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{{#Wiki_filter:SOLID RADMASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION 84ii020288 84i030'DR ADQCK-05000528.*pgp 0 IJ C.I 0 TABLE OF CONTENTS Section 1.0 2.0 Title PURPOSE DEFINITIONS AND ABBREVIATIONS
{{#Wiki_filter:SOLID RADMASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION 84ii020288 84i030'DR ADQCK-05000528.*pgp 0 IJ C.I 0 TABLE OF CONTENTS Section 1.0 2.0 Title PURPOSE DEFINITIONS AND ABBREVIATIONS
~Pa e 3.0 PROGRAM DESCRIPTION
~Pa e 3.0 PROGRAM DESCRIPTION 3.1 Maste Types 3.2 Process Parameters 3.3 Haste Classification 3.4 Waste Preconditioning 3.5 Verification of Solidification 3.6 Stability Requirements 3.7 Data Sheets 3.8 Record Retention 3.9 Radiological Precautions
 
===3.1 Maste===
Types 3.2 Process Parameters
 
===3.3 Haste===
Classification
 
===3.4 Waste===
Preconditioning
 
===3.5 Verification===
of Solidification
 
===3.6 Stability===
Requirements 3.7 Data Sheets 3.8 Record Retention 3.9 Radiological Precautions


==4.0 REFERENCES==
==4.0 REFERENCES==


APPENDICES Appendix A-Schematic Flow Diagram Appendix B-Radwaste Cement Solidification System Diagram l I 0  
APPENDICES Appendix A-Schematic Flow Diagram Appendix B-Radwaste Cement Solidification System Diagram l I 0 1.0 PURPOSE The purpose of the Process Control Program (PCP)for the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3 is to establish a set of process parameters which will provide reasonable assurance of complete solidification of various liquid radioactive"wet wastes" including resin slurries, evaporator bottoms, filter sludges, and chemical drains in accordance with the requirements of applicable portions of the PVNGS Quality Assurance Program, PVNGS Technical Specifications, PVNGS Final Safety Analysis Report, Depart-ment of Transportation (DOT)regulations, Nuclear Regulatory Commission (NRC)regulations, and licensed burial facilities acceptance criteria for solidification, packaging, and ship-ment to an approved offsite burial site.There are no Arizona State Regulations applicable to PVNGS.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 regulations 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.
 
===1.0 PURPOSE===
The purpose of the Process Control Program (PCP)for the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3 is to establish a set of process parameters which will provide reasonable assurance of complete solidification of various liquid radioactive"wet wastes" including resin slurries, evaporator bottoms, filter sludges, and chemical drains in accordance with the requirements of applicable portions of the PVNGS Quality Assurance Program, PVNGS Technical Specifications, PVNGS Final Safety Analysis Report, Depart-ment of Transportation (DOT)regulations, Nuclear Regulatory Commission (NRC)regulations, and licensed burial facilities acceptance criteria for solidification, packaging, and ship-ment to an approved offsite burial site.There are no Arizona State Regulations applicable to PVNGS.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 regulations 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.
2.'0 DEFINITIONS AND ABBREVIATIONS a.ALARA b.Batch c.Bench Test As low as is reasonably achievable.
2.'0 DEFINITIONS AND ABBREVIATIONS a.ALARA b.Batch c.Bench Test As low as is reasonably achievable.
A quantity of water type(s)prepared in the waste feed tank for solidification.
A quantity of water type(s)prepared in the waste feed tank for solidification.
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Class B and C waste will be processed in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.
Class B and C waste will be processed in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.
0 e.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"Solidifi-cation Process Control" procedure",or a portable solidification system will be used in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.f.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.
0 e.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"Solidifi-cation Process Control" procedure",or a portable solidification system will be used in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.f.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.
 
3.3 Waste Classification a~The"Solidified Radioactive Waste Classification" procedure shall provide PWR scaling factors for identifying specific radionuclides as required by 10 CFR 61.55,"Waste Classification." b.Scaling factors shall be verified or updated annually by waste stream analysis to ensure acceptable standards are maintained for waste classification.
===3.3 Waste===
Classification a~The"Solidified Radioactive Waste Classification" procedure shall provide PWR scaling factors for identifying specific radionuclides as required by 10 CFR 61.55,"Waste Classification." b.Scaling factors shall be verified or updated annually by waste stream analysis to ensure acceptable standards are maintained for waste classification.
c.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"Solidified Radio-active Waste Classification" procedure.
c.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"Solidified Radio-active Waste Classification" procedure.
 
3.4 Waste Preconditionin a.The"Operation of Solidification System" procedure shall designate the required mixing/recirculation times and system operations to ensure a representative sample is obtained after chemical addition and prior to process initiation.
===3.4 Waste===
Preconditionin a.The"Operation of Solidification System" procedure shall designate the required mixing/recirculation times and system operations to ensure a representative sample is obtained after chemical addition and prior to process initiation.
b.Adjustment of the waste solution pH shall be in accordance with the"Operation of Solidification System" procedure.
b.Adjustment of the waste solution pH shall be in accordance with the"Operation of Solidification System" procedure.
c.The"Operation of Solidification System" procedure shall designate when heat tracing is required to ensure chemical suspension.
c.The"Operation of Solidification System" procedure shall designate when heat tracing is required to ensure chemical suspension.
 
3.5 Verification of Solidification a~Solid Radwaste S stem 1)The solidification bench tests, in accordance with the Hittman Topical Report, Radwaste Solidification System (Cement), HN-R1109, Revision 4, provide the solidification bench testing base data for the"Solidification Process Control" procedure for use with'class-A type waste.
===3.5 Verification===
of Solidification a~Solid Radwaste S stem 1)The solidification bench tests, in accordance with the Hittman Topical Report, Radwaste Solidification System (Cement), HN-R1109, Revision 4, provide the solidification bench testing base data for the"Solidification Process Control" procedure for use with'class-A type waste.
lf P 0 2)The solidification bench tests in, accordance with a vendor's NRC approved 10 CFR 61 Topical Report will provide the bench testing base data for the"Solidification Process Control" procedure for use with class-B and C type waste.3)During solidification system operations, additions'o the waste feed tank, waste feed pump operation, and process mixing ratio adjustments shall be in accordance with the"Operation of Solidification System" procedure.
lf P 0 2)The solidification bench tests in, accordance with a vendor's NRC approved 10 CFR 61 Topical Report will provide the bench testing base data for the"Solidification Process Control" procedure for use with class-B and C type waste.3)During solidification system operations, additions'o the waste feed tank, waste feed pump operation, and process mixing ratio adjustments shall be in accordance with the"Operation of Solidification System" procedure.
i.No additions will be made to the waste feed tank while the tank is being recirculated for sampling or processing.
i.No additions will be made to the waste feed tank while the tank is being recirculated for sampling or processing.
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7)Solidification product quality is controlled by the performance of the"Operation of Solidification System" procedure.
7)Solidification product quality is controlled by the performance of the"Operation of Solidification System" procedure.
b.Portable Solidification S stem The portable solidification vendor will verify proper solidification of the waste product in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.c~Handling of containers of unacceptable solidified waste shall be in accordance with the"Operation of Solidifi-cation System" procedure.
b.Portable Solidification S stem The portable solidification vendor will verify proper solidification of the waste product in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.c~Handling of containers of unacceptable solidified waste shall be in accordance with the"Operation of Solidifi-cation System" procedure.
0  
0 3.6 Stabilit Re uirements-The"Solidification Process Control" procedure shall identify the stability specifications as set forth in 10 CFR 61.56,"Haste Characteristics," and Branch Technical Position ETSB 11-3, Revision 2, July 1981,"Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Mater-Cooled Nuclear Power Reactor Plants." 3.7 Data Sheets a.For each solidification bench test actually used fo'waste processing, a test data record shall be maintained in accordance with the"Solidification Process Control" procedure.
 
===3.6 Stabilit===
Re uirements-The"Solidification Process Control" procedure shall identify the stability specifications as set forth in 10 CFR 61.56,"Haste Characteristics," and Branch Technical Position ETSB 11-3, Revision 2, July 1981,"Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Mater-Cooled Nuclear Power Reactor Plants." 3.7 Data Sheets a.For each solidification bench test actually used fo'waste processing, a test data record shall be maintained in accordance with the"Solidification Process Control" procedure.
b.For each batch solidification process, a feed rate determination shall be completed in accordance with the"Solidification Process Control" procedure.
b.For each batch solidification process, a feed rate determination shall be completed in accordance with the"Solidification Process Control" procedure.
c.For, each batch solidification process, records shall be maintained of the unique batch information in accordance with the"Solidification Process Control" procedure.
c.For, each batch solidification process, records shall be maintained of the unique batch information in accordance with the"Solidification Process Control" procedure.
d.For each batch solidification process, a waste classi-fication record shall be completed in accordance with the"Solidified Radioactive Waste Classification" procedure.
d.For each batch solidification process, a waste classi-fication record shall be completed in accordance with the"Solidified Radioactive Waste Classification" procedure.
 
3.8 Record Retention For each batch solidification process, all records generated shall be maintained in accordance with the"Document/Record Turnover Control" procedure.
===3.8 Record===
3.9 Radiolo ical Precautions 4.0 The radiological precautions necessary for implementing the Process Control Program shall be followed and are covered in the"Radiation Protection Program" procedure.
Retention For each batch solidification process, all records generated shall be maintained in accordance with the"Document/Record Turnover Control" procedure.
 
===3.9 Radiolo===
ical Precautions 4.0 The radiological precautions necessary for implementing the Process Control Program shall be followed and are covered in the"Radiation Protection Program" procedure.
REFERENCES a.NUREG-0472,"Radiological Effluent Technical Specifications for PWRS," Revision 2, July 1, 1979.b.10 CFR 20,'Standards for, Protection Against Radiation." c.10 CFR 71,"Packaging and Transportation of Radioactive Material.",
REFERENCES a.NUREG-0472,"Radiological Effluent Technical Specifications for PWRS," Revision 2, July 1, 1979.b.10 CFR 20,'Standards for, Protection Against Radiation." c.10 CFR 71,"Packaging and Transportation of Radioactive Material.",
I 1 Palo Verde Nuclear Generating Station Technical Specifications.
I 1 Palo Verde Nuclear Generating Station Technical Specifications.
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==2.0 REFERENCES==
==2.0 REFERENCES==


==3.0 DEFINITIONS==
3.0 DEFINITIONS 4.0 RESPONSIBLITIES 5.0 JOB PLANNING 6.0 INSTRUCTIONS PROCEDURE NO.75RP-9SROl REVISION Page 3 of 23 PAGE NUMBER ,5APPENDICES Appendix A-Waste Process Record Appendix B-Bench Test Data Record 13 14 Appendix Appendix C D Haste Formulation Table 16 Bench Feed Rate Determination Record 15 Appendix E-Standard Feed Rate Determination Record 18 Appendix F-Feed Curves 19 PV216400 REV.SI82 IIf H 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SR01 REVISION Page 4 of 231~0 2.0~Fur ose The purpose of the Solidification Control procedure is to provide process parameters and detailed instructions for bench testing and determining process feed rates in accordance with the requirements set forth in 75PR-9ZZ02,"Solid Radwaste Process Control Program".This also provides a historical and auditable record of the solidification process for packaging, transport and bur ial requir ements, References 2.1 Implementing References 2.1.1 750P-1SR02, Operation of Solidification System.2.1.2 75AC-9ZZ01, Radiation Exposure Author ization, Permits and Control 2.2 Developemental References 2~2~1 2''Hittman Topical Report Radwaste Solidification System (Cement)Report No.HN-R1109, Rev.4 75PR-9ZZ02, Solid Radwaste Process Control Program 2.2e3 75PR-OZZ01, Radiation Protection Program 2.2.4 Vendor Waste Form Test Report 2.2.5 LCTS Serial Numbers@lk19N',%5SRP1@gxig8 cGz6rd PV21640D AEV.8/82 t s v I g~1 0 9RAF7 LNPOBMAYJOX OM,PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.75RP-9SR01 REVISION SOLIDIFICATION PKCESS CONTROL Page 5 of 23 3,0 Definitions 3.1 Bench Test-A test performed on a reduced scale to check and verify a specific chemical process.3.2 Batch-A quantity of waste type(s)prepared in the waste feed tank for solidifiction.
 
===4.0 RESPONSIBLITIES===
5.0 JOB PLANNING 6.0 INSTRUCTIONS PROCEDURE NO.75RP-9SROl REVISION Page 3 of 23 PAGE NUMBER ,5APPENDICES Appendix A-Waste Process Record Appendix B-Bench Test Data Record 13 14 Appendix Appendix C D Haste Formulation Table 16 Bench Feed Rate Determination Record 15 Appendix E-Standard Feed Rate Determination Record 18 Appendix F-Feed Curves 19 PV216400 REV.SI82 IIf H 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SR01 REVISION Page 4 of 231~0 2.0~Fur ose The purpose of the Solidification Control procedure is to provide process parameters and detailed instructions for bench testing and determining process feed rates in accordance with the requirements set forth in 75PR-9ZZ02,"Solid Radwaste Process Control Program".This also provides a historical and auditable record of the solidification process for packaging, transport and bur ial requir ements, References
 
===2.1 Implementing===
References 2.1.1 750P-1SR02, Operation of Solidification System.2.1.2 75AC-9ZZ01, Radiation Exposure Author ization, Permits and Control 2.2 Developemental References 2~2~1 2''Hittman Topical Report Radwaste Solidification System (Cement)Report No.HN-R1109, Rev.4 75PR-9ZZ02, Solid Radwaste Process Control Program 2.2e3 75PR-OZZ01, Radiation Protection Program 2.2.4 Vendor Waste Form Test Report 2.2.5 LCTS Serial Numbers@lk19N',%5SRP1@gxig8 cGz6rd PV21640D AEV.8/82 t s v I g~1 0 9RAF7 LNPOBMAYJOX OM,PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.75RP-9SR01 REVISION SOLIDIFICATION PKCESS CONTROL Page 5 of 23 3,0 Definitions
 
===3.1 Bench===
Test-A test performed on a reduced scale to check and verify a specific chemical process.3.2 Batch-A quantity of waste type(s)prepared in the waste feed tank for solidifiction.
3.3 Wet Waste-Liquid radioactive wastes, sludges, or ion exchanger resins.3.4 Waste Substitute
3.3 Wet Waste-Liquid radioactive wastes, sludges, or ion exchanger resins.3.4 Waste Substitute
-A solution or slurry which has chemical properties matching thoses of a specific wet waste type.3.5 Monolith-A free standing, solid object.3.6 REF-Radiation Exposure Permit.3.7 Cure Time-The time required for the liquid waste to change to a free standing solid as a result of a chemical reaction.3.8 LCTS-Licensing Commitment Tracking System, 4.0 Res onsibilities 4,1 The Unit Hadwaste Supervisor's have the responsi-bility for implementation of this procedure.
-A solution or slurry which has chemical properties matching thoses of a specific wet waste type.3.5 Monolith-A free standing, solid object.3.6 REF-Radiation Exposure Permit.3.7 Cure Time-The time required for the liquid waste to change to a free standing solid as a result of a chemical reaction.3.8 LCTS-Licensing Commitment Tracking System, 4.0 Res onsibilities 4,1 The Unit Hadwaste Supervisor's have the responsi-bility for implementation of this procedure.
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't , v 4~0 IlVVOHMATEOÃ M1 j.V.Ea)RAFY PROCEDURE NO.75RP-9SR01 REVISION SOLIDIFICATION PROCESS CON'QVL PALO VERDE NUCLEAR GENERATING STATION MANUAL Page 6 of 23 5.0 Job Plannin 5.1 Resources 5.1.1 Mater ials 5.1.1.1 Survey Meters 5.1.1.2 Cement (for bench test only)5.1.1.3 Additive (for bench test only)5.1.1.4 Bench Test Lab 5,2 Precautions 5.2.1 5.2.2 5.2'5.2.4 A REP shall be issued in accordance with 75AC 9ZZ01, Radiation Exposure Authorization, Permits and Control for work within the Radiological Controlled Area.Proper ALARA practices shall be observed at all times.Waste process feed rate settings shall be de-ermined from the chemistry analysis results.If the type of waste according to its chemical constituents falls into one the waste formulation categories in the"Waste Formulation Table" Appedix D the"Standard Feed Rate Determination Record" Appendix E and"Feed Curves" Appendix F shall be used.For Class"A" waste;if the"Waste Formulation Table" is not applicable, the bench test shall be performed using"Bench Test Data" Appendix B,"Bench Feed Rate Data" Appendix C, and"Feed Curves" Appendix F.For Class"B" and"C" waste, if the"Waste Formulation Table" is not applicable; in addition to the Bench Test Performance using Appendix B, Appendix C and Appendix F;waste form testing shall be performed in acordance with a NRC approved Vendor and Waste Form Test Report.PV210-000 REV.8I82 I'
't , v 4~0 IlVVOHMATEOÃ M1 j.V.Ea)RAFY PROCEDURE NO.75RP-9SR01 REVISION SOLIDIFICATION PROCESS CON'QVL PALO VERDE NUCLEAR GENERATING STATION MANUAL Page 6 of 23 5.0 Job Plannin 5.1 Resources 5.1.1 Mater ials 5.1.1.1 Survey Meters 5.1.1.2 Cement (for bench test only)5.1.1.3 Additive (for bench test only)5.1.1.4 Bench Test Lab 5,2 Precautions 5.2.1 5.2.2 5.2'5.2.4 A REP shall be issued in accordance with 75AC 9ZZ01, Radiation Exposure Authorization, Permits and Control for work within the Radiological Controlled Area.Proper ALARA practices shall be observed at all times.Waste process feed rate settings shall be de-ermined from the chemistry analysis results.If the type of waste according to its chemical constituents falls into one the waste formulation categories in the"Waste Formulation Table" Appedix D the"Standard Feed Rate Determination Record" Appendix E and"Feed Curves" Appendix F shall be used.For Class"A" waste;if the"Waste Formulation Table" is not applicable, the bench test shall be performed using"Bench Test Data" Appendix B,"Bench Feed Rate Data" Appendix C, and"Feed Curves" Appendix F.For Class"B" and"C" waste, if the"Waste Formulation Table" is not applicable; in addition to the Bench Test Performance using Appendix B, Appendix C and Appendix F;waste form testing shall be performed in acordance with a NRC approved Vendor and Waste Form Test Report.PV210-000 REV.8I82 I'
tIIIRAFT JNFojttlAVj:ON ONKVPALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCES CONTROL PROCEDURE NO.75RP-9SROl REVISION Page 7 of 23.5.2.5 A solidification bench test shall be performed to support waste mixing ratios as follows: (LCTS: Qgg+Q5 5.2.5.1 At a minimum of every tenth batch of each waste type.5.2.5.2 When the sample analysis falls outside the normal envelopes established in appendix D, 5.2.5.3 When it is believed that some other contaminant may be present.5'''When deemed necessary by the Unit Radwaste Supervisor.
tIIIRAFT JNFojttlAVj:ON ONKVPALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCES CONTROL PROCEDURE NO.75RP-9SROl REVISION Page 7 of 23.5.2.5 A solidification bench test shall be performed to support waste mixing ratios as follows: (LCTS: Qgg+Q5 5.2.5.1 At a minimum of every tenth batch of each waste type.5.2.5.2 When the sample analysis falls outside the normal envelopes established in appendix D, 5.2.5.3 When it is believed that some other contaminant may be present.5'''When deemed necessary by the Unit Radwaste Supervisor.
5.2,6 5.2.7 5.2.8 5.2.9 The Bench Test shall be per formed using approximately
5.2,6 5.2.7 5.2.8 5.2.9 The Bench Test shall be per formed using approximately 0.6 pounds of waste or waste substitute resulting in a final test priduct weight of approximately 1.2 pounds.The use of waste substitute for bench testing shall be based on ALARA considerations.
 
===0.6 pounds===
of waste or waste substitute resulting in a final test priduct weight of approximately 1.2 pounds.The use of waste substitute for bench testing shall be based on ALARA considerations.
Use actual system fluids whenever practical.
Use actual system fluids whenever practical.
The cure time for the test;-will normally be 2 to 6 hours.If the sample is not solid after 24 hours, consideration shall be given to performing a new test with different cement/additive ratios.The bench test shall be considered unacceptable if the product is not a monolith having no free standin liquid in 72 hours.The maximum pH shall be 11.0 to minimize the potential for in-line solidification.
The cure time for the test;-will normally be 2 to 6 hours.If the sample is not solid after 24 hours, consideration shall be given to performing a new test with different cement/additive ratios.The bench test shall be considered unacceptable if the product is not a monolith having no free standin liquid in 72 hours.The maximum pH shall be 11.0 to minimize the potential for in-line solidification.
 
5.3 Prerequisites PV210400 REY.N82 5'.1 The waste feed tank is in recirculation and pH is adjusted in accordance with 750P-1SR02,"Operation of Solidification System", Section 9.0.  
===5.3 Prerequisites===
*H fi PALO VERDE NUCLEAR GEQ/PATIQG STATION MANUAL SOLIDIFICATION PEQCESS CCNTROL PROCEDURE NO.75RP-9SR01 REVISION Page 8 of 23.5.3.2 5'3 5~3~g The waste feed tank has been sampled and the required analyses are complete.Attach a copy of the chemical analysis results to Appendix A of this procedure A REP is issued for bench testing as required in accordance with 75AC-9ZZ01,"Radiation Exposure Authorization, Permits and Control".6.0 INSTRUCTIONS 6.1 Complete Lines 1 through 6 on Appendix A.6.2 Enter the values for pH, weight and volume percent for the following:
PV210400 REY.N82 5'.1 The waste feed tank is in recirculation and pH is adjusted in accordance with 750P-1SR02,"Operation of Solidification System", Section 9.0.  
*H fi PALO VERDE NUCLEAR GEQ/PATIQG STATION MANUAL SOLIDIFICATION PEQCESS CCNTROL PROCEDURE NO.75RP-9SR01 REVISION Page 8 of 23.5.3.2 5'3 5~3~g The waste feed tank has been sampled and the required analyses are complete.Attach a copy of the chemical analysis results to Appendix A of this procedure A REP is issued for bench testing as required in accordance with 75AC-9ZZ01,"Radiation Exposure Authorization, Permits and Control".6.0 INSTRUCTIONS
 
===6.1 Complete===
Lines 1 through 6 on Appendix A.6.2 Enter the values for pH, weight and volume percent for the following:
Water Bor ic Acid Bead Resin Sodium Sulfate Ammonium Sulfate NOTE Sodium Chloride Crud Oil Citr ic Acid~EDTA The waste formulations are general categories and will never completely duplicate actual conditions, Wastes in the Waste Feed Tank contain small amounts of metal oxides, carbonates, phosphates, silicates, chromates, hydrazine, chlorides, oil, detergents, etc., in addition to the expected H380 , Na SO>, or Bead Resin.As long as th)imp5riCies are present in small amounts (less than two percent each)the solidification of the cement will not be impaired.Actual waste weight percentages must be within 10$of the waste formula for the table to be applicable.
Water Bor ic Acid Bead Resin Sodium Sulfate Ammonium Sulfate NOTE Sodium Chloride Crud Oil Citr ic Acid~EDTA The waste formulations are general categories and will never completely duplicate actual conditions, Wastes in the Waste Feed Tank contain small amounts of metal oxides, carbonates, phosphates, silicates, chromates, hydrazine, chlorides, oil, detergents, etc., in addition to the expected H380 , Na SO>, or Bead Resin.As long as th)imp5riCies are present in small amounts (less than two percent each)the solidification of the cement will not be impaired.Actual waste weight percentages must be within 10$of the waste formula for the table to be applicable.
If any impurity is greater that 2$or the combined weight percetages vary greater that 10$, a bench test must be performed and mixing ratios determined.
If any impurity is greater that 2$or the combined weight percetages vary greater that 10$, a bench test must be performed and mixing ratios determined.
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==3.0 REFERENCES==
==3.0 REFERENCES==


LIMITATIONS AND PRECAUTIONS
LIMITATIONS AND PRECAUTIONS 4.0 SYSTEM AL1GNMENT 5.0 FILLING THE STANDBY CEMENT FEED TANK 6.0 REPLACING THE'N-SERV1CE CEMENT FEED TANK 7.0 FILLING ADDITIVE FEED TANK 8.0 FILLING CHEMICAL ADDITION TANK 9.0 WASTE FEED TANK RECIRCULATION AND CHEMICAL ADJUSTMENT 14 l7 19 21 10.0 11.0 55 GALLON DRUM FILL OPERATION"" LINER FILL OPERATION 0P 5 37 12.0 TRANSFERRING FILTER INTO WASTE CONTAINER 13.0 CEMENT/WASTE MIXER PLUSH 46 APPENDICES Appendix A-Valve Verification List~I Appendix B-Control Panel Settings List Appends C-Electrical/Misc.
 
===4.0 SYSTEM===
AL1GNMENT 5.0 FILLING THE STANDBY CEMENT FEED TANK 6.0 REPLACING THE'N-SERV1CE CEMENT FEED TANK 7.0 FILLING ADDITIVE FEED TANK 8.0 FILLING CHEMICAL ADDITION TANK 9.0 WASTE FEED TANK RECIRCULATION AND CHEMICAL ADJUSTMENT 14 l7 19 21 10.0 11.0 55 GALLON DRUM FILL OPERATION"" LINER FILL OPERATION 0P 5 37 12.0 TRANSFERRING FILTER INTO WASTE CONTAINER 13.0 CEMENT/WASTE MIXER PLUSH 46 APPENDICES Appendix A-Valve Verification List~I Appendix B-Control Panel Settings List Appends C-Electrical/Misc.
List Appendix D-Heat Tracing Breakers"List Appendix E-Troubleshooting 52 59 63 PO10409 m8I82 P p 0'I M'gy7'WFOBMpyqog(0~PAL'0 VERDE NUCLEAR GENER'ATING STATION IVlANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Pago 3 of 83 1.0 OBJECTIVE This procedure provides instructions for system alignment; filling the cemont:, additive and chemical addition tanks;recirculating waste food tank contents;adding chemicals t:o the wasto.food t:ank;transferring filt:ors into waste containers; filling drums and liners and tho cement/waste mixer flush.A troublo shoot:ing guide is provided to assist in dot:ormining what actions aro nocossary to correct system oporating problems.
List Appendix D-Heat Tracing Breakers"List Appendix E-Troubleshooting 52 59 63 PO10409 m8I82 P p 0'I M'gy7'WFOBMpyqog(0~PAL'0 VERDE NUCLEAR GENER'ATING STATION IVlANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Pago 3 of 83 1.0 OBJECTIVE This procedure provides instructions for system alignment; filling the cemont:, additive and chemical addition tanks;recirculating waste food tank contents;adding chemicals t:o the wasto.food t:ank;transferring filt:ors into waste containers; filling drums and liners and tho cement/waste mixer flush.A troublo shoot:ing guide is provided to assist in dot:ormining what actions aro nocossary to correct system oporating problems.


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+All air oporatod valvos~All pumps and mixors~All lovel and prossuro measuring systems~Transfer cart and carousel~Comont storage and food systom~Addit ive f ood sys tom~Radwasto 30 ton crano~Capping machino~Chomical addition system 4.3.3 Perform Electrical/Hics.
+All air oporatod valvos~All pumps and mixors~All lovel and prossuro measuring systems~Transfer cart and carousel~Comont storage and food systom~Addit ive f ood sys tom~Radwasto 30 ton crano~Capping machino~Chomical addition system 4.3.3 Perform Electrical/Hics.
List, Appendix"C", 4.3.4 On SRN-E01, depress tho"Programmable Controller Power On" pushbutton to onorgizo tho procoss computor.CAUTION DO NOT ADD RESINS TO THE WASTE FEED TANK SRN-Tol WHILE THE HEAT TRACING IS ON AND DO NOT TURN THE HEAT TRACING ON WHILE RESINS ARE IN THE WASTE FEED TANK, 4.3.5 Perform Heat Tracing Breakers List, Appendix"D", o>>ly who>>liquid radioactive waste is to bo procossod.
List, Appendix"C", 4.3.4 On SRN-E01, depress tho"Programmable Controller Power On" pushbutton to onorgizo tho procoss computor.CAUTION DO NOT ADD RESINS TO THE WASTE FEED TANK SRN-Tol WHILE THE HEAT TRACING IS ON AND DO NOT TURN THE HEAT TRACING ON WHILE RESINS ARE IN THE WASTE FEED TANK, 4.3.5 Perform Heat Tracing Breakers List, Appendix"D", o>>ly who>>liquid radioactive waste is to bo procossod.
 
