:
3.4.2 Chemical regenerative and decontamination waste evaporator concentrates from a forced recirculation evaporator.
3.4.3 Boric acid waste from the Boric Acid Concentrator.
3.4.4 Bead resin waste as a slurry from the Spent Resin Tanks.
3.4.5 Chemical Drain Tank waste 3.4.6 Spent filter cartridges.
35 Process Parameters 3.5.1 An acceptable waste product for transfer and disposal in accordance with 10 CFR 20.311 for class A, B, and C waste shall be provided by compliance with the "Solidification Process Control" procedure and 76DP-ORW03, "Classification of Radioactive Waste" procedure.
3.5.2 The process parameter for various class A wastes shall be based on the Hittman Radwaste Solidification System (Cement) Topical Report, HN-R1109, Revision 4, U.S. Gypsum Envirostone Topical Report 5/84, or Chem-Nuclear Systems, CNSX-WF-C P, (or a vendor process control program) and the "Solidification Process Control" procedure. These documents establish boundary conditions to provide reasonable assurance that solidification will be complete.
(RCTS 032631-01)
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL pqae )) pf 25 Rcvtston SOLID RAD%'ASTE PROCESS COKIROL PROGRAM 76PR-9RWOl 2 3.5.3 For class-A waste types containing concentrations of chemical that do not fall within the bound of chemical concentrations for which preoperational solidification tests have been performed by Hittman Nuclear and Development Corporation, U.S. Gypsum, or Chem-Nuclear Systems acceptable base data for test solidification shall be developed in accordance with the "Solidification Process Control" procedure.
(RCTS 032646-01, 032647-01)
- 3. 5.'4 As plant conditions dictate, including ALARA considerations as well as inplant system inoperability due to maintenance, repairs, or modifications a portable solidification system will be used to process class A waste in accordance with approved operating procedures. Class A ion exchange resins may be dewatered in an appropriate container in accordance with approved operating procedure.
3.5.5 For class-B and class-C waste types, a 10 CFR 61 qualified solidification process will be used on the installed solid radwaste system in accordance with the "Solidification Process Control" procedure or a portable solidification system will be used in accordance with approved operating procedures and a 10 CFR 61 Topical Report approved by, or under review by the NRC.
3.5.6 Process mixing ratios for class A, B, and C waste types shall be determined for each waste batch in accordance with the "Solidification Process Control" procedure or the vendors operating procedure.
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NUCLEAR ADMINlSTRATlVEAND TECHNlCAL MANUAL P~<e g2 pf 25 Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PRe9RWOl 2 3.5.7 Packaging Class B and class C Radioactive waste in High Integrity Containers.
3.5.7.1 Class B and Class C ion exchange resins may be dewatered in an approved High Integrity Container in accordance with a Process Control Program and a 10 CFR 61 Topical Report approved by or under review by the NRC.
3.5.7.2 Class B and Class C spent filters and other appropriately sized Radioactive material may be placed in an approved High Integrity Container for disposal, in accordance with approved procedures, provided all the requirements of 10 CFR 61 are ensured.
3.6 Waste ClassiTication 3 ' 1 The Classification of Radioactive Waste procedure provides for the use of PWR scaling factors for identifying specific radionuclides as required by 10 CFR 6 1 55 g
'Waste Cl ass ification" 3.6.2 Scaling factors. shall be verified or updated as required in 10 CFR Part 61 by waste stream analysis to ensure acceptable standards are maintained for waste classification.
3.6.3 During incident conditions where the use of the existing scaling factors is questionable, the waste shall be classified by correlation factors or actual sample analysis in accordance with the "Classification of Radioactive Waste" procedure.
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL P><< 13 Of 25 Rcvtsion SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 2 3.7 Waste Preconditioning 3.7. 1 The "Operation of Solidification System" procedure shall designate the xequired mixing/recirculation times and syst: em operations to ensure a representative sample is obtained after chemical addition and prior to process initiation.
(RCTS 032643-01, 032645-01) 3.7.2 Adjustment of the waste solution pH shall be in accordance with the "Operation of Solidification
, System" px'ocedure.
3.7.3 The "Opexation of Solidification System" procedure shall designate when heat tracing is required to ensure chemical suspension.
3.8 Verification of Solidification 3.8.1 This PROCESS CONTROL PROGRAM shall be used to verify the SOLXDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., spent resins, evaporator bottoms,, and boric acid solutions).
