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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17313B0991999-10-14014 October 1999 Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing ML17313B0881999-10-12012 October 1999 Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2 ML17300B3501999-09-29029 September 1999 Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7 ML17300B3551999-09-28028 September 1999 Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl ML17313B0851999-09-24024 September 1999 Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles ML17313B0781999-09-20020 September 1999 Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included ML17300B3331999-09-14014 September 1999 Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3 ML17300B3351999-09-0808 September 1999 Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met ML17313B0761999-09-0303 September 1999 Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H ML17313B0731999-08-31031 August 1999 Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML17313B0581999-08-0606 August 1999 Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included ML17313B0311999-08-0303 August 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17313B0431999-07-30030 July 1999 Advises of Listed Senior Mgt Changes That Have Taken Place at Plant ML17313B0441999-07-30030 July 1999 Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps. ML17313B0151999-07-20020 July 1999 Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys ML17313B0091999-07-20020 July 1999 Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1 ML17313B0171999-07-16016 July 1999 Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations ML17300B3111999-07-15015 July 1999 Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr ML17300B3141999-07-15015 July 1999 Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790 ML20209G6771999-07-0808 July 1999 Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl ML17300B2931999-07-0202 July 1999 Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval ML17313A9951999-06-26026 June 1999 Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML17300B2831999-06-26026 June 1999 Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl ML17313A9901999-06-15015 June 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr ML17313A9521999-05-24024 May 1999 Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55 ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML17313A9311999-05-13013 May 1999 Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload ML17313A9481999-05-12012 May 1999 Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address ML17313A9261999-05-0707 May 1999 Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML17313A9091999-04-30030 April 1999 Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld ML17313A9181999-04-30030 April 1999 Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790 ML17313A9191999-04-30030 April 1999 Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422 ML17300B3751999-04-23023 April 1999 Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool ML17313A9081999-04-23023 April 1999 Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531 ML20205T7421999-04-21021 April 1999 Forwards Partially Withheld Insp Repts 50-528/99-05, 50-529/99-05 & 50-530/99-05 on 990322-26.Determined That Security Program Properly Implemented.Insp Repts Details Withheld (Ref 10CFR73.21) ML17313B0271999-04-21021 April 1999 Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl ML17313A9031999-04-21021 April 1999 Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection ML17313A8971999-04-20020 April 1999 Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections 05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999 Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing ML17313A8931999-04-14014 April 1999 Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met ML20205Q0821999-04-13013 April 1999 Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item ML17313A8901999-04-13013 April 1999 Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing ML17313A8831999-04-0808 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3 ML20205F3491999-03-30030 March 1999 Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1) ML17313A8671999-03-24024 March 1999 Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3) ML17313A8601999-03-16016 March 1999 Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon ML17313A8551999-03-0505 March 1999 Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17313B0991999-10-14014 October 1999 Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing ML17313B0881999-10-12012 