4.3.6 Check levels of tanks, if not at adequate lovel for operation perform tho following:
====4.3.6 Check====
levels of tanks, if not at adequate lovel for operation perform tho following:
Entor>>N/h" who>>not roquirod.4.3.6.1 4.3.6.2 Fill or replace Cement Feed Tank SRN-T04 in accordance with Section 5.0 or 6.0 respectively.
Entor>>N/h" who>>not roquirod.4.3.6.1 4.3.6.2 Fill or replace Cement Feed Tank SRN-T04 in accordance with Section 5.0 or 6.0 respectively.
Fill Additive Feed Tank SRN-T02 in accordance with Section 7.0, e PV210400 BEY.Olla' J0 aJ f PALO.VERDE NUCLEAR GENERATING, STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02.REVISION Page 9 of 83 4.3.6.3 Fill Chemical Addition Tank SRN-T03 in accordanco with Section.8,0, It:ems of Section 4,0 of this procedure have been completed or except:ions have boon rocordod and properly documented, Performed By: Signature and Inxtxal Items of Section 4.0 of t:his procodure have boon roviowod and found acceptablo:
Fill Additive Feed Tank SRN-T02 in accordance with Section 7.0, e PV210400 BEY.Olla' J0 aJ f PALO.VERDE NUCLEAR GENERATING, STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02.REVISION Page 9 of 83 4.3.6.3 Fill Chemical Addition Tank SRN-T03 in accordanco with Section.8,0, It:ems of Section 4,0 of this procedure have been completed or except:ions have boon rocordod and properly documented, Performed By: Signature and Inxtxal Items of Section 4.0 of t:his procodure have boon roviowod and found acceptablo:
Line 189: Line 136:
PVllS400 REV.OIQ k II 0  
PVllS400 REV.OIQ k II 0  
.~GRAFT ,PAlO, VERDE, NUCLEAR QFNgRATINQ STATlON MANUAL OPERATION OF SOLIDIFICATION SYSTEN PROCEDURE NO.750P-1SR02 REVISION Page 10 o f 83 5.0 FILLING THE STANDBY CENENT FEED TANK 5.1 Personnel Indoctrination.J>>l>>1?1 l l 1'AQ t AB CBMBl<t'I'BBA t BI"<It W 1 l I I"BQul V'P ORB 0 Lt<=.t l i'I't'<n?f<itAwhst B I Bcl1Y'<l cl<sF<lcPBY<B
.~GRAFT ,PAlO, VERDE, NUCLEAR QFNgRATINQ STATlON MANUAL OPERATION OF SOLIDIFICATION SYSTEN PROCEDURE NO.750P-1SR02 REVISION Page 10 o f 83 5.0 FILLING THE STANDBY CENENT FEED TANK 5.1 Personnel Indoctrination.J>>l>>1?1 l l 1'AQ t AB CBMBl<t'I'BBA t BI"<It W 1 l I I"BQul V'P ORB 0 Lt<=.t l i'I't'<n?f<itAwhst B I Bcl1Y'<l cl<sF<lcPBY<B
<B1 ol"<<8 l alBl<BI"<fJ ovlB Au)<.t1'I 1 BA H<tAw<'ts'c I Bctcl I Bcpl?1c1 BY'IIcv'<tAB oABI~<3t<.<l" wllo I'l<'15<'~ps<t Bhi I BSAOVlS1 11 1 1t'y<'A)10 COOl A 1 V<<.<t B!tflB OQPY'iAt)Ol<~5,1,2 It will t:ako approximately thirt:y minutes to fill the comont: food tank SRN-T04.5,1,3 Operations will bo porformod in I;lto 100 ft:, rudwust'o si Idification area and outside at t:ho comont: Silo.5.1.4 Cement silo vibrator pressure operating range is 54 to 66 psig on PCV-388.5.1.5 Cement: silo aerator pressure operating rango is 2 to 4 psig on PCV-387.5.1.6 A cement feed tank may be complotoly emptied by placing it'.on top of another tank and manually operating tho outlot: valvo, 5,1.7 Cement silo food rato is 4.2 cu.ft:,/min, 5.1.8 The cement: silo feed rotary valve is t:imed for a 5 minut:o fill cycle which will deliver 21 cu.ft:, of cement:.5;1.9 Cement feed tank volume is 90 cuft:.5.1.10 Hearing protect:ion" will be required during cement;: ilo operation, 5.1.11 Cement silo volume at alarm levels aro as follows: h-3-900 cu.ft., A-1-326 cu.fl:~, h"2-100 cu.fl;.5.2 Prerequisites
<B1 ol"<<8 l alBl<BI"<fJ ovlB Au)<.t1'I 1 BA H<tAw<'ts'c I Bctcl I Bcpl?1c1 BY'IIcv'<tAB oABI~<3t<.<l" wllo I'l<'15<'~ps<t Bhi I BSAOVlS1 11 1 1t'y<'A)10 COOl A 1 V<<.<t B!tflB OQPY'iAt)Ol<~5,1,2 It will t:ako approximately thirt:y minutes to fill the comont: food tank SRN-T04.5,1,3 Operations will bo porformod in I;lto 100 ft:, rudwust'o si Idification area and outside at t:ho comont: Silo.5.1.4 Cement silo vibrator pressure operating range is 54 to 66 psig on PCV-388.5.1.5 Cement: silo aerator pressure operating rango is 2 to 4 psig on PCV-387.5.1.6 A cement feed tank may be complotoly emptied by placing it'.on top of another tank and manually operating tho outlot: valvo, 5,1.7 Cement silo food rato is 4.2 cu.ft:,/min, 5.1.8 The cement: silo feed rotary valve is t:imed for a 5 minut:o fill cycle which will deliver 21 cu.ft:, of cement:.5;1.9 Cement feed tank volume is 90 cuft:.5.1.10 Hearing protect:ion" will be required during cement;: ilo operation, 5.1.11 Cement silo volume at alarm levels aro as follows: h-3-900 cu.ft., A-1-326 cu.fl:~, h"2-100 cu.fl;.5.2 Prerequisites 5.2.1 Verify that the Cement Silo has sufficiont comont to fill the Cement Feed Tank as indicatod by no alarm condit:ion from"Alarm 2" indicator on SRN-E03.PVlt040D REV.e?Q 5.2,2 If the cement feed tank service by Section 6 of'volume remaining in the in service, enter"N/A" to be filled was removed from t: he this procedure, note the cement tank.If the tank has not yet been for this stop.
 
====5.2.1 Verify====
that the Cement Silo has sufficiont comont to fill the Cement Feed Tank as indicatod by no alarm condit:ion from"Alarm 2" indicator on SRN-E03.PVlt040D REV.e?Q 5.2,2 If the cement feed tank service by Section 6 of'volume remaining in the in service, enter"N/A" to be filled was removed from t: he this procedure, note the cement tank.If the tank has not yet been for this stop.
t)K Pl'0 INFO'Iox 0@I,V PALO VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEH PROCEDURE NO.750P"1SR02 REVISION 0 Page ll of 83 5.2.3 Determine the number of cycles required to fill the feed tank using the information provided from Step 5.1.8 and 5.2.2.Number of cycles 5 Rlvis't I I.ict 1aris CftU f'IQN CHECK FGRI(t IFT CAPACITY 10 IElu3URt.wt.-:.Ib!-
t)K Pl'0 INFO'Iox 0@I,V PALO VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEH PROCEDURE NO.750P"1SR02 REVISION 0 Page ll of 83 5.2.3 Determine the number of cycles required to fill the feed tank using the information provided from Step 5.1.8 and 5.2.2.Number of cycles 5 Rlvis't I I.ict 1aris CftU f'IQN CHECK FGRI(t IFT CAPACITY 10 IElu3URt.wt.-:.Ib!-
i'I(~lI7.i ARE iuQ i'XCF1)ED.
i'I(~lI7.i ARE iuQ i'XCF1)ED.
Line 205: Line 149:
I 0' PALO VERDE NUCLEAR GENERA'ihi STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEOURE NO.750P-1SR02 REVISION 0 Page 14 of 83 6.0 REPLACING THE IN-SERVICE CEMENT FEED TANK>.>f".t"i'><or>rip.
I 0' PALO VERDE NUCLEAR GENERA'ihi STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEOURE NO.750P-1SR02 REVISION 0 Page 14 of 83 6.0 REPLACING THE IN-SERVICE CEMENT FEED TANK>.>f".t"i'><or>rip.
I 1r>rfr ce rir iria r, 1r.rl tr>.J~.I<<fa>(~J a(;~riri rrte 2 n-r>C>i'V 1CrJ Cr~rfit~rir, f(>tr!n,t>ttr>V.W1'.t l I'e(Iu I I (><'rlr!Qua i 1 f 1 t d I(aowaStt I Pcrlrilc1".tl i ar>41 rJ)<L~At.ta l 1 f'J fi>()'r(itONa:>
I 1r>rfr ce rir iria r, 1r.rl tr>.J~.I<<fa>(~J a(;~riri rrte 2 n-r>C>i'V 1CrJ Cr~rfit~rir, f(>tr!n,t>ttr>V.W1'.t l I'e(Iu I I (><'rlr!Qua i 1 f 1 t d I(aowaStt I Pcrlrilc1".tl i ar>41 rJ)<L~At.ta l 1 f'J fi>()'r(itONa:>
ti r!LBrtrJ~I I'!Crtril Cl ari Wl I>>rirtS>F>I<St r ((I r't." SI101>S I I)1 I I r p arit!C>Jrjl"C1\"iat BS tl ir>!MQBr'at 1(>rl~6.1,2 It will take approximately ono hour t:o roplaco t:lio in-sorvi.co cement: food tank.6,1,3 Oporations will bo performod in t:ho 100 and 110't.solidificat:ion aroa.6.2 Prerequisitos
ti r!LBrtrJ~I I'!Crtril Cl ari Wl I>>rirtS>F>I<St r ((I r't." SI101>S I I)1 I I r p arit!C>Jrjl"C1\"iat BS tl ir>!MQBr'at 1(>rl~6.1,2 It will take approximately ono hour t:o roplaco t:lio in-sorvi.co cement: food tank.6,1,3 Oporations will bo performod in t:ho 100 and 110't.solidificat:ion aroa.6.2 Prerequisitos 6.2.1 Verify the availability of a fillod ccmont;i':ood tank.6.3 Instructions 6.3.1 6.3.3 Verify that the main circuit breaker for SRN-E01 is in t:ho"Og" position.NAt 6 t t'IL~CBmPI it V@1 u((f&FBI(l tilri1 rfrJ J.ri'(l I'llr>!1<i'-".,i.'.i
 
====6.2.1 Verify====
the availability of a fillod ccmont;i':ood tank.6.3 Instructions 6.3.1 6.3.3 Verify that the main circuit breaker for SRN-E01 is in t:ho"Og" position.NAt 6 t t'IL~CBmPI it V@1 u((f&FBI(l tilri1 rfrJ J.ri'(l I'llr>!1<i'-".,i.'.i
'i;i';'.ll'ii>frum LI-385"Cement Vnlumr!Heaac ut" (>ri hrt(4-t-"><'i.:
'i;i';'.ll'ii>frum LI-385"Cement Vnlumr!Heaac ut" (>ri hrt(4-t-"><'i.:
or'>>" Y'80lacB(RBrlt ariG I QcQr'Q thir'>val t(6>ver a 9 J ar!at'r(;;lri(2 attiach trJ the tarift, Turn off LI<<385 on SRN>>E01 by placing selector swit;cli"Cement Volume Readout" LI-385 to"OFF", 6.3.4 6,3.5 Close inst:rumont air to tho comont food taiik vilJrlit.or uittI aerator by placing"cement food tank vibrat:or HY-347", HS-347 on SRN-EQ1 in the"Close" position.Close HV-354 by placing"comont: out:lot: volvo IIY-354", IIS-354 on SRN-E01 in the"Close" position.6.3.6 At the cement feed assembly, disconnect aerator t:ubing on cement feed tank from UV-361A.6.3.7 At the cement feed assembly disconnect HV-354 from its operating cylinder by removing the cylinder rot:aining pin.6, 3, 8 SBcur Bs ca 0'c 0'0 Il&vsPrit crt t Qp,:, c(e>N(!rrt;
or'>>" Y'80lacB(RBrlt ariG I QcQr'Q thir'>val t(6>ver a 9 J ar!at'r(;;lri(2 attiach trJ the tarift, Turn off LI<<385 on SRN>>E01 by placing selector swit;cli"Cement Volume Readout" LI-385 to"OFF", 6.3.4 6,3.5 Close inst:rumont air to tho comont food taiik vilJrlit.or uittI aerator by placing"cement food tank vibrat:or HY-347", HS-347 on SRN-EQ1 in the"Close" position.Close HV-354 by placing"comont: out:lot: volvo IIY-354", IIS-354 on SRN-E01 in the"Close" position.6.3.6 At the cement feed assembly, disconnect aerator t:ubing on cement feed tank from UV-361A.6.3.7 At the cement feed assembly disconnect HV-354 from its operating cylinder by removing the cylinder rot:aining pin.6, 3, 8 SBcur Bs ca 0'c 0'0 Il&vsPrit crt t Qp,:, c(e>N(!rrt;
Line 228: Line 169:
aY<a ane c.u<~<l1r1c~d f(aawast;r<
aY<a ane c.u<~<l1r1c~d f(aawast;r<
t-r<<rlQ'i PCltll')1 f..1<tl'<Wf'tG flR!5 5$6t r.fil I f2<<CI<".<VlS'I t))l 1 t'<<<'ll<(I I GC<t~dIl'latBr4<
t-r<<rlQ'i PCltll')1 f..1<tl'<Wf'tG flR!5 5$6t r.fil I f2<<CI<".<VlS'I t))l 1 t'<<<'ll<(I I GC<t~dIl'latBr4<
tflr.CJCJBV'<i'C 16<i'I~8.1.2 Filling t: he chomical addit:ion t:ank will t:akc approximately two hours, 8,1.3 Operations will bo performed on tho 110 ft.of I:hc solidificat;ion area.8.1,4 Chemical Addition Tank SRN-T03 capacity is 260 gallons wit:h approximat:ely
tflr.CJCJBV'<i'C 16<i'I~8.1.2 Filling t: he chomical addit:ion t:ank will t:akc approximately two hours, 8,1.3 Operations will bo performed on tho 110 ft.of I:hc solidificat;ion area.8.1,4 Chemical Addition Tank SRN-T03 capacity is 260 gallons wit:h approximat:ely 4.2 gallons por inch, 8.1.5 50%sodium hydroxide is-usod in=t;hc chemical addit:ion t:ank for waste feed pH adjustment.
 
8.2 Prerequisites 8.2.1 Ensure applicable emergency shower/oye wash stations aro operable, 8.2.2 Check chemical addition tank level t:o determine the quant:ity of chemical required to fill the tank to a lovol which will support a batch chemical adjustment, 8.2.3 Verify the availability of protective clot:hing and face shield f'r use in chemical addition, 8.3 Ins truct ions.8.3.1 Check Closed chemical addition tank outlet: V-084 CAUTION CAUSTIC MILL CAUSE CHEMICAL BURNS.HANDLE MITH APPROPRIATE SAFETY EQUIPMENT.
===4.2 gallons===
por inch, 8.1.5 50%sodium hydroxide is-usod in=t;hc chemical addit:ion t:ank for waste feed pH adjustment.
 
===8.2 Prerequisites===
 
====8.2.1 Ensure====
applicable emergency shower/oye wash stations aro operable, 8.2.2 Check chemical addition tank level t:o determine the quant:ity of chemical required to fill the tank to a lovol which will support a batch chemical adjustment, 8.2.3 Verify the availability of protective clot:hing and face shield f'r use in chemical addition, 8.3 Ins truct ions.8.3.1 Check Closed chemical addition tank outlet: V-084 CAUTION CAUSTIC MILL CAUSE CHEMICAL BURNS.HANDLE MITH APPROPRIATE SAFETY EQUIPMENT.
8.3.2 Open lid on the chemical addition tank.f<V214400'REV'4/42' E'ia k+))0 9RAFY pg Og~YIoyPALO'VERDE NUCLEAR GENERATilNG STATlON NANUALi OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 20 o f 83 8.3,3 Fill chemical addition tank to desirod level but not closer than five (5)inchos from the top.8.3,4'lose lid on the tank, Items of Section 8,0 of this procedure have boen completod or oxcopt:ions have been recorded and properly documented, Performed By: Signat:uro and Init:ial Dat:o Items of Soction 8,0 of this proceduro havo boon reviewed and found accept:ablo:
8.3.2 Open lid on the chemical addition tank.f<V214400'REV'4/42' E'ia k+))0 9RAFY pg Og~YIoyPALO'VERDE NUCLEAR GENERATilNG STATlON NANUALi OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 20 o f 83 8.3,3 Fill chemical addition tank to desirod level but not closer than five (5)inchos from the top.8.3,4'lose lid on the tank, Items of Section 8,0 of this procedure have boen completod or oxcopt:ions have been recorded and properly documented, Performed By: Signat:uro and Init:ial Dat:o Items of Soction 8,0 of this proceduro havo boon reviewed and found accept:ablo:
Approved By: Signature Dat:o Attach original copy(ios)of appendix(cos), route to Unit Rad Waste Supervisor.
Approved By: Signature Dat:o Attach original copy(ios)of appendix(cos), route to Unit Rad Waste Supervisor.
Line 243: Line 177:
'PAL'0 VERDE NUCLEAR GENERATlNG STAT!ON MANUAI OPERATION OF SOLIDIFICATION SYSTEM PROCEPURE NO.750P"1SR02 REVISION Page 21 of 83 9,0 MASTE FEED TANK RECIRCULATION AND CHEMICAL ADJUSTMENT 9'!r>V'S>'>V>L~.":.
'PAL'0 VERDE NUCLEAR GENERATlNG STAT!ON MANUAI OPERATION OF SOLIDIFICATION SYSTEM PROCEPURE NO.750P"1SR02 REVISION Page 21 of 83 9,0 MASTE FEED TANK RECIRCULATION AND CHEMICAL ADJUSTMENT 9'!r>V'S>'>V>L~.":.
l">QOc2l>V'1 Vr"l't 1 O<CI'v<!a<'it f I'<1>r<U t aV>rr.V<Br-'1l'"O clVIG l".I'!r>A11 C"LL aG J UGt laL>>V>l;W',l i 1 V'BQ l.t1 V'r OV>8 Gila I 1 f'80 VIBOWaS'68 I P.r.".rlV>1 G 1 a Vr al">0<<Vrf!>Olla 1 1 f is!G itaawa~~t t.r>ad!facnv>1r..1<nv>wno na~'>cyst l>r>l V r SO@V!<>1 b1 i 1t y arid r Oav'O1V>at efl>t;nC!nnr>!"<nt: 1 c-.>V>~9,1.2 Recirculation and chomical adjustmont will t:ako ono to four hours.9, 1.3 All oporat ions will bo por formod at: t:ho Solidi f ica tio>>Cont:rol Panel SRN-E01 unless ot:horwiso>>ol:od, 9.1.4 Tho chemical addition pump, SRN-P03 will t:rip on a high dischargo pressure of 82 (80 to 84)psig and a low discharge prossure of 3 (2 to 4)psig, 9.1.5 The chemical addition pump, SRN-P03 has a design flow raI:o of 4.5 to 5.5 gpm at 45 to 55 psig.9.1,6 9.1.7 pH indicator, AI-317 should road with in.04 pH units of t:ho chemistry laboratory results from the waste food t:ank samples.The waste feed pump, SRN-P02 will trip on a high discharge pressure of 55 (50 to 60)psig and a low discharge pressure of a 4 (3.3 to'4.7)'psi.g.
l">QOc2l>V'1 Vr"l't 1 O<CI'v<!a<'it f I'<1>r<U t aV>rr.V<Br-'1l'"O clVIG l".I'!r>A11 C"LL aG J UGt laL>>V>l;W',l i 1 V'BQ l.t1 V'r OV>8 Gila I 1 f'80 VIBOWaS'68 I P.r.".rlV>1 G 1 a Vr al">0<<Vrf!>Olla 1 1 f is!G itaawa~~t t.r>ad!facnv>1r..1<nv>wno na~'>cyst l>r>l V r SO@V!<>1 b1 i 1t y arid r Oav'O1V>at efl>t;nC!nnr>!"<nt: 1 c-.>V>~9,1.2 Recirculation and chomical adjustmont will t:ako ono to four hours.9, 1.3 All oporat ions will bo por formod at: t:ho Solidi f ica tio>>Cont:rol Panel SRN-E01 unless ot:horwiso>>ol:od, 9.1.4 Tho chemical addition pump, SRN-P03 will t:rip on a high dischargo pressure of 82 (80 to 84)psig and a low discharge prossure of 3 (2 to 4)psig, 9.1.5 The chemical addition pump, SRN-P03 has a design flow raI:o of 4.5 to 5.5 gpm at 45 to 55 psig.9.1,6 9.1.7 pH indicator, AI-317 should road with in.04 pH units of t:ho chemistry laboratory results from the waste food t:ank samples.The waste feed pump, SRN-P02 will trip on a high discharge pressure of 55 (50 to 60)psig and a low discharge pressure of a 4 (3.3 to'4.7)'psi.g.
9.1.8 If operations do not proceed as described in sect:io>>9.3, notify the Radwaste Unit Supervisor and chock"Troubleshooting," Appendix E for possible causes and suggested technical act:ion.9.2 Prerequisites
9.1.8 If operations do not proceed as described in sect:io>>9.3, notify the Radwaste Unit Supervisor and chock"Troubleshooting," Appendix E for possible causes and suggested technical act:ion.9.2 Prerequisites 9.2.1 System Alignment, Sect:ion 4.0 is comp lo to.9.2.2 The requirements of 75AC-9ZZ01,"Radiation Exposure Authorization, Permits and Cont;rol" have boon roviowed and action taken as necessary.
 
9.3 Instructions 9.3.1 Place>>Auto/Manual Selector" HS-325 in"Auto".9.3.2 Place"Mode Selector" HS-326 in"Waste Recirc", PV210409 iRQL N22 t'/I 0 GRAF7 PALO VERDE NUCL A GRIST RAT AG STATION, IVIANUAL.OPERATION OF SOLIDIFICATION SYSTEM 750P"1SR02 REVISION Page 22 of 83 9.3.3 9.3,4 Place Masto 1'eed Tk Mixer SRN-Q03 , llS"328, in Start Check that<<Cement/Masto Mixer SRN-Q01", liS-327, is in<<St<<p I NOTE Tho following will occur when the"Node Start" pushbutton is doprossod:
====9.2.1 System====
Alignment, Sect:ion 4.0 is comp lo to.9.2.2 The requirements of 75AC-9ZZ01,"Radiation Exposure Authorization, Permits and Cont;rol" have boon roviowed and action taken as necessary.
 
===9.3 Instructions===
9.3.1 Place>>Auto/Manual Selector" HS-325 in"Auto".9.3.2 Place"Mode Selector" HS-326 in"Waste Recirc", PV210409 iRQL N22 t'/I 0 GRAF7 PALO VERDE NUCL A GRIST RAT AG STATION, IVIANUAL.OPERATION OF SOLIDIFICATION SYSTEM 750P"1SR02 REVISION Page 22 of 83 9.3.3 9.3,4 Place Masto 1'eed Tk Mixer SRN-Q03 , llS"328, in Start Check that<<Cement/Masto Mixer SRN-Q01", liS-327, is in<<St<<p I NOTE Tho following will occur when the"Node Start" pushbutton is doprossod:
~The Waste Feod Tank Dischargo Valvo 1{V-343,opens.
~The Waste Feod Tank Dischargo Valvo 1{V-343,opens.
+Tho Waste Food Pump SRN"P02 is onorgixod.
+Tho Waste Food Pump SRN"P02 is onorgixod.
Line 258: Line 187:
PV210400 BEY.elhi 9
PV210400 BEY.elhi 9
GRAFT PgyoHMAYjtWI ONI.VPALO VLRDE NUCLEAR GENERATING
GRAFT PgyoHMAYjtWI ONI.VPALO VLRDE NUCLEAR GENERATING
$TATION MANUAL OPERATION OP Sor.IDIPICATION SVSTEZ PROCEDURE NO.750P"1SR02 REVISION Page 24 of 83 NOTE 9.3.11.5 The Chemical Addition Tank SRN-T03 has approximately
$TATION MANUAL OPERATION OP Sor.IDIPICATION SVSTEZ PROCEDURE NO.750P"1SR02 REVISION Page 24 of 83 NOTE 9.3.11.5 The Chemical Addition Tank SRN-T03 has approximately 4.2 gallons por inch and tho Chemical Addit: ion Pump SRN" P03 delivers fluid at 5 GPM, I To commence chemical addit:ion for pll adjustmo>>t, sot the"Chemical System Phase Soloctor" llS-330 on"Chem Thru".9.3.11.6 Honitor pll on AI-317 during t:ho chemical addition.9.3.11.7 Whon t:ho roquirod amount of cltomical.
 
===4.2 gallons===
por inch and tho Chemical Addit: ion Pump SRN" P03 delivers fluid at 5 GPM, I To commence chemical addit:ion for pll adjustmo>>t, sot the"Chemical System Phase Soloctor" llS-330 on"Chem Thru".9.3.11.6 Honitor pll on AI-317 during t:ho chemical addition.9.3.11.7 Whon t:ho roquirod amount of cltomical.
Itas lion>><<<Ideal socuro chc~'cal addition by placing llS-330 to"Cltom Recirc".9,3.11.8 9.3.11.9 9.3.11.10-Wait approximatoly 15 minutes t:o allow pll t:o stabilize, then observe and rocord t: he-roading from tho Radwast:o pll , meter AI-317;To secure Chemical Rocirc, place llS-330 I:o"Ol'l'".To secure the Chemical Tank Hixor place HS-332 to IISTOPlf 9.3.11.11"Notify the chemistry section to sample tho Wasto l'ood Tank contents and perform the chomistry analyses required by 75RP-lZZOl,"Solidified Radioactivo Wasto Classification" and 75RP-9SR01,"Solidificntio>>
Itas lion>><<<Ideal socuro chc~'cal addition by placing llS-330 to"Cltom Recirc".9,3.11.8 9.3.11.9 9.3.11.10-Wait approximatoly 15 minutes t:o allow pll t:o stabilize, then observe and rocord t: he-roading from tho Radwast:o pll , meter AI-317;To secure Chemical Rocirc, place llS-330 I:o"Ol'l'".To secure the Chemical Tank Hixor place HS-332 to IISTOPlf 9.3.11.11"Notify the chemistry section to sample tho Wasto l'ood Tank contents and perform the chomistry analyses required by 75RP-lZZOl,"Solidified Radioactivo Wasto Classification" and 75RP-9SR01,"Solidificntio>>
Process Control".NOTE 9.3.12'The last three steps may be porformod concurrently.
Process Control".NOTE 9.3.12'The last three steps may be porformod concurrently.
Line 487: Line 413:
==2.0 REFERENCES==
==2.0 REFERENCES==


==3.0 DEFINITIONS==
3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 JOB PLANNING 6.0 INSTRUCTIONS 4'PPENDICES Appendix A-Waste Product Record Appendix B-Waste Isotope Worksheet Appendix C-Filter Isotope Worksheet Appendix D-Combined Waste Worksheet Appendix E-Waste Classification Worksheet Appendix F<<Isotope to Table 13 15 16 17 18 PY21040D REV.N82 58<A O.
 
===4.0 RESPONSIBILITIES===
5.0 JOB PLANNING 6.0 INSTRUCTIONS 4'PPENDICES Appendix A-Waste Product Record Appendix B-Waste Isotope Worksheet Appendix C-Filter Isotope Worksheet Appendix D-Combined Waste Worksheet Appendix E-Waste Classification Worksheet Appendix F<<Isotope to Table 13 15 16 17 18 PY21040D REV.N82 58<A O.
BP@Fy EVFOPMAYioN o'er,Y 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 3 of 19 1.0 PURPOSE This procedure provides the requirements for classifying solidified low-level radioactive waste in accordance with 10 CFR 20 and 10 CFR 61.(LCTSg 011008)The waste shall be identified as Class A, Class B or Class C depending on the concentrations of both long and shore-lived radio-nuclides, the waste form physical stability due to its structure and presence of liquids or voids.This identification shall be completed prior to solidification to provide control over transfer and disposal requirements.(LCTSjj 011171)This classification will use the"indirect method" for classifying waste.A1F/NESP-02 generic scaling factors shall be used initially for determining quantities of the difficult-to-measure nuclides in waste streams and filters.After 100 full power days and on a Biannual basis a composite sample of=.the reactor coolant system shall be taken for--complete nuclide analysis.
BP@Fy EVFOPMAYioN o'er,Y 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 3 of 19 1.0 PURPOSE This procedure provides the requirements for classifying solidified low-level radioactive waste in accordance with 10 CFR 20 and 10 CFR 61.(LCTSg 011008)The waste shall be identified as Class A, Class B or Class C depending on the concentrations of both long and shore-lived radio-nuclides, the waste form physical stability due to its structure and presence of liquids or voids.This identification shall be completed prior to solidification to provide control over transfer and disposal requirements.(LCTSjj 011171)This classification will use the"indirect method" for classifying waste.A1F/NESP-02 generic scaling factors shall be used initially for determining quantities of the difficult-to-measure nuclides in waste streams and filters.After 100 full power days and on a Biannual basis a composite sample of=.the reactor coolant system shall be taken for--complete nuclide analysis.


==2.0 REFERENCES==
==2.0 REFERENCES==


===2.1 Implementing===
2.1 Implementing 2.1.1 750P-lSR02, Operation of Solidification System.2.2 Developmental 2.2.1 10 CFR 20, Standards for Protection Against Radiation.
2.1.1 750P-lSR02, Operation of Solidification System.2.2 Developmental 2.2.1 10 CFR 20, Standards for Protection Against Radiation.
2.2.2 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste.2.2.3 2.2.4 Methodologies for Classification of Low-Level Radioactive Wastes from Nuclear Power Plants.AIF/NESP-027 NRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification May 1983 Rev.0 2.2.5 75RP-9ZZ02, Solid Radwaste Process Control Program.2.2.6 LCTS Serial Number: 011008, 011171, 011011 PV218400 AEV.8/82 684 A s t
2.2.2 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste.2.2.3 2.2.4 Methodologies for Classification of Low-Level Radioactive Wastes from Nuclear Power Plants.AIF/NESP-027 NRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification May 1983 Rev.0 2.2.5 75RP-9ZZ02, Solid Radwaste Process Control Program.2.2.6 LCTS Serial Number: 011008, 011171, 011011 PV218400 AEV.8/82 684 A s t
MAFV PilPOK'v~lT'fojy 0)~qj y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 4 of 19 3.0 DEFINITIONS
MAFV PilPOK'v~lT'fojy 0)~qj y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 4 of 19 3.0 DEFINITIONS 3.1 Indirect Method: The practice of using a scaling factor which infers to concentration of one difficult-to-measure nuclide from another which is actually measured.3.2 Waste Product: The result of combining the waste stream, additive,and cement to form one free-standing monolith.3.3 Waste form: A qualified standard to which a waste product is tested to ensure specific stability requirements are maintained after burials 3.4 Class A Waste: Waste containing the lowest concentrations of radionuclides-and meeting the minimum waste form requirements.stated in 10 CFR 61.3.5 Class B and C Waste: Waste containing higher concentrations of radionuclides and meeting more rigorous waste form and stability requirements stated'in 10 CFR 61.4.0 RESPONSIBILITIES 4.1 The Manager, Radioactive Materials Control has the responsibility for implementation of this procedure.
 
