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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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~g~~~/I Palo Verde Nuclear Generating Station James M.Levine Senior Vice President Nuclear TEL (602)393-5300 FAX (602)393-6077 Mail Station 7602 P.O.Box 52034.Phoenix, AZ 85072-2034 U.S.Nuclear Regulatory Commission Attention:
Document Control Desk Mail Station P1-37 Washington, DC 20555-0001 102-04206-JMUAKK/MLG November 10, 1998
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos.STN 50-628/629/530 Response to Generic Letter 98-04 This letter provides Arizona Public Service Company's (APS), 120 day response to NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment." Items 1 and 2(i)of the Required Information section of the Generic Letter are addressed in the enclosure to this letter.APS is participating in the NEI Emergency Core Cooling System Performance Task Force and the Combustion Engineering Owners Group (GEOG)in addressing the issues associated with the referenced Generic Letter.(No commitments are being made to the NRC by this letter.Should you have any questions or concerns, please contact Scott A.Bauer at (602)393-5978.98iii80296 98iii0 PDR ADQCK 05000528 Sincerely P PDR JMUAKK/MLG/rlh Enclosure q nnA',O cc: E.W.Merschoff P.H.Harrell M.B.Fields J.H.Moorman
~~g ENCLOSURE GENERIC LETTER 98-04 REQUIRED INFORMATION 1 I t)t!P GENERIC LETTER 98-04 REQUIRED INFORMATION PVNGS Responses to Applicable Questions The PVNGS licensing basis requires that the amounts of unqualified coatings be tracked.PVNGS UFSAR, Section 1.8, describes commitments to NRC Regulatory Guide 1.54,"Qu'ality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants." Consequently, the following responses address NRC Generic Letter 98-04 Questions 1 and 2(i)only.Generic Letter 98-04, Question 1: Include a summary description of the plant-specific program or programs implemented to ensure that Service Level 1 protective coatings used inside the containment are procured, applied, and maintained in compliance with applicable regulatory requirements and the plant-specific licensing basis for the facility.Include a discussion of how.the plant-specific program meets the applicable criteria of 10 CFR Part 50, Appendix B, as well as information regarding any applicable standards, plant-specific procedures, or other guidance used for: (a)controlling the procurement of coatings and paints used at the facility, (b)the qualiTication testing of protective coatings, and (c)surface preparation, application, surveillance, and maintenance activities for protective coatings.Maintenance activities involve reworking degraded coatings, removing degraded coatings to, sound coatings, correctly preparing the surfaces, applying new coatings, and verifying the quality of the coatings.PVNGS Response:.PVNGS has implemented controls for the procurement, application, and maintenance of Service Level 1 protective coatings used inside the containment in a manner that is consistent with the licensing basis and regulatory requirements applicable to PVNGS.The requirements of 10.CFR Part 50, Appendix B are implemented through specification of appropriate technical and quality requirements for the Service Level 1 coatings program which includes ongoing maintenance activities.
For PVNGS, Service Level 1'oatings are subject to the requirements and guidance of ANSI N 101.2,"Protective Coatings (Paints)for Light Water Nuclear Reactor Containment Facilities", ANSI N 101.4,"Quality Assurance for Protective Coatings Applied to Nuclear Facilities", ANSI N 5.9,"Protective Coatings (Paints)for the Nuclear Industry" (later reissued as ANSI Standard N 5.12, and Regulatory Guide 1.54."Quality Assurance Requirements For Protective Coatings Applied To Water-Cooled Nuclear Power Plants".Assurance that the applicable requirements for the procurement, application, inspection, and maintenance are adequately implemented, is provided by'ur response applies to Service Level 1 coatings used in primary containmcnt that arc procured, applied and maintained by Arizona Public Service or their contractor 1 of4 4'
procedures and programmatic controls approved under the PVNGS Quality Assurance progr'am (a)Service Level 1 coatings used for new applications or repair/replacement activities are procured from a vendor(s)with a quality assurance program meeting the applicable requirements of 10 CFR Part 50, Appendix B.The applicable technical and quality requirements that the vendor is required to meet are specified by PVNGS in procurement documents.
Acceptance activities are conducted in accordance with procedures that are consistent with ANSI N 45.2,"Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants," requirements (e.g., receipt inspection, source surveillance, etc.).This specification of required technical and quality requirements combined with appropriate acceptance activities provides adequate assurance that the coatings received meet Service Level 1 requirements.(b)The qualification testing of Service Level 1 coatings used for new applications or repair/replacement activities inside containment meets the applicable standards and regulatory guidance referenced above.These coatings, including any substitute coatings, have been evaluated to meet the applicable standards and regulatory guidance previously referenced.
