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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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ACCELERATED DI RIBVTION DEMONS ATION SYSTEM QEGULATO INFORMATION DISTRIBUTION TEM (RIDS)
SUBJECT:
Forwards revised relief requests for PVGS Inservice Testing Program.DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
Inservice Inspection/Testa.ng/Relic from ASME Code S 05000528 05000529/05000530 A NOTES:STANDARDIZED PLANT Standardized plant.Standardized plant.ACCESSION'NBR 9209170159 DOC.DATE: 92/09/08 NOTARIZED:
NO 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 RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)RECIPIENT ID CODE/NAME PD5 LA TRAMMELL,C INTERNAL: ACRS NRR/DET/EMEB 7E OC LF E LE 01 ES" DSTR EIB EXTERNAL EGSG BROWN g B NRC PDR COPIES LTTR ENCL 1 0 2 2 6 6 1 1 1 0 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PDS PD NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS1 RES MILLMAN,G EG&G RANSOME,C NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 0 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM PI-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19
.Ja 0 0~l l I t I'%;i l
~~~~r Arizona Public Service Company P.O.BOX 53999~PHOENIX, ARIZONA 85072-3999 10 CFR 50.55a WILLIAM F.CONWAY EXECUTIVEVICEPRESIDENT NUCLEAR 102-02269-WFC/JRB September 08, 1992 U.S.Nuclear Regulatory Commission ATIN: Document Control Desk Mail Station P1-37 Washington, DC 20555
Reference:
Letter 161-00496-JGH/BJA, dated September 10, 1987, from J.G.Haynes, APS, to NRC,"PVNGS Inservice Testing Program"
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)Units 1,2, and 3 Docket Nos.STN 50-528/529/530 Revised Relief Requests for PVNGS Inservice Testing Program File: 92-056-026 In the referenced letter, Arizona Public Service Company (APS)submitted Valve Relief Request Numbers 33 and 34 in accordance with 10 CFR 50.55a(g)(5)(iii).
These relief requests requested relief from ASME Section XI, paragraph IWV-3520 for Safety Injection Tank discharge check valves and Safety Injection Tank/Reactor Coolant System loop check valves.APS has identified several improvements which can be realized by full-stroke exercising these valves to the position required to fulfill their safety function during each refueling outage.Pursuant to 10 CFR 50.55a(g)(5)(iii), revised Valve Relief Request Numbers 33 and 34 which incorporate this improved testing methodology are being submitted as Enclosure 1.Additional information regarding these revised relief requests is provided in Enclosure 2.Currently approved Valve Relief Request Numbers 33 and 34 are provided as Enclosure 3.The check valves to which Valve Relief Request Numbers 33 and 34 apply are depicted on the Piping and Instrumentation Diagram provided as Enclosure 4.If you should have any questions, please contact Thomas R.Bradish at (602)393-5421.Sincerely, WFC/JRB/pmm Enclosures cc: J.B.Martin (all w/enclosures)
J.A.Sloan 15004'209170159 920908'DR ADQCK 05000528 PDR
~~
ENCLOSURE 1 REVISED VALVE RELIEF REQUEST NOS.33 AND 34 t%I~
~~VALVE RELIEF REQUEST NO.33 SYSTEM: Safety Injection and Shutdown Cooling (Sl)COMPONENTS:
SIE-V215, SIE-V225, SIE-V235, SIE-V245 P&ID COORDINATES:
13-M-SIP-002
@A15, A12, A7, and A5 CATEGORY: AC CLASS FUNCTION: OPEN to provide a flow path from the Safety Injection Tanks to the Reactor Coolant System.CLOSE to prevent backflow of primary coolant into the Safety Injection Tanks.TEST REQUIREMENT:
Full-stroke exercise every three months, or part-stroke exercise every three months and full-stroke test during cold shutdown.BASIS FOR RELIEF: Full-stroke exercising these valves is not practical in any plant mode except refueling shutdown when the reactor vessel head is removed.Part stroke testing every 3 months is not practical since a plant mode reduction would be required to perform the test.ALTERNATE TESTING: Full-stroke exercise during each refueling outage when the reactor vessel head is removed.