===3.1 Indirect===
Method: The practice of using a scaling factor which infers to concentration of one difficult-to-measure nuclide from another which is actually measured.3.2 Waste Product: The result of combining the waste stream, additive,and cement to form one free-standing monolith.3.3 Waste form: A qualified standard to which a waste product is tested to ensure specific stability requirements are maintained after burials 3.4 Class A Waste: Waste containing the lowest concentrations of radionuclides-and meeting the minimum waste form requirements.stated in 10 CFR 61.3.5 Class B and C Waste: Waste containing higher concentrations of radionuclides and meeting more rigorous waste form and stability requirements stated'in 10 CFR 61.4.0 RESPONSIBILITIES 4.1 The Manager, Radioactive Materials Control has the responsibility for implementation of this procedure.
4.2 The chemistry section is responsible for isotopic analysis of the waste stream and filter smears.4.3 The Unit Radwaste Supervisor shall ensure that the solid radioactive waste is classified in accordance with this procedure and that the appendices to this procedure are forwarded to the Support Group in a timely manner.4.4 The Radioactive Support Supervisor shall receive and review the classification documents.
4.2 The chemistry section is responsible for isotopic analysis of the waste stream and filter smears.4.3 The Unit Radwaste Supervisor shall ensure that the solid radioactive waste is classified in accordance with this procedure and that the appendices to this procedure are forwarded to the Support Group in a timely manner.4.4 The Radioactive Support Supervisor shall receive and review the classification documents.
5.0 JOB PLANNING 5.1 Resources 5.1.1 Weight scale of sufficient.
5.0 JOB PLANNING 5.1 Resources 5.1.1 Weight scale of sufficient.
capacity to weigh 55 gallon or 80 cu.ft.containers with a maximum weight of approximately 10200 lbs.PVR1MOD REV.SI82 564 A Il L v 0' i%FOB.MAYf ON 05YLY PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-lZZ01, REVISION Page 5 of 19 5.1.2 One low range beta/gamma survey instrument.
capacity to weigh 55 gallon or 80 cu.ft.containers with a maximum weight of approximately 10200 lbs.PVR1MOD REV.SI82 564 A Il L v 0' i%FOB.MAYf ON 05YLY PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-lZZ01, REVISION Page 5 of 19 5.1.2 One low range beta/gamma survey instrument.
5.1.3 One high range beta/gamma survey instrument.
5.1.3 One high range beta/gamma survey instrument.
 
5.2 Precautions 5.2.1 Solidified waste shall contain as little free-standing, non-corrosive liquid as is reasonably achievable but in no case shall the liquid exceed 0.5X of the volume.(LCTSi/011011)5.2.2 Work with radioactive material shall be conducted under the guidance of a current Radioactive Exposure Permit to keep personnel radiation exposure as low as reasonably achievable (ALARA).5.2.3 Waste gispos'al site approval is required prior to'shipment of radioactive-waste which does not meet the.criterion for non detectable free-standing liquid (i.e., not greater than 0.5%, liquid by volume).5.3 Prerequisites 5.3.1 The chemistry section has completed the isotopic analysis of the waste stream, filter or filter smear in accordance with 750P-1SR02"Operation of Solidification System".5.3.2 All survey meters and scales used in this procedure are currently calibrated.
===5.2 Precautions===
6.0 INSTRUCTIONS Appendices A, B, and E plus C and D when solidifying a filter, shall be kept together in a work package.This package shall be maintained until written notification is recoived from the burial site that tho shipment has been received.The package will thon bo sent to Drawing and Document Control.6.1 Obtain the isotopic analysis sheet from the Chemistry Section of the gamma spectroscopy on the waste sample/filter and/or filter smear.6.2 Complete Waste Product Record Appendix A, steps 1 through 7.PV216400 AEV.N82 SS4 A PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 6 of 19 6.3 To determine waste stream isotopic concentration, complete Waste Isotope Worksheet Appendix B as follows: 6.3.1 Column A-list isotopes with half-lives 25 years in the top portion and isotopes with half-lives h8 days to<5 years in the bottom portion of the table from the isotopic analysis sheet.6.3.2 Column B-enter yCi/cc from the isotopic analysis sheet.6.3.3 Column C-record the volume of waste (in cc)from Appendix A, delivered from the waste feed tank to one container.
 
6.3.4 Column D-multiply column B by column C and enter the total yCi of that isotope for one container.
====5.2.1 Solidified====
waste shall contain as little free-standing, non-corrosive liquid as is reasonably achievable but in no case shall the liquid exceed 0.5X of the volume.(LCTSi/011011)5.2.2 Work with radioactive material shall be conducted under the guidance of a current Radioactive Exposure Permit to keep personnel radiation exposure as low as reasonably achievable (ALARA).5.2.3 Waste gispos'al site approval is required prior to'shipment of radioactive-waste which does not meet the.criterion for non detectable free-standing liquid (i.e., not greater than 0.5%, liquid by volume).5.3 Prerequisites 5.3.1 The chemistry section has completed the isotopic analysis of the waste stream, filter or filter smear in accordance with 750P-1SR02"Operation of Solidification System".5.3.2 All survey meters and scales used in this procedure are currently calibrated.
 
==6.0 INSTRUCTIONS==
Appendices A, B, and E plus C and D when solidifying a filter, shall be kept together in a work package.This package shall be maintained until written notification is recoived from the burial site that tho shipment has been received.The package will thon bo sent to Drawing and Document Control.6.1 Obtain the isotopic analysis sheet from the Chemistry Section of the gamma spectroscopy on the waste sample/filter and/or filter smear.6.2 Complete Waste Product Record Appendix A, steps 1 through 7.PV216400 AEV.N82 SS4 A PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 6 of 19 6.3 To determine waste stream isotopic concentration, complete Waste Isotope Worksheet Appendix B as follows: 6.3.1 Column A-list isotopes with half-lives 25 years in the top portion and isotopes with half-lives h8 days to<5 years in the bottom portion of the table from the isotopic analysis sheet.6.3.2 Column B-enter yCi/cc from the isotopic analysis sheet.6.3.3 Column C-record the volume of waste (in cc)from Appendix A, delivered from the waste feed tank to one container.
 
====6.3.4 Column====
D-multiply column B by column C and enter the total yCi of that isotope for one container.
6.3.5 6;3.6 Column E--enter the waste product volume as calculated in step 5 of-Appendix A (cc).Column F-.divide column D by column C and enter the total yCi/cc of the waste product.6.3.7 Column I-enter the value from column D for the appropriate isotope in column H.6.3.8 Column K-multiply column I by column J and enter the scaled yCi.6.3.9 Column L-enter the waste product volume as calculated in step 5 of Appendix A (cc).6.3.10 Column M-divide column K by column L and enter the scaled yCi/cc.6.3.11 Column 0-multiply column K by column N and enter the yCi's for the isotopes having a conversion listed in column N.6.3.12 Column P-enter the waste product density from Appendix A step 7 for the isotopes which have a conversion listed in column N.6'.13 Column Q-multiply column M by N/P and enter the qCi/g.6.3.14 Box R-sum column M for scaled isotopes with half-lives
6.3.5 6;3.6 Column E--enter the waste product volume as calculated in step 5 of-Appendix A (cc).Column F-.divide column D by column C and enter the total yCi/cc of the waste product.6.3.7 Column I-enter the value from column D for the appropriate isotope in column H.6.3.8 Column K-multiply column I by column J and enter the scaled yCi.6.3.9 Column L-enter the waste product volume as calculated in step 5 of Appendix A (cc).6.3.10 Column M-divide column K by column L and enter the scaled yCi/cc.6.3.11 Column 0-multiply column K by column N and enter the yCi's for the isotopes having a conversion listed in column N.6.3.12 Column P-enter the waste product density from Appendix A step 7 for the isotopes which have a conversion listed in column N.6'.13 Column Q-multiply column M by N/P and enter the qCi/g.6.3.14 Box R-sum column M for scaled isotopes with half-lives
<5 years.6.3.15 PV21B400 REV.8I82 584 A Box S-sum column M for scaled isotopes with half-lives
<5 years.6.3.15 PV21B400 REV.8I82 584 A Box S-sum column M for scaled isotopes with half-lives
Line 532: Line 443:
<5 years.6.6.2 On Table II, list the yCi/cc values for H-3, Co-60, Ni-63, Ni-63 activated metal, Sr-90, Cs-137 and the total Ci/cc value of radionuclides having half-lives of>8 days to<5 years.PV210400 AEV.8l82 684 A 98AFY PIFORMAYEoly Ogj,y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 10 of 19 6.6.3 Divide the yCi/cc value and the yCi/g value by the limit given on the classification worksheet, for each isotope, and enter the result in the space provided.6.6.4 Add the results of each column.NOTE If the sum of any column is<1.0, use the Radwaste Classification Worksheet flow chart to determine the classification.
<5 years.6.6.2 On Table II, list the yCi/cc values for H-3, Co-60, Ni-63, Ni-63 activated metal, Sr-90, Cs-137 and the total Ci/cc value of radionuclides having half-lives of>8 days to<5 years.PV210400 AEV.8l82 684 A 98AFY PIFORMAYEoly Ogj,y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 10 of 19 6.6.3 Divide the yCi/cc value and the yCi/g value by the limit given on the classification worksheet, for each isotope, and enter the result in the space provided.6.6.4 Add the results of each column.NOTE If the sum of any column is<1.0, use the Radwaste Classification Worksheet flow chart to determine the classification.
6.6.5 If the sum for Table I is h1.0, the waste is not acceptable for near surface disposal.6.6.6 If the sum for Table II Column 1 is hl.0, list and calculate the radionuclides.in column 2 of Table II.6.6.7 If the sum for Table II Column 2 is 21.0, list and calculate the radionuclides-in-column'3 of Table II.6.6.8 If the sum for Table II Column 3 is h1.0, the waste is not acceptable for near surface disposal.6.6.9 Complete all spaces, sign and date the Radwaste Classification Worksheet.
6.6.5 If the sum for Table I is h1.0, the waste is not acceptable for near surface disposal.6.6.6 If the sum for Table II Column 1 is hl.0, list and calculate the radionuclides.in column 2 of Table II.6.6.7 If the sum for Table II Column 2 is 21.0, list and calculate the radionuclides-in-column'3 of Table II.6.6.8 If the sum for Table II Column 3 is h1.0, the waste is not acceptable for near surface disposal.6.6.9 Complete all spaces, sign and date the Radwaste Classification Worksheet.
6.6.10 Summarize the isotopic content in mCi on Appendix A step 10.6.7 Waste Characteristics
6.6.10 Summarize the isotopic content in mCi on Appendix A step 10.6.7 Waste Characteristics 6.7.1 Ensure that the packaged waste meets the following 10 CFR 61.56(a)minimum requirements for all waste classifications, enter yes or no and initial the space provided on Appendix A step lla.6.7.1.1 The waste is not packaged in a cardboard or fiber board box.6.7.1.2 Liquid in solid material does not exceed 1'X by volume.6.7'-3 The waste is not readily capable of detonation or explosive decomposition or reaction at normal pressure and temperature, or of explosive reaction with water.PV21840D REV.8/82 88' l..l l.iI r PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP"1ZZ01 REVISION Page ll of 19 6.7.1.4 The waste does not contain or is not capable of generating quantities of toxic gases, vapors or fumes harmful to handlers of the waste.6.7.1.5 The waste is not pyrophoric.
 
====6.7.1 Ensure====
that the packaged waste meets the following 10 CFR 61.56(a)minimum requirements for all waste classifications, enter yes or no and initial the space provided on Appendix A step lla.6.7.1.1 The waste is not packaged in a cardboard or fiber board box.6.7.1.2 Liquid in solid material does not exceed 1'X by volume.6.7'-3 The waste is not readily capable of detonation or explosive decomposition or reaction at normal pressure and temperature, or of explosive reaction with water.PV21840D REV.8/82 88' l..l l.iI r PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP"1ZZ01 REVISION Page ll of 19 6.7.1.4 The waste does not contain or is not capable of generating quantities of toxic gases, vapors or fumes harmful to handlers of the waste.6.7.1.5 The waste is not pyrophoric.
6.7.1.6, Waste containing hazardous biological, pathogenic or infectious material has been treated to reduce to the maximum extent practicable the potential hazard from these materials.
6.7.1.6, Waste containing hazardous biological, pathogenic or infectious material has been treated to reduce to the maximum extent practicable the potential hazard from these materials.
6.7.2 For Class B or Class C waste, ensure that the following stability requirements of 10 CFR 61.56(b)are met, enter yes, no or N/A, as applicable and initial the space provided on Appendix A step lib.6.7.2.1 The waste is structurally stable and will generally maintain its physical dimensions and form under expected disposal conditions (weight-of overburden and compaction equipment, presence of moisture, microbial activity and internal factors, such as radiation effects and chemical changes).6.7.2.2 Liquid waste or waste containing liquid has been converted into a form which contains as little free-standing and noncorrosive liquid as is reasonably achievable but not exceeding 1X by volume in a disposal container designed to ensure stability, or 0.5%%d by volume for waste processed to stable form.6'.2.3 Void spaces within the waste or between the waste are reduced to the extent practicable.
6.7.2 For Class B or Class C waste, ensure that the following stability requirements of 10 CFR 61.56(b)are met, enter yes, no or N/A, as applicable and initial the space provided on Appendix A step lib.6.7.2.1 The waste is structurally stable and will generally maintain its physical dimensions and form under expected disposal conditions (weight-of overburden and compaction equipment, presence of moisture, microbial activity and internal factors, such as radiation effects and chemical changes).6.7.2.2 Liquid waste or waste containing liquid has been converted into a form which contains as little free-standing and noncorrosive liquid as is reasonably achievable but not exceeding 1X by volume in a disposal container designed to ensure stability, or 0.5%%d by volume for waste processed to stable form.6'.2.3 Void spaces within the waste or between the waste are reduced to the extent practicable.
 
6.8 Chelating Agents 6.8.1 Obtain from the chemistry section the weight of any of the following chelating agents used over the period during which the waste was produced.EDTA DTPA Hydroxy-Carboxylic.
===6.8 Chelating===
Agents 6.8.1 Obtain from the chemistry section the weight of any of the following chelating agents used over the period during which the waste was produced.EDTA DTPA Hydroxy-Carboxylic.
and polycarboxylic acids (ex.Citric, Carbolic and Glucinic Acids).6.8.2 Assess the potential for the chelating-agent being present in the waste.PV21MOO REV.8I82 564 A 0 0 9RM"f 1NFORISJiI~~YEON OM,V PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION.Page 12 of 19 6.8.3 Determine if the container may contain a chelating agent and calculate the percent by weight, chelating agent, for the container, as follows: Wei ht of Chelatin A ent in Container 6.8.4 Weight of Waste in Container List any chelating agent present in the container equal to or exceeding O.l%%d by weight for the container and complete ll.c as appropriate.
and polycarboxylic acids (ex.Citric, Carbolic and Glucinic Acids).6.8.2 Assess the potential for the chelating-agent being present in the waste.PV21MOO REV.8I82 564 A 0 0 9RM"f 1NFORISJiI~~YEON OM,V PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION.Page 12 of 19 6.8.3 Determine if the container may contain a chelating agent and calculate the percent by weight, chelating agent, for the container, as follows: Wei ht of Chelatin A ent in Container 6.8.4 Weight of Waste in Container List any chelating agent present in the container equal to or exceeding O.l%%d by weight for the container and complete ll.c as appropriate.
NOTE If the chelating agent is equal to or greater than 0.1%by weight, permission from Hanford Disposal Site must be granted prior.to shipping the waste.PV2N40D REV.SI82 SS4A I v 0 0 QUART~FO@~YEO&#xc3;(ygy\PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION APPENDIX A Page 1 of 1 Page 13 of 19 1.Batch Number WASTE PRODUCT RECORD 10.0 ISOTOPIC  
NOTE If the chelating agent is equal to or greater than 0.1%by weight, permission from Hanford Disposal Site must be granted prior.to shipping the waste.PV2N40D REV.SI82 SS4A I v 0 0 QUART~FO@~YEO&#xc3;(ygy\PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION APPENDIX A Page 1 of 1 Page 13 of 19 1.Batch Number WASTE PRODUCT RECORD 10.0 ISOTOPIC  

Revision as of 06:37, 6 May 2019

Solid Radwaste Process Control Program. Draft Procedures 75RP-9SR01, Solidification Process Control, 75OP-1SR02, Operation of Solidification Sys & 75RP-1ZZ01, Solidified Radwaste Classification, Encl
ML17298B451
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 10/30/1984
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17298B450 List:
References
PROC-841030, NUDOCS 8411020288
Download: ML17298B451 (269)


Text

SOLID RADMASTE PROCESS CONTROL PROGRAM PALO VERDE NUCLEAR GENERATING STATION 84ii020288 84i030'DR ADQCK-05000528.*pgp 0 IJ C.I 0 TABLE OF CONTENTS Section 1.0 2.0 Title PURPOSE DEFINITIONS AND ABBREVIATIONS

~Pa e 3.0 PROGRAM DESCRIPTION 3.1 Maste Types 3.2 Process Parameters 3.3 Haste Classification 3.4 Waste Preconditioning 3.5 Verification of Solidification 3.6 Stability Requirements 3.7 Data Sheets 3.8 Record Retention 3.9 Radiological Precautions

4.0 REFERENCES

APPENDICES Appendix A-Schematic Flow Diagram Appendix B-Radwaste Cement Solidification System Diagram l I 0 1.0 PURPOSE The purpose of the Process Control Program (PCP)for the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3 is to establish a set of process parameters which will provide reasonable assurance of complete solidification of various liquid radioactive"wet wastes" including resin slurries, evaporator bottoms, filter sludges, and chemical drains in accordance with the requirements of applicable portions of the PVNGS Quality Assurance Program, PVNGS Technical Specifications, PVNGS Final Safety Analysis Report, Depart-ment of Transportation (DOT)regulations, Nuclear Regulatory Commission (NRC)regulations, and licensed burial facilities acceptance criteria for solidification, packaging, and ship-ment to an approved offsite burial site.There are no Arizona State Regulations applicable to PVNGS.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 regulations 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.

2.'0 DEFINITIONS AND ABBREVIATIONS a.ALARA b.Batch c.Bench Test As low as is reasonably achievable.

A quantity of water type(s)prepared in the waste feed tank for solidification.

(Laboratory testing of the solidification process on a reduced scale with representative mixing ratios and similar operational techniques.

d.Wet Waste Types Liquid radioactive wastes, sludges, and ion exchanger resins.3.0 e.Monolith-A freestanding, solid object.PROGRAM DESCRIPTION a.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:

~i 1)Chemical regenerative and decontamination waste (evaporator concentrates) from a forced recirculation evaporator.

2)Boric acid waste from the Boric Acid Concentrator.

3)Bead resin waste as a slurry from the Spent Resin Tanks.4)Chemical Drain Tank waste.5)Spent filter cartridges.

b.Typical and atypical wet waste types shall be identified by the"Solidification Process Control" procedure, which provides a record of waste formulations.

c~When the radiation level of a waste batch is determined to be excessive by ALARA standards, a waste substitute shall be prepared in accordance with the"Solidification Process Control".3.2 Process Parameters a~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 the"Solidified Radioactive Waste Classification" procedure.

b.The process parameters for various class-A wastes shall be based on the Hittman Radwaste Solidification System (Cement)Topical Report, HN-R1109, Revision 4 (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.co For class-A waste types containing concentrations of chemicals that do not fall within the bound of chemical concentrations for which preoperational solidification tests have been performed by Hittman Nuclear and Develop-ment Corporation, acceptable base data for test solidifications shall be developed in accordance with the"Solidification Process Control" procedure.

d.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 the vendor's operating procedures.

Class B and C waste will be processed in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.

0 e.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"Solidifi-cation Process Control" procedure",or a portable solidification system will be used in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.f.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.

3.3 Waste Classification a~The"Solidified Radioactive Waste Classification" procedure shall provide PWR scaling factors for identifying specific radionuclides as required by 10 CFR 61.55,"Waste Classification." b.Scaling factors shall be verified or updated annually by waste stream analysis to ensure acceptable standards are maintained for waste classification.

c.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"Solidified Radio-active Waste Classification" procedure.

3.4 Waste Preconditionin a.The"Operation of Solidification System" procedure shall designate the required mixing/recirculation times and system operations to ensure a representative sample is obtained after chemical addition and prior to process initiation.

b.Adjustment of the waste solution pH shall be in accordance with the"Operation of Solidification System" procedure.

c.The"Operation of Solidification System" procedure shall designate when heat tracing is required to ensure chemical suspension.

3.5 Verification of Solidification a~Solid Radwaste S stem 1)The solidification bench tests, in accordance with the Hittman Topical Report, Radwaste Solidification System (Cement), HN-R1109, Revision 4, provide the solidification bench testing base data for the"Solidification Process Control" procedure for use with'class-A type waste.

lf P 0 2)The solidification bench tests in, accordance with a vendor's NRC approved 10 CFR 61 Topical Report will provide the bench testing base data for the"Solidification Process Control" procedure for use with class-B and C type waste.3)During solidification system operations, additions'o the waste feed tank, waste feed pump operation, and process mixing ratio adjustments shall be in accordance with the"Operation of Solidification System" procedure.

i.No additions will be made to the waste feed tank while the tank is being recirculated for sampling or processing.

ii.The waste feed pump will not be stopped during sampling.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.5)If any solidification bench test is found to be not acceptable, subsequent operations and testing shall, be in accordance with the"Solidification Process Control" procedure.

6)The solidification bench test acceptance criteria shall be in accordance with the"Solidification Process Control" procedure.

7)Solidification product quality is controlled by the performance of the"Operation of Solidification System" procedure.

b.Portable Solidification S stem The portable solidification vendor will verify proper solidification of the waste product in accordance with the vendor's operating procedures and a NRC approved 10 CFR 61 Topical Report.c~Handling of containers of unacceptable solidified waste shall be in accordance with the"Operation of Solidifi-cation System" procedure.

0 3.6 Stabilit Re uirements-The"Solidification Process Control" procedure shall identify the stability specifications as set forth in 10 CFR 61.56,"Haste Characteristics," and Branch Technical Position ETSB 11-3, Revision 2, July 1981,"Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Mater-Cooled Nuclear Power Reactor Plants." 3.7 Data Sheets a.For each solidification bench test actually used fo'waste processing, a test data record shall be maintained in accordance with the"Solidification Process Control" procedure.

b.For each batch solidification process, a feed rate determination shall be completed in accordance with the"Solidification Process Control" procedure.

c.For, each batch solidification process, records shall be maintained of the unique batch information in accordance with the"Solidification Process Control" procedure.

d.For each batch solidification process, a waste classi-fication record shall be completed in accordance with the"Solidified Radioactive Waste Classification" procedure.

3.8 Record Retention For each batch solidification process, all records generated shall be maintained in accordance with the"Document/Record Turnover Control" procedure.

3.9 Radiolo ical Precautions 4.0 The radiological precautions necessary for implementing the Process Control Program shall be followed and are covered in the"Radiation Protection Program" procedure.

REFERENCES a.NUREG-0472,"Radiological Effluent Technical Specifications for PWRS," Revision 2, July 1, 1979.b.10 CFR 20,'Standards for, Protection Against Radiation." c.10 CFR 71,"Packaging and Transportation of Radioactive Material.",

I 1 Palo Verde Nuclear Generating Station Technical Specifications.

49 CFR Subchapter C-"Hazardous Materials Regulations." Palo Verde Nuclear Generating Station Final Safety Analysis Report, Sections 11.4, 12.1, and 12.3.Palo Verde"~Nuclear Generating Station procedure,"ALARA Program." Palo Verde Nuclear Generating Station Final Safety Analysis Report, Section 17.2;"Quality Assurance During the Operating Phase." Palo Verde Nuclear Generating Station manual,"Operations Quality Assurance Criteria Manual," Revision 1, August 31, 1984.Palo Verde Nuclear Generating Station procedure,"Solidification Process Control." Palo Verde Nuclear Generating Station procedure,"Operation of Solidification System." Pa3o Verde Nuclear Generating Station procedure,"Solidified Radioactive Waste Classification." Palo Verde Nuclear Generating Station procedure,"Document/

Record Turnover Control." Topical Report, Radwaste Solidification System (Cement), Report No.HN-R1109 (Non Proprietary), Revision 4 (Interim Revision 5), April 1977,Section VII,"Cement Solidification Process Chemistry>" Hittman Nuclear and Development Corporation.

USNRC 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." 10 CFR 61,"Licensing Requirements for Land Disposal of Radioactive Waste." Palo Verde Nuclear Generating Station procedure,"Radiation Protection Program."

APPENDIN A BOR I C ACID CONCENTRATOR EVAPORATOR CONCENT ATE MONITOR TANKS WASTE FEED TANK CHEMICAL DRAIN TANKS CEt 1ENT AND ADDITIVE WASTE/CEMENT PROCESSOR SPENT RESIN TANKS SPENT FILTER CARTRIDGES DRUt1 OR LINER SCHEf1ATIC FLO'll DIAGRAt1 0

APPENDIX B ADDITIVE ROTARY VALVE ADDITIVE FEED CONVEYOR CEMEHT TANK INPUTS MIXER CEMENT ROTARY VALVE AND CONVEYOR l/WASTE FEED TANK WASTE/CEMENT PROCESSOR DRUf1 OR LINER RADWASTE CEMENT SOLIDIFICATION SYSTEM D I AGRAM f~3RAIFV Pfpopg>M+pigog PALO YERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CCÃZROL PROCEDURE NO.7SRP-9SR01 REVISION Page 1 of 23 DEPT.MANAGER/DEPT.HEAD PRB/PRG TRRG REVIEW APPROVED BY EFFECTIVE DATE DN-a38~V/0573V DATI.'ATL'ATl PV21040D AEV.Sl82 0~i PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS COHTEQL PROCEDURE NO.75RP-9SR01 REVISION Page 2 of 23 Rev.No.Date REVISION HISTORY Revised Pages CommentsPV210400 REV.BI82 t I 0 JNFOHMATH)N OMLV PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL TABLE OF CONTENTS SECTION 1.0 PURPOSE

2.0 REFERENCES

3.0 DEFINITIONS 4.0 RESPONSIBLITIES 5.0 JOB PLANNING 6.0 INSTRUCTIONS PROCEDURE NO.75RP-9SROl REVISION Page 3 of 23 PAGE NUMBER ,5APPENDICES Appendix A-Waste Process Record Appendix B-Bench Test Data Record 13 14 Appendix Appendix C D Haste Formulation Table 16 Bench Feed Rate Determination Record 15 Appendix E-Standard Feed Rate Determination Record 18 Appendix F-Feed Curves 19 PV216400 REV.SI82 IIf H 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SR01 REVISION Page 4 of 231~0 2.0~Fur ose The purpose of the Solidification Control procedure is to provide process parameters and detailed instructions for bench testing and determining process feed rates in accordance with the requirements set forth in 75PR-9ZZ02,"Solid Radwaste Process Control Program".This also provides a historical and auditable record of the solidification process for packaging, transport and bur ial requir ements, References 2.1 Implementing References 2.1.1 750P-1SR02, Operation of Solidification System.2.1.2 75AC-9ZZ01, Radiation Exposure Author ization, Permits and Control 2.2 Developemental References 2~2~1 2Hittman Topical Report Radwaste Solidification System (Cement)Report No.HN-R1109, Rev.4 75PR-9ZZ02, Solid Radwaste Process Control Program 2.2e3 75PR-OZZ01, Radiation Protection Program 2.2.4 Vendor Waste Form Test Report 2.2.5 LCTS Serial Numbers@lk19N',%5SRP1@gxig8 cGz6rd PV21640D AEV.8/82 t s v I g~1 0 9RAF7 LNPOBMAYJOX OM,PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.75RP-9SR01 REVISION SOLIDIFICATION PKCESS CONTROL Page 5 of 23 3,0 Definitions 3.1 Bench Test-A test performed on a reduced scale to check and verify a specific chemical process.3.2 Batch-A quantity of waste type(s)prepared in the waste feed tank for solidifiction.

3.3 Wet Waste-Liquid radioactive wastes, sludges, or ion exchanger resins.3.4 Waste Substitute

-A solution or slurry which has chemical properties matching thoses of a specific wet waste type.3.5 Monolith-A free standing, solid object.3.6 REF-Radiation Exposure Permit.3.7 Cure Time-The time required for the liquid waste to change to a free standing solid as a result of a chemical reaction.3.8 LCTS-Licensing Commitment Tracking System, 4.0 Res onsibilities 4,1 The Unit Hadwaste Supervisor's have the responsi-bility for implementation of this procedure.

4.2 The Chemistry Section is responsible for waste sampling and analysis.4.3 The Radwaste Technician shall ensure that the appli-cable portions of this procedure are completed for each new batch of wet waste prior to being processed and all tests and inspections are completed and verified by signature.

The Technician should keep this procedure with the"Operation of the Solidifi-cation System" procedure during processing and will ensure all required information is recorded on the appendices.