However, when a new qualified coating is applied over an existing qualified coating, but the coatings have not been qualified together, care is taken to measure and record the surface area of the new installation over the existing qualiTied coated surface.The measured area is entered in the unqualified coating log.(c)Surface preparation, application and surveillance activities during installation of Service Level 1 coatings used for new applications or repair/replacement activities inside containment meet the applicable standards and regulatory guidance referenced above.Documentation of completion of these activities is performed consistent with the applicable requirements.
Where the standards and regulatory guidance did not address or were not.applicable to repair/replacement activities, these activities were performed in a manner consistent with the generally accepted practices for coatings repair/replacement.
These practices are described in various ASTM standards and industry coating guidelines issued subsequent to those that constitute the plant-specific licensing basis for PVNGS.PVNGS periodically conducts condition assessments of Service Level 1 coatings inside containment.
Coating condition assessments are conducted as part of the PVNGS Component Monitoring Program, Procedure 81DP-OZZ01.
Inspections of coatings systems are scheduled every outage on a pre-established basis to verify containment liner coating thickness.
General visual surveillance of other coatings in containment is also conducted in conjunction with the'coatings program.In accordance with the program, a total surface area equivalent to one unit will be inspected among the three units over a period of approximately ten (10)years.2of4 0 I J>, A V t When loc'alized areas of coating defects are identified during the inspections, those areas are evaluated and scheduled for touch-up, repair or replacement, as necessary.
The periodic condition assessments, and the resulting repair/replacement activities, assure that the amount of Service Level 1 coatings which may be susceptible to detachment from the substrate during a LOCA event is minimized.
Generic Letter 98-04, Question 2(i): Information demonstrating compliance with item (i): (i)For plants with licensing-basis requirements for tracking the amount of unqualified coatings inside the containment and for assessing the impact of potential coating debris on the operation of safety-related SSCs during a postulated design basis LOCA, the following information shall be provided to demonstrate compliance: (a)The date and findings of the last assessment of coatings, and the planned date of the next assessment of coatings.(b)The limit for'he amount of unqualified protective coatings allowed in the containment and how this limit is determined.
Discuss any conservatism in the method used to determine this limit.(c)If a commercial-grade dedication program is being used at your facility for dedicating commercial-grade coatings for Service Level 1 applications inside the containment, discuss how the program adequately qualifies such a coating for Service Level 1 service.Identify which standards or other guidance is currently being used to dedicate containment coatings at your facility.PVNGS Response, Question 2(i): (a)The date of the latest condition assessment at PVNGS was October 15, 1998 during the scheduled Unit 3R7 outage.The pre-established areas were visually inspected and coating thickness were measured and verified.It was concluded that all surveilled coatings were in satisfactory condition with the exception of two minor defects noted on the containment liner plate.Two minor blisters were identified on an unqualiTied coating application totaling an approximate surface area of 2 in'.The identified degraded coatings were evaluated and noted.The evaluation determined that the surface area of the blisters were sufficiently small that it was acceptable to postpone rework of the areas until other coating work is performed in the same area.A component monitoring report for coatings is used to track the identified areas.3 of 4 a Similar walk downs have been completed for PVNGS Units 1 and 2.Defects'ound have likewise been identified.
The total quantity of unqualified coatings for each unit is well within the limits prescribed by PVNGS specification AO-AN-331A and PVNGS study 13-MS-A41.
As noted previously, coating condition assessments are conducted as part of the PVNGS Component Monitoring Program, Procedure 81DP-OZZ01.
Visual inspections of containment coating systems, if accessible, are performed at the frequency set forth in the monitoring program.The planned date for the next assessment of coating condition is during the Unit Two outage, which is currently scheduled to begin in March, 1999.(b)The limit for unqualiTied coatings has been conservatively established at 12,500 ft'his limit is documented in PVNGS specification AO-AN-331A, PVNGS study 13-MS-A41,"Evaluation'f Fiberfrax and Unqualified Paints/Coatings" and in PVNGS calculation 13-MC-SI-309,"Emergency Sump Screen Blockage." As an additional conservatism a limit is in place that not more than 150 ft'f the total allowable unqualified coatings be located below the 100 ft.containment elevation due to the determination in,,PVNGS Calculation 13-MC-Sl-309 that unqualiTied coatings in the lower regions of containment are more likely to result in sump blockage.Although the commitment to track unqualified coatings was established during initial plant licensing, the basis for the allowable amount of unqualified coatings was established in conjunction with the requirements of Regulatory Guide 1.82, Sumps for Emergency Core Cooling and Containment Spray Systems.The above listed analyses concluded an allowable quantity of unqualified coatings (i.e., 12,500 ft')based on an assessment of ECCS sump performance and the consequential affect on ECCS pump net positive suction head availability.(c)APS does not currently employ commercial grade dedication for Service Level 1 coatings used inside containment at the Palo Verde Nuclear Generating Station.f 4 of4.
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