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{{#Wiki_filter:ATTACHMENT 3 SOLID RADWASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 REVISION 2 2Q PDR ADOCK 05000528 PDR  
{{#Wiki_filter:ATTACHMENT3 SOLID RADWASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 REVISION 2 2Q PDR   ADOCK 05000528 PDR
\l 1 I NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL p><e g pf 25 Revts(on SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01 REVISION DATE RECORD OF REVISIONS REASON FOR AND DESCRIPTION OF CHANGE 08/23/89 05/08/90 New Issue 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 hVVIACER REVIEW PATE OA CONCVRREIICE (PR, AC)PRBITRRC REVIEW SICIIATVRE, (IF REOVIREO)PATE Effectiv DBIo: APPROVED BY: POCVhIEIVT APPROVER POC OIILY ASBIGNEO CCPY INCUMBER e I l, I l l~
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL SOLID RADWASTE PROCESS CONTROL PROGRAM Revision 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 3.3 3.4 Precautions Prerequisites Waste Types 10 3.5 Process Parameters
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===3.6 Waste===
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)
Classification
Effectiv DBIo:
PRBITRRC REVIEW SICIIATVRE, (IF REOVIREO)        PATE APPROVED BY:
POC OIILY ASBIGNEO CCPY INCUMBER POCVhIEIVT APPROVER


===3.7 Waste===
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Preconditioning
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===3.8 Verification===
NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revision SOLID RADWASTE PROCESS CONTROL PROGRAM        76PR-9RW01            2 TABLE OF CONTENTS SECTION                                              PAGE NUMBER 1.0  'PURPOSE AND SCOPE
of Solidification
    .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


===3.9 Stability===
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Requirements 3.10 Data Sheets 3.11 Record Retention 4.0 DEPINXTIONS AND ABBREVIATIONS
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===4.1 Definitions===
NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL                       pa     f g 3 p 25 Revision SOLID RADWASTE PROCESS CONTROL PROGRAM                 76PR-9'1 TABLE OF CONTENTS (con't)
4.2 Abbreviations 10 12 13 13 16 16 17 17 17 20
SECTION                                                         PAGE NUMBER
!i, 1 l f NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL pa g 3 p f 25 Revision SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9'1 SECTION  


==5.0 REFERENCES==
==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


===5.1 Implementing===
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5.2 Developmental
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==6.0 APPENDICES==
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),
TABLE OF CONTENTS (con't)PAGE NUMBER 20 20 21 23 Appendix A-Schematic Flow Diagram r Appendix.B,-Radwaste Cement Solidification System Diagram 24 25 PV21548NI t 84S1 V 1 sI' NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL pg e 4 Of 75 Revision SOLID RADWASTZ PROCESS CONTROL PROGRAM 76PR-9RW01
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.


===1.0 PURPOSE===
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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 0 1 I 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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l E k I.I H(I'l 0 NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL page 5 Of 25 76PR-9RW01 Revtston 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.
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==2.0 RESPONSIBILITIES==
NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL                                            page 5 Of 25 Revtston 76PR-9RW01 l~    Scope
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".
                  .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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====2.2.2 Ensure====
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that the Pex iodic Review Control Form is forwarded to NRM-DDC and copies are distxibuted to the following:
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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.PY21648NI (84@
I I:I Oi, l NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Rcvh joe SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9R%'01


====2.2.4 Report====
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:
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.
2.2.4.1 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.


====2.2.6 Develop====
1
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.
                '1
1'1.<,l J,')'I 1'>4l , f),il!l f NUCLEAR ADMINISTRATIYE-AND TECHNICAL MANUAL Pg~e 7 pf 25 Rcvtston SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RWOl
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====2.3.3 Monitoring====
NUCLEAR ADMINISTRATIYE-ANDTECHNICAL MANUAL                          Pg~e 7 pf 25 Rcvtston SOLID RADWASTE PROCESS CONTROL PROGRAM                      76PR-9RWOl
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. 3     Monitoring the activities of Vendor personnel to, assure Vendor compliance with the Process Control Program.
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
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.
NUCLEAR ADMINISTRATIVE AND 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,.
2.3.5       Communicating, to the appropriate department, the need   for proceduxe changes, or new procedures to
Solid Radwaste System Surveillance Test Procedure.
                    'maintain compliance with the Process Control P'rogram.
3.1.5 I f 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:
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.
Identification of the inoperable equipment or subsystems and the reason for inoperability.
3.1.2       Step 3.1.1 above     is applicable at all times.
Action(s)taken to restore the inoperable
F   1-3     The   solid radwaste system(s) shall be demonstrated OPERABLE   at. least once per 92 days by:
'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.
(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
PVZ 1648NI (848) l I 0 ti I J j 1 1 NUCLEAR ADIVIINISTRATIVE AND TECHNICAL MANUAL P><e 9 pf 25 SOLID RADWASTE PROCESS CONTROL PROGRAM Revision 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====
l NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL                          Page 3 of zs Revision SOLID RADWASTE PROCESS CONTROL PROGRAM                  76PR-9RW01
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.
: 3. 1.4 Step 3.1.3    (a)  &  (b) above  shall   be documented by completion of 76ST-XSR01,. Solid          Radwaste System Surveillance Test Procedure.
33 Prerequisites
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.
PVZ 1648NI (848)