October 1999 Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2 ML17300B3501999-09-29029 September 1999 Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7 ML17300B3551999-09-28028 September 1999 Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl ML17313B0851999-09-24024 September 1999 Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles ML17313B0781999-09-20020 September 1999 Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included ML17300B3331999-09-14014 September 1999 Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3 ML17300B3351999-09-0808 September 1999 Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met ML17313B0761999-09-0303 September 1999 Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H ML17313B0731999-08-31031 August 1999 Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55 ML17313B0581999-08-0606 August 1999 Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included ML17313B0311999-08-0303 August 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001 ML17313B0441999-07-30030 July 1999 Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps. ML17313B0431999-07-30030 July 1999 Advises of Listed Senior Mgt Changes That Have Taken Place at Plant ML17313B0151999-07-20020 July 1999 Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys ML17313B0091999-07-20020 July 1999 Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1 ML17313B0171999-07-16016 July 1999 Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations ML17300B3111999-07-15015 July 1999 Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr ML17300B3141999-07-15015 July 1999 Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790 ML20209G6771999-07-0808 July 1999 Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl ML17300B2931999-07-0202 July 1999 Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval ML17313A9951999-06-26026 June 1999 Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML17300B2831999-06-26026 June 1999 Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl ML17313A9901999-06-15015 June 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr ML17313A9521999-05-24024 May 1999 Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55 ML17313A9311999-05-13013 May 1999 Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload ML17313A9481999-05-12012 May 1999 Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address ML17313A9261999-05-0707 May 1999 Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML17313A9191999-04-30030 April 1999 Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422 ML17313A9181999-04-30030 April 1999 Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790 ML17313A9091999-04-30030 April 1999 Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld ML17313A9081999-04-23023 April 1999 Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531 ML17300B3751999-04-23023 April 1999 Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool ML17313B0271999-04-21021 April 1999 Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl ML17313A9031999-04-21021 April 1999 Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection ML17313A8971999-04-20020 April 1999 Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections 05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999 Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing ML17313A8931999-04-14014 April 1999 Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met ML20205Q0821999-04-13013 April 1999 Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item ML17313A8901999-04-13013 April 1999 Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing ML17313A8831999-04-0808 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3 ML20205F3491999-03-30030 March 1999 Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1) ML17313A8671999-03-24024 March 1999 Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3) ML17313A8601999-03-16016 March 1999 Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon ML17313A8551999-03-0505 March 1999 Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe ML17313A8241999-02-23023 February 1999 Advises That Kp Jarvis,License OP-50287-1,no Longer Needs to Maintain License as Permanently Assigned to Position Requiring No License ML17313A8111999-02-18018 February 1999 Forwards PVNGS Unit 3 7th Refueling Outage, Which Provides Complete Results of SG Tube Inservice Insp Performed,Per TS 5.6.8 ML17313A8721999-02-16016 February 1999 Discusses Resolution of Generic Safety Issue 171, ESF Failures from Loss-of-Offsite Power Subsequent to Loca. Util Has Low Vulnerability to Loca/Grid Collapse/Loop Scenario ML17313A7611999-01-22022 January 1999 Forwards PVNGS