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| {{#Wiki_filter:CATEGORYj.REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)r~ACCESSION NBR:9603210226 DOC.DATE: | | {{#Wiki_filter:CATEGORY j.REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)r~ACCESSION NBR:9603210226 DOC.DATE: 96/03/3."5 NOTARIZED: |
| 96/03/3."5 NOTARIZED: | | NO''FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G!tAUTH.NAME AUTHOR AFFILIATiON MECREDY,R.C. |
| NO''FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G!tAUTH.NAME AUTHORAFFILIATiON MECREDY,R.C. | | Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
| Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardsapplication foramendtolicenseDPR-18,to incorporate methodology fordetermining LTOPlimitsintoAdministrative ControlsSection5.6.6,RCS PressureTempLimitsRept.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
| | Forwards application for amend to license DPR-18,to incorporate methodology for determining LTOP limits into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: |
| GeneralDistribution DOCKET05000244ENOTES:License Expdateinaccordance withlOCFR2,2.109(9/19/72).
| | General Distribution DOCKET 05000244 E NOTES:License Exp date in accordance with lOCFR2,2.109(9/19/72). |
| 05000244QRECIPIENT IDCODE/NAME PD1-1LAJOHNSON,A INTERNAL:
| | 05000244 Q RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A INTERNAL: p LE CE~l NRRQDR H HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D 0 U E N NOTE TO ALL"RIDS" RECIPIENTS: |
| pLECE~lNRRQDRHHICBNRR/DSSA/SRXB OGC/HDS3EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D"5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL ll I AND ROCHESTER GAS AND ElECTRIC CORPORA71ON |
| NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111D0UENNOTETOALL"RIDS"RECIPIENTS:
| | ~89 EASTAV&IUE, ROCHESTER, N.Y.146d9-0001 AREA CODE71rS$6-2700 ROBERT C.MECREDY Vice President Nvdeor operations March 15, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555 |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D"5(EXT.
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| 415-2083) | |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR12ENCLllI ANDROCHESTER GASANDElECTRICCORPORA71ON
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| ~89EASTAV&IUE, ROCHESTER, N.Y.146d9-0001 AREACODE71rS$6-2700ROBERTC.MECREDYVicePresident Nvdeoroperations March15,1996U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-3Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating LicenseImplementation ofGenericLetter96-03Rochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Application for Amendment to Facility Operating License Implementation of Generic Letter 96-03 Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==References:== | | ==References:== |
| | | (a)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, |
| (a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating License,Methodology forLowTemperature Overpressure Protection (LTOP)Limits,datedFebruary9,1996.(b)GenericLetter96-03,Relocation ofthePressureTemperature Li1nitCurvesandLoivTeniperature Overpressure Protection SystemLimits(c)LetterfromL.T.Marsh,NRC,toR.C.Mecredy,RG&E, | | Application for Amendment to Facility Operating License, Methodology for Low Temperature Overpressure Protection (LTOP)Limits, dated February 9, 1996.(b)Generic Letter 96-03, Relocation of the Pressure Temperature Li1nit Curves and Loiv Teniperature Overpressure Protection System Limits (c)Letter from L.T.Marsh, NRC, to R.C.Mecredy, RG&E, |
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| ==Subject:== | | ==Subject:== |
| RLr.Ginna-Acceptance forReferencing ofPressureTemperature LimitsReport(TACI/M92320), | | RLr.Ginna-Acceptance for Referencing of Pressure Temperature Limits Report (TAC I/M92320), dated December 26, 1995. |
| datedDecember26,1995.