P P lh I h II VALVE RELIEF REQUEST NO.34 SYSTEM: Safety Injection and Shutdown Cooling (Sl)COMPONENTS'IE-V217, SIE-V227, SIE-V237, SIE-V247 P8 ID COORDINATES:
13-M-SIP-002 A13, A10, A6, and A3 CATEGORY: AC CLASS: FUNCTION'PEN to provide a flow path from Safety Injection and Shutdown Cooling to the Reactor Coolant System (RCS).CLOSE to prevent pressurization of Sl piping from RCS loop pressure.TEST REQUIREMENT:
Full-stroke open every three months, or part-stroke open every three months and full-stroke open at cold shutdown.BASIS FOR RELIEF: These valves can only be stroked open by initiating flow through the valves into the RCS.Safety Injection pump head is not sufficient to overcome RCS pressure and stroke the valves during plant operation.
Full-stroke exercising is not practical during any plant mode except refueling shutdown when the reactor vessel head is removed.Part stroke testing every three months is not practical since a plant mode reduction would be required to perform the test.ALTERNATE TESTING: Full-stroke exercise during each refueling outage when the reactor vessel head is removed.
I Il ENCLOSURE 2 ADDITIONAL INFORMATION REGARDING REVISED VALVE RELIEF REQUEST NOS.33 AND 34 r t g'I ADDITIONAL INFORMATION REGARDING REVISED VALVE RELIEF REQUEST NOS.33 AND 34 ASME Section XI Re uirement ASME Section XI, paragraph'IWV-3520, requires check valves to be exercised at least once every three months to the position required to fulfill their function unless such operation is not practical during plant operation.
If only limited operation is practical during plant operation, the check valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns.
Basis For Relief The Safety Injection Tank (SIT)discharge check valves (SIE-V215, SIE-V225, SIE-V235, SIE-V245)and the Safety Injection Tank/Reactor Coolant System (SIT/RCS)loop check.valves (SIE-V21 7, SIE-V227, SIE-V237, SIE-V247)can only be full-stroke exercised during refueling shutdowns when the vessel head is removed.Current Alternate Testin Method One SIT discharge check valve and one SIT/RCS loop check valve are disassembled and inspected to verify freedom of disc movement each refueling outage.If a disassembled valve's full-stroke capability is questionable, the other three SIT discharge check valves or SIT/RCS loop check valves, as applicable, are disassembled, inspected, and full-stroke exercised during the same outage.In addition, the SIT discharge check valves are part-stroke exercised in Mode 3 after each refueling outage when the SIT pressure is above 600 psig.Pro osed Alternate Testin Method Each SIT discharge check valve and SIT/RCS loop check valve will be full-stroke exercised to the position required to fulfill its safety function during each refueling outage.To conduct the test, an initial SIT level and pressure will be selected to maximize rate and duration of flow without discharging nitrogen into the RCS or exceeding the capacity of the SIT structural supports.Flow will be initiated by opening the SIT discharge motor-operated valve located just upstream of the SIT discharge check valve.The rate of change in SIT pressure and level will be recorded and analyzed to determine the system hydraulic resistance or,'k'actor.Hydraulic resistance, or'k'actor, is a function of piping configuration and check valve disc position, but is independent of flow rate.Therefore, the'k'actor determined during this test will be representative of system performance during accident conditions.
The determined
'k'actor will be compared to the calculated maximum'k'actor provided in the UFSAR.A'k'actor less than or equal 0 J ,l to,the maximum'k'actor provided in the UFSAR will demonstrate the ability of the check valve to fulfill its safety function.Two full-scale tests have been performed using this test method.The first test was performed on Unit 2 in the fall of 1991 and the second test was performed on Unit 1 in the spring of 1992.Acoustic data from both tests provided additional assurance that the check valves actually stroked fully open during the tests.Justification For Pro osed Alternate Testin Method The proposed alternate testing method offers the following improvements over the current alternate testing method: Full-stroke exercising the SIT discharge check valves and SIT/RCS loop check valves with flow to the position required to fulfill their safety function provides greater assurance that the valves function properly.Each SIT discharge check valve and SIT/RCS loop check valve will be tested every refueling outage.Full-stroke exercising the SIT discharge check valves to the position required to fulfill their safety function eliminates the need to part-stroke exercise the valves after each refueling outage.The possibility of reassembly errors and bonnet sealing problems encountered during the current testing method of disassembly and inspection will be eliminated.
