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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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CATEGORY j.RFGULATOkINFORMATION DISTRIBUTION TEM (RIDE)A ACCESSION NBR:9602210186 DOC.DATE: 96/02/08 NOTARIZED:
NO DOCKET¹FACIL: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 STEWART,W.L.
Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Submits APS response to NRC request for addi info're 960102 ltr,GL 95-03,"Circumferential Cracking of SG Tubes." DISTRIBUTION CODE: A001D COP1ES RECEIVED:LTR I ENCL I SIZE: TITLE: OR Submittal:
General Distribution NOTES:STANDARDIZED PLANT Standardized plant.Standardized plant.E 05000528 05000529 6 05000530 0 RECIPIENT ID CODE/NAME PD4-2 LA HOLIAN, B INTERNAL: ACRS NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 6 6 1 1 1 1 1 1 1 1 RECIP'IENT ID CODE/NAME PD4-2 PD THOMAS,C c@BMAGEN~RAEMNM0 NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1.0 1 1 D U E NOTE TO ALL"RIDS" RECIPIENTS'LEASE HELP US 70 REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL-18 WILLIAM L.STEWART EXECUTIVE VICE PRESIDENT NUCLEAR Arizona Public Service PALO VERDE NUCLEAR GENERATING STATION'.O.
BOX 52034 PHOENIX, ARIZONA 85072-2034 102-03601-WLS/SAB/NLT February 8, 1996 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
References:
1)Letter dated January 2, 1996, from Charles R.Thomas, Project Manager-Palo Verde, USNRC/NRR, to W.L.Stewart, Executive Vice President, Nuclear, APS 2)Letter No.102-03401, dated June 27, 1995, from W.L.Stewart, Executive Vice President, Nuclear, APS, to USNRC
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos.STN 50-528/529/530 Response to the Request for Additional Information Regarding Generic Letter 95-03 By letter dated January 2, 1996 (Reference 1), the NRC requested that Arizona Public Service Company (APS)submit additional information regarding Generic Letter (GL)95-03,"Circumferential Cracking of Steam Generator Tubes." Enclosed with this letter is the requested information to supplement that which was previously provided by letter dated June 27, 1995 (Reference 2), in response to GL 95-03.Should you have any questions, please contact Scott A.Bauer at (602)393-5978.Sincerely, 96022iOi86 960208 PDR ADOCK 05000528 P PDR WLS/SAB/NLT/AI Enclosure cc: L.J.Callan K.E.Perkins B.E.Holian K.E.,Johnston 2j.0073 h f.
ENCLOSURE RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 95-03
Response to the Request for Additional Information Regarding Generic Letter 96-03 1.CLARIFICATION OF INSPECTIONS TO BE PERFORMED AT THE EXPANSION TRANSITION DURING NEXT OUTAGE AT UNITS 1 2 AND 3 NRC REQUIRED INFORMATION ITEM 1 There appear to be some discrepancies in your Generic Letter 95-03 response regarding the examinations to be performed during the next outage at Units 1, 2, and 3 at the expansion transition region.In Section IX, for example, you state that a 100 percent plus-point motorized rotating pancake coil (MRPC)exam will be performed in U3R5: This is consistent with Table 3.However, in Section X, you state that a 20 percent initial sample will be performed and the sample will be expanded to 100 percent if a circumferential indication is found and 12 months have passed since the last 100 percent inspection.
Furthermore, in Section X you state that 1000 tubes (approximately 10 percent)'ill be examined in the cold leg at the'xpansion transition during U3R5;however, this program may be discontinued for U1R6 and U2R6 pending the Unit 3 results.Table 3, however, indicates that 10 percent of the cold-leg expansion transitions will be examined during U2R6.As you noted in your Generic Letter 95-03 response, these discrepancies may be a result of the uncertainties associated with the allowable run times for Units 1, 2, and 3.However, please clarify the inspections to be performed at the expansion transition during the next outage at Unit 1, 2, and 3.APS RESPONSE TO ITEM 1=Section X of APS'esponse to Generic Letter 95-03 (Reference 2)defined a minimum standard MRPC inspection program for the assessment
'of circumferential cracking in the PVNGS steam generators.