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| ==DearMr.Johnson,== | | ==Dear Mr.Johnson,== |
| ByReference (a),RG&EproposedtorevisetheGinnaStationTechnical Specifications toincorporate themethodology fordetermining thelowtemperature overpressure protection (LTOP)limitsintoAdministrative ControlsSection5.6.6,RCSPressureandTemperature LimitsReport(PTLR).ThischangewouldallowRG&EtoperformfutureLTOPevaluations usingNRCapprovedmethodology withoutrequiring apotential technical specification change.However,anychangestotheRCSpressuretemperature (P/T)limits,whicharealsoincludedinthePTLR,wouldstillrequirepriorNRCreviewandapproval.
| | By Reference (a), RG&E proposed to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the low temperature overpressure protection (LTOP)limits into Administrative Controls Section 5.6.6, RCS Pressure and Temperature Limits Report (PTLR).This change would allow RG&E to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change.However, any changes to the RCS pressure temperature (P/T)limits, which are also included in the PTLR, would still require prior NRC review and approval.Incorporation of the methodology for the P/T limits was not requested at the time since the NRC's review of the latest reactor vessel capsule data (which would provide input into the P/T limit determination) was incomplete. |
| Incorporation ofthemethodology fortheP/Tlimitswasnotrequested atthetimesincetheNRC'sreviewofthelatestreactorvesselcapsuledata(whichwouldprovideinputintotheP/Tlimitdetermination) wasincomplete. | | 21AA c t"'tttrt032i0226 cst603i 5 PDR ADQCK 05000244 P PDR 0~lt gpss However, the NRC's review of the latest reactor vessel capsule data is nearing completion which would allow use of previously NRC approved methodology. |
| 21AAct"'tttrt032i0226 cst603i5PDRADQCK05000244PPDR 0~ltgpss However,theNRC'sreviewofthelatestreactorvesselcapsuledataisnearingcompletion whichwouldallowuseofpreviously NRCapprovedmethodology.
| | In addition, Generic Letter 96-03 (Ref.(b))has been released by the NRC.This generic letter provides guidance for licensees to relocate the P/T limits and LTOP limits from technical specifications and to provide a mechanism for licensees to make changes to the limits using NRC approved methodology. |
| Inaddition, GenericLetter96-03(Ref.(b))hasbeenreleasedbytheNRC.Thisgenericletterprovidesguidanceforlicensees torelocatetheP/TlimitsandLTOPlimitsfromtechnical specifications andtoprovideamechanism forlicensees tomakechangestothelimitsusingNRCapprovedmethodology.
| | RG8cE has previously relocated these limits;however, a license amendment is still required for all changes to the actual limits since the methodology for determining these limits has not been approved for future applications (Ref.(c)).As such, RGB is submitting this license amendment request (LAR)to incorporate the methodology for determining both LTOP limits and RCS P/T limits into Administrative Controls Section 5.6.6 consistent with Generic Letter 96-03.Therefore, this LAR supersedes that provided in Reference (a).Generic Letter 96-03 requests that licensees provide the following in their LAR: 1.Provide a reference to the NRC approved P/T limit and LTOP limit methodology in the technical specifications; 2.Develop a PTLR or similar document that contains the figures, values, parameters, and any explanations derived from the methodology; and 3.Provide other required changes to various technical specifications (e.g., definitions section)to support the relocation of the P/T and LTOP limits.The purpose of this LAR is to provide the reference to the P/T limit and LTOP limit methodology in the technical specifications (item 1).A PTLR has been previously developed as part of the conversion to improved standard technical specifications (Ref.(c)).However, the revised PTLR required to support use of the proposed methodology is dependant upon the input data which is used, including that derived from the latest reactor vessel capsule.Once the NRC's review of the reactor vessel capsule is complete, RG&:E will provide the revised PTLR using the proposed methodology. |