Unit 3 Inservice Insp Rept Seventh Refueling Outage, Per 10CFR50.55a.Ltr Contains No New Commitments 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML17305B0681990-09-17017 September 1990 Forwards Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Exam Dates,Anticipated Number of Candidates & Requalification Exam Schedules for FY91-FY94 Also Encl ML17305B0491990-09-12012 September 1990 Forwards Palo Verde Nuclear Generating Station Unit 2 Steam Generator Eddy Current Exam,Second Refueling Outage Apr 1990. ML17305B0281990-08-27027 August 1990 Forwards fitness-for-duty Semiannual Performance Rept for Period of Jan-June 1990,per 10CFR26.71(d) ML17305B0111990-08-15015 August 1990 Responds to Request for Addl Info Re Emergency Lighting,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25. Availability Info Provided in Ref 2,most Appropriate Analysis of Lighting Sys Availability ML17305B0021990-08-0909 August 1990 Provides Update on Status of Record 546 post-restart Item, Per 900412 Ltr.Record Will Revise Procedures for Analyzing & Disseminating Incident Investigation,Operations & Maint Experience to Appropriate Dept ML17305A9871990-08-0303 August 1990 Forwards Rev 1 to Abb Impell Rept 01-1658-1815, Emergency Lighting Independent Review, Per Insp Repts 50-528/90-25, 50-529/90-25 & 50-530/90-25 ML17305A9791990-07-31031 July 1990 Forwards, Conceptual Design for Palo Verde Nuclear Generating Station for Diverse Auxiliary Feedwater Actuation Sys (Dafas) for Review.Schedule of Implementation as Indicated ML20056A4161990-07-31031 July 1990 Forwards Revised Security Plan Implementing Procedures.Encl Withheld (Ref 10CFR2.790) ML17305A9831990-07-27027 July 1990 Requests Temporary Waiver of Compliance from Limiting Condition for Operation 3.6.3 to Allow Corrective Maint to Be Performed on Main Feedwater Isolation Valves by Extending Allowed Outage Time to 12 H Instead of 4 H ML20055J2671990-07-25025 July 1990 Forwards Info Constituting Decommissioning Financial Assurance Certification Rept,Per 10CFR50.33(k)(2) & 50.75(b) ML17305A9771990-07-25025 July 1990 Forwards Status of Corrective Actions to Min Multiple Control Element Assembly Drop Events at Plant.Insp of Insulation Coils & Replacement of Defective Coils for Units 1 & 2 Completed ML20055J1711990-07-25025 July 1990 Forwards Certification of Decommissioning Financial Assurances for Plant,Per 10CFR50.75(b) & 50.33(k)(2) ML20055J1031990-07-25025 July 1990 Forwards Certification of Decommissioning Financial Assurances ML17305A9411990-07-20020 July 1990 Forwards Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. ML17305A9431990-07-17017 July 1990 Forwards Rev 1 to Palo Verde Nuclear Generating Station Annual Radiological Environ Operating Rept for 1987. Rev Results from Internal Review Bu Nuclear Safety Group & Audit Performed by Radiation Protection Stds ML17305A9601990-07-13013 July 1990 Forwards Preliminary Response Re Justification for Continued Operation of Fire Protection Sys Equipment,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25 ML17305A9331990-07-12012 July 1990 Discusses Util Compliance w/fitness-for-duty Program Implementation.Lab Specialists,Inc Audited & Monitored W/ Satisfactory Results.Ltr of Agreement Has Been in Place Since 900202 ML17305A9391990-07-0909 July 1990 Forwards Endorsement 44 to Maelu Policy MF-116 & Endorsement 62 to Nelia Policy NF-266 ML17305A9341990-07-0909 July 1990 Submits Results of 900514-18 NUREG-1220 Audit,Per NRC 900608 Request,Per Insp of Plant.Remaining Licensed Operators Found to Be in Conformance W/Medical Exam Requirements of 10CFR50.55 ML17305A9151990-06-29029 June 1990 Forwards Emergency Lighting Failure Data Update,Per 900621 Request ML17305A9061990-06-26026 June 1990 Suppls 891114 Response to Violations Noted in Insp Rept 50-528/89-16.Application for Amend to License NPF-41 Will Be Submitted in Oct 1990 to Permit Lower Flow Rate for RCS & Shutdown Cooling Sys ML17305A9111990-06-25025 June 1990 Responds to Generic Ltr 90-04, Status of Implementation of Generic Safety Issues. ML17305A9081990-06-25025 June 1990 Forwards Schedule Reiterating Util Plans for Implementation of USIs A-9 & A-44 & Provides Current Forecast Refuel Dates ML17305A9051990-06-25025 June 1990 Forwards Endorsement 45 to Maelu Policy MF-116 & Endorsement 63 to Nelia Policy NF-266 ML17305A9121990-06-24024 June 1990 Forwards Discharge Test Voltage Curve,Per 900623 Request for Completion of Emergency Lighting Exide Power Supply Prior to Entry Into Mode 2 ML17305A9171990-06-24024 June 1990 Confirms Compliance W/Agreed Upon Course of Action for Restart of Facility as Outlined in 891224 Ltr & Completion of Items Contained