Table 3 of Reference 2 provided a projected inspection plan for the following three inspections at PVNGS (U3R5, U2R6 and U1R6).Since the projected inspections listed in Table 3 exceed the minimum MRPC program defined in Section X, APS does not regard the information to be in conflict.The Staff requested additional clariTication of eddy current inspections to be performed at the expansion transition location.Since the submittal of Reference 2, the U3R5 steam generator inspections have been conducted.
As'indicated in'Page 1
Table 3 of our response, a 100%Hot Leg MRPC inspection and a 10%Cold Leg MRPC inspection was conducted at the expansion transition region.Based on the U3R5 results, the approved eddy current scope for U2R6 has been established and is provided as Attachment 1 of this response.As indicated in the attached Table, the inspection includes a 100%Plus Point MRPC inspection of expansion transitions in the Hot Leg and a 500 tube MRPC sample in the Cold Leg.The inspection scope also identifies the applicable Cold Leg inspection expansion criteria.The U1R6 inspection program has not been finalized at this time, however APS intends to conduct a 100%Hot Leg MRPC of the expansion transition region as indicated in'Table 3 of Reference 2.2;CLARIFICATION OF INSPECTIONS AT THE U-BEND AND SQUARE BEND REGION NRC REQUIRED INFORMATION ITEM 2 In your response, you indicated that U-bend (Row 1 and 2)and square bend inspections were performed and that no indications of circumferential cracking were reported.Please clarify the extent of these examinations (e.g., 3 percent of the tubes in Row 1 and 2).If this region is susceptible to circumferential cracking, please provide the future inspections plans for this region.APS RESPONSE TO ITEM 2 APS has conducted a 100%MRPC inspection of Row 1 and 2 U-bends in all three PVNGS units.As indicated in Reference 2, no circumferential defects have been identified.
As indicated in Attachment 1, continuation of this program is planned for U2R6.Since 1993, APS has conducted over 32,000 square bend MRPC inspections at PVNGS.These inspections were conducted to determine the extent of axial cracking in the upper bundle region of the steam generators.
No circumferential cracks have been identified in these inspections.
APS therefore concludes that these areas are not susceptible to circumferential cracking.APS will continue to perform inspections in this area for axially oriented defects.Page 2
3.CLARIFICATION OF',.'SEVERE" DENTING NRC REQUIRED INFORMATION ITEM 3 In your response, you stated that there has been no evidence of"severe" denting of the Palo Verde steam generators.
Please clarify what is meant by severe denting.If a voltage threshold is used for determining the severity of dented locations, provide the calibration procedure used (e.g., 2.75 volts peak-to-peak on 4-20 percent through-wall ASME holes at 550/130 mix).In addition, provide the past inspection scope and your future inspection plans for dented locations if these areas are susceptible to circumferential cracking.APS RESPONSE TO ITEM 3 In Reference 2, APS highlighted the cfesign features of the System80 steam generators which preclude denting.The use of the term"severe" was to emphasize the relationship between industry identified circumferential cracking and dented support locations.
As stated previously, the horizontal supports at PVNGS are of eggcrate design, while the bend and horizontal regions are supported by batwing and vertical lattice supports respectively.
The supports are manufactured from Type 409 ferritic stainless steel..The large flow area in the System80 support design provides better irrigation and reduces the potential for steam blanketing, and is therefore less likely to be blocked by crud, boiler water deposits, and corrosion products.Since the support material is Type 409 ferritic stainless steel, it is not susceptible to magnetite corrosion which has resulted in denting and lockup at plants with carbon steel supports.Furthermore, APS has incorporated boric acid secondary water treatment for corrosion mitigation.