| RG8cEhaspreviously relocated theselimits;however,alicenseamendment isstillrequiredforallchangestotheactuallimitssincethemethodology fordetermining theselimitshasnotbeenapprovedforfutureapplications (Ref.(c)).Assuch,RGBissubmitting thislicenseamendment request(LAR)toincorporate themethodology fordetermining bothLTOPlimitsandRCSP/TlimitsintoAdministrative ControlsSection5.6.6consistent withGenericLetter96-03.Therefore, thisLARsupersedes thatprovidedinReference (a).GenericLetter96-03requeststhatlicensees providethefollowing intheirLAR:1.Provideareference totheNRCapprovedP/TlimitandLTOPlimitmethodology inthetechnical specifications; 2.DevelopaPTLRorsimilardocumentthatcontainsthefigures,values,parameters, andanyexplanations derivedfromthemethodology; and3.Provideotherrequiredchangestovarioustechnical specifications (e.g.,definitions section)tosupporttherelocation oftheP/TandLTOPlimits.ThepurposeofthisLARistoprovidethereference totheP/TlimitandLTOPlimitmethodology inthetechnical specifications (item1).APTLRhasbeenpreviously developed aspartoftheconversion toimprovedstandardtechnical specifications (Ref.(c)).However,therevisedPTLRrequiredtosupportuseoftheproposedmethodology isdependant upontheinputdatawhichisused,including thatderivedfromthelatestreactorvesselcapsule.OncetheNRC'sreviewofthereactorvesselcapsuleiscomplete, RG&:EwillprovidetherevisedPTLRusingtheproposedmethodology.
| | Therefore, item 2 is not being provided at this time.No other technical specification changes are required to implement Generic Letter 96-03 (item 3)since this was addressed during the conversion to the improved technical specifications. |
| Therefore, item2isnotbeingprovidedatthistime.Noothertechnical specification changesarerequiredtoimplement GenericLetter96-03(item3)sincethiswasaddressed duringtheconversion totheimprovedtechnical specifications. | | Following the NRC's review of the latest reactor vessel capsule data, it is anticipated that the P/T limits may not be valid for startup from the 1996 refueling outage.As such, RGkE requests NRC consideration of this LAR in order to support a planned startup date of May 30, 1996.To provide a necessary implementation period, RGB should receive NRC acceptance of this LAR by May 10, 1996.The revised PTLR using the proposed methodology will be submitted shortly after receipt of the NRC's review of the latest reactor vessel capsule in order to support this short schedule.Very truly yours, Robert C.Mecredy MDF>817 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Allen R.Johnson (Mail Stop 14B2)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr.F.William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253}} |
| Following theNRC'sreviewofthelatestreactorvesselcapsuledata,itisanticipated thattheP/Tlimitsmaynotbevalidforstartupfromthe1996refueling outage.Assuch,RGkErequestsNRCconsideration ofthisLARinordertosupportaplannedstartupdateofMay30,1996.Toprovideanecessary implementation period,RGBshouldreceiveNRCacceptance ofthisLARbyMay10,1996.TherevisedPTLRusingtheproposedmethodology willbesubmitted shortlyafterreceiptoftheNRC'sreviewofthelatestreactorvesselcapsuleinordertosupportthisshortschedule. | |
| Verytrulyyours,RobertC.Mecredy MDF>817Attachments xc:U.S.NuclearRegulatory Commission Mr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector Mr.F.WilliamValentine, President NewYorkStateEnergy,Research, andDevelopment Authority 2Rockefeller PlazaAlbany,NY12223-1253}}
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Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
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Text
CATEGORY j.REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)r~ACCESSION NBR:9603210226 DOC.DATE: 96/03/3."5 NOTARIZED:
NOFACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G!tAUTH.NAME AUTHOR AFFILIATiON MECREDY,R.C.
Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards application for amend to license DPR-18,to incorporate methodology for determining LTOP limits into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution DOCKET 05000244 E NOTES:License Exp date in accordance with lOCFR2,2.109(9/19/72).