PV216400 REV.8!82

't , v 4~0 IlVVOHMATEOÃ M1 j.V.Ea)RAFY PROCEDURE NO.75RP-9SR01 REVISION SOLIDIFICATION PROCESS CON'QVL PALO VERDE NUCLEAR GENERATING STATION MANUAL Page 6 of 23 5.0 Job Plannin 5.1 Resources 5.1.1 Mater ials 5.1.1.1 Survey Meters 5.1.1.2 Cement (for bench test only)5.1.1.3 Additive (for bench test only)5.1.1.4 Bench Test Lab 5,2 Precautions 5.2.1 5.2.2 5.2'5.2.4 A REP shall be issued in accordance with 75AC 9ZZ01, Radiation Exposure Authorization, Permits and Control for work within the Radiological Controlled Area.Proper ALARA practices shall be observed at all times.Waste process feed rate settings shall be de-ermined from the chemistry analysis results.If the type of waste according to its chemical constituents falls into one the waste formulation categories in the"Waste Formulation Table" Appedix D the"Standard Feed Rate Determination Record" Appendix E and"Feed Curves" Appendix F shall be used.For Class"A" waste;if the"Waste Formulation Table" is not applicable, the bench test shall be performed using"Bench Test Data" Appendix B,"Bench Feed Rate Data" Appendix C, and"Feed Curves" Appendix F.For Class"B" and"C" waste, if the"Waste Formulation Table" is not applicable; in addition to the Bench Test Performance using Appendix B, Appendix C and Appendix F;waste form testing shall be performed in acordance with a NRC approved Vendor and Waste Form Test Report.PV210-000 REV.8I82 I'

tIIIRAFT JNFojttlAVj:ON ONKVPALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCES CONTROL PROCEDURE NO.75RP-9SROl REVISION Page 7 of 23.5.2.5 A solidification bench test shall be performed to support waste mixing ratios as follows: (LCTS: Qgg+Q5 5.2.5.1 At a minimum of every tenth batch of each waste type.5.2.5.2 When the sample analysis falls outside the normal envelopes established in appendix D, 5.2.5.3 When it is believed that some other contaminant may be present.5When deemed necessary by the Unit Radwaste Supervisor.

5.2,6 5.2.7 5.2.8 5.2.9 The Bench Test shall be per formed using approximately 0.6 pounds of waste or waste substitute resulting in a final test priduct weight of approximately 1.2 pounds.The use of waste substitute for bench testing shall be based on ALARA considerations.

Use actual system fluids whenever practical.

The cure time for the test;-will normally be 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.If the sample is not solid after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, consideration shall be given to performing a new test with different cement/additive ratios.The bench test shall be considered unacceptable if the product is not a monolith having no free standin liquid in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.The maximum pH shall be 11.0 to minimize the potential for in-line solidification.

5.3 Prerequisites PV210400 REY.N82 5'.1 The waste feed tank is in recirculation and pH is adjusted in accordance with 750P-1SR02,"Operation of Solidification System", Section 9.0.

  • H fi PALO VERDE NUCLEAR GEQ/PATIQG STATION MANUAL SOLIDIFICATION PEQCESS CCNTROL PROCEDURE NO.75RP-9SR01 REVISION Page 8 of 23.5.3.2 5'3 5~3~g The waste feed tank has been sampled and the required analyses are complete.Attach a copy of the chemical analysis results to Appendix A of this procedure A REP is issued for bench testing as required in accordance with 75AC-9ZZ01,"Radiation Exposure Authorization, Permits and Control".6.0 INSTRUCTIONS 6.1 Complete Lines 1 through 6 on Appendix A.6.2 Enter the values for pH, weight and volume percent for the following:

Water Bor ic Acid Bead Resin Sodium Sulfate Ammonium Sulfate NOTE Sodium Chloride Crud Oil Citr ic Acid~EDTA The waste formulations are general categories and will never completely duplicate actual conditions, Wastes in the Waste Feed Tank contain small amounts of metal oxides, carbonates, phosphates, silicates, chromates, hydrazine, chlorides, oil, detergents, etc., in addition to the expected H380 , Na SO>, or Bead Resin.As long as th)imp5riCies are present in small amounts (less than two percent each)the solidification of the cement will not be impaired.Actual waste weight percentages must be within 10$of the waste formula for the table to be applicable.

If any impurity is greater that 2$or the combined weight percetages vary greater that 10$, a bench test must be performed and mixing ratios determined.

PV218400 REV.SI82 t 0

..GRAF<.HFOBMAZjoy 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL 75RP-9SR01 REVISION SOLIDIFICATION PKCESS CPM)L Page 9 of 23 6.3 Standard Feed Rate Determination NOTE The"Standard Feed Rate Determination Record" Appendix E shall be completed for each solidification process that does not require a bench test when the waste chemical composition is categorized by"Waste Formulation Table" Appendix D, Use Appendices B and C when a bench test is required.Ensure that the batch number is entered on Appendix E to provide waste batch identification.(LCTS: 032650)6.3.1 6.3.2 6.3.3 6.3.4 6.3.5 From the sample results recorded in step 6.2, determine which category of the"Waste Formulation Table" Appendix D may be used.Waste Formulation Category Find the applicable category on the"Standard Feed Rate Determination Record" Appendix E and record the Waste Feed pump dial setting and pump RPM (SRN-SI-314 located on Radwaste Solidification Control Panel, 1-J-SHN-E01) in the"Actual Set" column in accordance with that"Waste Feed Curve" Appendix F.Record the corresponding cement feed dial setting and RPM (SRN-SI-315, located on Solidification Control Panel)in the"Actual Set" column in accordance with the"Cement Feed Curve" Appendix F.Record the corresponding additive feed dial setting and RPM (SRN-SI-316, located on Solidification Control Panel)in the"Actual Set" column in accordance with the"Additive Feed Curve" Appendix F.Sign and date Appendix E, PV21840D REY.8/82 rt V GRAFY gqpog(~)@0~PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SR01 REVISION Page 10 of 23 6.4 Bench Test Per formance NOTE Use"Bench Test Data" Appendix B for Section 6.4.Appenidx B shall be maintained for each bench test which has actually been used for waste processing, Ensure that the batch number is entered on Appendix B to provide waste identification.

The standard density (githout aeration)for Portland 1 Cement is 94 lbs/ft agd for anhydrous sodium metasilicate is 64 lbs/ft.(LCTS: 032649)6.4.1 6.4.2 Measure approximately 250 to 350 ml's and (0.6 lb.)of waste slurry or substitute into a diposable beaker and enter the ml value in Section 1.Weigh the waste slurry and enter the lb and g value in Section 1.NOTE The weight of cement and additive used for this test shall be determined by taking a percentage of the waste (80 to 110$)from step 6.4.2 for the cement quantity and a percentage of the cement (8 to 12$)for the additive quantity.These percentage may vary to affect the packing efficiency and product quality-.6.4.3 6.4.4 6.4.5 Enter the weight of cement and additive to be used in the test in sections 2 and 3 respectively.

Mix the additive and cement together in one beaker, Add the cement;/additive mixture slowly to the waste slurry while mixing with the slow speed stirrer for approximately two mintes.Record Date Time PV810409 REV.8/82 rP'0 1NFORMAYggg Om,y PALO VERDE NUCLEAR GENERATING STATION MANUAL, SOLIDIFICATIChV PROCES COVZROL PROCEDURE NO.75RP-9SR01 REVISION Page 11 of 23 NOTE6.4.6 After mixing and an adequate cure time, perform the following solidification checks, and record on Appendix B.If any bench test fails to verify solidification, the solidification process for that batch shall not commence until additional test are obtained in accordance with 750P-1SR02,"Operation of Solidification System" and alternative solidification parameters are determined and verified in accordance with section 6,0 of this procedure, (LCTS: 011113)When a bench test is determined to be unacceptable, each consecutive batch of that wet waste type shall be tested until three consecutive initial tests demostrate proper solidification.(LCTS: 011114)Observe specimen for freestanding water and record results in Section 8.6.4.7 Check to see if specimen is monolithic with a definite volume and shape.Record results in Section 8.6.4.8 6.4.9 Weight the final product and enter weight in Section 4.Determine final product volume by measure-ment and record and calculate ft in section 5.6.4.10 Determine product density by performing calculation in section 6.NOTE lbs/ft may be changed to g/cc as follows: (lbs/ft)(.016)=g/cc PV21840D REV.8I82 0

PALO'VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SR01 REVISION 0-Page 12 of 23 6.4.11 6.4.12 6.4.13 Determine packing efficiency by performing calculation in section 7.Record the, reason for the bench test, any abnormalities, other tests or checks, etc.in section 9.Sign and date section 10., noting the pre-24 hour results.PV218400 REV.8l82 0 0 OII'MA YIoyPALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SR01 REVISION Page 13 of 23 6.5 Bench Feed Rat'e Determination NOTE Use"Bench Feed Rate Determinations" Appendix C for Section 6.5.Determine the waste feed rate to be used from Appendix F, note the corresponding pump RPM and dial setting and,record in Section 1.6.5.2 Using the data from section 1 and 2 of Appendix B complete the equation in section 2.6.5.3 NOTE Complete Section 11 of Appendix B 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter mix time.Use the cement feed rate (C)and Appendix F to find the corresponding RPM and dial setting and record in Section 2.Using the data from sections 1 and 3 of AppendixB, complete the equation in section 3.Use the additive feed rate (B)and Appendix F to find the corresponding RPM and dial setting and record in Section 3.6.5.6 Sign and date Appendix C.PV21MOD REV.SI82 0

~FO~MAYLoiX Oiyl PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS COFZROL PROCEDURE NO.75RP-9SR01 REVISION Page 14 of 23 Items of section 6.0 of this procedure have been completed or exceptions have been recorded and documented below.Performed by: Signature and Initial Date Review of this procedure for data versus acceptance criteria to determine the success or failure of the procedure and confOrmance with the prodecural requirements, Reviewed by: Signature and Initial Date This procedure has been reviewed and found acceptable.

Approved by: Signature and Initial Date Attach original copy(ies)of Appendix(ces) and route to the Unit Radwaste Supervisor in accordance with 75RP-9ZZ26, Radwaste Forms Control.PV218400'REV.

8I82 l l l4 j 9RAF7 INFORMAYNNY ONI.V PALO VERDE NUCLEAR GENERATING STATION 1VIANUAL soLIDIFlcA'rroN r Rocrss coN'rRoL PROGEOuRE NO.75RP-~)SR01 REVISION APPENDIX A Page 1 of 1 Page 15 of 23 l.Batch Number 2~Wast:e Type LI-310 Init;ial: WASTE PROCESS RECORD Final: 3, Filter Included Yes No Source Number of 4.Cement: 'fype LI-385 Initial: 5.Additive Type 6.Container Type List Serial No's Final: 7.Process Date/Time Start: 8, Storage Location 9, Remarks: Stop: 10.Operation Complete: Technician PV210400 REV.8I82 I'e p J f.I IM'OHMIC Trod OzjLV PALO VERDE NUCLEAR GE/ERATlNG STATION lNANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.'75RP-9SR01 REVISION APPENDIX B Page 1 of 1 Page 16 of 23 Batch No.BENCH TEST DATA RECORD 1.Waste Slurry: (w)lb, g ml (1 f t/28,320ml) 2.Cement: (D)3.Additive: (B)4, Product Weight: 5.Product Volume: (lb.lb.lb.in)/(1728 in/ft)6.Product Density: ($4 1bs/ft~7.Packing Efficiency:

Waste Slurr ft3 x 100 Product Vol.ft3 8.Observations:

-Cure'ime Period hrs.-Any free standing water yes no-Is sample monolithic with a definite volume and shape yes no 9.Remarks: 10.Test Complete: Technician Pre 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Result,s Acceptable Date Unacceptable 11, 24 Hour Observation:

Remarks: Date: Sat.Time 2 Unsat, PV218 00D REV.8I82 a 1 I'j t j 0 0 9P@Fr 1NFORMAYION OM.V/~PALO VERDE NUCLEAR GENER'ATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SI<01 REVISION APPENDIX C Pago 1 of 1 Pago 17 of 23 Batch No.BENCH FEED RATE DETERMINATION RECORD NOTE Tho dosirod rosin waste food rate is 8.0 to 12,0 GPM.1.Waste Food: Rate (F)GPM, Dial 1 RPM 2.Cement Feed: Rate (C)lbs/min, Dial RPM C=(F)(D/W)(10'l/.26418 ga 1)C=Cement Feod Rato F'Waste Feed Race D=Cement Weight, App.B W=Waste Slurry ml, App, B 3.Additive Feed: Rate (A)lbs/min, Dial Ill'M)A=(F)(B/W)(10'l/.26418 gal)A=Additive Feed Race F=Waste Feed Rate B=Additive Weight, App.B W=Waste Slurry ml, App.B 4.Performed By: Technician PVl15409 MY.SI4R I,

9RAIF7 INFOBIT PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP"9SR01 REVISION APPENDIX D Pago 1 of 2 Pago 18 of 23 WASTE FORMULATION TABLE NOTE Formulations aro weight porcont.The data given in this Cable is supported by Che Vondor Wasto I'orm Tost Roport, This Cable shall be oxpandod as noodod.Co acoomodate now waste form data.Formulations aro weight porcont.A.Boric acid waste of a forced recirculation ovaporacor-Water: Boric Acid: Crud: Temperature; pH: B.Bead resin waste-87.9/12,0%0,1%170 F 8 to 10 Water: Bead Resin: Temperature:

pH;50/50%70 F 1 C.Chemical regenerate waste of a forced recirculation evaporacor-Pl01040D mel82 Water: Sodium Sulfate: Ammonium Sul f ate: Sodium Chloride: Crud: Temperature:

pH: 73,4/14.9%9.6%2,0%0.1%170 F 7to8 VP

~08ÃiA j fog OM PALO VERDE NUCLEAR GUS(ATIQQ.

STATION MANUAL SOLIDIFICATION PROCESS CONTROL PROCEDURE NO.75RP-9SI<01 REVISION APPENDIX D Page 2 of 2 Page 19 of 23 D, Chemical regenerat:ive wast:e of an evaporat:or-Wat:er: Sodium Sulfate: Ammonium Sul fat:e;Sodium Chloride: Crud: Temperat:ure; pH;50%29/16, 8/4.0%0.2%150 to 250 F 7 to 8 E.Decontamination waste of an evaporat:or-Water: EDTA: Citric Acid: Crud: Hydraulic Oil g2: Lubricating Oil g2: Temperature:

pH: 50%9.8%19%0,2/0.5%0.5%150 to 250 F 8 to 10 PV210.000 REV.NQ 0 0,

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F'T t 0 0 0 l3Y (,I II<:I%I I)IIY j1 0 rj0 C/Js/mir J A 0 I t l 0 GRAF'." Q S.1NFOBMA7g)N 0@L y I)/4 I I I)lb I I'IJI)JI I I Pr)8/r I u4 r-c=~=D c gPPc=tui>r k DI i?u~"iI II I I II()I 3 fail+)I)II I II)'7)IMP-g St20 I

,k h ql 0~'j'f' EWORMAYLog OM,Q PALO'VERDE NUCLEAR, GENERATING STATION MANUAL oPERATIoN or: sor,IDIFICATIoN sYsTEz PROCEDURE NO.750P"1SR02 REVISION 0 Pago 1 of 83DEPT.HEAD , PRB/PRG REVIEW APPROVED BY EFFECTIVE DATE DN"2275V/0548V DATE DATE DATE K",(>>i I jg V0 LNFOEVATj'ON 0~@PALO VERDE NUCLEAR GENERATING STATION MANUAL.'750P-1sR02 REVISION OPERATION OF SOLIDIFICATION SYSTEM Page 2 of 83 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 3.2.0

3.0 REFERENCES

LIMITATIONS AND PRECAUTIONS 4.0 SYSTEM AL1GNMENT 5.0 FILLING THE STANDBY CEMENT FEED TANK 6.0 REPLACING THE'N-SERV1CE CEMENT FEED TANK 7.0 FILLING ADDITIVE FEED TANK 8.0 FILLING CHEMICAL ADDITION TANK 9.0 WASTE FEED TANK RECIRCULATION AND CHEMICAL ADJUSTMENT 14 l7 19 21 10.0 11.0 55 GALLON DRUM FILL OPERATION"" LINER FILL OPERATION 0P 5 37 12.0 TRANSFERRING FILTER INTO WASTE CONTAINER 13.0 CEMENT/WASTE MIXER PLUSH 46 APPENDICES Appendix A-Valve Verification List~I Appendix B-Control Panel Settings List Appends C-Electrical/Misc.

List Appendix D-Heat Tracing Breakers"List Appendix E-Troubleshooting 52 59 63 PO10409 m8I82 P p 0'I M'gy7'WFOBMpyqog(0~PAL'0 VERDE NUCLEAR GENER'ATING STATION IVlANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Pago 3 of 83 1.0 OBJECTIVE This procedure provides instructions for system alignment; filling the cemont:, additive and chemical addition tanks;recirculating waste food tank contents;adding chemicals t:o the wasto.food t:ank;transferring filt:ors into waste containers; filling drums and liners and tho cement/waste mixer flush.A troublo shoot:ing guide is provided to assist in dot:ormining what actions aro nocossary to correct system oporating problems.

2.0 REFERENCES

2,1 Implomont:ing Roforoncos 2.1.1 410P-1IA01, Instrument and Service Air;needed for St:op 4.2.1.'2, 2.2.2.~2~1,2 410P-1CHOl, Reactor Makoup Wat:or;noodod for St'op 4.2.2.1.3 410P-lGA01, Service Gas;neoded for St:op 4,2.3.1,4 410P-lDS01, Domostic Wator, needed for St:op 4,2,4, 1.5 410P-1NH01, 480 Non Class IE MCC needed for Step 4,2,6, 1,6 410S-1NG01, 480 Non Class IE Swit:chgoar needed for Stop 4,2.7, 2.1.7.750P-1HR01, Radwasto Bldg.HVAC System needed for Stop 4.2.5, 2.1.8 75AC-9ZZ01, Radiation Exposure Authorization, l'ormits and Control needed for Steps 9.2.2, 10.2.5 and 11.2.5.2.1.9 7SRP-9SR01, Solidification Procoss Cont:rol, ncodod for Stol~a 9~3'13<10~2'2s 10~3~lt ll~2~2s ll~3~1, 3~9~2,1.10 75RP-9ZZ57, Fackaging, Marking and Labeling of Radioactive Matorial,.noodod for St:ops 10.2.4 and 11.2.4.2.1.11 75RF-1ZZ01, So%'idified Radioactive Waste Classification, needed for Steps 9.3.14, 10.2.3 and 11.2.3.2.2 Developmental References 2.2.1 P&ID 13-N-SRP-002, Rev.6 2.2.2 Single Line Diagram, 13-E-NHA-014, Rev.9 PV21040D REV.N02 t(tq K~p p (]Pgi'()]EMICTION ONLY.PALa yERDP,NuCLeAR GFNSRATIXG ,STATION, MANuAL OPERATION OF SOLIDI1 ICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 4 of 83 2.2.3 Single Line Diagram, 13-E-NHA-012, Rev.7 2.2.4 Single Line Diagram, 13-E-NKA-004, Rev, 4 2.2.5 Elementary Diagram, 13-E-SRB-003, Rev, 4 2.2.6-Elementary Diagram, 13-E-SRB-004, Rev.2 2.2.7 Elementary Diagram, 13-E-SRB<<005, Rev, 5 2.2,8 Bechtel Log No.13-10407-E052-80-6, Rev.6 2.2,9 Bechtel Log No, 13-10407"E052-111-3, Rov.1 2.2.10 Bechtel Log No.13-10407-E052-112-6, Rov.5 2.2.11 Bechtel Log No, 13-10407-E052-113-7, l<ov.8 2.2,12 Bechtel Log No.13"10407-E052-114"5, Rov, 4 2.2.13 2.2.14 I 2.2.15 Bechtel Log No.13-10407-E052-445"4, Rov, 5 Bechtel Log No.13-10407-E052-526-3, Rcv.3"Radwaste Solidification Syst: em Operating and Maintenance Manual", Vol.1, Bk, 1, Hittman Nuclear and Development Corp, 1981 2.2.16 LCTS Serial Numbers RMO: 011089 011108 011110 011111 011165'32642" 032644 RMS: 010592 010593 011011 011019 011035 011037 011161 2.2,17 2.2.18 75PR-OZZ01, Radiation Protection Program.Unit One Interim Technical SPecifications 3/4,11.3, Solid Radioactive

'Haste.;PY21440D REV.NOR t W4 g,'".t~4'f 00

@RAFT LNFOBMAYE oj3 Oj>jy PALO'VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE'O.

750P-1SR02 REVISION Pago 5 of 83 3.0 LIMITATIONS AND PRECAUTIONS 3,1 Personnel should avoid cont:act with system fluids as chemical burns or radioactive contamination may rosult:.3~2 3.3 Act:uation of SRN-HS-333, Emergency Stop Pushbutton will secure all'cont:rol power Co SRN-E01, Solidificat:ion Control Panel, Tho following condit:iona wi11 secure process fill operation and align Waste foed t;o rocirculation;

~Loading flange, SRN-M06 in Cho"Up" position.~Liner echo lostl liner over fill alarm.3,4~Addit:ivo rotary valve, SRN-M08 sCop, Sustained loss of cement flow signal, The following conditions will secure procoss fill and wast:e food recirculation:

~Loss of waste feed tank mixer, SRN-Q03,+Loss of wasto food pump, SRN-P02.Waste feed tank recirculation will be automatically shutdown by the following control signals:<Shutdown 200 signal from programmablo controller.

~Loss of waste feed tank mixer., 3.6 All operations will be in compliance with 75PR-0'l'401, Radiation Protection Program.

  • I'fq<>v'sar>neL LnaocTV'1 v>aT ior>4.l.l."'>y T,em al i>:>nr>leva wi 1 1 v edu1i"e or>c aual i f 1ed hadwas'I'e I BCI I'n1C1"in al>a OY>B Qual 1t led AaGW ls'Ce I-Baa I eanV>)Cl ir>wno nas sysver>i v Bspor>sl a111Ty and cool d1r>aves Tne<<.aev'a'6 1 oi">~L.r'0 wl L l P>>>aulPB<aaou'6'I oui'4)noui'6'co fieÃT<<.v'frl ar>a L 1 fir>f>lev>T

~4.1.8 i h 1 5 sec'0 1ol>w 1 I I v>oi f>la 1 I y<l'U l.f>ler>%

V'e'0 ur<r>'CO Sel Vlcc ciTt Bi f>la,'}OV'<i"i i Y<T>."~f)<LY>CI>><<.'VBpa 1i" oi'ys'0 ef>l O'Ii ave ua pi"epav'aT, 1 Gr>s~C)pevaixor>s w1i1.ae'p'er Tovr>iea on v,ne L>>!>>/i ana))>f>'.eve i.ot one vaawasce oui ia1nn ar>a at vai'ious>'<LI<<c<;v>r'.iL paV>B L se 4~~pv'crea u1 s1 v es.4.R.1 Inst vur>ler>e ana sevv1ce a1r 1 s 1n=er v1ce To f: fic.soliaiticatxon system 1r>accuvdar>ce wxzn 4LQi>>-L LiieL.4 2 2 Reaccov'>latceup watep 15 1v>sei'"V1c>=

T<'ci'le<'..o)L()L i'i.:<'," i<sysTer>i ir>accovdar>ce with 41QI-1CHeL.4.R.3<ligvooen pov 4 ion, of sei'v1ce Oases syscerf>15 1V><=-f.v'vie<<<l:o the sol 1di t icat 1on syst Brfi 1v>acov aai<c>:.wL Tn f>l I3>-1 HA81.g~<<~R.4 L)or>iesaT ic water sysT Bf>l 15 ir>sev v1ce I o~n><sol 1di fica1;1ori sysTBr>i 1n accov'aar>ce w1 I;>">~>.I I)>>-I I)','.>>fi

~~5.Radwaste Erlda tlVAC is ir>sev vice 1r>accovaar>r:B wli:Il 75DP-XHRSl.

<<.R.6 Electr ical aower is avai ladle to tuii>V->>>i4 av>a Iuii>u-<>'<".'/

1 r>accor dance wich 410p-liuHSl.

4.3 4.3.instr uct;ions pet Tov rfi VaLve Ver 1 ti caT 1or>L-istic, Apper>a iiI"(I".4.3.2 pev<Tovr>I Cor>tvol panel SBT~1ng I isT,, Apper>a1i>

"&".

'I~q/(f'(0 PALO VERDE NUClEAR GENERA'nNG STATlON MANUAL OPERATION OF SOLIDIFICATION SYSTEti PROCEDURE NO.7SOP"1SR02 REVISION Page'of 83 NOTE Completing Steps 4.3.3 and 4.3,4 will energize the solidification control panel and provide power to tho following components:

+All air oporatod valvos~All pumps and mixors~All lovel and prossuro measuring systems~Transfer cart and carousel~Comont storage and food systom~Addit ive f ood sys tom~Radwasto 30 ton crano~Capping machino~Chomical addition system 4.3.3 Perform Electrical/Hics.

List, Appendix"C", 4.3.4 On SRN-E01, depress tho"Programmable Controller Power On" pushbutton to onorgizo tho procoss computor.CAUTION DO NOT ADD RESINS TO THE WASTE FEED TANK SRN-Tol WHILE THE HEAT TRACING IS ON AND DO NOT TURN THE HEAT TRACING ON WHILE RESINS ARE IN THE WASTE FEED TANK, 4.3.5 Perform Heat Tracing Breakers List, Appendix"D", o>>ly who>>liquid radioactive waste is to bo procossod.

4.3.6 Check levels of tanks, if not at adequate lovel for operation perform tho following:

Entor>>N/h" who>>not roquirod.4.3.6.1 4.3.6.2 Fill or replace Cement Feed Tank SRN-T04 in accordance with Section 5.0 or 6.0 respectively.

Fill Additive Feed Tank SRN-T02 in accordance with Section 7.0, e PV210400 BEY.Olla' J0 aJ f PALO.VERDE NUCLEAR GENERATING, STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02.REVISION Page 9 of 83 4.3.6.3 Fill Chemical Addition Tank SRN-T03 in accordanco with Section.8,0, It:ems of Section 4,0 of this procedure have been completed or except:ions have boon rocordod and properly documented, Performed By: Signature and Inxtxal Items of Section 4.0 of t:his procodure have boon roviowod and found acceptablo:

Approved Dy:.Signat:uro DateAttach original copy(ios)of appendix(cos), routo to Unit Rad-'lfaste Suporvisor.

PVllS400 REV.OIQ k II 0

.~GRAFT ,PAlO, VERDE, NUCLEAR QFNgRATINQ STATlON MANUAL OPERATION OF SOLIDIFICATION SYSTEN PROCEDURE NO.750P-1SR02 REVISION Page 10 o f 83 5.0 FILLING THE STANDBY CENENT FEED TANK 5.1 Personnel Indoctrination.J>>l>>1?1 l l 1'AQ t AB CBMBl<t'I'BBA t BI"<It W 1 l I I"BQul V'P ORB 0 Lt<=.t l i'I't'<n?f<itAwhst B I Bcl1Y'<l cl<sF<lcPBY<B

<B1 ol"<<8 l alBl<BI"<fJ ovlB Au)<.t1'I 1 BA H<tAw<'ts'c I Bctcl I Bcpl?1c1 BY'IIcv'<tAB oABI~<3t<.<l" wllo I'l<'15<'~ps<t Bhi I BSAOVlS1 11 1 1t'y<'A)10 COOl A 1 V<<.<t B!tflB OQPY'iAt)Ol<~5,1,2 It will t:ako approximately thirt:y minutes to fill the comont: food tank SRN-T04.5,1,3 Operations will bo porformod in I;lto 100 ft:, rudwust'o si Idification area and outside at t:ho comont: Silo.5.1.4 Cement silo vibrator pressure operating range is 54 to 66 psig on PCV-388.5.1.5 Cement: silo aerator pressure operating rango is 2 to 4 psig on PCV-387.5.1.6 A cement feed tank may be complotoly emptied by placing it'.on top of another tank and manually operating tho outlot: valvo, 5,1.7 Cement silo food rato is 4.2 cu.ft:,/min, 5.1.8 The cement: silo feed rotary valve is t:imed for a 5 minut:o fill cycle which will deliver 21 cu.ft:, of cement:.5;1.9 Cement feed tank volume is 90 cuft:.5.1.10 Hearing protect:ion" will be required during cement;: ilo operation, 5.1.11 Cement silo volume at alarm levels aro as follows: h-3-900 cu.ft., A-1-326 cu.fl:~, h"2-100 cu.fl;.5.2 Prerequisites 5.2.1 Verify that the Cement Silo has sufficiont comont to fill the Cement Feed Tank as indicatod by no alarm condit:ion from"Alarm 2" indicator on SRN-E03.PVlt040D REV.e?Q 5.2,2 If the cement feed tank service by Section 6 of'volume remaining in the in service, enter"N/A" to be filled was removed from t: he this procedure, note the cement tank.If the tank has not yet been for this stop.

t)K Pl'0 INFO'Iox 0@I,V PALO VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEH PROCEDURE NO.750P"1SR02 REVISION 0 Page ll of 83 5.2.3 Determine the number of cycles required to fill the feed tank using the information provided from Step 5.1.8 and 5.2.2.Number of cycles 5 Rlvis't I I.ict 1aris CftU f'IQN CHECK FGRI(t IFT CAPACITY 10 IElu3URt.wt.-:.Ib!-

i'I(~lI7.i ARE iuQ i'XCF1)ED.

nlACIi~lUol WEtG!-I f'F t)E!aEbl7 Ft=.i="Ci!%IluK I..i t f!), i!)8e L.'i.~J%S LI$1'l10 a far'kl 1 fl,'cv'avlspa't t tl IP cefnevlt'!'eeo 1 am<rc Pasitiori cfivectly aelaw the eernr=t sila f11 t aaaatei".clCAUTIQIV UBE BPEBCIAL CflUTIQN 70 PRFVBEiu1'iluY BQLII')FQREI BN l<IA I'ER I AL F RQPI EluTER IluL'l 7!.Ii.L ClnElu7 I=EED TANK.A NUT, BQL7 Qw WRf-..lut.;l-!

f)AQ>)I t 1)Ifu70 THE TAiuK WII t JAll 1HE CEvit=iver/WAB'IE NICER IF NGT RE!XQVED P R I QR TQ hlBTE PRQCEBBINB NG f L.Ta'nxriirnize tile PoteAt ial far cserneriv, clottirig, ao riot allow waT,ev~o rna1.-.t<<ve

.)ra ertev the cernerit feea tarsal<.Removal of the lici ft am the cernerit fee!a cavil(v'equires 15/q6 irich size aaevi eria wveriches av socket asserna 1 y.5.3.2 RErnave lid fram cernerit tarift.5.Z.4 Urieap the verit ori toa of the cernerit fi ecl tarsal<.Secure tne cerneviv silo f1li aaanrav'no triF cerner<" 1'i~ao tank.5e3eb Eries tl1ze bRlu-t.-.if)3 ay olaclvici Yne aawc'.I'v'eai(c:lv, i fail<=QN'-Posit larl art SRtu-E83.PV110400 BEY.NS2 I V'7l GRAFT jm'ORMAYLorq OM.wLo vERDE wucLEAR oEwsR'Avirro 1 STATION MANUAL I OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION Page 12 of 83 NOTE Depressing the stop pushbutton on Coment Silo Unloading Station Control Panol SRN-E03 stops the Sill mode immodiatoly, Tho following will occur after Cho start: pushbutton has boon doprossod:

~The Cement Rotary Valve V393 on t:ho cement silo starts, Instrumont air t:o comont: silo vibrator and aerator V389 opons, supplying air Co cement silo vibrator and aerator.~Aftor a Cimo delay (sot: t:o allow tlro comenC food Conk t:o bo fillod)V393 and V389 close.~The baghouso shakor starts.+Af tor a time delay (suf f iciont: to c loan-Che baghouso filter)the baghouso shakor sCops~5,3.7 Depress fill mode starC pushbutt:on on SBN"E03.NOTE 5.3.8 5,3.9 5.3,10 Cement delivery will st:op automat:ically after 5 minutes.Repeat Step 5.3,7 to fill tho comont food t;Qnk as tlotormilloCl by SCep 5.2,3.Deenergize SRN-E03 by placing tho power broakor t:o t:ho"OF1'" position on SRN-E03 whon t:ho comont food tarrk fill oporrrtio>>

is complete o Remove the cement silo fill adapter from tho cement feed tank and secure adapt:or to tho lrousirrg.