3.8.1.1 Xf any test specimen fails to verify SOLIDIFICATION, the SOLIDXFICATXON of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLXDIFXCATION parameters can be determined in accordance with this PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLlDXFXCATXON.
SOLXDXFXCATXON of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by this PROCESS CONTROL PROGRAM.
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL P~ e l4 pf g5 Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 3.8.1.2 If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, this PROCESS CONTROL PROGRAM provides for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. This PROCESS CONTROL PROGRAM shall be modified as required, as provided in Technical Specification 6 13i to assure SOLIDIFICATION of subsequent batches of waste.
3.8;1.3 Verification of solidification of test specimens shall be documented by completion of 76ST-9SR02, Process Control Program Solidification Verification.
3.8.2 Solidification Bench Test
'3.8.2.1 The solidification bench tests, in accordance with the Hittman Topical Report, Radwaste Solidification System (Cement), HN-R1109, Revision 4, or U.S. Gypsum Envirostone Topical Report 5/84, or Chem-Nuclear Systems (CNSI-HF-C-02-P) provide the solidification bench testing base data for the "Solidification Process Control" procedure for use with class-A type waste.
3.8.2.2 The solidification bench tests in accordance with a vendor's 10 CFR 61 Topical Report approved by, or under review by the NRC will provide the bench testing base data for the "Solidification Process Control" procedure for use with class-B and C type waste.
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NUCLEAR ADMINISTRATIVEAND,TECHNICALMANUAL p Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 2 3.8.2.3 During solidification system operations, additions to the waste feed tank, waste feed pump operation, and process mixing ratio adjustments shall be .in accordance with the "Operation of Solidification System" procedure.
No additions will be made to the waste feed tank while the tank is being recirculat'ed for sampling or processing. (RCTS 032644-01)
The waste feed pump vill not be stopped during sampling.
3.8.2.4 A periodic solidification bench test shall be performed as specified by and in accordance with the "Solidification Process Control" procedure for verification of an acceptable solidification process.
3.8.2.5 Xf any solidification bench test is found to be not acceptable, subsequent operations and testing shall be in accordance with the "Solidification Process Control" procedure.
3.8.2.6 The solidification bench test acceptance criteria shall be in accordance with the "Solidification Process Control" procedure.
3.8.2.7 Solidification .product quality is controlled by the performance of the "Operation of Solidification System" procedure.
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Reve!on 76PR-9RW01 2 3.8.3 Portable Solidification System 3.8.3.1 The portable solidification vendor will verify proper solidification of the waste product in accordance with the vendor's operating procedure and a 10 CFR 61 Topical Report approved by or under review by the NRC.
3.8.3.2 Handling of containers of unacceptable solidified waste shall be in accordance with the "Operation o f Solidification System" procedure.
3.9 Stability Requirements 3 '.1 Wet radioactive waste shall be classified in accordance with "Classification ,of Radioactive Waste" procedure prior to solidification to assure stab'ility specification set forth in 10CFR61.56 "Waste Characteristics," and branch technical position ETSB 11-3, Revision 2, July 1981, "Design Guidance For Solid Radioactive Waste Management Systems installed in Light-Water/cooled Nuclear Power Reactor Plants".
3.10 Data Sheets (RCTS 032649@I) 3.10.1 For each solidification bench'test actually used for waste processing, a test'ata record shall be maintained in accordance with the "Solidification Process Control" procedure.
3.10.2 For each batch solidification process, a feed rate determination shall be completed in accordance with the "Solidification Process Control" procedure.
(RCTS 032650-01)
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revtsion SOLID RADAR'ASTE PROCESS CONTROL PROGRAM 76PR-901 2 3.10.3 For each batch solidification process, records shall be maintained of the unique batch information in accordance with the "Solidification Process Control" procedure.
3.10.4 For each batch solidification process, a waste classification record shall be completed in accordance with the "Classification of Radioactive Waste" procedure.
3.11 Record Retention 3.11.1 For each batch solidification process, all records generated shall be maintained in accordance with 84AC-ORH05, "Document/Record Turnover Control" procedure.
4.0 DEFINITIONS AND ABBREVIATIONS 4.1 DeGnitions 4.1.1 Batch An isolated quantity of waste feed to be processed having essentially constant physical and chemical characteristics, or A quantity of wet waste type{s) prepared in the waste feed tank for solidification.
- 4. 1.2 Bench test. A prequalification program of the solidification process, performed on a reduced scale with representative mixing ratios, implemented to demonstrate that the proposed method of wet waste processing will result in a waste form acceptable to the land disposal facility.