in Restart List Provided as Attachment to 900111 Ltr ML17305A8961990-06-20020 June 1990 Responds to NRC 900521 Ltr Re Violations Noted in Insp Repts 50-528/90-12,50-529/90-12 & 50-530/90-12.Corrective Action: Wiring in PPS Cabinets & Cabinet Drawers Reworked in Accordance W/Approved Work Authorization Documents IR 05000528/19900021990-06-19019 June 1990 Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite ML17305A9041990-06-19019 June 1990 Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite ML17305A8891990-06-15015 June 1990 Informs NRC That post-restart Items Due Prior to Scheduled Restart Have Been Completed on Schedule W/Listed Exceptions ML17305A8871990-06-14014 June 1990 Advises That Fuel Pool Cooling & Cleanup Procedures Being Restructured,Per Response to Violations in Insp Repts 50-528/89-36 & 50-530/89-36 ML17305A8731990-06-0808 June 1990 Responds to Bulletin 88-005 Re Product Forms Other than Fittings & Flanges for Plant.Significant Number of Lugs Delivered to Plant.Util Should Be Notified,If NRC Previous Review of Records Has Identified Other Product Forms ML17305A9421990-06-0101 June 1990 Forwards Pinnacle West Response to State of Az Corp Commission Complaint Filed W/Us Securities & Exchange Commission on 900521,to Revoke Exemption from Public Utils Holding Co Act ML17305A8661990-05-31031 May 1990 Forwards Projected 1990 Cash Flow Statements ML17305A8391990-05-31031 May 1990 Forwards 1990 Reactor Containment Bldg Integrated Leak Rate Test,Final Rept. ML17305A8571990-05-31031 May 1990 Forwards Amended Pages of Feb,Mar & Apr 1990 Monthly Operating Repts for Palo Verde Nuclear Generating Station Unit 2 ML17305A8201990-05-23023 May 1990 Provides Status of Improvements to Eliminate Possibility of Multiple Control Element Assembly Drop Events.Licensee Developed Mod to Ground Fault Detection Sys to Assure Continuous Monitoring & Annunciation of Any Future Faults ML20043B6421990-05-19019 May 1990 Forwards Amend 26 to Security Plan.Amend Withheld (Ref 10CFR2.790(d) & 10CFR73.21) ML17305A7841990-05-15015 May 1990 Forwards Special Rept 2-SR-90-002 Re Steam Generator Tube Plugging Due to Inservice Insp Activities.Twenty Tubes Plugged in Steam Generator 1 & ninety-one Tubes Plugged in Steam Generator 2 ML17305A8721990-05-14014 May 1990 Forwards Arizona Corp Commission Complaint Filed W/Us Securities & Exchange Commission Seeking Revocation or Mod of Exemption of Pinnacle West Capital Corp.Complaint Wholly W/O Merit ML17305A7621990-05-11011 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-528/90-03,50-529/90-03 & 50-530/90-03.Corrective Actions: Night Order Written for Guidance on Use of Instrumentation W/Maint Tag Present ML17305A7921990-05-0808 May 1990 Forwards Public Version of Rev 2 to EPIP-14, Dose Assessment. W/900523 Release Memo ML20043A0511990-05-0303 May 1990 Forwards Public Version of Revised Epips,Including Procedure Change Notice 11 to Rev 12 to EPIP-04 & Procedure Change Notice 1 to Rev 6 to EPIP-15 ML17305A7421990-05-0303 May 1990 Responds to 900330 Enforcement Conference Re Violations Noted in Insp Repts 50-528/90-04,50-529/90-13 & 50-530/90-13.Corrective Action:Special Locking Mechanisms Installed on Currently Posted Radiation Area Doors & Gates ML17305A8861990-04-30030 April 1990 Forwards EPIP Update,Including Rev 7 to EPIP 02,Rev 12 to EPIP 03 & Rev 9 to EPIP 20.W/o Encl ML17305A7381990-04-30030 April 1990 Forwards Annual Environ Operating Rept for 1989 & Annual Rept for Salt Deposition Monitoring Program 1989. ML17305A7131990-04-20020 April 1990 Responds to NRC 900321 Ltr Re Violations Noted in Insp Rept 50-530/90-08.Corrective Action:Plant Guideline Providing Addl Guidance Re Prioritization of Work Promulgated ML17305A6891990-04-16016 April 1990 Forwards Rev to Cycle 3 Reload Analysis Rept,Submitted 891024.Rev Reflects Early end-of-cycle Unit Shutdown & Replacement of Eight New Fuel Assemblies ML17305A7011990-04-12012 April 1990 Forwards Rev 3 to Palo Verde Nuclear Generating Station Post-Restart Actions, Per JB Martin 891224 Ltr ML17305A7081990-04-0909 April 1990 Forwards post-exam Security Agreements for Dk Hendrick, D Ensign,M Alavi & Author.Agreement Certifies That Signatories Will Not Divulge Info Re 900320 Exams 1990-09-17
[Table view] |
Text
REGUL RY INFORMATION DISTRIBUT SYSTEM (RIDS) 1 ACCESSION NBR: 8109010110DOC DATE'! 81/08/25 NOTARIZKD!'ES DO~>>>>
FACIL>>:STN~50 528 Palo Verde Nucl
~
cari Statfonr Unft STN-50-529 Palo Verde Nuclear Statfoni Unit 2R Arizona Publi ii Ar izona Publi 05000529 STN-50-530 Palo Verde Nuclear Stations Unit 3i Ar.fzona Publi 05000530 AUTH>>, NAME" AUTHOR AFFILIATION VAN BRU>>4TR Kr, K", i Ar zona Publ f c Service Co.
