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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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Text
ACCESSION NBR:960 3180137 DOC.DATE: 96/03/07 NOTARIZED: NO DOC KE'g g FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000/29 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 050005'30 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:
Forwards revised pages 1-5,2-5,2-6 6 UFSAR page 15.6-73 associated w/util 950502 submittal requesting NRC review &
'pproval of change to larke break LOCA dose consequences for plant.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution Q
NOTES:STANDARDIZED PLANT 05000528 Standardized plant. 05000529 0 Standardized plant. 05000530 R
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL .
PD4-2 LA 1 1 PD4-2 PD 1 1 HOLIAN, B 1 1 THOMASiC 1 1 INTERNAL: ACRS NRR/DE/EMCB NRR/DSSA/SPLB 6
1 1
6 1
1 FILrE CENT NRR DRCH/HICB NRR/DSSA/SRXB 1,
1 1
1 1
1" D NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 N
NOTE TO ALL "RIDS" RECIPIENTS: .
PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESKI 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 ENCI 18
Arizona Public Service PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 PHOENIX. ARIZONA 85072-2034 102-03620-WLS/SAB/GAM WILLIAML STEWART March 7, 1996 EXECUTIVE VICE PRESIDENT NUCLEAR U. S. Nuclear Regulatory Commission ATI N': Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
References:
(1) Letter 102-03345, dated May 2, 1995, from W. L. Stewart, Executive Vice President - Nuclear, APS, to USNRC, "Request for NRC Review of LOCA Dose Consequences" (2) Letter 102-03578, dated January 5, 1996, from W. L. Stewart, Executive Vice President - Nuclear, APS, to USNRC, "Proposed Amendments to Facility Operating Licenses and to Technical Specifications and Various Bases, Related to Power Uprate"
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units1,2, and 3 Docket Nos. STN 50-528/529/530 Supplement to Loss of Coolant Accident (LOCA)
Dose Consequences In Reference 1, Arizona Public Service Company (APS) requested NRC review and approval of a change to the large break loss of coolant accident (LOCA) dose consequences for PVNGS due to a new identiTied release path through a depressurized secondary system. In Reference 2, APS stated that an evaluation was being performed of the LOCA dose consequences related to power uprate and that the NRC would be notiTied if the dose consequences exceeded those reported in Reference 1. During this evaluation it was identified that the base calculation, upon which the Reference 1 dose values were calculated, contained an error. The error was the omission of the low population zone (LPZ) X/Q value for the time period from 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to 30 days following an accident. The original version of this calculation, the source of the original design basis large break LOCA dose consequences, did not contain this error.
The calculation performed to account for the new release path discussed in Reference 1 ratioed the results of the base calculation to account for the increased release through the depressurized secondary system. As such, this calculation carried over the previous error. The base calculation has now been revised to correct the error. The revised
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J' U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Supplement to LOCA Dose Consequences Page 2 calculation identified an increase of the LPZ 30-day thyroid dose from 149.7 rem, reported in Reference 1, to 186.5 rem, which remains lower than the 10 CFR 100 limit of 300 rem. The LPZ 30-day whole body dose increased from 1.46 rem, reported in Reference 1, to 1.5 rem, which remains lower than the 10 CFR 100 limit of 25 rem.
Included as-an enclosure to this letter are revised pages to the Reference 1 letter with the corrected dose values.'n Section D.6 of Reference 2, it was identified that a new source term was used for LOCA calculations associated with the power uprate project, and, as discussed above, that a detailed evaluation of the revised source term inventories was being performed.
That evaluation has been completed, and the identified LOCA doses associated with power uprate are less than those reported in Reference 1 as revised by this sub'mittal.
Should you have any questions, please contact Scott A. Bauer at (602) 393-5978.
Sincerely, WLS/SAB/GAM/rv
Enclosure:
Revised Pages 1-5, 2-5, 2-6, and UFSAR page 15.6-73 Associated with APS Submittal No. 102-03345, Dated May 2, 1995, to USNRC cc: L. J. Callan K. E. Perkins B. E. Holian K. E. Johnston
t II I
ENCLOSURE Revised Pages 1-5, 2-5, 2-6, and UFSAR page 15.6-73 Associated with Enclosures to APS Submittal No. 102-03345, Dated May 2, 1995
E I'I A
V'1
Table 1-1 LOCA DOSE COMPARISON
SUMMARY
e A. Previous B. NRC C. Revised D. 10 CFR 100 or APS Cele'No Calculated APS Cele 10 CFR 50, GDC 19 secondary Valuesb (Assuming secondary Criteria depressurlzathn) depressurlzation)
Thyroid EAB (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) 132.8 Dose LPZ (30 day) 104 9d 188.5d Cntrl Rm 7.0 <10.0 17.2 (30 day)
INh ale EAB (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) <2.6 3.98 Body LPZ (30 day) 1.0 <1.2 1.5 25 Dose Control Room 0.95 <1.0 1.472 (30 day)
Beta Skin Control Room 19.1 29.67 Dose (30 day) v ues rn rem APS calculations 13.NC-ZY-205, Revisions 0 and 1, and 13.NC-ZJ-201, Revisions lM, as rePorted to the NRC In letter 181 ~01 9, dated June 25, 1991, 'Technical Specification Amendment Request Section 3/4.6.2.2 and Bases.
NRC calculated values as provIdedln tho Safety Evaluation related to amendinents 64, 50, and 37 to PVNGS Units 1, 2, and 3 respectively, dated September 8, 1992.
APS calculation 13-NC-ZY-205, Revision 2.