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NUCLEAR ADMINISTRATIYEAND TECHNICALMANUAL Revhfoa SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 4.1.3 Chelating Agent For the purpose of this document chelating agents are amine polycarboxylic acids (e.g., EDTA, DTPA), hydroxy-carboxylic acids, and polycarboxylic acids (e.g., citric acid, carbolic acid, picolanic acid and glucinic acid) as defined in 10 CFR Part. 61.2.
4.1.4 Approved High Integrity Container: A container used to provide the long term stability xequirement of 10 CFR 61. 'pproval to be evidenced by a copy of the 10 CFR 61 "Certificate of Compliance" being reviewed prior to the containers use and maintained in station file during and subsequent to the containers use.
- 4. 1. 5 Low level radioactive waste .
(LLW) 4.1.5.1 Those low-level radioactive wastes containing souxce, special nuclear, ox. by-product material that are acceptable for disposal in a neax surface land disposal facility.
4.1.5.2 Radioactive waste that contains no hazardous materials as defined in RCRA.
4.1.5.3 Radioactive waste not classified as high-level radioactive waste, transuranic waste or spent nuclear fuel.
4.1.6 Monolith A freestanding, solid object.
4.1.7 Operable A system, subsystem, train, component or device shall be OPERABLE or have OPERABXLXTY when it is capable of performing its specified function(s),
and when all necessary attendant instrumentation, control, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required fox the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 2 4 ~ 1.8 Procedure A document that specifies or prescribes how an activity is to be performed. Procedures shall be approved for use in accordance with the PVHGS Procedure "Review and Approval of Nuclear Administrative and Technical Procedures".
- 4. 1. 9 Process (ing) Changing, modifying, and/or packaging the commercial nuclear power plant generated wet radioactive waste into a form that is acceptable to a disposal facility.
- 4. 1'. 10 Quality Assurance/Quality Control As used in this document, "quality assurance" compxises all those planned and systematic actions necessary to provide adequate confidence that a stxucture, system, or component will perform satisfactorily in service.
the physical characteristics 'f Quality assurance includes quality control, which comprises those quality assurance actions xelated to
..a material, structuxe, component, or syst: em which provide a means to control the quality of the material, structure, component, or system to predetermined requixements.
4.1.11 Solidification The conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
- 4. 1. 12 Stability - As used in this document, "stability" means structural stability. Stability requires that the waste form maintain its structural integrity under the expected disposal conditions.
4.1.3.3 Waste Container An appxoved vessel of any shape, size, and composition used to contain the final processed waste.
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 4.1.14 Waste Form: Waste in a waste container acceptable for disposal at a licensed near-surface disposal facility.
4.1.15 Wet Waste Types Liquid radioactive wastes, sludges, spent filter cartridges, and ion exchanger resins.
42 Abbreviations 4.2.1 ALARA - As Low As Reasonably Achievable 4..2.2 HXC High integrity Container 4.2.3 PCP - Process Control Program 4.2.4 RCRA Resource Conservation and, Recovery Act
5.0 REFERENCES
5.1 Implementing 5.1.1 76ST-XSR01, Solid Radwaste System Surveillance Test Procedure.
5.1.2 76ST-9SR02, Process Control Program Solidification Verification.
5 1 3 7 6RW XSRO 1 I Rev 1, nQperat ion of So lidification System".
- 5. 1. 4 76RW-9SR01, Rev 1, "Solidification Pr ocess Control" .
5.1.5 76DP-OAP02, Rev 1, "Review of Radwaste and Radwaste Process Control'rogram".
- 5. 1.6 76DP-ORW01, Rev 1, "Waste Stream Sampling and Data Base Naintenancen.
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL p> e 21 Of 25 Revtsjon SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 5.1.7 76DP-ORW03, Rev 1, "Classification of Radioactive Waste".
5.1.8 76DP-9RW01, Rev 2 >>Aquaset, Aquaset II, Petroset, and Petroset II Solidification Process".
52 Developmental 5.2.1 10 CFR 20, "Standards for Protection Against Radiation".
5.2.2 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste". (RCTS 032637-01) 5.2.3 10 CFR 71, "Packaging and Transportation of Radioactive Material".
5.2.4 49 CFR Subchapter Ci "Hazardous Materials Regulations".