REC IP ~ >>4AMKr RECIPIENT AFFIL>>IATION TEDESCO RL>>, Assistant Director i for Licensing
SUBJECT:
" For wards responses to Questions" 2815 281,8Rr equested in>> NRCr 810813 ltr ~ Also forwards marked up FSAR pages which will into future'mend be'ncorporated
~
DISTRIBUTION CODEi: B001S COPIES RECEIIVED! L>>TR "
ENCL>> ~ SIZE'::
TITLKi: PSAR/FSAR AMDTS and Related Correspondence NOTES:Standardized Plant. 1 cy1.C Grimes 05000528 Standardized Plant,1 cy!C Grimes 05000529 Standardized Plant F 1 cy:Ci Grimes 05000530 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME) LTTR ENCL' ID COOK/NAME LTTR ENCL ACT'ION: A/D LI CEi4SNG L>>I C BR ¹3 BC 1 0 L>>IC" BR ¹3 LA 1 0 KKRRIGANrJ ~ 04 1 1.-
INTERNAL>>; ACCXD E>>VAL 1 1 AUX SYS BR 27 1 1 09 BR26'HEM E>>4G BR 11 1 CONT SYS BR 1 1 CORE PERF BR 10. 1 1 EFF TR SYS BR12 1 1 EMRG PRP DEV 35 1 1 EMRG PRP LIC 36 3 3-EQUIP QUAL BR13>> 3 3 FEMA REP DIV 39 1 1 GEOSCIENCES 28 2 2 HU>>>>l FACT KNG 40 1 1 HYD'/GKO BR 30. 2 2 ILC SYS BR 16 1 1 ILKI 06" 3 3 L>>I C GU ID BR 33 1 1 LIC, QUAL BR 32", 1 MATLI ENG BR 17 1 1 MECH E>>4G BR 18 1 MPA 1 0.
OELD 1 0 OP LZC BR 34 1 1 ~
POINTER SYS BR 19 1 1 PROC/TST REV 20 1 1 QA BR 21 1 1 SS 8R22' 1 1 REAC SYS BR 23>> 1 1 FILE 01 1 1.
SIT'NAL BR 24 1 1 ST ENG BR25 1 1 EXTERNAl.i: ACRS 41 16 16 LPDR 03 1 1 NRC PDR 02~ 1 1 i4S IC 05 1 1 NTIS 1 1
&~ sr TOTAL NUHBER OF COPIED REQUIRED:', LiTTR P1 ENCL'.
L I
g rmnazm mswvmeaa amzmmmr PHOENIX, ARIZONA 85036 STA. P.o. BOX 21666 A'ugust 25, 1981 ANPP-18740 JMA/KWG Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3 Docket Nos. STN-50-528/529/530 File:. 81-056-026'.1.10
Reference:
Letter from R. L. Tedesco to E. E. Van Brunt, Dated August 13, 1981,
Subject:
Chemical Engineering Branch Questions
Dear Mr. Tedesco:
Please find attached a copy of our responses to the questions 281.5 281.8. Also included are marked up FSAR pages which show this information which will be incorporated in a future amendment.
If you have any questions, please contact me.
Very truly our euu &~~4 E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects ANPP Project Director EEVBJr/KWG/pc Attachment cc: J. Kerrigan (w/a) goo/
P. Hourihan 5 A. C.'Gehr i/(
Bi090iOiiO 8i0825 PDR ADOCK 05000528' IPDR~
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Mr. R. L. Tedesco August 25, 1981 Page Two I, Edwin E. Van Brunt, Jr., represent that I am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, that'I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.
i+,~C +
Edwin "E. Van Brunt, Jr.;;,'~
0 w Sworn to before me thfs~tu+day of 1981.
otary Public My Commission expires:
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FSAR UESTION 6A.62 281.5 In your response to our request for information 281.1, you (6.1.1, 6.5.2) stated that no surveillance of the trisodium phosphate (TSP) baskets will be conducted other than to assure that the baskets are full. It is our position, as stated in CE-PWR Standard Technical Specification (3/4.5.2), that this ECCS subsystem shall be demonstrated operable at least once per 18 months by (1) verifying that a minimum total volume of solid granular TSP dodecahydrate is contained within the TSP baskets, and (2) verifying that when a r'epresentative sample of TSP from a TSP basket is submerged, without agitation, in borated water from the Refueling Water Tank, the pH of the mixed solution is raised to an acceptable level within 4 hours. Indicate that these sur-veillance requirements will be met.
Also, provide the minimum total volume of TSP to be stored in the TSP basket and state the basis for the stored quantity.
RESPONSE
The response is given in the amended response to Question 6A.4.
The minimum total volume of TSP is 154 ft (12 tons anhydrous trisodium phosphate). This minimum volume was calculated by CE to result in a "worst case" minimum sump solution pH of approximately 7.0. PVNGS has installed (in each unit) 9 baskets of dimensions 2' 2' 2'nd 8 baskets of 4' 4' 4'.
