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| {{#Wiki_filter:CATEGORYj.REGULATCIINFORMATIONDISTRIBUTIONSTEM(RIDE)r~ACCESSIONNBR:9603210226DOC.DATE:96/03/3."5NOTARIZED:NO''FACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterG!tAUTH.NAMEAUTHORAFFILIATiONMECREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONJOHNSON,A.R. | | {{#Wiki_filter:CATEGORYj.REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)r~ACCESSION NBR:9603210226 DOC.DATE: |
| | 96/03/3."5 NOTARIZED: |
| | NO''FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G!tAUTH.NAME AUTHORAFFILIATiON MECREDY,R.C. |
| | Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsapplicationforamendtolicenseDPR-18,toincorporatemethodologyfordeterminingLTOPlimitsintoAdministrativeControlsSection5.6.6,RCSPressureTempLimitsRept.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionDOCKET05000244ENOTES:LicenseExpdateinaccordancewithlOCFR2,2.109(9/19/72).05000244QRECIPIENTIDCODE/NAMEPD1-1LAJOHNSON,AINTERNAL:pLECE~lNRRQDRHHICBNRR/DSSA/SRXBOGC/HDS3EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD1-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL1111111111D0UENNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D"5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCLllI ANDROCHESTERGASANDElECTRICCORPORA71ON~89EASTAV&IUE,ROCHESTER,N.Y.146d9-0001AREACODE71rS$6-2700ROBERTC.MECREDYVicePresidentNvdeoroperationsMarch15,1996U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:AllenR.JohnsonProjectDirectorateI-3Washington,D.C.20555
| | Forwardsapplication foramendtolicenseDPR-18,to incorporate methodology fordetermining LTOPlimitsintoAdministrative ControlsSection5.6.6,RCS PressureTempLimitsRept.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: |
| | GeneralDistribution DOCKET05000244ENOTES:License Expdateinaccordance withlOCFR2,2.109(9/19/72). |
| | 05000244QRECIPIENT IDCODE/NAME PD1-1LAJOHNSON,A INTERNAL: |
| | pLECE~lNRRQDRHHICBNRR/DSSA/SRXB OGC/HDS3EXTERNAL: |
| | NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111D0UENNOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D"5(EXT. |
| | 415-2083) |
| | TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR12ENCLllI ANDROCHESTER GASANDElECTRICCORPORA71ON |
| | ~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:== |
| ApplicationforAmendmenttoFacilityOperatingLicenseImplementationofGenericLetter96-03RochesterGas&ElectricCorporationR.E.GinnaNuclearPowerPlantDocketNo.50-244
| | Application forAmendment toFacilityOperating LicenseImplementation ofGenericLetter96-03Rochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244 |
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| |
|
| ==References:== | | ==References:== |
| | |
| (a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | | (a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, |
|
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| ==Subject:== | | ==Subject:== |
| ApplicationforAmendmenttoFacilityOperatingLicense,MethodologyforLowTemperatureOverpressureProtection(LTOP)Limits,datedFebruary9,1996.(b)GenericLetter96-03,RelocationofthePressureTemperatureLi1nitCurvesandLoivTeniperatureOverpressureProtectionSystemLimits(c)LetterfromL.T.Marsh,NRC,toR.C.Mecredy,RG&E,
| | 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, |
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| ==Subject:== | | ==Subject:== |
| RLr.Ginna-AcceptanceforReferencingofPressureTemperatureLimitsReport(TACI/M92320),datedDecember26,1995. | | RLr.Ginna-Acceptance forReferencing ofPressureTemperature LimitsReport(TACI/M92320), |
| | datedDecember26,1995. |
|
| |
|
| ==DearMr.Johnson,== | | ==DearMr.Johnson,== |
| ByReference(a),RG&EproposedtorevisetheGinnaStationTechnicalSpecificationstoincorporatethemethodologyfordeterminingthelowtemperatureoverpressureprotection(LTOP)limitsintoAdministrativeControlsSection5.6.6,RCSPressureandTemperatureLimitsReport(PTLR).ThischangewouldallowRG&EtoperformfutureLTOPevaluationsusingNRCapprovedmethodologywithoutrequiringapotentialtechnicalspecificationchange.However,anychangestotheRCSpressuretemperature(P/T)limits,whicharealsoincludedinthePTLR,wouldstillrequirepriorNRCreviewandapproval.IncorporationofthemethodologyfortheP/TlimitswasnotrequestedatthetimesincetheNRC'sreviewofthelatestreactorvesselcapsuledata(whichwouldprovideinputintotheP/Tlimitdetermination)wasincomplete.21AAct"'tttrt032i0226cst603i5PDRADQCK05000244PPDR 0~ltgpss However,theNRC'sreviewofthelatestreactorvesselcapsuledataisnearingcompletionwhichwouldallowuseofpreviouslyNRCapprovedmethodology.Inaddition,GenericLetter96-03(Ref.(b))hasbeenreleasedbytheNRC.ThisgenericletterprovidesguidanceforlicenseestorelocatetheP/TlimitsandLTOPlimitsfromtechnicalspecificationsandtoprovideamechanismforlicenseestomakechangestothelimitsusingNRCapprovedmethodology.RG8cEhaspreviouslyrelocatedtheselimits;however,alicenseamendmentisstillrequiredforallchangestotheactuallimitssincethemethodologyfordeterminingtheselimitshasnotbeenapprovedforfutureapplications(Ref.