5.2.5 NUREG-0472, Rev 2, July 1979, "Radiological Effluent Technical Specification for PWRS>>.
5.2.6 NUREG-1301, f Rev. 0, April . 1991, >>Of site Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors".
5.2.7 Palo Verde Nuclear Generating Station Technical Specifications. Sections 1.24, 6.10.2, 6.13.
(Ammendment 56, U-l, 43, U-2, 29, U-3) 5.2.8 Palo Verde Nuclear Generating Station updated Final Safety Analysis Report, Sections 11.4, 12.1, 12.3, and 17.2.
(RCTS 032632-01) 5.2-9 01PR-OQQ01, Rev 0, "Quality Assurance Program>>.
(RCTS 032634-01)
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NUCLEAR ADMINISTRATItr'E AND TECHNICAL MANUAL Pz<e 22 Of 25 Rcvtslon 76PR-9RW01 2 5.2.10 75PR-ORP01, Rev 1, "Radiation Protection Program".
5.2.11 75PR-ORP03, Rev 2, "ALARA Program". (RCTS 032633-01) 5 2 ~ 12 0 1AC OAPO 1 g Rev 1, "Format & Content of NuclearAdministrative And Technical Procedures".
5.2.13 75AC-ORP01, "Review of Radiological Protection and Chemistry Program Performance", Rev 1 5.2.14 84AC-ORM05, Rev 2, "Document/Record Turnover Control".
5.2.'15 USNRC Branch Technical Position ETSB 11-3, Rev 2, July 1981 "Design Guidance'or Solid Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Reactor Plants.." (RCTS 032636-01) 5.2.16 NRC Technical Position on Waste Form, Rev 0, May 1983.
- 5. 2. 17 Chem-Nuclear Systems (CNSI-WF-C-02-P), "Development and Testing of Waste Solidification Formulas to meet Title 10 CFR Part 61 Waste Form Criteria".
5.2.18 U.S. NRC Standard Review Plan 11.4, Rev 2, July 1981 "Solid Waste Management Systems" (RCTS 032635-01).
5.2.19 U.S. Gypsum Envirostone Topical Report 5/84.
- 5. 2. 20 NRC Information Notice 89-27 5.2.21 Technical Specification Interpretation
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 2 5.2.22 Commitment Action Tracking System Commitment, Action Procedure Partition Number Number Section RCTS 032630 01 1.1.2 RCTS 032631. 01 3.5.2 RCTS 032632 01 5.2.8 RCTS 032633 01 5.2.11 RCTS 032634 01 5.2.9 RCTS 032635 01 5.2.18 RCTS 032636 01 5.2.15 RCTS 032637 01 5.2.2 RCTS 032638 01 The PCP RCTS 032639 01 1.1.2 RCTS 032641 01 6.0 RCTS 032643 Ol 3.7.1 RCTS 032644 01 3.8.2.3 RCTS 032645 01 3.7.1 RCTS 032646 01( 3.5.3 RCTS 032647 Ol 3.5.3 RCTS 032648 01 3.2.2 RCTS 032649 01 3.10 RCTS 032650 01 3.10.2 6.0 APPENDICES Appendix A - Schematic Flow Diagram (RCTS 03264141)
Appendix 8 - Radwaste Cement SolidiTication System Diagram Pll l 648>l (8.68l
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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revts [on RADWVASTE COPY CONTROL PROGK4ri 76PR-9RWVOl APPEi KlXAPAGE 1 OF 1
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ir CROSS-ORGANIZATION H,E>lEEV il l 5QNAGE'.)IEai7 REVIEW ri DISCIPLI,fE REVIEW I I LEGS,L REVIE')V C. gL.-.Si).i )
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Provasoli 1515 I -~'-'2-r)160 oEscal prlo!t 0F cK4ÃGEs:
Relocation of procedural details from Tech Specs to the PCP per NUREG 1301.
T/S 3/4.11.3 and Surveillance Requirement 4.11.3.1:
Incorporated into PCP as section 3.1 (3.1.1 through 3.1.5).
Surveillance Requirement 4.11.3.2 incorporated into PCP as section 3.8 (3.8.1 through 3.8.2).
T/S 1.32, deGnition of solidiQcation placed into PCP as step 4.1.11.
Changed heading of step 3.8.2: Was "Solid Radwaste System'o "Solidification Bench Test".
Changed several references from Developmental to Implementing. Added reference 76ST-XSR01, 76ST-9SR02, and NUREG 1301.
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RESOLl. it0% CROSS.ORGASIZAitON RLV)E)V t.') tiiALS:
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