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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
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9111050104 DOC.DATE: 91/10/25 NOTARIZED:
YES DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION CONWAY,W.F.
Arizona Public Service Co.(formerly Arizona Nuclear Power RECIQ.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards response to Generic Ltr 91-06,"Resolution of Generic Issue A-30,'Adequacy of Safety-Related DC Power Supplies.'" DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution D NOTES: STANDARDIZED PLANT Standardized plant.Standardized plant.RECIPIENT ID CODE/NAME PD5 LA TRAMMELL, C INTERNAL: ACRS NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR NOTES: COPIES LTTR ENCL 1 1 2 2 6 6 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD THOMPSON,M NRR/DET/ECMB 7D NRR/DOEA/OTS B 1 1 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC F 01 NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 1 1 05000528 05000529 05000530 D D NOTE TO ALL"RIDS" RECIPIENTS:
D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25 P~
Arizona Public Service Company P.O.BOX 53999~PHOENIX, ARIZONA 85072<999 WILLIAM F.CONWAY EXECUTIVE VICE PRESIDENT NUCLEAR 161-04240-WFC/GAM October 25, 1991 Docket Nos.STN 50-528/529/530 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-37 Washington, D.C.20555
Dear Sirs:
Sub)ect: Palo Verde Nuclear Generating.Station.(PVNGS)
Units 1, 2, and 3 Response to Generic Letter 91-06,"Resolution of Generic Issue A-30,"Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54 (f)" File: 91-010-026; 91-056-026 Enclosed with this letter is the Arizona Public Service Company (APS)response to Generic Letter 91-06,"Resolution of Generic Issue A-30,"Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54 (f)." This response is being submitted to the NRC under oath or affirmation.
Should you have any questions regarding this submittal, please contact Michael E.Powell of my staff at (602)340-4981.Sincerely, WFC/GAM/gam Enclosure cc: J.B.Martin D.H.Coe A.C.Gehr A.H.Gutterman 9iii050104 9ii025 PDR ADOCK 05000528 P*PDR'I 1 ,~1 t I 161-04240-WFC/GAM Octobe" 251991 STATE OF ARIZONA))ss.COUNTY OF MARICOPA)I, W.F.Conway, represent that I am Executive Vice President Nuclear, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, 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 and correct.W..F.Conway Sworn To Before Me This 8 Dey Of C 1991."No.tary Public e Hy Commission Expires 0 3 C RESPONSE TO GENERIC LETTER 91-06 UESTION RESPONSE The following information is to be provided for each unit at each site: 1.Unit: PVNGS All three PVNGS units are essentially identical, and the Units 1,2&3 information provided herein is applicable to all three units.2.a.The number of independent redundant divisions of Class IE or safety-related DC power for this plant is: (Include any separate Class IE or safety-related DC, such as any DC dedicated to the diesel generators.)
Two There are two independent redundant divisions (load groups)of Class IE or safety-related DC power.Each load group is comprised of two subsystems.
The two DC load groups are identified in the PVNGS Technical Specifications, Table 3.8-1 as Trains A and B.This configuration is graphically shown in the PVNGS UFSAR Figure 8.3-4.b.The number of functional safety-related divisions of DC power necessary to attain safe shutdown for this unit is: One The PVNGS UFSAR, Section 8.3.2.2.1.3 describes that the complete loss of either of the DC subsystems (one per each DC load group)which supply control power for their respective Class IE AC load groups will not prevent the minimum safety functions from being performed.
3.Does the control room at this unit have the following separate, independently annunciated alarms and indications for each division of DC power?a.Alarms: (BL001S)A-1 0 3%V*<P f RESPONSE TO GENERIC I EITER 91-06 UESTION RESPONSE 1.Battery disconnect or circuit breaker open?Yes On annunciator panels ESA-UA-2E and ESB-UA-2F (Procedures 41AI 1ES2A, 41AL-1ES2B, 42AI 2ES2A, 42AI 2ES2B, 43AL-3ES2A, and 43AI 3ES2B).2.Battery charger disconnect or circuit breaker open (both input AC and output DC)?No A separate independently annunciated alarm for an open charger disconnect or open input circuit breaker is not provided.However, these alarms are provided on the common charger trouble alarm for each charger, which provides annunciation, CRT display, and typewriter printout in the Control Room (Dwg 13-E-PKB-004).
3.DC system ground?No Independent annunciation is not provided, however, DC system ground is alarmed on a common alarm for each DC subsystem, which provides annunciation, CRT display, and typewriter printout in the Control Room (Dwgs 13-E-PKB-001 and 13-E-PKB-002).
4.DC bus undervoltage?
No Independent annunciation is not provided, however, DC system undervoltage is alarmed on a common alarm for each DC subsystem, which provides annunciation, CRT display, and typewriter printout in the Control Room (Dwgs 13-E-PKB-001 and 13-E-PKB-002).
5.DC bus overvoltage?
No Bus overvoltage is not provided, but overvoltage is alarmed as a part of the common alarm (the charger DC high voltage output relay is monitoring the DC bus potential).