====3.3.1 Typical====
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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.
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3.3.2 All Radioactive wet waste processing will be accomplished in accordance with an approved procedure.
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====3.3.3 Vendor====
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".
operating procedures will undergo the same review process as PVNGS procedures.
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 ADMINISTRATIVE AND, 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 solidif ication 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====
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acid waste from the Boric Acid Concentrator.
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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.
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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.
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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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, II 1 h I 1~l' NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL pqae]]pf 25 SOLID RAD%'ASTE PROCESS COKIROL PROGRAM Rcvtston 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.
NUCLEAR ADMINISTRATIVEAND,TECHNICAL MANUAL Revtsion SOLID RADWASTE< PROCESS CONTROL PROGRAiVl                        76PR-9RW01            2 3A    Waste Types
Class A ion exchange resins may be dewatered in an appropriate container in accordance with approved operating procedure.
                  ~ 3.4. 1    Appendix A, "Schematic Flow Diagram," and Appendix B, "Radwaste Cement Solidification. System Diagram,"
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.
illustrate the different waste types to be processed by the solidification system.          They are listed as follows:
PV2164BNI (8 88l  
3.4.2      Chemical regenerative        and decontamination  waste evaporator      concentrates              from  a  forced recirculation evaporator.
~,$'a t~l NUCLEAR ADMINlSTRATlVE AND TECHNlCAL MANUAL P~<e g2 pf 25 SOLID RADWASTE PROCESS CONTROL PROGRAM Revision 76PRe9RWOl 2 3.5.7 Packaging Class B and class C Radioactive waste in High Integrity Containers.
3.4.3       Boric acid waste from the Boric Acid Concentrator.
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 if ication" 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.
3.4.4       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.
PV21B48NI {8 88)


====3.6.3 During====
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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.
0,
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!i NUCLEAR ADMINISTRATIVE AND 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====
NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL                                  Page 16 pf 2$
of the waste solution pH shall be in accordance with the"Operation of Solidification
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.
, System" px'ocedure.
3.8.3.2 Handling          of  containers  of unacceptable solidified waste shall be in accordance with the "Operation o f Solidification System" procedure.
3.7.3 The"Opexation of Solidification System" procedure shall designate when heat tracing is required to ensure chemical suspension.
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)
PV21648NI (8 88)


===3.8 Verification===
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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).
V I
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.
I J
SOLXDXFXCATXON of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by this PROCESS CONTROL PROGRAM.
4i)P'!J!0' NUCLEAR ADMINISTRATIVE AND 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====
NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Revtsion SOLID RADAR'ASTE PROCESS CONTROL PROGRAM                       76PR-9''01          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.
Bench Test'3.8.2.1 The solidification bench tests, in accordance with the Hittman Topical Report, Radwaste Solidif ication 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.PV2154SNI (848) j 0 t f l If l NUCLEAR ADMINISTRATIVE AND,TECHNICAL MANUAL 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.
3.10.4    For each        batch  solidification process, a waste classification        record shall be completed in accordance with the "Classification of Radioactive Waste" 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)
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.
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.
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.
3.8.2.6 The solidification bench test acceptance criteria shall be in accordance with the"Solidification Process Control" procedure.
: 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.
3.8.2.7 Solidification.product quality is controlled by the performance of the"Operation of Solidification System" procedure.
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PV21B48NI{8 88) 0 f 0, NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 16 pf 2$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 Solidif ication System" procedure.


===3.9 Stability===
1'I I
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.
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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)
PV21648NI (8 88) l l V I I J NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL SOLID RADAR'ASTE PROCESS CONTROL PROGRAM Revtsion 76PR-9''01 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==
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.
AND ABBREVIATIONS
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).
Pv21SC8Nl (648)


===4.1 DeGnitions===
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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.
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====4.1.2 Bench====
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".
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.PV2t648W ram>
: 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.
1'I I O,i I I I hli NUCLEAR ADMINISTRATIYE AND TECHNICAL MANUAL Revhfoa SOLID RADWASTE PROCESS CONTROL PROGRAM 76PR-9RW01
: 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.
PV21oosNl Is 851