The available volume of these baskets is 684 ft .
PVNGS FSAR APPENDIX 6A sodium hydroxide solutions to preclude iodine evolution do not apply to PVNGS.. Initial spray pH levels are about 5.3, and within two hours of spray initiation, sump pH levels are stipulated to be maintained between 7.0 and 8.5. (See sections 6.1.1 and 6.5.2.) Even with sump pH of less than 7.0, iodine does not evolve from the sump.
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Indicate the total amount of protective coatings, paints, and organic materials (including uncovered cable insulation) used inside the containment that do not meet ANSI N101.2 (1972) and Regulatory Guide 1.54.
RESPONSE: Within the containment of Unit 1, there are cur-rently less than 4000 ft2 (of a total of about 393,600 ft )
of coated surfaces documented not to conform with ANSI N101.2 and Regulatory Guide 1.54. Exceptions taken to Regulatory Guide 1.54 are given in section 1.8 and include:
~ About 4,000 sq. ft. of insulated piping
~ About 140,480 sq. ft. enclosed within cabinets or enclosures.
Q" *' "! N" Q"" "* (1.8 and 6.5)
In Section 1.8 of the FSAR which deals with 'Conformance to NRC Regulatory Guides', reference is made to Regulatory Guide 1.52, Rev. '0 (June"1973 ) and Rev. 1 (July 1976) versions. Since Regulatory Guide 1.52, Revision 2, (March 1978), "Design, Testing and Maintenance Criteria for Post-Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" Amendment 4 6A-2 May 1981
1 I A
Insert A to Pa e 6A-2 The. following surveillance of the trisodium phosphate baskets shall be conducted at least once per 18 months:
a) Verifying that a minimum total of g),ggr,'ubic feet of solid gran-ular trisodium phosphate dodecahydrate (TSP) is contained within TSP storage baskets.
b) Verifying that when a representative sample of TSP from a TSP storage basket is submerged, without agitation, in borated water from the Refueling Water Tank (RWT), the pH of the mixed solution is raised to greater than or equal to 6.0 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
FSAR Question 6A.63 281.6 In Table 6 ~ 1-4 of the FSAR, you indicate that there are 259,560 pounds
/ il', 'l of cable insulation inside the containment building. Indicate what fraction of thi's weight consists of organic materials. We also need the following additional information for estimating the generation rate of combustible gases from organic materials in cable insulation under DBA conditions: (1) The quantity (weight and volume) of uncovered cable and cable in closed metal conduit or closed cable trays'e will give credit for beta radiation shielding for that portion of cable that is indicated to be in closed conduit or trays, (2) A breakdown of cable diameters and associated conductor cross section, or an equivalent cable diameter and conductor cross section that is representative of total cable surface area associated with the quantity of cable identified in 1) above. (3) The major organic polymer or plastic'aterial in the cables. If this information is not provided, we will assume the cable insulation to be polyethylene and assume a G value for combustible gas of 3.
Response
Table 6.1-4 has been revised in Amendment 5 to indicate 39,500 (37600 + 5%)
pounds of cable insulation within the containment.
(1) The quantity of covered/uncovered cable is not readily available.
Therefore, all cable is assumed exposed.
(2) 'A breakdown of cable diameters and conductor cross section is attached as Table 281.6-1.
(3) The major organic polymer in the cable insulation is flame-retardant ethylene propylene rubber and chlorinated polyethylene. (Other organic polymers in various insulation types are listed in Table 6.1-4.)
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Insert A to Pa e 9A-'22 The fuel pool cleanup filter cartridges will be replaced when the pressure drop across the filters exceeds 25 psid during operation of the system, or the gamma radiation reading on the outside of the filter housing exceeds a reading to be determined, when normal system radiation levels have been measured in order to maintain radiation exposures ALARA.
Fuel pool cleanup ion exchanger performance will be monitored by determining a decontamination factor from ion exchange inlet to outlet samples for gross activity and gross iodine. Ion exchanger resin will be replaced when the decontamination factor drops below a minimum efficiency level, as determined by examining initial operating decontamination factors, for 3 consecutive samples taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> apart or when the gamma radiation readings on the outside of the filter housing exceeds a reading to be determined when normal system radiation levels have been measured in order to maintain radiation exposures ALKQ..