Boric acid addition has proven to be effective in eliminating denting (EPRI Steam Generator Reference Book, EPRI TR-103824s-V1 R1, December 1994).APS stated, in Reference 2, that the expected impact of these design and operational measures have been substantiated via eddy current in all three units and tube pull activities in Unit 2.Since 1993 APS has conducted 100%full length bobbin coil inspections during PVNGS refueling outages.PVNGS has recorded/measured dents with a variety of techniques during past outages.These measurements have been influenced by changes in eddy current probe design, acquisition equipment, analysis set-up and calibration, and procedural requirements.
The current practice at PVNGS, as shown in the Bobbin Coil Technique Sheet provided as Attachment 2, is to set voltage on the 50%AVB/BW wear in the P2 (500/100 absolute mix)channel to 5 volts (Vmax)and save to all channels.This yields a voltage of approximately 4.5 volts in the P1 (500/100 differential mix)channel.In earlier outages, APS required the setup to be 4 volts on the 4-20%ASME holes and stored to all channels.This is consistent with 2.75 volts on the 4-20%ASME holes with the P1 channel.Page 3 J
This setup value has not been considered essential since eddy current inspections have not detected corrosion product type denting for the reasons stated above.APS does require, by procedure, the trending of recordable dent signals.New dents or changes in dent signals (>20 volts)require an MRPC exam.It should also be noted, that the square bend MRPC examinations described in Item 2, include inspection of two horizontal eggcrates (08H, 09H)and three vertical lattice supports (VS1, VS2 and VS3), and no evidence of circumferential cracking has been identified.
Consequently, the statements provided in Reference 2 regarding the susceptibility to circumferential cracking at support or dented locations are valid.No programmatic or scope changes are planned as a result of our previous inspections.
DISCUSSION OF THE.USE OF TERRAIN PLOTS NRC REQUIRED INFORMATION ITEM 4 During the Maine Yankee outage in July and August 1994, several weaknesses were identified in their eddy current program.The staff discussed these deficiencies in NRC Information Notice 94-88,"Inservice Inspection Deficiencies Resulting in Severely Degraded Steam Generator Tubes," and observed that several circumferential indications could be traced back to earlier inspections when the data was reanalyzed using terrain plots.These terrain plots had not been generated as part of the original field analysis for these tubes.For the rotating pancake coil (RPC)examinations performed at your plant at locations susceptible to circumferential cracking during the previous inspection (i.e., the previous inspection per your Generic Letter 95-03 response), discuss the extent to which terrain plots were used to analyze the eddy current data.If terrain plots were not routinely used at locations susceptible to circumferential cracking, discuss whether the RPC eddy current data has been reanalyzed using terrain mapping of the data.If terrain plots were not routinely used during the outage and your'data has not been reanalyzed with terrain mapping of the data, discuss your basis for-not reanalyzing your previous RPC data in light of the findings at Maine Yankee.Discuss whether terrain plots will be used to analyze the RPC eddy current data at.locations susceptible to circumferential cracking during your next steam generator tube inspection (i.e., the next inspection per your Generic Letter 95-03 response).
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APS RESPONSE TO ITEM 4 As stated on page 6 of 14 in Reference 2, APS submitted a description of the MRPC techniques used at PVNGS for circumferential cracking as a result of issues identified in the 1994 Maine Yankee inspections.
In that submittal APS stated that PVNGS eddy current procedures require analyst review of both the terrain plot (C-scan)and the lissajous presentation for tubesheet transition locations.
The letter further states that this requirement has been in place since 1993.This requirement has not changed and will remain unchanged for the U2R6 and U1R6 steam generator inspections.