5.3,11 Replace cement, feed tank lid.5.3.12 Replace cement feed Cank vont cap.PV21$40P REV.@82 l

PALO VERDE NUCLEAR GENERATING STATION!UIANUAL OPERATION OF SOLIDIFICATION SYSTEH PROCEDURE NO.750P-1SR02 REVISION Page 13 of 83 5.3.13 Transport cement feed tank to truck bay.Items of Section 5.0 of this procedure have been completed or exceptions have boon rocordod and properly documented.

Performed By;Signaturo and Initial Items oi'ection 5,0 of this procedure havo been roviowod and found acceptablo; Approved By: Signaturo Date Attach original copy(ies)of appendix(ces), route to Unit Rad Waste Supervisor.

I 0' PALO VERDE NUCLEAR GENERA'ihi STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEOURE NO.750P-1SR02 REVISION 0 Page 14 of 83 6.0 REPLACING THE IN-SERVICE CEMENT FEED TANK>.>f".t"i'><or>rip.

I 1r>rfr ce rir iria r, 1r.rl tr>.J~.I<<fa>(~J a(;~riri rrte 2 n-r>C>i'V 1CrJ Cr~rfit~rir, f(>tr!n,t>ttr>V.W1'.t l I'e(Iu I I (><'rlr!Qua i 1 f 1 t d I(aowaStt I Pcrlrilc1".tl i ar>41 rJ)<L~At.ta l 1 f'J fi>()'r(itONa:>

ti r!LBrtrJ~I I'!Crtril Cl ari Wl I>>rirtS>F>I<St r ((I r't." SI101>S I I)1 I I r p arit!C>Jrjl"C1\"iat BS tl ir>!MQBr'at 1(>rl~6.1,2 It will take approximately ono hour t:o roplaco t:lio in-sorvi.co cement: food tank.6,1,3 Oporations will bo performod in t:ho 100 and 110't.solidificat:ion aroa.6.2 Prerequisitos 6.2.1 Verify the availability of a fillod ccmont;i':ood tank.6.3 Instructions 6.3.1 6.3.3 Verify that the main circuit breaker for SRN-E01 is in t:ho"Og" position.NAt 6 t t'IL~CBmPI it V@1 u((f&FBI(l tilri1 rfrJ J.ri'(l I'llr>!1<i'-".,i.'.i

'i;i';'.ll'ii>frum LI-385"Cement Vnlumr!Heaac ut" (>ri hrt(4-t-"><'i.:

or'>>" Y'80lacB(RBrlt ariG I QcQr'Q thir'>val t(6>ver a 9 J ar!at'r(;;lri(2 attiach trJ the tarift, Turn off LI<<385 on SRN>>E01 by placing selector swit;cli"Cement Volume Readout" LI-385 to"OFF", 6.3.4 6,3.5 Close inst:rumont air to tho comont food taiik vilJrlit.or uittI aerator by placing"cement food tank vibrat:or HY-347", HS-347 on SRN-EQ1 in the"Close" position.Close HV-354 by placing"comont: out:lot: volvo IIY-354", IIS-354 on SRN-E01 in the"Close" position.6.3.6 At the cement feed assembly, disconnect aerator t:ubing on cement feed tank from UV-361A.6.3.7 At the cement feed assembly disconnect HV-354 from its operating cylinder by removing the cylinder rot:aining pin.6, 3, 8 SBcur Bs ca 0'c 0'0 Il&vsPrit crt t Qp,:, c(e>N(!rrt;

'I Bf>rJ'Gal if<., f>V21040D REV.e/22 4 0 0 PALO.VERDE NUCLEAR GENERATING

'STATION'ANUA'L' OPERATION OF SOLIDIFICATION SYSTEti PROGEOURE NO;750P-1SR02 REVISION Page 15 of 83 6.3.9 Attach lifting device to the cement feod tank, SRN-T04.6.3.10 6.3.11 6.3.12 Align t:ho 30 ton crano ovor t:ho cement food tank.Place comont feed tank lifting device on 30 ton crane hook.Lift tho cement feed tank clear from t:ho cemont food assembly and transport to tho t:ruck bay, 6.3.13 Disconnect the lifting device from tho comont: food I:ank, 6.3.14 Roconnoct tho lifting dovico t:o tho cemont: food t:ank filled in Section 5.0.6.3.15 Transport:

th" coment: food tank t:o coaI<<Itt food assoatbly, 6.3.16 Remove lift:ing devico from tank, 6,3.12 Stow lifting devico and crane.6'.18 Connect HV-354 to its operating cylindor and replaco UIIO cylinder retaining pin.6.3.19 Connect aerator tubing from cement feed tank t:o UV-316A, 6.3.20 Uncap tho vont on top of t: he cemont;food I:ank, 6.3.21 6.3.22 Place HS-354 in the"Auto" position on SRN-E01.Turn on LI-385 by placing selector switch t:o"ON", on SRN"E01.6.3,23 Note cement volume from t:ho in-servico tank from LI-385 on SRN"E01.PQ 14400 REV.4144 0

PALO VERDE NUCLEAR GENERATING STATION MANUAL l OPERATION OF SOLIDIFICATION SYSTEH'PROCEDURE

'NO.750P-1SR02 REVISION Page 16 of 83 6.3.24 Place HS-347 in the"Auto" position on SRN-E01.Items of Section 6.0 of this procedure have been completed or exceptions have been recorded and properly documented, Performed By: Signat:ure and Init:ial Dat:e Items of Section 6,0 of t:his procedure have been reviewed and found accept:able; Approved By: Signature l)a te Attach original copy(ios)of appendix(ces), rout:e to U>>it Rad Waste Supervisor,'PV210400 REV.8I82 00

@pe,Fr lÃFOBMATLON Ol&V PAL'0 VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 17 of 83 7.0 FILLING ADDITIVE FEED TANK 7.1 Personnel Indoctrination F x 1 lino I he aaai c ive feea t ariIi.wax l reauxr e uric oualii.iea Aaawa te Techriit.ian ann orie, qualii'red Aanwa<<.-.ce I.eaa i er.:hni t" i an wna llae eyec era veeoorie 1 9\.I i i;y aria c.'vGl 5 lriace'.i CI je 6f')el"a't 10n~7.1.2 It will Cake approximately ono hour Co fill tho additivo food tank.7,1,3 Operations will bo porformod in Cho 100 ft.radwasto solidification area, 7.1.4 Additive food Cank volume is 15 cu.ft.7-;1,5 Additive food cank is maincainod with a nitrogen ovor pressure of 2(1.5 Co 2.5)psig.7.2 Prerequisites 7.2,1 Verify tho availability of dust: masks and gloves for uso iii filling the additive food tank.7.3 Instructions

~~sw~7.3,1 Close nitrogen to additive feed tank isolation V-968 Co secure nitrogen ovorprossuro in tank.4 NOTE To minimize Cho potontial for motso boad clotting, do not allow wator or moisturo Co enter the additive feed tank.7.3,2 Carefully open lid on Cho additive food tank SRN-'i'02.

NOTE A dust mask and gloves shall bo worn by'personnel adding motso beads Co tho additivo feed tank.7.3.3 Inspect metso beads for clotting and foroign material.Break-up or remove any clots and dispose of any foreign material.PV210400 AEV.NOR v d 0

@PE,F@PYOBMAYLON OM.Q I?ALO, VERDE NUCLEAR GENER/TING STATION MANUAL opERATrou or sor.rDrr:rcATroz svsTEH PROCEDURE NO.750P"1SR02 REVISION Page 18 of 83 7.3.4 1'ill cho additive tank with mecso beads (anhydrous sodium metasilicate)

.7.3.5 7.3.6 Close the lid on the additive feed tank, Open V-968 to establish a nitrogen ovcrprossure condition in Che additive feed tank.7,3.7 Check nitrogen supply pressure as indicated by Pr-398.NOTl7.3,J Nitrogen pressure should bo bctwcen 1.5 and 2,5 psig, Adjust nitrogen conCrol valve, PCV-321 to 2 psig if not in the correct range.Enter>>N/A>>if not roquircd.rtems of Section 7,0 of Chis procedure have been completed or exceptions have been recorded and properly documented,'Performed By: Signature'nd Initial~I Date Items of Section 7,0 of this procedure liuvc i~co>>rcvicwc~l and found acceptable:

Approved By: 'Signatu're l)etc Attach original, copy(ies)of appendix(ccs), route Co Unit: Rad Haste Supervisor.

PYll840D REV.8/82 jtNFojRM~V ION 0 PALO VERDE NUCLEAR GENER'ATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM!PROCEDURE INO.750P"1SR02

<REVISION Page 19 of 83 8.0 FILLING CHEMICAL ADDITION TANK 8,1 Personnel Indoctrination n.l.t i-t i l'i l'<ft tf'ic<O'ABffllca l aclcj1't 1<<I'>'t O'AI(H1 l l'f PtItt1t'P.

C<Y<t<mual1txed NaaNa<atr<

I errlr<1t=1al<

aY<a ane c.u<~<l1r1c~d f(aawast;r<

t-r<<rlQ'i PCltll')1 f..1<tl'<Wf'tG flR!5 5$6t r.fil I f2<<CI<".<VlS'I t))l 1 t'<<<'ll<(I I GC<t~dIl'latBr4<

tflr.CJCJBV'<i'C 16<i'I~8.1.2 Filling t: he chomical addit:ion t:ank will t:akc approximately two hours, 8,1.3 Operations will bo performed on tho 110 ft.of I:hc solidificat;ion area.8.1,4 Chemical Addition Tank SRN-T03 capacity is 260 gallons wit:h approximat:ely 4.2 gallons por inch, 8.1.5 50%sodium hydroxide is-usod in=t;hc chemical addit:ion t:ank for waste feed pH adjustment.

8.2 Prerequisites 8.2.1 Ensure applicable emergency shower/oye wash stations aro operable, 8.2.2 Check chemical addition tank level t:o determine the quant:ity of chemical required to fill the tank to a lovol which will support a batch chemical adjustment, 8.2.3 Verify the availability of protective clot:hing and face shield f'r use in chemical addition, 8.3 Ins truct ions.8.3.1 Check Closed chemical addition tank outlet: V-084 CAUTION CAUSTIC MILL CAUSE CHEMICAL BURNS.HANDLE MITH APPROPRIATE SAFETY EQUIPMENT.

8.3.2 Open lid on the chemical addition tank.f<V214400'REV'4/42' E'ia k+))0 9RAFY pg Og~YIoyPALO'VERDE NUCLEAR GENERATilNG STATlON NANUALi OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 20 o f 83 8.3,3 Fill chemical addition tank to desirod level but not closer than five (5)inchos from the top.8.3,4'lose lid on the tank, Items of Section 8,0 of this procedure have boen completod or oxcopt:ions have been recorded and properly documented, Performed By: Signat:uro and Init:ial Dat:o Items of Soction 8,0 of this proceduro havo boon reviewed and found accept:ablo:

Approved By: Signature Dat:o Attach original copy(ios)of appendix(cos), route to Unit Rad Waste Supervisor.

PVl 14400 BEY.el el

'f I~I t f 0

'PAL'0 VERDE NUCLEAR GENERATlNG STAT!ON MANUAI OPERATION OF SOLIDIFICATION SYSTEM PROCEPURE NO.750P"1SR02 REVISION Page 21 of 83 9,0 MASTE FEED TANK RECIRCULATION AND CHEMICAL ADJUSTMENT 9'!r>V'S>'>V>L~.":.

l">QOc2l>V'1 Vr"l't 1 O<CI'v<!a<'it f I'<1>rrr.V<Br-'1l'"O clVIG l".I'!r>A11 C"LL aG J UGt laL>>V>l;W',l i 1 V'BQ l.t1 V'r OV>8 Gila I 1 f'80 VIBOWaS'68 I P.r.".rlV>1 G 1 a Vr al">0<<Vrf!>Olla 1 1 f is!G itaawa~~t t.r>ad!facnv>1r..1<nv>wno na~'>cyst l>r>l V r SO@V!<>1 b1 i 1t y arid r Oav'O1V>at efl>t;nC!nnr>!"<nt: 1 c-.>V>~9,1.2 Recirculation and chomical adjustmont will t:ako ono to four hours.9, 1.3 All oporat ions will bo por formod at: t:ho Solidi f ica tio>>Cont:rol Panel SRN-E01 unless ot:horwiso>>ol:od, 9.1.4 Tho chemical addition pump, SRN-P03 will t:rip on a high dischargo pressure of 82 (80 to 84)psig and a low discharge prossure of 3 (2 to 4)psig, 9.1.5 The chemical addition pump, SRN-P03 has a design flow raI:o of 4.5 to 5.5 gpm at 45 to 55 psig.9.1,6 9.1.7 pH indicator, AI-317 should road with in.04 pH units of t:ho chemistry laboratory results from the waste food t:ank samples.The waste feed pump, SRN-P02 will trip on a high discharge pressure of 55 (50 to 60)psig and a low discharge pressure of a 4 (3.3 to'4.7)'psi.g.

9.1.8 If operations do not proceed as described in sect:io>>9.3, notify the Radwaste Unit Supervisor and chock"Troubleshooting," Appendix E for possible causes and suggested technical act:ion.9.2 Prerequisites 9.2.1 System Alignment, Sect:ion 4.0 is comp lo to.9.2.2 The requirements of 75AC-9ZZ01,"Radiation Exposure Authorization, Permits and Cont;rol" have boon roviowed and action taken as necessary.

9.3 Instructions 9.3.1 Place>>Auto/Manual Selector" HS-325 in"Auto".9.3.2 Place"Mode Selector" HS-326 in"Waste Recirc", PV210409 iRQL N22 t'/I 0 GRAF7 PALO VERDE NUCL A GRIST RAT AG STATION, IVIANUAL.OPERATION OF SOLIDIFICATION SYSTEM 750P"1SR02 REVISION Page 22 of 83 9.3.3 9.3,4 Place Masto 1'eed Tk Mixer SRN-Q03 , llS"328, in Start Check that<<Cement/Masto Mixer SRN-Q01", liS-327, is in<<St<<p I NOTE Tho following will occur when the"Node Start" pushbutton is doprossod:

~The Waste Feod Tank Dischargo Valvo 1{V-343,opens.

+Tho Waste Food Pump SRN"P02 is onorgixod.

~Procoss Rocirc.light comes on.+Tho Fill/Recirc.

Valve llV-355 goes to the recirculation position, NOTE There shall be no furthor wasto additions to the Waste Foed Tank onco rocirculation has started.(LCTS: 032644), 9.3.5 9.3.6 9.3.7\To commence recirc.,'depress"Node Start<<pushbutton IIS-J29.Set radwaste rocizc.rate by placing"blasto Food l'ump Control" dial at"7.S" (107S RPM)approximatoly 12.5 Gl'll, After one and ono half hour of recirculation, observe<<<<ll~'alculate the amount: oi chemical required t:o ad.just: I>II t.v 8.0 to 10.0 as roquirod, (LCTS: 011165).At:t:ach t:ho chemist:ry analysis rosults arid pll ad.jiistill(illt calculations to 75RP-9SR01,"Solidificat:ion Procvss Cont:rol", Appendix"A", NOTE If pH indication on Al-317 docs not road wit:hin 0.4 PH unit:s of tlic laboratory results, inform t:hc Radwasto ioatl tccliniciiin

~9.3.11 Waste pH adjustment.(Enter"N/A" if not required), 9.3.11.1 Start"Chem.Tank Hixor" Sl<N-Q02 by placinp llS-332 to"Start".9.3.11.2 OPEN Chem.Add.Tank SRN-T03 outlot: V-II04.9.3.11.3 Set"Chemical System Phase Selector" HS-330 on"Chem.Recirc".-9.3.11.4 To START Chem.Add, Pump SIIN-PO3, doprcss"t'homical Addition Start" pushbutton.

PV210400 BEY.elhi 9

GRAFT PgyoHMAYjtWI ONI.VPALO VLRDE NUCLEAR GENERATING

$TATION MANUAL OPERATION OP Sor.IDIPICATION SVSTEZ PROCEDURE NO.750P"1SR02 REVISION Page 24 of 83 NOTE 9.3.11.5 The Chemical Addition Tank SRN-T03 has approximately 4.2 gallons por inch and tho Chemical Addit: ion Pump SRN" P03 delivers fluid at 5 GPM, I To commence chemical addit:ion for pll adjustmo>>t, sot the"Chemical System Phase Soloctor" llS-330 on"Chem Thru".9.3.11.6 Honitor pll on AI-317 during t:ho chemical addition.9.3.11.7 Whon t:ho roquirod amount of cltomical.

Itas lion>><<<Ideal socuro chc~'cal addition by placing llS-330 to"Cltom Recirc".9,3.11.8 9.3.11.9 9.3.11.10-Wait approximatoly 15 minutes t:o allow pll t:o stabilize, then observe and rocord t: he-roading from tho Radwast:o pll , meter AI-317;To secure Chemical Rocirc, place llS-330 I:o"Ol'l'".To secure the Chemical Tank Hixor place HS-332 to IISTOPlf 9.3.11.11"Notify the chemistry section to sample tho Wasto l'ood Tank contents and perform the chomistry analyses required by 75RP-lZZOl,"Solidified Radioactivo Wasto Classification" and 75RP-9SR01,"Solidificntio>>

Process Control".NOTE 9.3.12'The last three steps may be porformod concurrently.

If a bench tost is roquirod, samplo the Waste l'ood Ta>>k a>>d perform the test in accordance with 75RP-9SR01,'Solidification Process Control".Enter>>N/A>>if not required.9.3,13.Determine process feed rates in accordance with 75RP-9SROl,>>Solidification Process Control".0 PV21$40P BEY.N82 IJ q, R 0 EIR@F.III INFORMATION ONI,V PALO VERDE NUCLEAR GENER/TING STATION MANUAl OPERATION OI'QLIDlFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 25 of 83 9.3.14 When the chemistry analysis results are complete, perform 75RP-1H/01,"Solidified Radioact:ive Wast:e Classification".

Items of Section 9,0 of this procedure have been completed or exceptions have been recorded and properly documented.

Performed By: Signature and Init:ial Date Items of reviewed Approved Section 8,0 of t:his procedure ltave be<<>>and found acceptable; By: Signat:ure l)a I;u Attach original copy(ies)of appendix(ces), route I;o Unit;l(ad><esto Supervisor.

PVR10400 REV.8I82

rNFOZ VT~~;PALO VERDE NUCLEAR GKNFRATING STATION,1VIANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02.REVISION Pago 26 of 83 t 10.0 55 GALLON DROM FILL OPERATION 10.1 Personnel Indoct:rination I>I'.I s<>t'<81"<=.it 1<<.1'I I i<I" fbi'i 1 C: 1<'lVl 81!iC!VNQ I'I<:tG<Sy5t t"!O'I OGGI"<lt i GVi.W1 1 1 I'.C!Ul t P.<<VIP I:lllitl 1'I 1 BD I(lCIWil""CA' QvlE oil<ill 1 v i60 8-lGw l<.'GL8 I P<IG I Pc!I'Iv!it" 1 rll'!I eSOOnS10 i 1 i t y nVia I".Onr'a l V<'l't'C'!

<=, C I'<I" 10.1.2 Tho t:imo roquirod to fill a pallot: of drulss (6)is approximately 40 minut:os.10.1.3'perations will be porformod at tho solidification cont;rol panel SRN-E01.10.1.4 10.1.5 10.1.6 Loading and unloading of tho transfer cart: will bo porformod only whon cart is in tho"Toad In/Out: a>>d Swipe Ht;at:ion" position.Place drums on transfor cart only when drum pallot: spacor is installed.

If cement/waste mixer stops while procossing waste, t.lto mixer must be turned by installing tho handwhool on tho mixor motor ond shaft and turning by halld u<<tl.l ct!!!Io>>t II!I!cleared t:ho mixer int:ornals.

Do Not;Fluslt Syst.>>ill.

10.1.7 The desired feed rate for tho wasto feed pump SRN-P02 dur,i>>g resin waste procossing is 8.0 t:o 12.0 gpm.10.1.8 No solidification shall be performed unless an accopt:able bench test has, been performod within t: he last t:on batchos ol that wot waste type, A bench t:ost: shall bo porforlnod i<<accordance with 75RP-9SR01"Solidificat:ion Process Co>>troi", 10.1.9 Additive rotaryvalve, SRN-M08, delivers motso beads at: 0.014 (0.012 to 0.016)cu.ft:./rov, 10.1.10 ,Cement rotary valve, SRN-M02, delivers cement at 0.20 (0.18 to 0.22)cu.ft./rev.

10.l.11 The cement feed tank vibrator and aorator have an oporat:i<<g frequency of 3 seconds for every 10 seconds of procoss operation.

PV2!8400 AEV.8I82 Pl II II 0 0

!PAl'0 VERDE NUClEAR'ENKAATIN'8 STATION MANVAl PROCEDURE INO.75OP"1SR02 REVISION OPERATION OF SOLIDIFICATION SYSTEM 9R<!""<EVF0KCATK Pago 27 of 83 10.l.12 Upon loss of cement: flow, t:ho cemont: food I:ank vibrator and acrat:or st:art:, if aftor a 5 socond t:imo dolay comont flow.does noc start, process fill shut:s down and wast:o feed conk rocirculat:os, 10.1,13 A"Coment:/Waste Mixer Flush" alarm can only bo clearod by init:iat:ing a Cement:/Wast:o Mixor Flush in accordance with Section 13.0;10,1,14 Hearing protect:ion may bo dosirod during proccssi>>g operations, 10.1.15 Void spaces in all class wast:o packagos shall bc rcducod t:o t:ho ext:ent: practicablc.(LCTS: 011019)10.1.16 Solidified waste shall contain as lit:t,lo free st:andi>>g a>>d non-corrosive liquid as reasonably achievablc but;in>>o casu shall the liquid oxceod ono porccnt: of Chc volumo, (LOTS: 011011)18 1 17 It opevat io'As do rlot pvoceBQ as clesr'r'1 t)B(J 1!'I'r.."c 1 oA 1!3.;"', ret ify the Raawa te L.ead'I'c.cr7rixcx

-.tri;.tt>o cnr cI<"TI"ou17ieshoot ir!rj", Aoper!dii<"E" 7'ot" Doc!.7 i.7 te eau!il'"l'(riG suggestea technical act ior!.10.2 Prerequisites 10.2..1 Waste feed tank is in recirculation and pl{is adjusted i>>accordance with Section 9.0.10.2.2 Waste, cement and additive feed races have beon deccrminod in accordance with 75RP-9SROl,"Solidification Process Control".10.2.3 10.2.4 Waste classification has been completed in accordance wicl!75RP-12201,"Solidified Radioactivo Wasto Classification".

The applicable portions of 75RP-9ZZ57,"Packaging, Harki>>g and Labeling of Radioactive Material" have been completed for drum identification.

18.'de 5 The r equir eraer ts of 75AC-92281,"hae 1 at1orl e)<LIostlr r:.Author'ization, Per'mits and Coact'ol" have henri 7 ev7,ewcn ar!d REP issued co c!er 7orrn waste so'I ir7~7.~car.7.on.

4 J i I 0 1NV081VA TION ONj..PALG VERDE NUCLEAR GENFRAT~ING STATION MANUAL OPERhTION Or: SOLIDIFIChTION SVSTEN PROCEDURE NO.750P"1SR02 REVISION Pago 28 of 83 10.3 Instruct:ions Caution There shall be no addit:ions t:o t:ho Waste Pood Tank once t:ho solidificat:ion process has started, (LCTS;032644)10,3.1 Set waste, cement and additive iood rat:os in accordanco with 75RP-9SR01,"Solidification Procoss Cont:rol", NOTE 10.3.2 10.3.3 Ent:or"N/h" for St:ops 10,3,2, 10,3.3, and 10,3.4 if cart is already positioned in tho load in/out and swipe s tat ion.Place station seloct:or" llS-335 to tltn"load in/ouI: and swipe station" position, Place"cart diroction selector" llS-339 t:o"rnvorso".

NOTE 10.3.4 If tho cart must bo stopped, push the Cart: Stop Button illS-342 and t:ho cart: will stop immediately

..,.Depress the"Cart Start" pushbutton llS-341 t;o movo cart to'he load in/out and swipe st:ation.10.3.5 Load the cart with the drum".spacer".

., NOTE 10.3.6 Verify proper drum labeling prior to loading i pallet.Transfer the drum pallot to the loading aron t:o rocoivo a new drum" load, 10.3.7 10.3,8 Load the drum pallet with the required number of 17ll 55 gallon drums.Remove the locking pin from the 30 ton crane hook,'l'his will allow pallet rotation to accomodato spacor pog/pallol-'ole alignment.

0'0 PALO VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEN H.MAYION PROCEDURE jNO.I'750P" 1SR02 PREVISION 0 Page 29 of 83 10,3.9 Load the cart with the pal].et/drum assembly.10,3.10 Place"St.'ation Selector" HS-335 to the"Drum Fill and Capping St:ation" position.10.3.11 Place"cart: direct:ion selector" HS"339 in FWD'.10.3.12 10,3.13 10,3.14 Depress"cart start:" pushbut:ton llS-341 I;o move cart I:o I;lte drum fill and capping st:ation.Verify cart: locaI:ion by posit:ion indicat;or light: ZS 375>"drum filling capping st:at:ion" and by video indication.

Sot: ">>umber of drums on carousel" HS-334 I;o t.'h>>>>umber ol'rums t:o be solidifi~tl.

10.3.15 10.3.16 Check or place"mode selector" HS-326 in"Fill Cont:" posit:ion.

Place"Cement/Waste'ixer SRN-Q01", HS"327 in t:ho"St;art" position." NOTE The following sequence will occur when tho"loading flange position select:or" llS-322 is placed to down:~Drip pan fully retracts as indicated by"drip pan in position" lipht: ZS-380,~Loading flange moves down and engages drum as indicated by"loading flange full down" light ZS-378.~Overfill level probe moves inl;o posit:io>>.

10.3.17 Set loading flange down by placing"loading flange posit;ion selector" HS-332 to"Down", evem0o sar.eve

lSHAIF'r jim"OHM AYH)N OM,Y PALO VERDE NUCLEAR GENERATING STATION lVIANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.7SOP" 1SR02 REVISION Pago 30 of 83 NOTE For liquid and resin processing, t: he following soquonco will occur when the"modo start;" pushbutton is dopressod:

Simultaneously cement/adding inlot;valve,.--llV-353 opons, addit:ivo rotary valvo, SRN-M08 and addit:ivo feod conveyor, SRN-M07 start, and"process'illing" light comos on.Aft:or a prosot: timo for additive to roach tho ond of its conveyor, comont valve (HY-354)and drip valvo FV-100 opon, wast:o food fill/rocirc volvo HV-355 shifts to tlto fill position, and comont: i.d rotary valve/cement food convoyor mot:or, SRN-M02, start:,-Cemont, additive, and wast:e aro mixed in t:ho cement/waste mixor until"full lovel 200" is reached in'the drum.When"full lovel 200" is roached, carousol"posit:ion 1" and"full level 200" lights become energized.

HV"355 shifts'to rocirc, flush valve HV-356 opens and SRN-MOB sl:ops, Additivo and waste I':cods have stopped and a flush t:o cloan t:ho radwaste line to t;ho cement/wasto mixer is initiated.