These LpZ values were revised In calculation 13-NC-ZY-205, Revision 3, dated February 2, 1996, as a result of tho Inclusion of a previously Inadvertently omitted X/Q value. Seo APS Letter No. 102%3620r dated March 7r 1996.
GDC 19 requires that the control room dose will not exceed S rema whole body, or Its equivalent to any part ol the whole body, for the duration ol an scddent. The 00 rem beta skin dose limit shown here h based on the Suldance of Secthn 6 4 of the Standard Review phn, NUREG0800, Revision 2, July 1981. Thb value appears to have been derived from the okl 10 CFR 2L101 occupational skin limit of 7% rema per quarter. However, the new occupathnal skin dose limit, from 10 CFR 20.1201, effective January 1, 1994, has been Increased to 50 rema per year.
Table 2-1 (Page 1 of 3): COMPARISON OF POST-ACCIDENT DOSES (Thyroid)
PREVIOUS ANALYSIS VALUE'(rem) NEW VALUE (rem)
AREAJ CONTRIBUTOR (Secondary Side Pressurized) (Secondary Side Depressurized)
Exclusion Area Boundary (2-hour consequence)
Power access purge 2.3 Containment, leakage 77 115.5 (Primary & Secondary)
Recirculation leakage and 0.12 15b leakage to RWT TOtal (10 CFR 100 Criteria 300 rcm) 80 132.8 Low Population Zone (30-day consequence)
Power access purge Containment leakage 104.2'.4 0.4 155.8'ecirculation leakage and 0.28 30 3b leakage to RWT TOtal (10 CFR 100 Criteria 300 rem) 186 Sc Control Room (30-day consequence)
Containment leakage 7.0 14.7 (Primary & Secondary)
Recirculation leakage and 2.6 (-2) 2.5b leakage from RWT TOtal (10 CFR 50 GDC 19 criteria 30 rem) 7.0 17.2 APS calculations 13NC ZY 205, Revisions 0 and 1, and 13NC ZJ 201, Revisions 0 3, as reported to the NRC in Letter No. 161.04019, dated June 25, 1991, rechnical Specification Amendmcnt Request Section 3/4.6.2.2 and Bases."
Includes NRC Information Notice 91-56 Contribution.
'lhc LPZ values werc revised in calculation 13.NC-ZY-205, Revision 3, dated February 2, 1996, as a result of the inclusion of a previously inadvertently omitted X/Q value. See APS Letter No. 10243620, dated March 7, 1996.
Table 2-1 (Page 2 of 3): COMPARISON OF POST-ACCIDENT DOSES (Whole Body)
PREVIOUS ANALYSIS NEW VALUE (rem)
AREA/CONTRIBUTOR VALUE*(rem) (Secondary Side Depressurized)
Exclusion Area Boundary (2-hour consequence)
Power access purge 2.2(-3) 2.2(-3)
Containment, leakage 2.45 (Primary & Secondary)
Recirculation leakage and 2.7(-4) 03 leakage to RWT Total (lo cFR 100 critcria 25 rem) 2.5 3.98 Low Population Zone (30-day consequence)
Power access purge Containment leakage 1.02'.6(-4) 3.6(-4) 1.5'ecirculation leakage and 2.4(-4) 3.0E-4b leakage to RWT TOtal (10 CFR 100 Criteria 25 rem) 1.0 Control Room (30-day consequence) 1.5'ontainment leakage 0.945 1.47 (Primary & Secondary)
Recirculation leakage and 7.9(-7) 1.5E-3b leakage from RWT TOtal (10 CFR 50 GDC 19 criteria 5 rem) 0.95 1.472 AFS calculations 13 NC ZY 205, Revisions 0 and 1, and 13 NC ZJ 201, Revisions 0 3, as rcportcd to thc NRC in Letter No. 16144019, dated June 25, 1991, rechnical Specification Amcndmcnt Request Section 3/4.6.2.2 and Bases.
Includes NRC Information Notice 91-56 Contribution.
'lhc LPZ values werc revised in calculation 13-NC-ZY-205, Revision 3, dated February 2, 1996, as a result of the indusion of a previously inadvertently omitted XQ value. See APS Letter No. 10243620, dated March 7, 1996.
I 0 I II
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PVNGS UPDATED FSAR DECREASE ZN REACTOR COOLANT INVENTORY Table 15.6.5-2 RADXOLOG1CAL CONSEQUENCES OF A LARGE BREAK LOCA Thyroid Whole Body Beta Skin Dose Dose Dose Dose (rem) (rem) (rem)
Exclusion area boundary 2-hour consequence Power access purge 2.3 2.2 x 10 Containment leakage and secondary release C'3 0.3 Recirculation leakag (~>
Total Izz.'B ~ 3.98 Low population zone 30-day consequence e Power access purge 0. 4'S.
3.6 x 10-4 g
Containment leakage and secondary release
- 3. o Recirculation leakage@-l /8b 5 CQ x 10-4 Total Control room, 30-day consequence(>)
Containment leakage /.V.7 Z9.4 and secondary release. 7'.7 Recirculation x 10-6 jeakag~(e)
Total l7. 2- l.97> Z9. b7
- a. Assumes no credit for non-ESF filtration or for spray removal of particulates or organic iodines.
- b. Direct dose from fission products in containment atmosphere is less than 0.05 rem, neglecting credit for sprays.
C,. Co<krib~*on.frbM ZN 9 I Sk to~(Ukeh.
(2)
March 1994 15.6-73 Revision 6
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