05000244 Q RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A INTERNAL: p LE CE~l NRRQDR H HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D 0 U E N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D"5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL ll I AND ROCHESTER GAS AND ElECTRIC CORPORA71ON
~89 EASTAV&IUE, ROCHESTER, N.Y.146d9-0001 AREA CODE71rS$6-2700 ROBERT C.MECREDY Vice President Nvdeor operations March 15, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555
Subject:
Application for Amendment to Facility Operating License Implementation of Generic Letter 96-03 Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244
References:
(a)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Application for Amendment to Facility Operating License, Methodology for Low Temperature Overpressure Protection (LTOP)Limits, dated February 9, 1996.(b)Generic Letter 96-03, Relocation of the Pressure Temperature Li1nit Curves and Loiv Teniperature Overpressure Protection System Limits (c)Letter from L.T.Marsh, NRC, to R.C.Mecredy, RG&E,
Subject:
RLr.Ginna-Acceptance for Referencing of Pressure Temperature Limits Report (TAC I/M92320), dated December 26, 1995.
Dear Mr.Johnson,
By Reference (a), RG&E proposed to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the low temperature overpressure protection (LTOP)limits into Administrative Controls Section 5.6.6, RCS Pressure and Temperature Limits Report (PTLR).This change would allow RG&E to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change.However, any changes to the RCS pressure temperature (P/T)limits, which are also included in the PTLR, would still require prior NRC review and approval.Incorporation of the methodology for the P/T limits was not requested at the time since the NRC's review of the latest reactor vessel capsule data (which would provide input into the P/T limit determination) was incomplete.
21AA c t"'tttrt032i0226 cst603i 5 PDR ADQCK 05000244 P PDR 0~lt gpss However, the NRC's review of the latest reactor vessel capsule data is nearing completion which would allow use of previously NRC approved methodology.
In addition, Generic Letter 96-03 (Ref.(b))has been released by the NRC.This generic letter provides guidance for licensees to relocate the P/T limits and LTOP limits from technical specifications and to provide a mechanism for licensees to make changes to the limits using NRC approved methodology.
RG8cE has previously relocated these limits;however, a license amendment is still required for all changes to the actual limits since the methodology for determining these limits has not been approved for future applications (Ref.(c)).As such, RGB is submitting this license amendment request (LAR)to incorporate the methodology for determining both LTOP limits and RCS P/T limits into Administrative Controls Section 5.6.6 consistent with Generic Letter 96-03.Therefore, this LAR supersedes that provided in Reference (a).Generic Letter 96-03 requests that licensees provide the following in their LAR: 1.Provide a reference to the NRC approved P/T limit and LTOP limit methodology in the technical specifications; 2.Develop a PTLR or similar document that contains the figures, values, parameters, and any explanations derived from the methodology; and 3.Provide other required changes to various technical specifications (e.g., definitions section)to support the relocation of the P/T and LTOP limits.The purpose of this LAR is to provide the reference to the P/T limit and LTOP limit methodology in the technical specifications (item 1).A PTLR has been previously developed as part of the conversion to improved standard technical specifications (Ref.(c)).However, the revised PTLR required to support use of the proposed methodology is dependant upon the input data which is used, including that derived from the latest reactor vessel capsule.Once the NRC's review of the reactor vessel capsule is complete, RG&:E will provide the revised PTLR using the proposed methodology.
Therefore, item 2 is not being provided at this time.No other technical specification changes are required to implement Generic Letter 96-03 (item 3)since this was addressed during the conversion to the improved technical specifications.
Following the NRC's review of the latest reactor vessel capsule data, it is anticipated that the P/T limits may not be valid for startup from the 1996 refueling outage.As such, RGkE requests NRC consideration of this LAR in order to support a planned startup date of May 30, 1996.To provide a necessary implementation period, RGB should receive NRC acceptance of this LAR by May 10, 1996.The revised PTLR using the proposed methodology will be submitted shortly after receipt of the NRC's review of the latest reactor vessel capsule in order to support this short schedule.Very truly yours, Robert C.Mecredy MDF>817 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Allen R.Johnson (Mail Stop 14B2)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr.F.William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253