After a preset time to allow t: he mixer I;o bo cleared of waste, cement, and additive;simultaneously HV-353 closes, procoss complote annunciator comes on, process filling light goes off and a 10 minut:o timing out period begins.If within this period, tho filling of a now drum is not started, tho"comont:/wasto mixer fluslt" annunciator will alarm and can only be cleared by a"process flush" mode;the waste feed pump SRN-P02 stops and tho wasto food tan}c discharge valve HV-343 closos.10.3.18 Depress"mode start" pushbutton HS-329 and note date and time on 75RF-9SR01"Solidification Process Control".PVlt4400 REV.OI82

/E'il i 4 I' 1ÃFORMAYION ONI,V PALG VERDE NUCLt..AR.

GENFR'ATItl%9, STA I'tON MANUAl Ol'ERA'I'CON Ol'U1 IUIl'il:AT'I.ON HYH'I,'EH PPoGKDURE, NQ., 750l'" 1S)(02 Il,I.YISIQN Vugc!Jl oi UJ 10,3.13 hfcor tho wast:o, comont, and addit:ivo foods havo stttrtod, c:I!ock und adjust as nocossary, tho Cood dial sotti>>gs t:o u!aint:uir!

Circ!i>>dicut:od I(t'N Crom 75RI>-9SI<01"So lidi'ficutiotr-Procoss Control", (LCTS-032642)

NO'l'l1'rocluontly obsurvo tl!o rudiutio>>rr!o>>itors I;u chock Cor high or abnormal radiat:ior!

lovols, 10.3,20 Proc;oss coml>lot:o ur!r!u>>c,i,utor I!us rr lrrru!<<cl.

NOTI.>10.3.21 Tho following socius!>>co will occur wl!c>>!t.l!c>"loading flango posit:ion soloct:or" lie.<32 i.s placo up to:+Drip pan oxt:onds fully us indicut:od by light lS-380 going oCC,+Loading flango movos up as indicate!d l>y"loading flango full up" ligltt/S-3/II.~Overflow lovel probe moves out OC pos it ion.Raiso loading flango by plucirrg"lc>ucii!!I; I'Irr>>i,c'.

I>c>>i t.ic>>>selector" l{S-322 to"up".NOTE Mhen the"carousel indexer" butt;on is pushed, Che light for Cho ompt:y drum>>oxt;Co be filled will bo onorgirod i>>dl.c!ut.inI, Chitt Che full drum movod to tl!c!>>c!xt position and Che position"1" light will.turn off indicating Chat: an ompty drum 3s now in posit:iott for fill.l(ho>>t.l!o lr!st.drum is in position"1" t:ho>>lust clrclm annunciator will alarm, 10.3.22 Depress"carousel indoxor" HS-340 to rot:ato I:hc!clr>>ms t.c>the next filling position, 10.3'3 Repeat Steps 10,3,17 through 10.3.22 until tho Iroxr to I:hc>last drum has been fillod, thon procood to'l!>>>><<xt.t.c I>~

GRANI'V gypogM@Y]PALO'VERDE NUCLEAR GENERATilNG STATlON MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION Page 32 of 83 NOTE The following steps are for I:he last: drum fill operation, I.f 10.3.24 Place mode selector HS-326 in the last drum position, 10,3,25 Set the loading flange down by placing"loading flange posit:ion select:or" HS-322 to"Down", NOTE For the last drum process, t: he following sequence will occur t:hen t: he"mode start:" pushbut;t:on is depressed:

Simult:aneously cement:/addit:ive inlet: valve, HV-353 opens,-addit;ive-rotary valve SRN-MOG and additive feed conveyor SRN-M07 start:, and"process filling" light: comes on.After a preset t:ime for additive t:o reaclt the end of its conveyor, cement valve (HY-354)and drip valve FV-100 open, wast:e feed fill/recirc valve HV-355 shifts t:o l:ho fill position, and the cement: Ceed rot:ary valve/cement feed conveyor motor, SRN-M02 start.Cement, additive, and wast:e are mixed in tlte cement/waste mixer until"full level 300" is reached in the drum.When"full level 300" is reached, carousel"posit;ion 1" and"Cull level 300" lights become energized.

HV-355.shifts to recirc, the waste feed tank discharge valve closes, primary flush valve HV-346 and flush valve HV-356 open and SRN-M08 stops.Additive and wast:e Ceeds have stopped, a flush to clean the radwaste line to the cement/waste mixer and a flush to clean the waste feed pump and pH element: to the waste feed tank are initiat:ed.

After a preset, time, the waste feed pump stops, HV-346 and HV-356 close.PV214440 REY.NQ

/4 f g t cf I 0 ISRAFV V6"OHMIC jt'joy PALO, VERDE NUCLEAR.GENERATING.

~~STATION.MAN.UAL OPERATION OP SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION.Page 33 of 83 After a preset time to add additional cement to solidify flushing wator, HY-354 closes, SRN-M02 and SRM-l'107 st:op, After a prcsct: time co empty che mixer, discharge valve HV-348 and cement:/add inlet: valve HV-353 close.After HV-348 and HV-353 are fully closed, socondary flush accumulator, SRN-X04 flushes int:o tho mixer.Aft:or a presot t:imo for cloaning, HV-348 opens and drains int:o Cho drum, Aft:or a prosot: timo for draining, process comploto annunciat:ors alarms and procoss filling lighC goes out, 10.3.26 Dopross"modo st:art" pushbutton HS-329, 10.3.27,"Process complot:o" annunciat:or has alarmed.Not'.c date a>>d time on 75RP-9SROl"Solidification Process Cont:rol" if this is tho last: process wit:h this procoduro, 10,3.28 If no furcher processing is planned wit:h t:his procodurc, secure waste feed tank mixer by placing"waste food t:ank mixer SRN-Q03" HS-329 in"stop".Ent:cr"N/A" i.i.'()C applicablo.

10.3.29 If processing will cont;inuo, perform tho following:

10.3.29.1 Place HS-326"Modo Selector" to"Mast.c lice.i.re,".

10.3.29.2 Depress"Mode Start" pushbutton Co rostart t:ho Rocirc.10.3.30 Place"cement/waste mixer.SRN-Q01" HS-327 ln tho stol)" position.PVR1140p REY IISR P S 0 0 IGRAF It'ALO'VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 34 of 83 NOTE 10,3.31 10.3.32 The following sequence will occur when the"loading flange position selector" lIS-322 is placed to up;~Drip pan extends fully as indicated by Light ZS-380 going off,+Loading flange moves up as indicated by"loading flange full up" light ZS-370.+Overflow level probe moves out of'osition.

Raise the loading flange by placing"louding flange position selector" 1{S-322 to up".Rotate the first drum filled to"position 4" by depressing"carousel indexer" two (2)times.NOTE Haste processing may be stopped temporarily at this point.NOTE (>>Steps 10.3.33 through 10.3.39 will be performed in the"power control module area R-102 on SRN-P13,'capping machine, hoist local".Ensure the drum and cap markings match prior to installing the cap on the drum>>10.3,33 10.3,34" 10.3.35~w~10.3.36 Attach a cap to the capping fixture magnets.I>>Depress"hoist up" button until the hoist is in the up position, II\>>>>>>~~~Depress"trolley forward" button until the capping fixture moves into the filling aisle over the drum, Depress monorail"bridge rev" or"bridge for" pushbutton as appropriate to move capper monorail directly over the drum,>>PVllMSO MV.N82 "c yl 0 l5PlhFV'WORMATION ONr, Y PALO VERDE NUCLEAR GENERATING STATION NIANUAL OPERATraN Ol'OLrD?PZCATrON SVSTEN PROCEDURE NO.750P-1SR02 REVISION Pago 35 of 83 NOTE Roloase"hoist: down" pushbutton as soon as tension is off tho hoist hook.10.3.37 Depress"hoist down" pushbut:ton until cap is'ressed ont:o tho container and tho spring fastonors lock bonoath tho cont:ainor chimo, 10,3.38 10.3.39 Depress"hoist up" pushbut:t:on unt:il t:ho hoist:'s upper limit: switch stops tho hoist: motor.Depross"trolley rovorso" pushbut:ton until capping fixt:uro has rotuxnod I:o tho"powor control module aron".10.3.40 index carousel to rotato tho next uncapped drum into position by doprossing"carousol indoxor" llS-340.10.3.41 Repeat Stops 10,3,33 through 10.3,40 unt:il all drums leave been capped, then procoed to tho next st'ep.10.3.42 Lower capping fixt:uro t:o t:ho floor in t:ho"power co>>t:rol modulo area".10~3;43 10,3,.44 10.3.45 10.3.46 Place"station soloct:or" HS-335 t;o tho"load i>>/out a>>d swipe station position.Place"cart direction selector" HS-339 to tho"rovorso" position.Depress"cart start" pushbutton HS-341 to move t: he cart: t:o the load in/out and swipe posit:ion.

Verify cart location by position indicat:or

/S-373,"load in/out and"swipe station'nd by video indication, 10.3.47 10.3.48 Using tho'remote smear dovico, samplo t:ho accessible aroas of tho 55 gallon drums and drum pallet.Rotate the drums on the carousel as required for sampling by keeping tho"carousel indexer" HS-340 doprossod unt:il I;hc carousel is in a new position.PVRt040P MV.BIN

9RAIF 7 1NPORMATION OM V PALO VERDE NUCLFAR GEN'BR'ATIN'6 NPRQOCEDURE STATION M'ANUAL 750P-1SR02 REVISION OPERATION OF SOLIDIFICATION SYSTEM Page 36 of 83 NOTE If the smear activity levels are not greater than the loose surface contamination limits, proceed to'Step 10.3.49.If activity levels are greater than those limits reduce the contamination

'to below the established limits in accordance with 75PR-OZZ01,"Radiation Protection Program".10,3.49 Activity analysis results from the surface area contamination survey on the 55 gallon drums do not exceed the loose surfaco contamination limits.10,3.50 With, the radwaste 30 ton crane, transfer the 55 gallon drum pallet to the appropriate radioactive waste storage area.NOTE l.~Personnel exposure in and outside the storage area, changing the existing radiation levels and visibility of drum identification numbers shall all be taken into consideration when loading the drums into the storage area.Minimum clearance between drums should be 6 inches.10.3.51 Unload the 55 gallon drums from the drum pallet and note storage location on 75RP-95R01,"HolidJ.fhcaI.Iou I'rocess Control".NOTE Proceed to Step 10.3.53 if no further processing is planned and enter"N/A" for Step 10.3.52.Waste processing may be stopped temporarily at this point.PV110400 BEY.SISS 10.3.52 Repeat Steps 10.3.6 through 10.3.51 until processing is complete e

/~,'

PALO VERDE NUCLEAR GENERIATING STATION MANUAL OPERATlON OF SOLIDIFICATION SYSTEM PROCEDURE)NO.'50P"lSR02 REVISION Page 37 of 83 10.3.53 Properly st:ow drum pallet, lifting dovicos, and radwasto 30 ton crano.10, 3.54 10.3,55 10,3.56 10.3.57 Place"mode selector" HS-326 t:o the"OFF" position.Place"cart'.direction selector" HS-339 t:o tho"FMD" position, Place'"auto/manual seloctor" HS-325 to t:ho"OFF" posit:ion.

\Position"number of drums on carousel" llS-334 t:o"I'osition lu Items of Soct:ion 10,0 of t:his procoduro ltavu buon complot:od or oxcopt:ions have boon rocordud and propurly-documented.

Performed By;Signature and Init:ial Date Items of Section 10.0 of this procedure havu boun reviewed and found accoptable:

Approved By: Signature l)at;o Attach original copy(ies)of appendix(cos), rout:o to Unit'Rad Haste Supervisor, PVQ1040D REV.SI82 l j

~I g)QA,[Fr 11VVOBMATION 0ÃjLV~,." DE NUC'LE'AR O'E'N'E'RATING STATION MANUAL 750P-1SR02

, REVISION OPERATION OF SOLIDIFICATION SVSTEZ 0 Page 38 of 83 11,0 LINER FILL OPERATION 11.1 Personnel Indoct:rinat:ion Fi I I iI'l"I YI1(<?(r<B""ca?I i I rc?P w1 i 1?e?Gull I'B oY're?crt(QL i 7 1 a?(J<tHCIW<(SC(<

TC?CPlA1G1<<l'll

<<ll'1G Ol IQ (Jr(<(11 t'1(DG t(<<IGW<ISCt?

I (<<<IG I C."Gr"I'I'll C,'1 ilI'r, NhO" rl<<IS G<I<" 6 e?Ia I'l'i'.1 G JI"IS 1 (;)1 1 1 Ti f<"\I'I G O'.OOY'01'A<<It'(P':"r CI IB OD('>>Y'<<IC 1OI'r>>11,1,2 Time roquirod t:o fill a liner is about: 60 minut:cs.11.1.3 Oporat:iona will bo peri'ormcd al;Solidificat:ior(Co(rt:rol Par(cL SRN"E01.11,1.4 Liners shall bo placed on tho t:rane for cart: only when drum pallet: spacor is removed, 11.1.5 Loading and unloading of Cho transfer cart: will bc performed only when Che cart is-in-tho"load in/out and swipo st:at:ion" position, 11.1.6 11.1,7 If cemenc/waste mixer st:ops,while processing waste, cl(c mixer must be curned by, installing tho Itandwhool on t:ho mixer motor end shaft and turning by hand unt:il comont has'cleared tho mixer internals.

Do Nol;Flush Syst:cm.No,solidification shall be performed u>>less an acccptablo bench tost has been performed within t:ho last t:cn bat:chos oi that wet wasto typo.A bench losC shall bc perl'o>rrr(rd irr'5RP"9SR01"Solidification Process Cont;rol.11.1.8 Additive rotary valve, SRN-N08, dolivcrs motso beads nt 0.014 (0.012 Co 0.016)cu.fC./rov.

11.1.9 Cement rotary valve SRN-M02, delivers cement: at: 0,20 (0>>18 Co 0.22)cu.fC./rov, 11.1.10 The cement feed Cank vibrat:or and aerator havo an oporat:ing frequency of 3 seconds for every 10 seconds of process operation.

11,1.11 Upon loss of cement flow, Cho cement feed tank vibrator rtnd aerator start, if after a 5 second time delay ccmont: flow does not start, process fill shuts down and wasto foed t:ank recirculates.

pv2(Hoo BEY.erQ 1 I v' m0mwvv PALQ VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 39 of 83 11.1.12 A"cement/waste mixer flush" alarm can only be cleared by initiating a cement/wasto mixor flush in accordance with Section 13.0.11, 1.13 The desired feed rate for Che wasto food pump, SRN-P02, during resin waste processing is 8,0 Co 12,0.gpm, 11.1.14 Void spacos in all class wasto packages shall bo rcduccd to the extent practicablo.(LCTS: 0110l9)11,1.15 Solidified waste shall contain as little I ruu st<<>>dl,>>g<<iid noncorrosive liquid as is reasonably achiovablo but in iio case shall Cho liquid excood one porcont of tho volumo.(LCTS;011011)J~1~16 If operaCions do not proceed as describod in suction 11.3, notify the Radwasto uniC suporvisor and check"Troubleshooting","Appendix"E" for possiblo causus a>>d suggesCed technical action.11.2 Prerequisitos 11.2.1 Waste feed tank is in recirculation and pll adjustud in accordance with Section 9.0.11.2.2 Waste, cement, and additivo food ratos liavu buuii dul.uri<<i,>>uil in accordance with 75RP-9SR01,"Solidification Procoss Control".11.2.3 Waste classification has boon complotod i>>accoril<>>icu willi 75RP-1ZZ01,"Solidi'fied Radioactive Wasto Classification".

11.2.4 The applicable portions of 75RP-9ZZ57,"Packaging, Marking, and Labeling of Radioactivo Material" havu boon complotud for Liner Identification.

I 11,2.5 The requirements of 75AC-9ZZ01,"Radiacio>>

Exposuro gg~orization, Pormits and Control" havu buuii rcviowud<<>>d REP issued to perform waste soidif ication PV21040D REV.SISl i(0 0 0 O'MFY~oiR~Yyog ()pAt.o VaRPP Nucl.PAR QPNPRATlNQ sTATl0g IvlANUAL OPERATION OF SOLIDIFICATION SYS'1'EH PPOCEDUPP NO 750P"1SR02 PEV(SION Page 40 of 83 11.3 Instructions Caution There shall be no additions to the Waste Feed Tank once the solidification process has started, (LCTS: 032644)11.3.1 Set wast:e, cement and additive feed rates in accordance with 75RP"9SR01,"Solidification Process Control".NOTE 11.3.2 Enter"N/A", for Steps 11,3,2, 11,3.3, a>>d 1~.3,4, if cart is already positlo>>ed i>>tliu l.ad in/out and swipe position..Place"station selector" HS-335 t:o the"load i>>/out a>>d=swipe station" position.1..a" ar d, e tio e tor" HS->>9'o"revors".11.3.4 11.3.5 NOTE 8*If the cart must be stopped, push the cart stop button HS-342 and the cart will stop immediately.

Depress"cart start" pushbutton HS-341 to move c>>rt to tl>>.load in/out and swipe stat:ion.Unload drum"spacer" from cart, Enter"N/A" if not installed.

NOTE Verify proper liner labeling prior to loading on the cart.11.3.6 Load the cart with one open 80 cu.ft.liner.11,3.7 Place"station selector" HS-335 to"fill liner'osition, 11,3.8 Place"cart direction selector" HS-339 in"FWD".11.3,9 Depress"cart start" pushbutton HS-341 to move cart to the fill liner station.P/2gl400 PRY.@82 C t\

pm@5'7 INFojRMA'lL'j[Ojy PALO:VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION Page 41 of 83 11.3,10 11.3.11 11.3.12 Verify cart location by position indicator light ZS-376,"liner filling station" and by vidoo indication..

Place or chock"mode selector" HS"326 in tho"large container position.Place"comont/waste mixer".SRN-.Q01, HS-327 in tho"start" position, NOTE Tho following soquenco will occur whon tho"loading flange position selector" HS-322 is placed to down:~Drip pan fully retracts as indicat.od by"drip pan in position" light ZS-380.~-Loading flange moves down and ongagos liner as indicated by"loading flango full down" light ZS-378,~Overfull lovel probe moves into position.11.3.13 Set loading flange down by placing"loading flange position selector" HS-322 to"down".NOTE For liquid and rosin processing, tho following soquonco will occur when tho"mode start" pushbutton is doprossed:

Simultaneously cement/adding inlet valve, HV-353 opens, additive rotary valve, SRN>>M08 and additive feed conveyor, SRN-II07 start, and,"process filling" light comes on, h After a preset time for additive to roach the ond of its conveyor, comont valvo (HY-354)and drip valve FV-100 opon, wasto feed fill/recirc valve HV-355 shifts to fill position, and the cemont feed rotary valve/cement food conveyor motors, SRN-M02 start.Cement, additive and wasto aro mixed in the cement/waste mixer until"full level 300" is reached in the liner.When>>full level 300>>is reached, carousel>>position 1" and"full level 300" lights become energized.

HV-355 shifts.to recirc, the\PVll6400 REV.N82

'I'l~P l PALO VERDE NUCLEAR GENERATING STATION NlANUAL opERATloN or sor.lDrrlchTloN sYsTEM'PROCEDURE NO.750P"1SR02 REVISION Page 42 of 83 waste feed tank discharge valve closes, primary flush valve HV-346 and flush valve, HV-356 opens and SRN-M08 stops.Addit:ivc and waste feeds have stopped, a flush t:o clean the radwaste line Co the cement/wastc mixer and a flush to clean t: he waste feed pump and pH element Co tho wast:c food t:ank arc initiated.

After a preset time, Chc waste feed pump stops, llV-346 and HV-356 close.After a preset time Co add addit:ional cement t:o solidify flushing wat:cr, HY-354 closes, SRN-M02 and SRM-M07 stop.Aft:cr a preset time to empty thc mixer, discharge valve HV-348 and cemenC/add inlet valve llV-353 close, AfCcr HV-348 and HV-353 arc fully closed, secondary flush accumulat:or, SI<N-X04 flushes into the mixor.After a preseC t:imc for.cleaning IIV-348 opens and drains int:o t:hc drum, Aft:cr a preset time for draining;process complete annunciator'alarms and process filling light goes out.11.3.14 Depress"mode start:" pushbutCon HS-329, and not:c dal:c and time on 75RP-9SR01,"Solidification Process Control".11.3.15 After the waste,-cement, and additive feeds have sCart:cd, check and adjust as necessary the feed dial settings Co maintain the indicated RPM from t:ho 75RP-9SR01,"Solidification Process Cont:rol".(l,CTS: 032642)NQTE Frequently observe t:ho radiation monitors to check for high or abnormal radiation levels, 11.3.16"Process complete" annunciator has alarmed.Note dat:c and time on 75RP"9SR01,"Solidification Process Cont:rol" if this is the last process with this procedure.

PVR10409 REY.8I82 I rt PILAF'r LNYOHMATrop~

PALO VERDE NUCLEAR GENERATING STATION NlANUAL OPERurlON OP SOLIDIPICaTION SVSTEH PROCEDURE NO, 750P-1SR02 REVISION Page 43 of 83 11.3.17 If no further processing is planned with this procoduro, socuro wast:e food tank mixor by placing>>wasto food tank mixer SRNQP3>>HS 328 in>>stop>>Enter>>N/g>>

i f no applicable.

11.4.18 If processing will continue, perform the following:

Enter>>N/A>>if.not: applicablo.

11.4.18.1 Place HS-326"Node Selector" to>>Waste Rocirc".~11,4.18.2 Dopross>>Mode St:art:>>pushbutton I:o rest:art: I:l>o l(ocirc.11.3.19 Place>>cement/waste mixor SRN-QPl>>)IS-327 in t:ho>>st:op>>position, NOTE Tho following sequence will.occur whon I:ho"loading flange position seloctor>>IIS-322 is placed to up:~Drip pan extends fully as indicat:od by light ZS"380 going off.~Loading flange moves up as indicated by"loading flange full up>>light ZS-379,~Overflow lovel probes movos out: of position.11.3.20 11.3'1 11.3.22 11.3.23 11.3,24 Raise.tho loading flango by placing"loading flu>>go position selector" HS-332 to>>up".Place the>>station seloctor>>HS-335 t:o the linor cappi>>g>>position, Place>>cart direction selector" HS-339 to tho>>roverso>>position,.

Depress"cart start>>HS-341 to move the cart: t:o tho liner capping station.Verify cart location by"liner capping st:ation>>posit:ion indicator light ZS-374 and by video indication,;

PV210400 BEY.OIIQ 1 I

, 1NPORMAYLON ONLYPALO'ERDE NUCLEAR GENKRATING STATION MANUAL OPERATION OF SOLIDIFICATlON SYSTEt1 PROCEDURE NO.750F-1SR02 REVISION Pago 44 of 83 NOTE Waste process may be st;oppod tomporarily at: this point.NOTE St:ops 11,3,25 through 11.3,32 will bo porformed in t:ho"powor cont:rol module area", R-102 on SRN-F13,"capping machino, hoist local".Ensuro tho linor and cap markings match prior to installing I:ho cap on t: he liner.11.3.25 Attach a cap to tho capping fixture magnets, 11.3.26 11.3.27 11.3.28 Depress"hoist up" button until t: he hoist: is i<<tile up position.Depress"trolley forward" butt:on unt:il tho capping fixture moves int:o the filling aislo ovor tho liner.Depress monorail"bridge rov" or"bridgo for." pusltbut.to>>

<>t.il cappi<<g fixt'.uru has returned to the"power control module area".11.3.32 Lower capping fixture to the floor in t:ho"power cont:rol module area", 11.3.33 Place"station selector" HS-335 to tho"load in/out and swipe station>>position.PV21040P REV.SI82

l, INFORMATION ONj.VPALO,'VERDE NUCLEAR GENERATING.

STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION 0 Page 45 of 83 11.3.34 Depress"cart start" HS-342 to move the cart to the load in/out and swipo st:ation.11.3.35 Verify cart location by position indicator lighC ZS-373,"Load in/out: and swipe st:ation" and by video indication, 11.3.36 Using t:ho remote smoar device, samplo t: he accossiblo aroas of the liner.11,3.37 Rotat:o t:ho linor on t:ho carousel as required for.sampling by kooping t:ho"carousel indoxor" llS-340 dopressod until Clio carousel is in a now posit:ion, NOTI'.If Che smear activity levels are noC great:or Chan tho loose surfaco contamination limits, proceed to SCep 11.3.38.If act:ivit:y levels aro greater.Chan Chose limits, reduce.t:hc conCaminaCion to below the established limits in accordanco wit:h 75PR-OZZOl,"Radiation Protoct:ion Program".11.3.38 Activity, analysis results from tho surface area contamination survoy on t: he liner docs not: oxcccd tltc loose surface conCamination limit:s.11.3.39 With Che radwaste 30 Con crane, transfor the 80 cu.ft.linor Co tho radioactivo waste st:orago aron nntl note st;o)nl,c location on 75RP<<9SR01,"Solidification Pro<<css Cont.ro I"..NOTE Personnel exposure in and outsido tho storage area, changing the existing radiation levels and visibility of liner identification numbers shall all bo tnkcn into consideration when loading tho liner into the storage area.Proceed to Step 11.3.41 if no further processing is planned and enter"N/A" for Stop 11.3.40 waste processing may bo stopped temporarily at this point.11.3.40 Repeat Steps 11.3.6 through 11.3.39 until processing is complotee

  • ,l 0 Jl e kzrv PQLO VER/.E N.UCLEQR.G,ENE,ROTI,NG STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEN MAYKN OM,Y PROCEDURE NO.750P"1SR02 REVISION Page 46 of 83 11.3.41 11,3.42 11.3.43 11.3.44 Properly stow li.fting devices and radwaste 30 ton crane, Placo"mode soloct:or" liS-326 to the"OFF" position.Place"cart diroction selector" HS-339 to the"FMD" position, Placo"auto/manual soloct:or" 1IS-325 t:o tho"OFF" posit:ion.

Items of Soct:ion 11.0 of this procoduro have boon complot:od or oxcopt:ions havo been rocordod and properly documented.

Porformod By: Si" tturo and Init;ial I)a t.'o Items of Sect:ion 11.0 of t:his procoduro ltavo boon reviewedand found.acceptable; Approved By: Signature Dat:o Attach original copy(ios)of appondix(cos), route to Unit.Rad Waste Supervisor.

g)@@F7~MORMAYjfog OMLy PALO VERDE NUCLEAR GENERATINQ STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM'PROCEDURE ,NO.750P"1SR02 REVISION Pago 47 of 83 12.0 TRANSFERRING FILTER INTO WASTE CONTAINER 12.1 Personnol Indoctrinat.ion

~>~L~I-z lYer ct Br>s'rer oper aY xoris wl l t veaulve orie tluill 1 flea Hnawasve I ecvIriiaiar>

ana or>e aual x Pica ixaawasve Leva I ea1lr<1C'j iRVI WflG ll le;'">yt>'C efa r e".'iPQV'IR't Ql,l l'0 V"lr>>l amor'0xr>t'Gee ZAe Goer'Bt xar>12.1,2 Operat:ions will be porformod in l:ho radwasto building 120 corridor, 110 ft, radwast:o solidification area and tlto power control module area.12,1,3 Tho lransfor oporat:ion will roquivo about 1 lio>>r to I>orI>vtm.

12.2 Prerequisitos 12.2.1 12.2.2 Appropriate-wasto cont:ainor and filt:or cart:ridgo basket is available for.roceipt, of t:ho filt:ov..L Determine where to temporarily slow tho wast:o co>>tui>>or With filter using the expected radiat:ion lovols if fillov is not to be solidified upon receipt.12.3 Instructions 12.3.1 Install a"filter cartridge basket:" in t:ho wast:o container to be used for receipt of tho filtor.12.3,2 If'he waste container will bo st:owod prior t:o procossz>>g, placard the container to identify tho filter t:ypo and dat:o of receipt.Enter"N/A" if not roquirod.NOTE The waste container may be placed on tho floor of tho process.aisle or o>>t:ho transfer cart if, solidification is t;o immediately follow the transfer.I 12.3.4 Transfer the waste container to tho waste process aisle on the east side of the load in/out and swipe st:at:ion.

With the 30 ton crane, move the filter transfer cask to an area adjacent to the railing in t'ho"high levol st:orago area" R-101 100'evel.Enter"N/A" if cask is already located there.

IIi GRAF'r~O~MATLoy 0~PALO VERDE NUCLEAR, GENERATING STATION MANUAL OPERATION OF SOLlDIFICATION SYSTEM PROCEDURE NO.750P-1SR02

~REVISION Pago 48 of 83 12.3.5 With the filter transfer cask on tho floor in tho R-101 aroa, remove the ball lock pins to disconnoct the bottom shield plate from tho cask body.CAUTION DO NOT PUSH THE 2 BUTTONS MARKED"GRAPPLE".

THIS MILL RELEASE THE FILTER.12.3.6 Connoct: the power'cablo to a standard 240 volt: grounded source t:o provide powor to tho grapple hoi.st.CAWf ION WHEN LIFTING THE FILTER TRANSFER CASK WITHOUT THE BOTTOM SHIELD PLATE, OBSERVE TllE NECESSARY RADIOLOGICAL CONTROLS TO MINIMI/E THE POTENTIAL FOR THE SPREAD OF CONTAMINATION FROM A DRIPPING WET FILTER.ABSORBENT MATERIAL MAY BE PLACED OVER ANY WET AREAS ON THE BOTTOM SHIELD PLA'l'E.12.3.7 With the 30 ton crano, lower tho filter t:ransfor cask directly over t: he waste container to approximately 3 includes above the container opening.PVN4400 REV.@N

~P I/

INFORMATION 0ÃjL 7 PAL'0 VERDE NUCLEAR'GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02

'REVISION 0 Page 49 of 83 NOTE The chain mark indicates the filter top is positioned at the bottom of the cask body and the filter is ready for release into the drum, Filter drop distance will be approximately one foot.CAUTION WIIEN THE FILTER IS LOWERED INTO THE WASTE CONTAINER, RADIATION LEVELS MAY INCREASE UY AS MUCH AS A FACTOR OF:, APPICOPreZATE RADIOLOGICAL CONTROLS SHALL BE OBSERVED.12.3,8 12.3.9 12.3.10 12.3.11 12.3.12 12,3.13 Using the grapple pendant, depress the hoist"dow>>" pushbutton to lower the filter into the waste container until the chain mark is observed, Depress the grapple"down" pushbutton on tlute grapple pendant to release the filter into the waste container, Return the grapple to its retracted positio>>by dopr<<ssi>>g the hoist"up" pushbutton on the grapple pendant.With the 30 ton crane, return the filter tra>>sfor cask to the R-101 area and temporarily suspend cask adjacent to bottom shield plate.Decontaminate the bottom shield plate as>>ccessary usi>>g appropriate radiological controls.Decontaminate the cask body internal sleeve as necessary using appropriate radiological co>>trois.NOTE 12.3~14 Remove locking pin on the 30 ton cra>>c hook to ease cask alignment.