Your response to our previous Question 281.2 did not indicate any chemical or radionuclide limits for initiating replacement of filters and ion exchange resins. It is our position that chemical and radionuclide limits in the spent fuel pool water, such as conductivity, gross gamma and iodine activity, demineralizer differential pressure, pH,.and crude level, are needed for initiating corrective action to enable safe operating conditions in the pool. Verify that you will meet this position and provide the above information.
RESPONSE
The response is given in the amended response to Question 9A.34.
. PVNGS FSAR APPENDIX 9A Q"" (9.1.3)
For the fuel pool cleanup system, indicate that chemical analyses at least weekly and continuous radiological monitor-ing will be made for measuring the efficiency of the filters and ion exchange resins to remove impurities and radioactive materials from the pool water. State what criteria (chemical parameters, decontamination factors, etc.) will be used to determine replacement of the filters and ion exchange resins.
RESPONSE: For the fuel pool cleanup system, chemical analysis down stream of the filters and ion exchangers is done via batch sampling only. These samples as a minimum are to be taken at one week intervals.
Continuous radiological in-line monitoring is not a
. requirement for the system as outlined in Regulatory Guide 1.45 (also, see section 11.5.1 and table 9.3-3).
High electrical conductivity or radiation levels in the batch sample are the criteria used to determine replacement of the resin bed for the ion exchangers.
The cleanup filters are provided with pressure differential indicator switches which give local indication of pressure drop across the filters and alarm to the lo~cal anel on high pressure drop.',,!, - >', . r i op Jw~.'i =,!",..' '41.b CndViging C lr4r3.f, )<","-
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Describe the provisions to meet the requirements of post-accident sampling of the primary coolant and containment atmosphere. The description should address all the require-ments outlined in Section II.B.3 of Enclo'sure 3 in NUREG-0737 Amendment 4 9A-22 Nay 1981
~ C ~ ~
FSAR uestion 9A.60 281.8 Provide information that satisfies the attached proposed license (9.3.2, II.B.3) conditions for post-accident sampling.
NUREG-0737, II.B. 3 Post Accident Sam lin Ca abilit Provide a capability to obtain and quantitatively analyze reactor coolant and containment atmosphere samples, without radiation exposure to any individual exceeding 5 rem to the whole body or 75 rem to the extremities (GDC-19) during and following an accident in which there is core degradation.
Materials to be analyzed and quantified include certain radionuclides that are indicators of severity of core damage (e.g., noble gases, iodines, cesiums and non-volatile isotopes), hydrogen in the containment atmosphere and total dissolved gases or hydrogen, boron and chloride in reactor coolant samples in accordance with the requirements of NUREG-0737.
To satisfy the requirements, the applica nt .'hould (1) review and modify his sampling, chemical analysis and radionuclide determination capabilities as necessary to comply with NUREG-0737, II.B.3, (2) provide the staff with information pertaining to system design, analytical capabilities and procedures in sufficient detail to demonstrate that the requirements have been met.
EVALUATION AND FINDINGS The applicant has committed to a post-accident sampling system that meets the requirements of NUREG-0737, Item II.B.3 in Amendment , but has not provided, the technical information required by NUREG-0737 for our evaluation.
Implementation of the requirement is not necessary prior to low power operation because only small quantities of radionuclide inventory will exist in the reactor coolant system and, therefore, will not affect the health and safety of the public. Prior to exceeding 5% power operation, the applicant must demonstrate the capability to promptly obtain reactor coolant samples in the event of an accident in which there is core damage consistent with the conditions stated below:
- 1. Demonstrate compliance with all requirements of NUREG-0737, II.B.3, for sampling, chemical and radionuclide analysis capability, under accident conditions.
- 2. Provide sufficient shielding to meet the requirements of GDC-19, assuming Reg. Guide 1.4 source terms.
- 3. Commit to meet the sampling and analysis requirements of Reg. Guide 1.97, Rev. 2.
- 4. Verify that all electrically powered components associated with post-accident sampling are capable of being supplied with power and operated, within thirty minutes of an accident in which there is core degradation, assuming loss of offsite power.
- 5. Verify that valves which are not accessible for repair after an accident are environmentally qualified for the conditions in which they must operate.
- 6. Provide a procedure for relating radionuclide gaseous and ionic species to estimated core damage.