====4.1.3 Chelating====
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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).
Pv21SC8Nl (648) 0 I~'
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL SOLID RADWASTE PROCESS CONTROL PROGRAM Revision 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====
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.
(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.Quality assurance includes quality control, which comprises those quality assurance actions xelated to the physical characteristics
4.1.15     Wet   Waste     Types       Liquid radioactive wastes, sludges, spent     filter cartridges,     and ion exchanger resins.
'f..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.
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
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.PV21oosNl Is 851 I 0 (
NUCLEAR ADMINISTRATIVE AND 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==
==5.0 REFERENCES==


===5.1 Implementing===
5.1 Implementing 5.1.1       76ST-XSR01,     Solid Radwaste System Surveillance Test Procedure.
5.1.1 76ST-XSR01, Solid Radwaste System Surveillance Test Procedure.
5.1.2       76ST-9SR02,     Process   Control Program Solidification Verification.
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 3 7 6RW XSRO 1 I Rev 1, nQperat ion of So l idif ication System".5.1.4 76RW-9SR01, Rev 1,"Solidif ication Pr ocess Control".5.1.5 76DP-OAP02, Rev 1,"Review of Radwaste and Radwaste Process Control'rogram".
: 5. 1. 4     76RW-9SR01, Rev 1,     "Solidification    Pr ocess Control" .
5.1.6 76DP-ORW01, Rev 1,"Waste Stream Sampling and Data Base Naintenancen.
5.1.5       76DP-OAP02, Rev 1, "Review       of Radwaste and Radwaste Process   Control'rogram".
4 1 l l~
: 5. 1.6     76DP-ORW01,     Rev 1, "Waste Stream Sampling and Data Base Naintenancen.
NUCLEAR ADMINISTRATIVE AND 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".
4 1
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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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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
                        $ 6.0-13-01-00, May 4, 1990
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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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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.
COMME iS:
RESOLLitoi:                                                                                                                  CROSS    ORG~ltcAiIOii REHEN I StiLKLS:
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RESOLl. it0%                                                                                                                CROSS.ORGASIZAitON RLV)E)V t.') tiiALS:
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5.2.5 NUREG-0472, Rev 2, July 1979,"Radiological Effluent Technical Specification for PWRS>>.5.2.6 NUREG-1301, Rev.0, April.1991,>>Of f site Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors".
I
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 ADMINISTRATI tr'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".
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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 Inf ormation Notice 89-27 5.2.21 Technical Specification Interpretation
$6.0-13-01-00, May 4, 1990>YZ]548Nl (b+Sl l J li!t'I e NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL SOLID RADWASTE PROCESS CONTROL PROGRAM Revision 76PR-9RW01 2 5.2.22 Commitment Action Tracking System Commitment, Partition Number Action Number Procedure Section RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS RCTS 032630 032631.032632 032633 032634 032635 032636 032637 032638 032639 032641 032643 032644 032645 032646 032647 032648 032649 032650 01 01 01 01 01 01 01 01 01 01 01 Ol 01 01 01(Ol 01 01 01 1.1.2 3.5.2 5.2.8 5.2.11 5.2.9 5.2.18 5.2.15 5.2.2 The PCP 1.1.2 6.0 3.7.1 3.8.2.3 3.7.1 3.5.3 3.5.3 3.2.2 3.10 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 Pl ,I, t r I NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Revts[on RADWVASTE COPY CONTROL PROGK4ri 76PR-9RWVOl APPEi KlXA PAGE 1 OF 1:-VWORATOR R.W.Wit:CNS 4 CO'xRAT"=KONZTOR l~~1 WAST:.P l I1kl ls C:":~'.ICAL" DRAT!:~%:S C-&#x17d;AD l'>>aD I,'.I'WAS:=/C~l I O llew L=R.n.SuST=uB DRU..OR I I>>II SP&i R:-ST.h AS I I I C'a: Du:-S SC~l&XC:-0>>DIAORAu PV2'I848NI (8~1 e I 4 i I t
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Added reference 76ST-XSR01, 76ST-9SR02, and NUREG 1301.COMME iS: RESOLLitoi:
CROSS ORG~ltcAiIOii REHEN I StiLKLS: COMME'S: RESOLl.it0%CROSS.ORGASIZAitON RLV)E)V t.')tiiALS: COMME.'icosi RE!ll)LL i I 0Y))Zii)08<R))SS nR)),a Rt:rlE)v<YITIALS:
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Latest revision as of 09:21, 18 March 2020

Rev 2 to Nuclear Administrative & Technical Manual 76PR-9RW01, Solid Radwaste Process Control Program.
ML17306A474
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 10/30/1991
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
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References
76PR-9RW01, 76PR-9RW1, NUDOCS 9202250222
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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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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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NUCLEAR ADMINISTRATIVEAND TECHNICAL MANUAL Page 16 pf 2$

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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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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