The common alarm provides annunciation, CRT display, and typewriter printout in the Control Room (Dwgs 13-E-PKA-002, 13-E-PKA-004, 13-E-PKA-005, 13-E-PKA-007, and 13-E-PKB-004).(BLOOIS)A-2 0
RESPONSE TO GENERIC LEITER 91-06 UESTION RESPONSE 6.Battery charger failure?No Independent annunciation is not provided, however, battery charger failure is alarmed on a common alarm for each DC subsystem, which provides annunciation, CRT display, and typewriter printout in the Control Room (Dwgs 13-E-PKB-001 and 13-E-PKB-002).
7.Battery discharge?
No However, battery discharge is alarmed indirectly.
During normal operation, the 125 VDC load and battery charging current is supplied by the battery charger.Failure of the battery charger to supply those loads is alarmed.Charger output voltage is alarmed (charger undervoltage relay)at 120 volts DC.If the bus voltage drops to 112 volts, the DC bus undervoltage relay will actuate an additional alarm (Procedures 41AL-1RK1A, 42AL-2RK1A, 43AL-3RK1A).
b.Indications:
1.Battery float charge current?No Battery current indication does not read float charge current (it has 0-1500 amp scale).However, the control room has voltage indication that corresponds to charge/discharge.
Also, float charge current is verified during the 7-day surveillance (Procedure 32ST-9PK01).
2.Battery circuit output current?Yes Panel B01 (Dwgs 13-E-PKB-001 and 13-E-PKB-002).
3.Battery discharge?
No Battery discharge indicator is not provided;however, a weekly surveillance test is performed to obtain specific gravity and voltage of each designated pilot cell.This indicates the state of battery charge (Procedure 32ST-9PK01).
(8L001S)A-3 0'0 I RESPONSE TO GENERIC LEITER 91-06 UESTION 4.Bus voltage?Yes RESPONSE Panel B01 (Dwgs 13-E-PKA-002, 13-E-PKA-004, 13-E-PKA-005, 13-E-PEA-007).
c.Does the unit have written procedures for response to the above alarms and indications?
Yes These procedures are: Procedures 41AL-1RK1A, 41AI 1ES2A, 41AL-1ES2B 42AL-2RK1A, 42AI 2ES2A, 42AI 2ES2B 43AL-3RK1A, 43AL-3ES2A, 43AL-3ES2B 4.Does this unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the battery and battery charger from its DC bus and the battery charger from its AC power source during maintenance or testing?Yes Annunciation is provided when battery breakers are not in the closed operating position.Annunciation is provided when the charger AC power breaker is open or the DC disconnect is open, as discussed in question 3.a.2 response (Dwgs 13-E-PKB-001, 13-E-PKB-002, 13-E-PKB-004).
5.If the answer to any part of question 3 or 4 is no, then provide information justifying the existing design features of the facility's safety-related DC systems.*See note below.JustiGcation is provided in the Comments/JustiGcation section following each specific question with a"no" answer.6.(1)Have you conducted a review of maintenance and testing activities to minimize the potential for human error causing more than one DC division to be unavailable?
and No Physical separation, electrical isolation, and redundancy are provided to prevent the occurrence of common mode failures.In addition, no provision exists for transferring loads between redundant 125 V-DC subsystems (UFSAR 8.3.2.2.1.3 and 8.3.2.2.1.16).(BL001S)A-4 k
RESPONSE TO GENERIC LETTER 91-06 UESTION RESPONSE (2)Do plant procedures prohibit maintenance or testing on redundant DC divisions at the same time?Yes This is addressed in Procedures 40AC-90P18, and 73AC-9ZZ04.
Also, Technical SpeciGcations 3.8.2.1 and 3.8.2.2 require at least one operable DC train in all modes.If the facility Technical SpeciGcations have provisions equivalent to those found in the Westinghouse and Combustion Engineering Standard Technical Specifications for maintenance and surveillance, then question 7 may be skipped and a statement to that effect may be inserted here: The PVNGS Technical Specifications have provisions equivalent to those found in the Combustion Engineering Standard Technical Specifications for maintenance and surveillance; however, question 7 will be answered for veriGcation purposes.7.Are maintenance, surveillance and test procedures regarding station batteries conducted routinely at this plant?Specifically:
a.At least once per 7 days are the following verified to be within acceptable limits: 1.Pilot cell electrolyte level?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK01.
2.Specific gravity or charging current?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK01.
3.Float voltage?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK01.
(810018)
RESPONSE TO GENERIC LEITER 91-06 UESTION RESPONSE 4.Total bus voltage on fioat charge?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK01.
5.Physical condition of all cells?Yes Procedure 32ST-9PK01.
b.At least once per 92 days, or within 7 days after a battery discharge, overcharge, or if the pilot cell readings are outside the 7-day surveillance requirements are the following verified to be within acceptable limits: Technical Specification 4.8.2.1.b specifies these surveillance requirements be performed at least once per 92 days and within 7 days after a battery discharge with a battery terminal voltage below 105 volts, or battery overcharge with a battery terminal voltage above 145 volts.Technical specification Table 4.8-2, footnote (1)specifies that if any category A parameter (including pilot cell specific gravity or battery charging current less than two amps on charge)is outside the 7 day surveillance requirement, all category B measurements (including those parameters in Question 7.b, 1 through 6 of this response below)must be taken and found within their allowable values.1.Electrolyte level of each cell?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK02.