II Lower the filter tran fer cask body onto the bottom shield plate aligning the bottom and body ball lock pin guide plates.

l MATM)N ONLX ERDE~UC~EAR OH~ERAT~NO PROCEDURE STATION MANUAL 750P-1SR02 OPERATION OF SOLIDIFICATION, SYSTEM REVISION Page 50 of 83 12,3.15 Insert the ball lock pins t:o connect the bottom shield plat:c to t:ho cask body, 12.3,16 With the 5 ton hoist,.return thc filt:er t:ransfer cask to t: he Aux.Building Filt:er Access Area, A-232 for storage.NOTE 12.3.17 12.3.18 It: may be roquired to use a remot:o handling tool when inst:ailing the containor covor t:o minimize porsonnol exposure If t:ho wast:c containor with tho filtor will bo st:owud prior t:o procossing, provido a t:omporary covor for.I;hu co>>tai.>>ur to minimize the pot:ont:ial for airborne r ttaml>>atlo>>, I'.'>>tur"N/A" if not: required.Proceed wit:h solidification oporatlo>>s.

j?>>tur"N/h" if>>ot applicable.

12.3.19 With the 30 ton crane, transfer t:ho waste co>>l:ai>>ur t:o thu appropriate storage aroa and o>>sure t:hu eo>>t:ainur identification is visiblo whon complcl:o.

Entur"N/A" if>>ot applicable.

12.3.20 Observe the necessary radiological cont:rol praetieos t:o check the filter transfer, area for radioact:ivo contami>>at.ion, Items of Section 12.0 of this procoduro havu buu>>comploted or oxccpt;ions havo buu>>recorded>>>>d properly documented.

Performed By: Signat:uro and Inil:ial Dat u Items of Section 12.0 of this procodure have boon reviowod and..found accupl:ablo:

Approved By: Signature Dat:e Attach original copy(ies)of appendix(cos), rout:o to U>>.it Rad Waste Supervisor.

PQ144M REV.8lf9 ll P I l 11 ll lj PALO VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION Page 51 of 83 13.0 CEMENT WASTE MIXER FLUSH 13.1 Personnel Indoctrinat:ion

~L i.~~lr L 1-lush'irii2 the c Bnterit/waste lalHer wx I l t'Baulr'B orie a ua I i f'i Ba Raawast B Tech@i c imri aria orie aural l, t'x ea NarJtiilSte t Qaa I BChrilCiali WhO.hae SVStern I"BSBOrlSlbl.l Xt;g hrla cool"a 2.riBtes the oper M'Loli 13.1.2 The flush will require about 30 minut:es I:o perform.13,1.3 Operations will be performed at: the Solidifical:io<<Co<<t:rol Panel SRN-EOl.13.1.4 This flush operation may be required when the"I:imi<<g oul:" period is exceeded in Section 10.0 or when considered necessary t:o minimize cement buildup in tile mixer.13.1.5 If operations do not proceed as described in sect'.io<<13.3, notify the Radwaste lead technician and chock"Troubleshooting" Appendix"E" tor possible causes<<<<d suggested technical action.13.2 Prerequisites 13.2.1 An empty or partially full drum (" full level 300" or less)is aligned underthe loading flange.13.3 Instructions 13.3.1 Place"mode selector" HS-326 in"processor flush" posit:io<<.

NOTEPV210400 REV.N62 ,The following sequence will occur when t: he"loading flange position selector" HS-322 is placed to down:+Drip pan fully retracts as indicated by"drip pan in position" light ZS-380.~Loading flange moves down and engages drum as indicat:ed by"loading flange full down" light ZS-378,'Overfill level probe moves into position, 13.2.2 Set loading flange down by placing"loading flange posit;io<<selector" HS-322 to"down".

T)4 IAT'OPMATEOX OML PALO VERDE NuCLEAR.GENERATING STATION MANUALPERATION 01'OLIDIFICATION SYSTEH PROCEDURE NO"" 750P-1SR02.REVISION Page 52 of 83 NOTE The following sequence will occur when the"mode,.start." pushbutton is depressed:

~Discharge valve}!V-348 closes,'+..Secondary.

flush.accumulator SRN-X04 flushes.'+'fter a preset timer for cement/waste mixer to bo cleaned, 1IV-348 opens,~After, a preset time to allow waste/cement"to drain,'rocess complete" annunciator will alarm.13.3.3 13.3.4 Depress"mode start" pushbutton lIS-329.After"process complete" annunciator has alarmed, sot-cement/waste mixer IIS-327 in the"stop" positioII.

NOTE The following sequence will occur when I;ho"loading flange" position selector l{S-322 is placed to up,~Drip pan extends fully as indicated by light ZS-380 going off.~Loading flange moves up as indicated by"loading flange up" light ZS-379~Overfill level probe moves out of.position.Items of Section 13,0 of this procedure IIave beeII completed or exceptions have been recorded and properly documented.

I'erformed By: Signature and Initial Date Items of Section 13.0 of this procedure have been reviewed and found acceptable:

Approved By: Signature D Attach original copy(ies)of appendix(ces), route to Unit Rad Haste Supervisor.

PV210409 REV.OI82

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~~'I~~I~~~I~~I I~I~I a s a 0 0 99AFV I qpogMP.YION 0'"'AL'O'ERDE NUCL'EAR'ENERATING'TATION NIANUAL OPERATION OF SOI,IDIFICATION SYSTEM'PROGEOURE

'NO.750P"1SR02 REVISION APPENDIX E'age 1 of 20 Page 64 of 83 TROUBLE SHOOTING MODE 1'AILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Tank Tank Inlet valvos fail t:o open Tank inlot valves fail to closo 1, Tank will not: fill 1, Tank may overfill 2.Impropor wast:o food tank mat:orial ratio Chock for propor inlet valvo oporat:ion.

I nsuro I:ank is not: alroady filled t:o h.igh 1cvc1.C lose l:ank isolation valves and chock.inlet;valves.Loss of echo (waste foed t:ank)1.=All incoming valvos to wast:o food t:ank should close immediatoly'."Echo lost:" annunciat;or energized.

Opurator w111 l)c unable I:o cont:inuo with"fill t:ank" opcrat:ion until echo is ros to):ctl.Soloct:or swit:ch(os) not on auto 1.Syst: em cannot: st:art: S<<t: con t ro 1.'roper l.y.Selector switches moved from auto position during fill tank mode Ultrasonic level setpoints fail to actuate 1.System will drop out, of auto.Tank inlot valvos will close 2."Process interrupt:od" annunciator onorgizod 1.Redundant back-up probe will drop system out: of: aut:o upon roaching ll3 2."Process interrupt-ed" annunciator onergizod 3."High lovol holdup tank" annunciator energized Rcsot: switcl)to l)l'.ol)01 I)os I t I o)i Operator unablo to rostart system while Il3 con(li ti.()n cxis ts, opera tor must manually lower lovel in t:ank by pump out: PVg1040t)AEV.NOR 0 0 ARi ItlVIAN OiG,V,PALO VERDE NUCLEAR G,EN.E,R,AT.

IN.G STATION NIANUAL opERATroN or: sor.rDrl:rcATroN sYsTEN PROCEOURE NO.750P-1SR02 REVISION APPENDIX E Pago 2 of 20 Page 65 of 83 T R 0 v 8 r, E S H 0 0 T I N G CONT'D NODE FArr.vRE SCENAI<ro SYSTEII RESPONSE OPERATOR ACTION Waste Rocirc Waste food tank Chemical mixer fails to start Adjustmcnt (overloads out:)1.System will not go into waste recircu-lat:o 2.Pilot: lamp indicat:os motor not running Check motor reset overloads, check motor for serviceability Chemical addit:ion valvo fails to opon (rocirc valvo romains open)2.Syst: em will remain i>>recirculate Pilot lamps will indicates valves havo not yclcd CI<cclc volvo for propur opcrat:ion, i.c., Air/I', 1 cc t: r ic, Chemical addit:ion valve fails to open (recirc valve closes)Chemical addition valvo opens (recirc valvo remains opon)1, Chemical addition--.system will-sce high prossurc (see chemical addition pump high pressure)1.Chemical addition system.may seo low pressuro (see chomical addit:ion pump low pressure)Cltock volvo for.proper.opcrotio>>, i.e., Air/Eloct:ric Check volvo for propor oporation, I..o., h l,r/I', l ccl'r I c Chomical addition pump stops during recirculate mode 1.Systom will remain in,wast:o recirculat:c mode 2, Pilot lamp indicates mot:or not running Cltcck selector switclt sett.i>>g Check mot:or encl pump for service availability 3.Chemical addition system sees low prossuro (soe chemical pump low prossure)PVQt040P REV@Q

'I I k'~4 I 0 BRAKY 1ÃPOBMAYJON OWL'i PQLO'VEROE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE'NO.'II~750P-1SR02 REVISION APPENDIX E Pago 3 of 20 Page 66 of 83 T R 0 U 8 L E S H 0 0 T I N G CONT'D MODE 1'AILURE SCENARIO SYSTEM RESPONSE OPERATOR AC'l'ION Waste Recirc Chemical Adjustmont (Cont'd)Chomical addit:ion pump stops during thru modo 1, Syst:om will remain in wasto rocirculate modo 2, Pilot: lamp indicat:cs motor not running 3.Chomical addit:ion valve closos 4, Chomical rocirc valvo opons S.Chemical addit:ion system soos low pressure (refer to-chemical addit:ion-pump low prossuro)Chock solector switch sotting.Chock mot:or and pump for scrvicu~abilit:y and check that wast:o fuud t:ank is not f il lud I:o tlto H3 lovel which st:ops al l incoming I: low>>Wasto food tank mixor drops out during waste recirculate mode (overloads out)Waste feed tank chargo valve fails to open Rad Waste feed pump pressure high l.2~l.2.System will romain in waste rocirculal:o mode Pilot: lamp indicates motor not running Low prossuro switclt on waste pump discharge shuts down system (soo wast:o pump low prcssure)High pressure rad wasto pump annunciator Pressure switch on waste pump discharge shuts down syst:cm Check mixer, reset: over loads, el tuck motor for>>urvicu-abiiit'.y Cl tuck I or p ropu r discharge valve oporation Chock prossuro>>w 1 tclt Cor calibrat:or.

for blockage in lincWaste feed pump pressure low After time delay: l.Low pressuro radwasto pump annunciator energized 2.Prossure switch on radwaste pump shuts down system Chock radwasto suct2,on lxno ior.blockage;cltuck wast;e feed pump for.proper operation chock prcssuro>>wi.tch calibration PY21040D REV SN2

gP,Pyl 1NFOP~1HATÃN ONLY'PALO VERDE NUCLEAR GE'NBRA'TING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION APPENDIX E Pago 4 of 20 Pago 67 of 83 T R 0 U 8 L E S H 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTIONWaste Recirc Chemical Adjustment: (Cont'd)Chemical addition pump high pressure Chemical addition pump low pressure Chemical addit:ion pump fails t:o stop 1,"lligh" prossuro chemical addit:ion pump annunciat:or onorgizod 2.Chomical addit:ion pump stops Aft:or timo dolay: 1,"Low" prossuro chomical addit:ion pump annunciator onorgizod Chomical addition pump stops 2~1.Valves (addit:ion and rocirculat:o) revert to close and open respectively 2.Lamp indicat:os mot:or still running 3.Operator takes corrective action Chock chemical addit:ion skid discharge valvo;inspoct pump check valvo.Cho<<k line for b loclcago CI1ock<<hemi<<a 1 add,i tion ta11lc cont:ont:s discharge valvo, strainer pump and motor;also prossuro sonsor Manual ly sl1tt I: pump down PV210400 ael22 1 P 0~'

9RAF II PW0PilHAYllGN WLXV PALO'VERDE NUCLEAR GENER'ATING STAT(ON MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION APPENDIX E Page 5 of 20 Pago 68 of 83 rROUaLE sllooTING CONr'D MODE 1'AI LURE SCl'.MAR Io SYSTEM RESPONSE OPERATOR ACTION Fill Operat:ion 55-Gallon Drum (No Flush)Loading flange fails to dcscond Fil)drum oporation will not start-systom romains in recirculation Ensure that all systems aro oporating, i.o,, processor, con-voyors otc.Check loading fla>>gc I)>>cuma t icsLoading flango disongagos during 1.2~3~E.F, System revorts to I'.nsurc that all rocirculatc sy.ionia aro, A, Haste pump runs opcrati>>g, i,o.B.Fill/rocirc processor valve goes to convcyors Qtc.rccirculato Loadi>>g I'la>>gc C, Metso and comont pnoumatics stop"process recirculato" lamp onergisos"process incor-rupted annunciator.

energized Processor continues to run Loading flange down Lanip/interlock doonorgizcd No flush initiated Loading flango disengages (after full level)System will rospond as above, howovor primary flush will bo initiatod until thc moment of disengagoment Ensure I;hat<<l 1 systoms aro operating, i.o.processor con-voyors ctc.londi>>I, flange pneumatics Drip pan fails to retract 2.Loading flange will not descent to drum Fill operation will not start;, system will reinai.n in recirculate Check drip pan operation 0

.PALO VERDE NUCLEAR GENKRATiING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEN PROCEDURE NO.750P-1SR02 REVISION APPENDIX E Page 6 of 20 Page 69 of 83 T R 0 U 8 L E S H 0 0 T I N G CONT'D NODE Fill Operation 55-Gallon Drum (No Plush)(Cont d)1'AILURE SCENARIO Valve or mot:or fails to operate in sequence as described in operat:ing descript:ion (before full lovel), including any one or moro of.the following:

Discharge valve fails t:o open and stay open.Inlet;valve ails l:o open and stay open..Drip valve fails to open and stay open.~-Additive rotary valve or conveyor fails to start or to continuo to run.Cement rotary valve and conveyor fail to start or to continue to run, Radwaste holdup tank mixer"fails to continue to run, Waste feed valve fails to align to fill and stay in fill.SYSTEII RESPONSE After time delay: 1.System reverts to rocirculate (refer to"Mode 200, loading flange disengages" for descript:ion)

OPERATOR ACTION Check out: equipment:

failure, Operator must: select: manual flush (if (required).

Itesot an><uncia\:or PV114400 BEY.SIST 1 E.00' PALO VERDE NUCLEAR GENERATING STATION lNANUAL OPERATION OF SOLIDIFICA'1'ION SYSTEM PROCEDURE NO.750P"1SR02 REVISION APPENDIX E Pago 7 of 20 Pago 70 of 83 T R 0 U 1I L E S 11 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Operation 55-Gallon Drum (No Flush)(Cont'd)Valve or mot:or fails to oporato in sequence as doscribod in oporat:ing description (after full lovol but heforo last: cement is added), including ono or moro of tho following:

1.System will respond as above, howovor primary flush will bo initiatod until t:ho moment: system drops out: duo t:o syst:om ma 1 funcI: ion Chock out: oquipmont failure.Resot: annunciat:or Waste feed valvo fails to align t:o rocirc and stay in rocirc, Primary flush valvo.fails t:o open and stay'open.Discharge valvo fails to stay opon.Inlet: valvo fails to stay opon, Drip valve fails to stay opon.Additive conveyor fails to continuo to run.Coment rotary valvo and conveyor fail t:o continue to run.Processor fails to continuo to run.PY21440D REV.@82 hl GR@py'NPOBMAYj Off Oyry.PALP VERPE NUCLEAR GENBRATlNG STATlQN MANUAL 750P"1SR02 REVISION OPERATION OP SOLIDIPICATION SYSTEM APPENDIX E Pago 8 of 20 Page 71 of 83 T R 0 U 8 L E S II 0 0 T I N G CONT'D NODE FAILURE SCENARIO SYSTEH RESPONSE OPERATOR ACTION Fill Operation SS-Gallon Drum (No Flush)(Cont'd)Sustained loss of comont flow (before full lovel)Sustained loss of cement flow (after full level)1, Annunciator"no cement flow" energized 2, Vibrator and aoration pads onorgizod immodiatc ly 3, If after a time delay comont flow is not restarted, tho system will rovort to recirculate (refer to loading flange disengagod" for detailed description) 1.System will respond as above, however primary flush will bo initiatod until the system drops out due to malfunction.

Operator to dotormino cause of loss of comont flow Samo as above.Echo lost drum (before 1, Echo lost, full lovel)annunciator ollorgizod 2.All incoming flows to processor stop 3.System rcvorts to xecirculato (rofor to loading flango disengaged for dctailod dcscriptioll)

OIIorator wil 1 b(I unable to coIItiltuc with"fill operation" ulltil (Icllo is L os lo I'.('(I~PVRI0409 IIEV.(Iles I I f%J.

GRAIF tI"PALO,:VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM;PROCEDURE INO.750P-1SR02 ,REVISION APPENDIX E Pago 9 of 20 Pago 72 of 63 T R 0 U 13 L E S ll 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Operat:ion 55-Gallon Drum (No Flush)(Cont'd)Echo lost drum (aft:er full lovel 1, Systom will respond Samo as above.as above, howevor holdup tank dischargo valve will bo closod and primary flushes will bo init:iat:cd (bot:h radwast:c pump flush and radwastc/ccmcttt mixor flush).Tho ocho lost condit:ioii will immodiatoly t:orminato t;ho flushes 2, No socondary flush.will bo init:iat:od Ultrasonic lovol setpoints fail to ac'tuate 1, Redundant back-up probe will drop system out of aut:o fill modo upon roaching overfill condition 2.All incoming flows to processor st:op Qporat:or catliiot cont: iiiuc willi fil1 operate oii wliilc over.f i1l condit:ion oxis ts.Clici.k coiidit ioii oI.'robos, Aii cttipty cont:ainor will 1!c itccdod t;o I!rociio<l witlt fil 1iiig 3.Overfill Lovel annunciator energized 4, System rovorts to recirculate (refer to loading flange disengaged" for detailod descript:ion)

PVR14400 RKY.tMLt 0

P6'0BMAYI05 0~y PALO VERDE NUCLEAR GENFRATING STATION MANUAL 750P"1SR02 REVISION OPERATION OF SOLIDIFICATION SYSTEM APPENDIX E Pago 10 of 20 Pago 73 of 83 T R 0 U 8 L E S II 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Last Drum Sustained loss of cement flow (boforo full-lovol)Operator to determine causo of loss of comont flow.l<osot annunciator.

1.Annunciator

>>no cement flow" energized 2, Vibrator and aoration pads onorgizod immediat:oly 3.If aft:or a t:imo dolny comont;flow is not: restartod, syst: em will rovort: 1:o rocirculnto (rofor t:o>>loading flange.disengaged>>

for dot:nilod doscript:ion).Sustained loss of cement flow (after full lovol)1.=System will operate OI>orat:or t:o as above, howovor: dot:ormino cnuso of: A.JIoldup I:ank of loss ol cement dischargo valve flow nt!d rosoI;will bo closed.annunciator and primary flushes will bo init:iatod (botI<rndwasto pump flush and radwasto/cement: flush)unt;il tho momont: system drops out due t:o mnl function Valve or motor fails to operate in sequence as described in oporat;ing description (before full level)including one or more of the following:" Aft:or time delay: 1.System roverts to rocirculat:o (rofer to>>loading fin!!gt!disongagos>>

for detailed description Oporat:or selects manual flush (if required).

Chock out: o(Iu l.I>lllolt t fniluro.Itosot annunciator Discharge valve fails to open and stay open PV110400 BEY.NR k, 0 REFORMATION Op+,pPALO VERDB NUCL'EAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION APPENDIX E Pago 11 of 20 Page 74 of 83 T R 0 U 0 L E S 11 0 0 T I N G CONT'D MODE FAILURE SCENAI<IO SYSTEM RESPONSE OPERATOR ACTIONLast Drum (Cont'd)Inlet: valvo fails to opon and st:ay open Drip valves fails tio open and stay open.Additive rotary valvo or conveyor fails t:o st:art or to cont;inue to run.Ccmont rot:ary valvo and conveyor fail to start or to continuo to run.Procossor fails t:o start or to continuo to run.Radwasto holdup tank mixer fails t:o cont:inuo to run.Wast:e feed valvo fails to align to fill and st:ay in fill.Valve or motor fails fails to oporato in sequonco as dofinod in operating description (after full but boforo last is added), including:

Waste feed valve fails to align to rocirc, and stay in rocirc.Primary flush valves fail to open and stay open~Discharge valve fails to stay open.Oporat:or t;o dotormino catts11 ol: of malfunct;ion and resot: tho annunc1.ator Oporat.or selects ma11ual flusl1 (if required)~System will operate as above howovor: a.11oldup tank discharge valve will bo closed and primary flushos will bo initiated (both radwasto pump flush a11d radwasto/comont mixer fluslt)until tho moment: system drops out: duo t:o malfunct:ion PV21040P REY.NQ f I~'

RIIIAYION OM,V No STATION MANUAL'50P" 1SR02 REVISION OPERATION OF SOLIDIFICATION SYSTEM APPENDIX E Page 12 of 20 Pago 75 of 83 T R 0 U 8 L E S ll 0 0 T I N G CONT'D MODE FAILORE SC)NARIO SYSTEM RESPONSE OPERATOR ACTION Last, Drum (Cont'd)Inlet valvo fails to stay opon.Additive conveyor fails to continuo to run Comont rotary valve and conveyor fail to continuo to run Processor'fails to continuo to runKoading flango fails to descent Loading flango engages during fill operation (before full level)l.F1'1 last: drum op ration will not start, system remains in recirculate 1.System will immediatoly revert to recirculate 2.All incoming flows to procossor stop 3.No flush (either primary or secondary) will bo initiated l)ot.ormi>>o ca11so ol'lango 1110 1 i'u>>ct'.io11

~Chock t)1at drip p<1>>vot vacl.'s.Cl1ock pvossuro switcl1 calibr.atio11.

SAI110 As AIJDvv Loading flange disengagos during fill operation (after full level but before last cement is added System will operate as above, howevor, holdup tank discharge valve will be closed and primary flushes will be initiat.ed (both radwasto pump flush and radwasto/cement mixer flush)until tho moment of disongagomont Same as Abovo PV210400 RKV.@22 rll I GRAFr EVFOBM PALG VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOI,IDIl'ICATION SYSTEM PROCEDURE~NO;750P-1SR02 REVISION APPENDIX E Pago 13 of 20 Page 76 of 83 T R 0 0 l3 L E S ll 0 0 T I N G CONT'D MODE 1'AI LURE SCENAI<IO SYSTEM RESPONSE OPERATOR ACTION Last Drum (Cont'd)Loading flange disengagos during Wator will remain in processor.

Discharge valvo will bo provont:od from oponing unt:il loading flango recngages and shutdown condit:ion is cleared.Dctormine reason for failure.En-suro a drum is in p lace.Repos i I: ion loading flango, Rosct: annuiiciat:or,Drip pan fails I:o rot:ract Echo lost drum (before full)evol)1, Loading flango will not: dcscond Co druui 2.Fill last dry.operation will not:'tart, syst: em will remain in recirculat:o 1,"Echo lost" annunciator ccicrgisod 2.All incoming flows Co procossor st:op 3.System roverCs Co rocirculat:o No flushes will be initiated Chock drip l>cnl opc ra C loll olid l i Rl i C swil'cll Op<<rator wii.l.bc unablo t:o ci>iit: iiilill with"Cii1 I.ccs t drum" oporcltioii unt:il echo is rest:orcd.

Echo lost drum (after full lovol)Syst:om will rospond Haiso is il>ovc as above, however, holdup tank dischargo valve will bo closed, and" primary f lushos will bo initiat:od (boCh radwasto pump flush and radwasto/comont;mixer f lusli).The echo lost coiiditioii will immediatoly terminate tho flushos.2.No secondary flush will be initiatedPQlMX)REV.NOR

@RAPT'ALO VERDE NUCLEAR GENERATING, STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"lSR02 REVISION APPENDIX E Pago 14 of 20 Pago 77 of 83 T R 0 U II L E S H 0 0 T I N G CONT'D MODE 1'AILURE SCENARIO SYSTEM RESFONSE OPERATOR ACTION Last Drum (Cont'd)Echo lost drum (during secondary flush)1.Socondary flush CItock lovol control water will ontor t: he systom for drum, No ot:hcr sorvicoabilit:y other flush wat:or will bo diroct:ed to processor.

Low prossuro radwaste pump Cltcck prcssure switclt calibration, CILcck puIIIp<<n(I mot or, Cltcck for adcquat:o wast:o lcvol (NPSII)in tank Aft:or Cimo dolay;1."Low pressuro wast:o pump" annunciator onergizod 2.Radwasto pump stops 3.Holdup tank dischargo valve closes 4."Frocoss inCerrupt:od" annunciator energized 5.Fill/rccirc wast:c valve goos Co recirc 6.Frimary flush init;iatod 7.Additivo rot:ary valvo stops After another t:ime delay;8.Primary flush stops: 9.Drip valve closes 10.Additive conveyor st:ops ll.Comont rotary valve stops 12.Comont convoyor st:ops 13.Frocossor inlet: closos High pressure radwaste pump Same as low pressure shut:down but first time delay is not: used 1.Annunciator indicator high pressure rather Chan low prcssure Chock prossuro switclt cal ilirat: ion.Chock syst.cm for lino blockages, PYR14400 REV.SIR

  • r 0 ggkII'4 IMF0BMATX0N 0M,V PALOVHBDE NUCLEAR GENERATING STATION MANuAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 ,REVISION APPENDIX E Pago 15 of 20 Page 78 of 83 T R 0 U 8 L E S ll 0 0 T I N G CON'1" D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Operation Largo Container Sustained loss of comont flow (boforo full lovel)2.3.Annunciator"no cement flow" energized Vibrator and aorat:ion pads energized If after a I:imo dolay comont: flow is not rostart:od, syst:om will rcvort: t:o rocirculatc (rolor.t:o"loading flange disengaged" for dctailod descript.ion)

Oporat:or to dot:ormino causo of comont f low.Rcsot;annunciat:or.

Oporat:or must sc Lect;Rlanua 1 flusl<(i f required)Sustained loss of.cemont flow (after full lovel)System will operat:c Opcrat:or sita Ll as abovo howovor: dotcrminc cause A, llo ldup tank o f l oss o f corno>>t dischargo valve Ilow<<>>d rosot.will bo closed annunciat:or and primary flushos will bo initiatod (both radwaste/cement mixer flush)unt:il I:ho momo>>t;system drops out due to malfunction Valve or motor fails to oporato in sequence as'described in operating description (boforo full lovel), including ono or moro of the following:

'ischarge valve fails to open and stay open.Inlet valve fails to open and stay open.Aft;cr t:imo delay;1.Syst:om rovorts to recirculate (refer to"loading flango disongagod" for dot:ailod description)

Ol)c ra I or lluls t.select: manual flush (if roquirod), Oporat:or to<Io to rsi I>>>>cause of equip-ment malfunction, Reset ann>>>terat:or.

PV11HOO REV.@SR ti 0 0 I 9PAiF II 1NFofGU 7 ON 0ÃI.Y PALO VERDE NUCLEAR GENERAT)NG STATION MANUAL OPERATION OI: SOLIDIFICATION SYSTEM PROCEDURE NO.750P-lSR02 REVISION APPENDIX E Page 16 of 20 Page 79 of 83 T R 0 V I3 L E 8 H 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION F~ill Operation Largo Containor (Cont'd)Drip valve fails to opon and stay opon Additive rotary valvo--or conveyor fails to start or to continuo to run, Comont rotary valve and convoyor fail to start or to continuo to run, Procossor fails to start or to continue to run Holdup tank mixor fails to continuo to run..Waste feed valvo fails to align to fill and stay in fill Valve or motor, fails to operate in sequence as dofinod in operating description (after full lovel but before last cement is added), including:

Waste feed valve fails to align to rocirc and stay in recirc Primary flush valvo.fail to opon and stay opens Discharge valve fails to stay open Additive conveyor fails to continue to run 1, System will operato as above, howovor: A, Holdup I.'ank discharge valve will be closod and primary flushes will bo initiated (both radwasto pump flush and radwasto/cement mixor flush)unti the moment syst: em drops out duo t.o ma 1 f unc t io>>Opo ra to r s 1 la 1 1 d(llo 1 ill L>>o (>>Uho 0 I malfu>>etio>>

a>>d reset tho annunciator.