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ATTACHMENT 1
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Steam Generator Eddy Current Outage Scope Outage U2R6 Table 1: Eddy Current Scope 100%Full Length Bobbin Program MRPC ARC Upper Bundle ARC Sample'.!;~,'--Inspection Method Bobbin MRPC MRPC-'<'xtent"":-Full Length 07H-2nd VS 07H-2ndVS!IL SG'2-Il'-10,700-2700-200'SG 2-2-10,000-2700-200'Purpose Standard Refueling Outage Bobbin Program (Ref memo 323-00258-DFG/ECS 1/25/93)Area of Interest for ARC Region axial defects.Sample of Areas between Columns40-150 and Rows90-110 based on ATHOS Model Results Hot Leg 100%Top of Tubesheet Program Row 1 and 2 MRPC>20%bobbin-from U2RS Cold Leg MRPC Program MRPC MRPC MRPC MRPC TSH 07H-07C Support Locations 10,700-110 125+-500-10,000-110 250+-500 Circumferential Indications Generic Letter 95-03 Short Radius U-bend cracking Bounds results of Unit 2RS support cracking Program to match U2RS MMI locations/
Generic Letter 95-03 Note: Thc plus point MRPC Probe will be utilized in U2R6 Expansion Criteria Axial ARC Region Indications:
Five (5)tube buffer zone (all directions)
MRPC of any Bobbin indications that exceed PVNGS Plugging Criteria MRPC of all I codes and bobbin indications pcr 73TI-9RC01 Circumfcrntial Cracks Expand to 100%of Cold Lcg Tubcshcet if(1)SCI/MCI is detected in cold lcg sample Expand to 20%of Cold Lcg Tubcshcet if SCI/MCI>50 tubes in affcctcd SG T/te followiag eqaipntent sltoalrl be available or rearly to<leploy based oa Tabeslteet exanls UT Probes In-Sita Pressare I:qaiinneal Silasti e MolrVID PT Test I."qaiplneat j I ATTACHMENT 2
P PALO VERDE NUCLEAR GENERATING STATION NUMBER REV APPLICABILITY:
AlVALFSIS TECHNIQUE SHEET BOBBIN COIL EXAMINATIONS OI" STEAM GENERATOR TUBING APPLICABLE ATS NUMBERS: SG10 EQUIPMENT MODEL: 700 SOFPiVARE NO: EDDYNET 95 p 1.4 MANUF: ZETEC DIFFERENTIAL PI (1-5)P3 (1-5)P4(1-3-5)SPAN PHASE 509o 50%40 DEG 40 DEG 50%40 DEG 50%EC 50%40 DEG PM-HORZ R-TRASH 50%PM-HORZ PM-HORZ CAL STD CURVE ASME ASME DEGREE NA ASME DEGREE NA DEGREE ASME ASME ASME ASME NA SUPPRESS SPAN PHASE CAL STD SUPPRESS NA 30%UP/PM-H ASME NA NA NA NA 30%UP/PM-H ASME NA NA~SUFI'-R NA BSOLUTE 10%UP/PM-H ASME NA NA SUFl'-R 50%EC UP/90 DEG EGGCRATE NA NA SUFI'-R/R-'IR P2 (2-6)30%(50%wear)UP/PM-H VOLT SUPT-R VOLTS: SET the 50%WEAR in P2 TOSV (VMAX)AND SAVE(STORE TO ALL CHANNELS NOTES: 1.THE ABOVE SPANS ARE A MINIMUM 2.THE ABOVE PHASE SHOULD BE WH~+5 DEGREES 3.UNLESS NOTED, THE ABOVE SPANS AND PHASE ARE OF THE.100%HOLE 4.COLORS UIILIZED FOR SCREEN PRESENTATION SHALL BE THOSE USED FOR CALIBRATION RECORDING REQUIREMENTS CHANNEL P1 P1 P1,5,6 P4 P2 INDICATION ALL DEGRADATION TSH&OIH CRACKING UPPER HOTLEG CRACKING EXP TRANS CRACKING BW, EC,&VS WEAR Pl Pl P1 INDICATION PRIMARY ANALYSIS ONLY DNT p20V p5V p5V RESOLUTION ONLY GRAPHICS: D4 FOR ALL'" CODES, CRA CKING, PLP's, PLI's, ALOD ALL~EFFECTIVE DATE: l0-23-u5 PREPARER'PS APPROYhLt PAGE I OF2
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