2.The average specific gravity of all cells?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK02.
3.The specific gravity of each cell?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK02.
4.The average electrolyte temperature of a representative number of cells?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK02.(BL0018)A-6 I'
RESPONSE TO GENERIC L5WHER 91-06 UESTION RESPONSE 5.The float voltage of each cell?Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK02.
6.Visually inspect or measure resistance of terminals and connectors (including the connectors at the DC bus)?No Technical Specification Surveillance Requirement 4.8.2.1 and Procedure 32ST-9PK02 require visual inspection or resistance measurement of battery terminals and connectors during the 92 day surveillance test of station batteries.
However, the DC bus connector visual inspection is done as part of the inspection and testing of the DC motor control center, scheduled every third refueling outage.Increased periodicity of the DC bus connector visual inspection is not considered necessary because these connectors are not in close proximity to the battery cells, and therefore are not subject to the potentially corrosive environment of the battery.c.At least every 18 months are the following verified: 1.Low resistance of each connection (by test)?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK03.
2.Physical condition of the battery?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK03.
3.Battery charger capability to deliver rated ampere output to the DC bus?Yes Technical Specification Surveillance Requirement 4.8.2.1;Procedure 32ST-9ZZ34.(BL001S)A-7 0
I RESPONSE TO GENERIC LEITER 91-06 UESTION RESPONSE 4.The capability of the battery to deliver its design duty cycle to the DC bus?Yes Technical SpeciGcation Surveillance Requirement 4.8.2.1;Procedure 32ST-9PK03.
5.Each individual cell voltage is within acceptable limits during the service test?Yes Procedure 32ST-9PK03 requires that each cell voltage be monitored during the 18 month battery service discharge test, so that the test can be suspended when any cell voltage drops below acceptable limits.d.At least every 60 months, is capacity of each battery veriGed by performance of a discharge test?Yes Technical Specification Surveillance Requirement 4.8.2.1.e.At least annually, is the battery capacity veriGed by performance discharge test, if the battery shows signs of degradation or has reached 85%of the expected service life?Yes Technical SpeciGcation Surveillance Requirement 4.8.2.1.8.Does this plant have operational features such that following loss of one safety-related DC power supply or bus: (BU$1S)A-8 E
RESPONSE TO GENERIC LETTER 91-06 UESTION RESPONSE a.Capability is maintained for ensuring continued and adequate reactor cooling?Yes The PVNGS UFSAR, Section 8.3.2.2.1.13 discusses how each unit has separate and independent DC electric systems capable of supplying minimum ESF loads and loads required for attaining a safe and orderly cold shutdown of the unit assuming a single failure.Procedures 41AO-1ZZ17, 42AO-2ZZ17 and 43AO-3ZZ17 provide guidance to the operators for actions following loss of 125 VDC Class IE electrical power and address the capability to ensure that continued and adequate core cooling is maintained.
b.Reactor coolant system integrity and isolation capability are maintained?
Yes The PVNGS UFSAR, Section 8.3.2.2.1.13 discusses how each unit has separate and independent DC electric systems capable of supplying minimum ESF loads and loads required for attaining a safe and orderly cold shutdown of the unit assuming a single failure.Procedures 41AO-1ZZ17, 42AO-2ZZ17 and 43AO-3ZZ17 provide guidance to the operators for actions following loss of 125 VDC Class IE electrical power and address maintaining reactor coolant system integrity and isolation capability.
c.Operating procedures, instrumentation (including indicators and annunciators), and control functions are adequate to initiate systems as required to maintain adequate core cooling?Yes Procedures 41AO-1ZZ17, 42AO-2ZZ17, 43AO-3ZZ17, provide guidance to the operators for actions following loss of 125 VDC Class IE electrical power.These procedures describe the indicators and annunciators and control functions to initiate systems as required to maintain adequate core cooling.(BM01S)A-9 RESPONSE TO GENERIC LEITER 91-06 UESTION RESPONSE 9.If the answer to any part of question 6, 7 or 8 is no, then provide your basis for not performing the maintenance, surveillance and test procedures described and/or the bases for not including the operational features cited."See note below.The basis for the"no" answers to questions 6(1)and 7.b.6 are provided in the Response section for those questions.
All other parts to question 6, 7 and 8 are answered"yes".*Note: For questions involving supporting type information (question numbers 5 and 9), instead of developing and supplying the information in response to this letter, you may commit to further evaluate the need for such provisions during the performance of your individual plant examination for severe accident vulnerabilities (IPE).If you select this option, you are required to: The supporting information and justiGcation for any"no" responses has been provided in this submittal.
No further evaluation of the need for the provisions with"no" responses is planned.(2)So state in response to these questions, and Commit to explicitly address questions 5 and 9 in your IPE submittal per the guidelines outlined in NUREG-1335 (Section 2.1.6, Subitem 7),"Individual Plant Examination:
Submittal Guidance." (BL001S)A-10 f't 1 A 4 I l I