OP>>1>>lol.e('

('('ls Illa>>(lll l I l (lail (I.I,'equire(l) weleee Ilev.enu l 0 0 PALO'ERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P"1SR02 REVISION APPENDIX E Page 17 of 20 Pago 80 of'3'1'0 U 8 L E S H 0 0 T I N G CONT'D MODE I'AILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Operation Largo Containor (Cont d)Comont: rot:ary valve and convoyor fail t:o continuo t:o run, Processor fails to continuo l:o run Loading flange fails to dosccnd N 1, Fill operut:io>>

wi11.not: start, syst:cm romains in rccircu 1 at;c Dctcrllll.>>c clltlsc oI: f 1 ange mal f u>>c t;.io>>Chock I;hat: drip pa>>I'it rile I s e tillc>c'k I)ross c sw I.tc'll calibrat: io>>Loading flange disongages during---operation (before full level)1, Syst;om will immodiat:oly rover t: to rocirculato 2.All incoming flows to procossor st:op 3.No flush (oit:hcr primary or secondary) will be initiat:od iballlc as ailovc Loading flange engages during fill operation (aftor full lovel but, before last cement is added)1.System will oporate as above, however, holdup t:ank discharge valvo would bo closed and primary flushes would bo initiated (both radwast:c pump flush and radwastc/comont mixer flush)until tho moment, of d isongagcmont:

2.Socondary flush will be initiated Same as above Loading flange disengagos during first part of secondary flush operation Water will remain in pzocossor.

Discharge valve will bo provontod from oponing until loading flango rocngagos and shutdown condition is cleared.Dc tel rm i>>c I.'clll so>>for failuro, Ell-sur<<a drum, is.in placo, Roposit:.lon load i>>g I'la>>go.Reset: annunciat:or.

PV214400 IIEY.4IQ F-/'l PALO VERDE NUCLEAR GENERATING STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEH PROCEDURE NO.750P-1SR02 REVISION APPENDIX E Pago 18 of 20 Page 81 of 83 T R 0 U 8 L E S Il 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Operation Large Containor (Cont'd)Drip pan fails to ret:ract 1, Loading flange will Chock drip pan not: doscont t:o liner'porat:ion and limit 2, Fill last: drum swit:ch operation will'not: st:art, system will romain in rocirculatc Echo lost;liner (before full lovol)l."Echo lost:" annunciat:or energized 2.All incomi>>g Clows t:o procossor stop 3.System rovorts to rocirculat:o 4, No Clushos will ho-initiated Opcrat;io>>

w.i.l l bc unable I;o co>>t i>>uc wit:lt f.il I ol>>~r>>t.io>>

u>>tii cclto is rest:orod Echo lost liner (after full lovel)Syst: em will respond Samo as above, as above, however, holdup t:ank discharge valve would bo closed and primary flushes would bo init:iatod (bot:h radwaste pump Clush and radwaste/cement mixer flush), Tho ocho lost condition would immediately t:crminatc the flushes 2.No secondary Clush would be initiated Echo lost liner (during secondary flush)1.Socondary Cluslt wator alroady in tlute processor will enter tho liner.No othor flush wator will bc directed to t:ho processor.

Clicck lovel co>>t:tol sys t:cm Cor serviccabiiit:y PV2$400 REV.NQ J I~0 t, 0 0

'1NFOH.PvIATI05 ONI,Q PALO VERDE NUCLEAR GEMERATIMG STATION MANUAL OPERATION OF SOLIDIFICATION SYSTEM PROCEDURE NO.750P-1SR02 REVISION APPENDIX E Pago 19 of 20 Page 82 of 83 T R 0 U 8 L E S li 0 0 T I N G CONT'D MODE FAILURE SCENARIO SYSTEM RESPONSE OPERATOR ACTION Fill Operation Large Container (Cont'd)Low pressure radwasto pump After time delay: 1."Low prossuro wasto--*----.pump"-annunciator energized 2.Radwasto pump stops 3.lloldup tank discharge valvo closos 4.Procoss interrupted annunciator energized Chock prossuro switch calibration Chock pump and motor.Chock for adequate water lovel (Nl'Sll)i,n tanlc Low pressure radwaste pump (Cont.'d)5.Fill/rocirc waste valvo goos to rocirc 6, Primary flush initiated 7.Additive rotary valvo stops Aftor another timo delay: 8, Primary flush stops 9., Drip valvo closos 10, Additive conveyor stops ll.Cement rotary valvo stops 12.Cement conveyor stops 13.Processor inlot closes High pressure radwasto pump Samo as low prossuro shutdown but first timo delay is not used, 1.Annunciator indicatos high pressure rathor than low pressure Chock pressure switch ca1ibraI;ion.

Check pump and motor, Choclc system I'or line blockages PQ$400 BEY.BIS2 I'1 I i, H 0 0 0 vm.sFV(~OPMAYvoÃ0~j PALO'VERDE NUCLEAR GENERATING STATION MANUAL OFERATION OF SOLI'DIFICATION SYSTrM PROCEDURE NO.750P-1SR02 REVISION APPENDIX E Pago 20 of 20 Page 83 of 83 T R 0 U 8 L E S H 0 0 T I N G (CONT'D MODE FAILURE'SCENARIO SYSTEM RESFONSE OPERATOR ACTION Cement/Waste Drip pan fails to Mixer Plush rotract Syst: em will bo provcnt:cd, Clrock drip pan from st:arting flush operation and oporation switcll Loading f'lango fails to engago drum/cont:ainor Loading flange disongages dut.ag flush operation System will bo provent:ed from starting flush oporation Wat:or will rornairr irr procossor, Discharge valve will bo prevented from opening unt:il loading-flange roongagos and shutdown condit:ion is cleared.Dot:ormine reason for fa i.lure.Ertsurc drum is in I>lace I)ctcrlll L>>c re>>soll for failuro, 1>>-sure a drum is in place, Rcpos.i t iorr loading flange.Rosot annunciator Discharge valve fails to open Flush wator will remain in processor Check discharge valvo oporatio>>

V 0 0 Doclllll(7ll t Ilo e...,g+Qp QQ+(Q I'(c!v e I'I<7 e C~Dooii!afoot:

7iL'lo...Qegp+Tlotu g ,$Q-L(Qlp{cgfg

<QPIJ SgCiLw Boa(-on For Cancel 1 ati oil.'....GAknX'.a....

g)PDCc-:.04<-.'C=-...7K

..~?18',i........SR<...CS F!<...../gap-f5'l2o+~g,7ggp-l 5/20M Y c""." Do'ln'/I i(:o n:i ncl CczlAIA i I'.IAGn 1'.'I'r'lc)(in<a

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(.I.,C'I'5)~i t(i(A.;)u!-i: thia ero'ocluz-:-.:..-:;A cli.".Iio."i tion cloculA<!nl': Tf yea, ar(7 the.";o L.C75 i tern@,zclr'quit.ciy clio;po";xtioncd by anot h!ar CIO("ulACon t?I 1%E I~~ui3 lll J.t t A7(9 b'Ii~pa.-tA<<>>t<<l~'acI L:ql!O..,.,v,,;,, f>lenc::.4a~l L.C'L (2C.'..'~.!IJii l'i!Cancel 1".~tion f~pprovai Ef f'acti vo.Dai,o Hanua'lo Lclcil~'loti fi 7d/'ncic;".>>

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l vc!

0 K(IRAFY I lui<~'(J FI fil I I'Liv, 4 I slI',<(VaQCI:>>uLLI'.

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'7a DP-I Sf2DW HILKTTL"N OY ILF.V18 LOH I)ATL'/W ZV LLL:Vl.Li.WL".O O Y Wz Sd NANL" (VLLlNT)LIAISON L"QLL L'LLOCI'DUlLI" CIIANGLl;>>L" PT.>>ATILtoviow I ho procedure-for oa'ch of thc following-charttcturist:icu

~Lf it: passossos Lho charactori.stic, chock YH8;if it, laclcs the ctt'(ruat;urist;ic, chealth NQ.Tf Lho chttractoristic does not apply to L;ho procutluru, clluclL~NA (nat applicable)

~Provide'ouuuonts or rocouuuondations for t:lto"u itemS ChOClCOd NQ, On Suttuttary Of'OuuuentS SOCtian prOVidod at;tile und Of tho checklist,~G~N Qt*L'oes tho procedure conform to applicable regulatory cammitmonts7 la Does this.xevf.s4on affect any Licensing Commitment Tracking System (LGTS)items as a disposition documonL:,, lbl:f yes, avo t:hose LClS Stoma adequately disposl,tioned by another documents Does the title page format conform with the guidance in Section 5.3 of-7QAG-QKKQl,7 Does the Yable of Contents li,st all tttajor sections 494 appendi ces)along with their page nLttttller i Ave aLl-pages (inclu4jng tLppendices) properly i,don" CiA,ett with title, page nutttbev, and revision nutttb<<r'f YVS NO N/A l~l t 1t (~7 l:Jt)C~3()l (I (ll I I I I I I (Wl(II I 5, ,Ks chs pcocsdoce nombsc cons).scans w(,ch secs(.on 5 13 (~l (I (I ond Appendjcos As Sr C and D Qf 70AC~QKZOl7 J f 0 VRQ CII)IJ III".COH'I'I" O'I': 6, Ooo" tice overall format confor(I(with I ho appli cable Writers Guide of 70AC-OZKOlV Ts I ho purpose'r obJocti vo of tho proc:ocluro y inc lu din[)thc proceclure s ap'pl icabi ll ty)c lear ly stated i.n tho Pur os>>Qb ective section7'He're I:I(c'.latest rov isionb of u3.I cluvu.I.c)I) ul((un ta.l allcl ill'Ip1ullluut'1nlt rul c:rune:us usucl'ln tl>u cluvo'l.ul)ulllu((I:

ol: I:hib prouoclurcY 0, Ar6 all i(1(plo(((onting and dc:velopalontal r'ofuconcu" listed and correctly identi.fied in tl>u It>>for<<ncu sectionY 9, Douu t;ho procedure conforal to roquiru((lonts i.n the references'0.

  • ro interfaces with other procedures properly identifiedf 11, Are Icey terms and abbreviations do f inod in Do f i-nitions ancl Abbreviations soctionY 12.Are individual.

responsibili.ties outlined, including minimum number of personnel and.qualification r'o" quiroa(ent s'l 13.ls the content of the procedure consistent with that recommended in tho applicablo Writers Guide of 7 OAG,04 0 1 7 l4>la the procedure essentially self-contained, so that the least qualified user'an'er'L'orm t!he'c;quired activity, baaed on the procedure alone'L5e*re'Ale~'ins true'tions writ tbn"'in short,'conc iso, identi fiable steps (as opposed to multi-step para-Irapha)>which cannot be easily misinterpxeted7 I l6i Do the steps follow a norma3 sequence to completion (no jumping ahead to hitcher number steps, then re" Cuvninl to a lower number)l I,:I 1, l I.)I I I I (I t l (l I I I I I I t~J(ll (I (I (I (~i I (Qll ll) 0l GRAFT PilFOBMATLON ONJ,V~V~~V V IONA l(uv.6 Page 3 of 4 17, Is space provi.ded to signoff (or initial)the per-Co r))lane 6 0 C': I.)I~~YES NO H/A a.Prerequi.si.tes b.Major procedure steps c, QC hold points d.Computations (i.ndependent verifi.cation required))~l))[~)[)[)['))[)[l[~)[~)t e, Hquipment lineups (independent verification recommended)

C.Restoration steps (indep<<ndent verification requi red)18.Are precautions essentialo'personnel and equips)en" safety listed immediately ahead of the applicable step2'he source of these precautions includes vendor manuals, technical specifications, industria1 and electrical safety, hazardous materials handling, and fire prevention.

19.If there are"Open Items" can the procedure b<<correctly performed wi,th the'Open Items" present (i.e."Open'Items" have no"a'dverse affect on nuclear safety, personnel safety or equipment protection)?

20.Are the parameters that are'expected.Co change dur-ing performance of a step identified, along with identificati'on and location'o'f the indicators moni-toring those parametersv 1[)[))[)[))[)l))~)))I I'21, Are quantitative acceptance criteria provided that are consisCent with related design documents7 22, Are contingency provisions included for reasonable deviations outside the acceptance criteria limitsf 23.Are visual aids such as graphs, charts, and tables legible;adequate for readability, interpolation, and extraction of values;and consistent with their associated instructions 7[)[)[~))~)

0

'8M'Y Bgyogm@~ojyy y I UA'4 V4CiVC ltuv.6 Page 4 of 4 24.IXs the syst: em returned to normaIl operating',alignment at the conclusion of the repair or'test procedure.

l I WAT.K"<l'lll40UG ll YES NO N/A 25.As a Cinal check of procedure adequacy, a detailed walk-through is desirable by the least qualified user for which the procedure is intended, Evat.ua-tion oC the walk"through should assure all the following criteria are met: b, Are equipment'umbers and/or nomenclature used in the procedure identical to those displayed on the equipment2 a.'an the procedure be perC'ormed in the sequence it is written2[)t I (I c,.Can, the user locate and identify all equipment referred to in the instructions2

'e.Can the user perform the procedure without obtaining additional information, direct assis-tance, or documenCs from sources not specified by the procedure2 When general rather Chan specific instructions are provided, can Che user explain in detail how Co perform the general j.nstructions2 J (I I 1 l j 1 P l 00 SUR"fh1<Y OF CONTENTS Cl II.',CKLT.HT rlP NUMI)l.'I<

SUMMhl<Y.Ol" (lOMMI':NT/l)l.'.FT(!1:I'CY SUMHhRY DV I<I'.SDI.UTlDN DhTI/TNITIhI.S 0 r 0 0~~~Il~)~~~~~0 0~Q y~~r~

ORMS'I"I PALO YERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP"1ZZ01 REVISION Page 2 of 19 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 PURPOSE

2.0 REFERENCES

3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 JOB PLANNING 6.0 INSTRUCTIONS 4'PPENDICES Appendix A-Waste Product Record Appendix B-Waste Isotope Worksheet Appendix C-Filter Isotope Worksheet Appendix D-Combined Waste Worksheet Appendix E-Waste Classification Worksheet Appendix F<<Isotope to Table 13 15 16 17 18 PY21040D REV.N82 58<A O.

BP@Fy EVFOPMAYioN o'er,Y 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 3 of 19 1.0 PURPOSE This procedure provides the requirements for classifying solidified low-level radioactive waste in accordance with 10 CFR 20 and 10 CFR 61.(LCTSg 011008)The waste shall be identified as Class A, Class B or Class C depending on the concentrations of both long and shore-lived radio-nuclides, the waste form physical stability due to its structure and presence of liquids or voids.This identification shall be completed prior to solidification to provide control over transfer and disposal requirements.(LCTSjj 011171)This classification will use the"indirect method" for classifying waste.A1F/NESP-02 generic scaling factors shall be used initially for determining quantities of the difficult-to-measure nuclides in waste streams and filters.After 100 full power days and on a Biannual basis a composite sample of=.the reactor coolant system shall be taken for--complete nuclide analysis.

2.0 REFERENCES

2.1 Implementing 2.1.1 750P-lSR02, Operation of Solidification System.2.2 Developmental 2.2.1 10 CFR 20, Standards for Protection Against Radiation.

2.2.2 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste.2.2.3 2.2.4 Methodologies for Classification of Low-Level Radioactive Wastes from Nuclear Power Plants.AIF/NESP-027 NRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification May 1983 Rev.0 2.2.5 75RP-9ZZ02, Solid Radwaste Process Control Program.2.2.6 LCTS Serial Number: 011008, 011171, 011011 PV218400 AEV.8/82 684 A s t

MAFV PilPOK'v~lT'fojy 0)~qj y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 4 of 19 3.0 DEFINITIONS 3.1 Indirect Method: The practice of using a scaling factor which infers to concentration of one difficult-to-measure nuclide from another which is actually measured.3.2 Waste Product: The result of combining the waste stream, additive,and cement to form one free-standing monolith.3.3 Waste form: A qualified standard to which a waste product is tested to ensure specific stability requirements are maintained after burials 3.4 Class A Waste: Waste containing the lowest concentrations of radionuclides-and meeting the minimum waste form requirements.stated in 10 CFR 61.3.5 Class B and C Waste: Waste containing higher concentrations of radionuclides and meeting more rigorous waste form and stability requirements stated'in 10 CFR 61.4.0 RESPONSIBILITIES 4.1 The Manager, Radioactive Materials Control has the responsibility for implementation of this procedure.

4.2 The chemistry section is responsible for isotopic analysis of the waste stream and filter smears.4.3 The Unit Radwaste Supervisor shall ensure that the solid radioactive waste is classified in accordance with this procedure and that the appendices to this procedure are forwarded to the Support Group in a timely manner.4.4 The Radioactive Support Supervisor shall receive and review the classification documents.

5.0 JOB PLANNING 5.1 Resources 5.1.1 Weight scale of sufficient.

capacity to weigh 55 gallon or 80 cu.ft.containers with a maximum weight of approximately 10200 lbs.PVR1MOD REV.SI82 564 A Il L v 0' i%FOB.MAYf ON 05YLY PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-lZZ01, REVISION Page 5 of 19 5.1.2 One low range beta/gamma survey instrument.

5.1.3 One high range beta/gamma survey instrument.

5.2 Precautions 5.2.1 Solidified waste shall contain as little free-standing, non-corrosive liquid as is reasonably achievable but in no case shall the liquid exceed 0.5X of the volume.(LCTSi/011011)5.2.2 Work with radioactive material shall be conducted under the guidance of a current Radioactive Exposure Permit to keep personnel radiation exposure as low as reasonably achievable (ALARA).5.2.3 Waste gispos'al site approval is required prior to'shipment of radioactive-waste which does not meet the.criterion for non detectable free-standing liquid (i.e., not greater than 0.5%, liquid by volume).5.3 Prerequisites 5.3.1 The chemistry section has completed the isotopic analysis of the waste stream, filter or filter smear in accordance with 750P-1SR02"Operation of Solidification System".5.3.2 All survey meters and scales used in this procedure are currently calibrated.

6.0 INSTRUCTIONS Appendices A, B, and E plus C and D when solidifying a filter, shall be kept together in a work package.This package shall be maintained until written notification is recoived from the burial site that tho shipment has been received.The package will thon bo sent to Drawing and Document Control.6.1 Obtain the isotopic analysis sheet from the Chemistry Section of the gamma spectroscopy on the waste sample/filter and/or filter smear.6.2 Complete Waste Product Record Appendix A, steps 1 through 7.PV216400 AEV.N82 SS4 A PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 6 of 19 6.3 To determine waste stream isotopic concentration, complete Waste Isotope Worksheet Appendix B as follows: 6.3.1 Column A-list isotopes with half-lives 25 years in the top portion and isotopes with half-lives h8 days to<5 years in the bottom portion of the table from the isotopic analysis sheet.6.3.2 Column B-enter yCi/cc from the isotopic analysis sheet.6.3.3 Column C-record the volume of waste (in cc)from Appendix A, delivered from the waste feed tank to one container.

6.3.4 Column D-multiply column B by column C and enter the total yCi of that isotope for one container.

6.3.5 6;3.6 Column E--enter the waste product volume as calculated in step 5 of-Appendix A (cc).Column F-.divide column D by column C and enter the total yCi/cc of the waste product.6.3.7 Column I-enter the value from column D for the appropriate isotope in column H.6.3.8 Column K-multiply column I by column J and enter the scaled yCi.6.3.9 Column L-enter the waste product volume as calculated in step 5 of Appendix A (cc).6.3.10 Column M-divide column K by column L and enter the scaled yCi/cc.6.3.11 Column 0-multiply column K by column N and enter the yCi's for the isotopes having a conversion listed in column N.6.3.12 Column P-enter the waste product density from Appendix A step 7 for the isotopes which have a conversion listed in column N.6'.13 Column Q-multiply column M by N/P and enter the qCi/g.6.3.14 Box R-sum column M for scaled isotopes with half-lives

<5 years.6.3.15 PV21B400 REV.8I82 584 A Box S-sum column M for scaled isotopes with half-lives

<5 years.

gy II 1 0' 9PAF II 1ÃFORjMA"I'Lola OXK,Y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP"1ZZ01 REVISION Page 7 of 19 6.3.16 Box T-combine Boxes R and S, for the total yCi/cc of isotopes with half-lives

<5 years.6.4 Determine filter isotopic concentration as follows: 6.4.1 Note filter radiation level measured in 750P-lSR02,"Operation of Solidification System""section 12.0 and complete step 8 of Appendix A.NOTE If the radiation level measured one foot from an unshielded filter is greater than 35 r/hr.DOT packaging requirements may change.Notify.,the Radwaste Unit Supervisor.

6;4'.'2 Complete Filter Isotope Morksheet Appendix C as follows: 6.4.'2.1 Column A-list isotopes from the isotopic analysis sheet with half.-lives 25 years in the top portion and isotopes with half-lives 28 days to<5 years in the bottom portion of the table.6.4.2.2 Column B-enter the yCi from the isotopic analysis of the smear or gamma spectroscopy.

For tritium, enter the reactor coolant concentration from the most recent quarterly average.6.4.2.3 Block C-sum column B (with exception to H-3).6.4.2.4 6.4.2.5 Column D-divide each column B entry (with exception to H-3)by the sum in block C and enter the fraction.Column E-the filter total yCi is calculated using the following equation: PV2$400 REV.8/82 I/i A

~OFMiATEON ONE,V PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 8 of 19 NOTE The value of (0.7 shall be used for (En).This is a calculated average energy from the expected radionuclides in the filter.C-number of curies EQUATION I: C=~R hr E-gamma energy 6 En n-number of disinte-grations/decay 6.4.2.6 Column F-multiply column E by-column D for the quantity of Ci's of each isotope.For Tritium: the column D volume=factor will be 1430 cc's.=Multiply column B by column D for the pCi of tritium.6.4.2.7 Column,I-,enter the value from.column F for the appropri'ate isotope in column H.6.4.2.8 Column K-multiply column I by column J and enter the scaled gCi.6.4.2.9 Column M-multiply column K by column L and enter the pCi's for the isotopes having a conversion listed in column L.6.5 To determine the combined waste stream and filter isotope concentration complete Combined Waste Worksheet Appendix D as follows: 6.5.1 6.5.2 6.5.3 Column A-list the isotopes from appendix B and Appendix C with half>>lives 25 years in the top portion and isotopes with half-lives 28 days to<5 years in the bottom portion of the table.Column B-list the pCi's of each isotope identified in'columns F and K of Appendix C.Column C-list the yCi's of each isotope identified in columns D and K of Appendix B.6.5.4 Column D" sum the yCi's from columns B and C for each isotope.PV210400 REV.8/82 SS4 A 0 ,

g RA,FV lÃgogipyyo@

0+~PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 9 of 19 6.5.5 Column E-enter the waste product total cc from Appendix A, line 5.6.5.6 Column F-divide column D by column E for the final waste" product concentration.

6.5.7 6~5~8 Block G-sum column F for the isotopes with half-lives

<5 years.Column H-list, the yCi's for the applicable filter isotopes from column M of Appendix C.6.5.9 Column I-list the yCi's for the applicable waste stream isotopes from column 0 of Appendix B.6.5.10 Column J-sum the yCi's from column's H and I for each isotope.6.5..11 Column'K-enter-the waste product weight (g)as calculated in step 6 of Appendix A.6.5.12 Column L-Divide column I by column K and enter the qCi/g for the applicable isotopes.6.6 To determine the waste classification perform the Radwaste Classification Worksheet, Appendix E as follows: NOTE Values shall be taken.from Appendix B columns F, M and Q or if a filter was solidified, from Appendix D columns F and L.6.6.1 List the following values on Table 1.a.pCi/cc values for C-14, C-14 activated metal, Ni-59 activated metal Ni-94 activated metal, Tc-99 and I-129.b.qCi/g values for Pu-241, Cm-242 and the total qCi/g values for TRU having half-lives

<5 years.6.6.2 On Table II, list the yCi/cc values for H-3, Co-60, Ni-63, Ni-63 activated metal, Sr-90, Cs-137 and the total Ci/cc value of radionuclides having half-lives of>8 days to<5 years.PV210400 AEV.8l82 684 A 98AFY PIFORMAYEoly Ogj,y PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION Page 10 of 19 6.6.3 Divide the yCi/cc value and the yCi/g value by the limit given on the classification worksheet, for each isotope, and enter the result in the space provided.6.6.4 Add the results of each column.NOTE If the sum of any column is<1.0, use the Radwaste Classification Worksheet flow chart to determine the classification.

6.6.5 If the sum for Table I is h1.0, the waste is not acceptable for near surface disposal.6.6.6 If the sum for Table II Column 1 is hl.0, list and calculate the radionuclides.in column 2 of Table II.6.6.7 If the sum for Table II Column 2 is 21.0, list and calculate the radionuclides-in-column'3 of Table II.6.6.8 If the sum for Table II Column 3 is h1.0, the waste is not acceptable for near surface disposal.6.6.9 Complete all spaces, sign and date the Radwaste Classification Worksheet.

6.6.10 Summarize the isotopic content in mCi on Appendix A step 10.6.7 Waste Characteristics 6.7.1 Ensure that the packaged waste meets the following 10 CFR 61.56(a)minimum requirements for all waste classifications, enter yes or no and initial the space provided on Appendix A step lla.6.7.1.1 The waste is not packaged in a cardboard or fiber board box.6.7.1.2 Liquid in solid material does not exceed 1'X by volume.6.7'-3 The waste is not readily capable of detonation or explosive decomposition or reaction at normal pressure and temperature, or of explosive reaction with water.PV21840D REV.8/82 88' l..l l.iI r PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP"1ZZ01 REVISION Page ll of 19 6.7.1.4 The waste does not contain or is not capable of generating quantities of toxic gases, vapors or fumes harmful to handlers of the waste.6.7.1.5 The waste is not pyrophoric.

6.7.1.6, Waste containing hazardous biological, pathogenic or infectious material has been treated to reduce to the maximum extent practicable the potential hazard from these materials.

6.7.2 For Class B or Class C waste, ensure that the following stability requirements of 10 CFR 61.56(b)are met, enter yes, no or N/A, as applicable and initial the space provided on Appendix A step lib.6.7.2.1 The waste is structurally stable and will generally maintain its physical dimensions and form under expected disposal conditions (weight-of overburden and compaction equipment, presence of moisture, microbial activity and internal factors, such as radiation effects and chemical changes).6.7.2.2 Liquid waste or waste containing liquid has been converted into a form which contains as little free-standing and noncorrosive liquid as is reasonably achievable but not exceeding 1X by volume in a disposal container designed to ensure stability, or 0.5%%d by volume for waste processed to stable form.6'.2.3 Void spaces within the waste or between the waste are reduced to the extent practicable.

6.8 Chelating Agents 6.8.1 Obtain from the chemistry section the weight of any of the following chelating agents used over the period during which the waste was produced.EDTA DTPA Hydroxy-Carboxylic.

and polycarboxylic acids (ex.Citric, Carbolic and Glucinic Acids).6.8.2 Assess the potential for the chelating-agent being present in the waste.PV21MOO REV.8I82 564 A 0 0 9RM"f 1NFORISJiI~~YEON OM,V PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION.Page 12 of 19 6.8.3 Determine if the container may contain a chelating agent and calculate the percent by weight, chelating agent, for the container, as follows: Wei ht of Chelatin A ent in Container 6.8.4 Weight of Waste in Container List any chelating agent present in the container equal to or exceeding O.l%%d by weight for the container and complete ll.c as appropriate.

NOTE If the chelating agent is equal to or greater than 0.1%by weight, permission from Hanford Disposal Site must be granted prior.to shipping the waste.PV2N40D REV.SI82 SS4A I v 0 0 QUART~FO@~YEOÃ(ygy\PALO VERDE NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZ01 REVISION APPENDIX A Page 1 of 1 Page 13 of 19 1.Batch Number WASTE PRODUCT RECORD 10.0 ISOTOPIC

SUMMARY

2.Waste Type 3.Container Ser.N Isoto e mCi 4.Container Type/Volume 5.Waste Product Volume cu.ft.cu.ft.(cu.ft.)(28320 cc/1 cu.ft.)=cc 6.Waste Product Weight (minus container weight)(lbs)(454 g/lb)=7.Waste product density: s)/(<<)='/<<8.Filter: Radiation Level Date Measured R/hr 9.Filter Density:.5 g/cc 10.Waste Characteristics:

a.The requirements of 10 CFR 61.56 (a)are met TOTAL Initial b.The requirements of 10 CFR 61.56 (b)for Class B or Class C waste are Initial c.Chelating Agents: t)None (or<0.1'X by weight))]>0.1X by weight.Name of Chelating agent(s)Verified by: Date PV216400 AEV.Sl82 684 A 0

KXIRWFV NFORM@moX Om,y PALO VERDE NUCLEAR GENERATlNG STATloN MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZOl REVISION 0 APPENDIX 8 Page 1 of 1 Page 14 of 19 BATCH IIUNBER DATE isoto c QCi/cc Cs-137 H-3 cc li Q cc sct.totnl C D E uCi/cc SCD CD isoto c 1-129 Tc-99 lli-63 Sz-90 PQ-241 scs ng iSOtO D Cs-137 C8-137 Co-60 Cs-137 C0-144 Ce-144 sca ng uCi scs ng fnctor 2.3K-7 1.2E" 7 0.5 5.6B-4 0.1 B.OE-3 sce ed III'c o 1.OV-nCl 1000 1000 nCl D)ns~C 1/I 144 4 r-51 Co-58 Fe-55 1'c-59 CI4-242 C-144 m 4)c zs Su combine c5 yzs SQI4 lt1]t 0 0PAIF IIR INI'OHMATH)N OM,V PALO'ERDE'NUCLEAR GENERATING STATION MANUAL SOLIDIFIED RADIOACTIVE WASTE CLASSIFICATION PROCEDURE NO.75RP-1ZZO1 REVISION 0 APPENDIX C Page 1 of 1 Page 15 of 19 DATE.RR isotope Co-60 Cs-137 nslysks Uci rect 0 of total ter otal uC u o isoto e sca e isoto e sca n8 isoto e I-129 CQ-137 C0-137 Tc-9 Sr-90 Cs-137 sca n8 uCi sca n8 factor 2.5E-7 I.28-7 5.6E-4 nCi V nCi TRU Ce-144 8.0E-3 1000 H-3 RC uCi cc vol.fnc.Ce-144 Mn-54 Cr-51 Co-58~Fc-55~Fc-59 V 0<5 yrs SutL

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