The proposed alternate testing method will result in reduced personnel radiation exposures.
ENCLOSURE 3 CURRENTLY APPROVED VALVE RELIEF REQUEST NOS.33 AND 34 (TYPICAL OF UNITS 1, 2, AND 3)
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ENCLOSURE i IIFORMATlloà 0,.NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL PVNGS ASME SECTION XI PUMP AND VALVE INSERVICE TESTING PROGhi, UNIT 1 Revisioa 73PR-1XI01 0 Appendix C Page 38 of 50 VALVE RELIEF RE UEST NO.33 SYSTEM: Safety Injection and Shutdown Cooling (SI)COMPONENTS:
SIE-V215, SIE-V225, SIE-V235.SIE-V245 P&ID COORDINATES:.
13-M-SIP-002 9 A15, A12, A7 and A5 CATEGORY: AC CLASS: FUNCTION: To prevent backflow of Primary Coolant into the Safety Injection Tanks while providing a flow path for Safety Injection Tank water into the RCS loops.TEST RE UIREMENT: Full stroke exercise every three months or part stroke exercise every three months and full stroke test during cold shutdown.BASIS FOR-RELIEF: Full stroke testing to stroke these valves is noq practical during any plant mode other than when t>e reactor vessel head's removed, fuel's off-loaded, and the core barrel is removed.Part stroke testing is feasible during hot shutdown.Plant design conditions allows part stroke testing with a maximum of 35gpm through the valve.Full stroke testing would require a full blowdown of SIT.This is not feasible and would create a significant crud burst, and airborne contamination.
ALTERNATE TESTING: 1.Part stroke exercise in Mode 3 after each refuelirig outage when the Safety Injection Tank pressure is above 600 psig.2.Disassemble valves and verify freedom of movement of disc motion on a re'fueling basis, such that one valve is inspected every refueling outage.3.If it is found that th..d3.sassembled valve's full-stroke capability is in question, the other valves shall also be disassembled, inspected and manually Eu'll-stroked the same outage.
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~~~s~~ENCLOSURE 3 8 IIIIIFOITTaIliATI6Ã 9 ut'"--NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL PVNGS ASME SECTION XI PUMP AND VALVE INSERVICE TESTING PROGRAM, UNIT 1 Revision ,73PR-1XI01 0 Appendix C Page 39 of 50 VALVE RELIEF RE VEST NO.'34 SYSTEM: Safety Injection and Shutdown Cooling (SI)COMPONENTS:
SIE-V217, SIE-V227, SIE-V237, SIE-V247 P&ID COORDINATES:
13-M-SIP-002 6 A13, A10, A6, A4, C14, C11, C6.C4 CATEGORY: AC CLASS: FUNCTION: Valves open to provide a flow path from Safety Injection and Shutdown Cooling to the Primary Loop.Category'AC" valves close to prevent pressurization of SI piping from RCS loop pressure.Full stroke open every three months or part stroke open every three months and full stroke open at cold shutdown.BASIS FOR RELIEF: These valves can only be stroked open by initiation of flow through the valves and into the RCS.Low Pressure Safety Injection pump head is not sufficient to exercise these valves due to pressure of the RCS.Discharge of Safety Injection Tank through the valves would create significant crud burst, airborne contamination and could uplift core vessel head and UGS is not in place or Fuel is not loaded.ALTERNATE TESTING: 1.Disassemble one valve each refueling outage to verify freedom of disc movement and structural soundness of internals; Manually full-stroke the valve..2 If it is found that the disassembled valve's full-stroke capability is in question, the other valves shall also l>e disassembled, inspected and manually full-stroked the same.outage.NOTE: Valves SIE-V540, V541.V542 and V543 are now covered under CSJ-31.PVtWOat<<(Wa>
'4F El-,i~'44 17'~~~~L<~II J' ENCLOSURE 4 PIPING AND INSTRUMENTATION DIAGRAM DEPICTING SAFETY INJECTION TANK DISCHARGE CHECK VALVES AND SAFETY INJECTION TANK/REACTOR COOLANT SYSTEM LOOP CHECK VALVES