- 7. State the design or operational provisions to prevent high pressure carrier gas from entering the reactor coolant system from on line gas analysis equipment, if it is used.
- 8. Provide a method for verifying that reactor coolant dissolved oxygen is at C O.l ppm if reactor coolant chlorides are determined to be 0.15 ppm.
- 9. Provide information on (a) testing frequency and type of testing to ensure long term operability of the post-accident sampling system, and (b) operator training requirements for post-accident sampling.
In addition to the above licensing conditions, the staff is conducting a generic review of accuracy and sensitivity for analytical procedures and on-line instrumentation to be used for post-accident analysis. We will require that the applicant submit data supporting the applicability of each selected analytical chemistry procedure or on-line instrument along with documentation, demonstrating compliance with the licensing conditions four, months prior to exceeding 5% power operation, but review and approval of these procedures will not be a condition for full power operation. In the event our generic review determines a specific procedure is unacceptable, we will require the applicant to make modifications as determined by our generic review.
RESPONSE
The PVNGS design uses in-line chemical and radionuclide analyses with backup grab sample capability to meet the requirements of NUREG-0737. These analyses fully meet the ranges and accuracies specified in Reg. Guide 1.97, Rev. 2.
The capability exists to sample'nd analyze the required samples over the required ranges within the allotted three hour time span. Table 1 provides further information on sample points and analyses. All samples, including grab samples, may be taken without exposing any individual to radiation levels in excess of GDC 19 criteria. Isotopic analysis is provided to identify and
quantify the isotopes of the nuclide categories corresponding to the source terms given in Reg. Guide 1.4 and 1.7. A manually loaded Class IE power source is'vailable within 30 minutes of an accident that assumes loss of offsite power. All equipment in the post-accident sampling system (PASS),
including valves, piping, cabling, motors and analyzer electronics, is qualified to the environment it would experience under accident conditions.
The PASS computer will determine estimated core damage by comparing the fraction of the core inventory in the RCS against the known core isotopic inventory. All listed analyses can be performed on any sample taken. This provides a complete picture of radiological and chemical data for historical comparison. Carrier gases are not used in the analyses.
The entire PASS system will be operated from a central computer which directs a controller to sample through valve and pump operation sequences. All data will be analyzed, stored and displayed on the computer. Ma-ual control will 1 be available on loss of the automatic functions. Grab samples can be taken remotely during post-accident conditions to minimize operator'exposure.
During normal operations, grab samples will be taken locally at the analyzer module.
Dissolved oxygen is verified to be below 0.1 ppm by the dissolved oxygen analyzer.
The PASS will provide weekly data during normal operations to meet various chemical and radiological technical specification sample times. Grab samples
will be taken on a routine basis to assure technician familiarity. Testing frequency will be determined by manufacturers requirements to maintain reliability. Operator training requirements will be determined at a later date.
Refer to Section 9.3.2 and PVNGS LLIR Section II.B.3 for further details of the PASS.
Refer to PVNGS LLIR Section II.B.2 for further details on plant shielding.
TABLE 1 FOR NRC QUESTION 281.8 (9.32 and II.B.3)
Post Accident Sampling System
~In uts
~Lt u1d Containment Recirculation Sump, Reactor Coolant System, Containment Radwaste Sump, Safety Injection A, Safety Injection B, Auxiliary Building Sumps, Letdown System Gas Containment Air, Volume Control Tank
~Out uts
~LL udd Equipment Drain Tank, Reactor Drain Tank Gas Containment Air
~Anal ses
~LX uld Gamma Spectrum 10 uCi/ml to 10 Ci/ml Isotopic Gross Gamma 10 uCi/ml to 10 Ci/ml Gross Boron 0 to 6000 ppm pH 1 to 13 (temperature compensated)
Dissolved Oxygen 0 to 20 ppm Dissolved Hydrogen 0 to 2000 cc (STP)/Kg Chlorida 0 to 20 ppm Gas
-3 -1 Gamma Spectrum 10 uCi/ml to 10 Ci/ml Isotopic Gross Gamma 10 uCi/ml to 10 Ci/ml Gross Gaseous Oxygen 0 to 30%
Gaseous Hydrogen 0 to 10% (provided by the Containment Hydrogen Control System)
Chemical analyses are done in parallel. Chemical analyses are performed while the radiological analyses are being performed.
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