(c)).Assuch,RGBissubmittingthislicenseamendmentrequest(LAR)toincorporatethemethodologyfordeterminingbothLTOPlimitsandRCSP/TlimitsintoAdministrativeControlsSection5.6.6consistentwithGenericLetter96-03.Therefore,thisLARsupersedesthatprovidedinReference(a).GenericLetter96-03requeststhatlicenseesprovidethefollowingintheirLAR:1.ProvideareferencetotheNRCapprovedP/TlimitandLTOPlimitmethodologyinthetechnicalspecifications;2.DevelopaPTLRorsimilardocumentthatcontainsthefigures,values,parameters,andanyexplanationsderivedfromthemethodology;and3.Provideotherrequiredchangestovarioustechnicalspecifications(e.g.,definitionssection)tosupporttherelocationoftheP/TandLTOPlimits.ThepurposeofthisLARistoprovidethereferencetotheP/TlimitandLTOPlimitmethodologyinthetechnicalspecifications(item1).APTLRhasbeenpreviouslydevelopedaspartoftheconversiontoimprovedstandardtechnicalspecifications(Ref.(c)).However,therevisedPTLRrequiredtosupportuseoftheproposedmethodologyisdependantupontheinputdatawhichisused,includingthatderivedfromthelatestreactorvesselcapsule.OncetheNRC'sreviewofthereactorvesselcapsuleiscomplete,RG&:EwillprovidetherevisedPTLRusingtheproposedmethodology.Therefore,item2isnotbeingprovidedatthistime.NoothertechnicalspecificationchangesarerequiredtoimplementGenericLetter96-03(item3)sincethiswasaddressedduringtheconversiontotheimprovedtechnicalspecifications.FollowingtheNRC'sreviewofthelatestreactorvesselcapsuledata,itisanticipatedthattheP/Tlimitsmaynotbevalidforstartupfromthe1996refuelingoutage.Assuch,RGkErequestsNRCconsiderationofthisLARinordertosupportaplannedstartupdateofMay30,1996.Toprovideanecessaryimplementationperiod,RGBshouldreceiveNRCacceptanceofthisLARbyMay10,1996.TherevisedPTLRusingtheproposedmethodologywillbesubmittedshortlyafterreceiptoftheNRC'sreviewofthelatestreactorvesselcapsuleinordertosupportthisshortschedule.Verytrulyyours,RobertC.Mecredy MDF>817Attachmentsxc:U.S.NuclearRegulatoryCommissionMr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspectorMr.F.WilliamValentine,PresidentNewYorkStateEnergy,Research,andDevelopmentAuthority2RockefellerPlazaAlbany,NY12223-1253}} | | 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. |
| | Incorporation ofthemethodology fortheP/Tlimitswasnotrequested atthetimesincetheNRC'sreviewofthelatestreactorvesselcapsuledata(whichwouldprovideinputintotheP/Tlimitdetermination) wasincomplete. |
| | 21AAct"'tttrt032i0226 cst603i5PDRADQCK05000244PPDR 0~ltgpss However,theNRC'sreviewofthelatestreactorvesselcapsuledataisnearingcompletion whichwouldallowuseofpreviously NRCapprovedmethodology. |
| | Inaddition, GenericLetter96-03(Ref.(b))hasbeenreleasedbytheNRC.Thisgenericletterprovidesguidanceforlicensees torelocatetheP/TlimitsandLTOPlimitsfromtechnical specifications andtoprovideamechanism forlicensees tomakechangestothelimitsusingNRCapprovedmethodology. |
| | 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, item2isnotbeingprovidedatthistime.Noothertechnical specification changesarerequiredtoimplement GenericLetter96-03(item3)sincethiswasaddressed duringtheconversion totheimprovedtechnical specifications. |
| | 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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1999-09-30
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ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
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
[Table view] |
Text
CATEGORYj.REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)r~ACCESSION NBR:9603210226 DOC.DATE:
96/03/3."5 NOTARIZED:
NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G!tAUTH.NAME AUTHORAFFILIATiON MECREDY,R.C.
Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwardsapplication foramendtolicenseDPR-18,to incorporate methodology fordetermining LTOPlimitsintoAdministrative ControlsSection5.6.6,RCS PressureTempLimitsRept.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
GeneralDistribution DOCKET05000244ENOTES:License Expdateinaccordance withlOCFR2,2.109(9/19/72).
05000244QRECIPIENT IDCODE/NAME PD1-1LAJOHNSON,A INTERNAL:
pLECE~lNRRQDRHHICBNRR/DSSA/SRXB OGC/HDS3EXTERNAL:
NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111D0UENNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D"5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR12ENCLllI ANDROCHESTER GASANDElECTRICCORPORA71ON
~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
Subject:
Application forAmendment toFacilityOperating LicenseImplementation ofGenericLetter96-03Rochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244
References:
(a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,
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,
Subject:
RLr.Ginna-Acceptance forReferencing ofPressureTemperature LimitsReport(TACI/M92320),
datedDecember26,1995.
DearMr.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.
Incorporation ofthemethodology fortheP/Tlimitswasnotrequested atthetimesincetheNRC'sreviewofthelatestreactorvesselcapsuledata(whichwouldprovideinputintotheP/Tlimitdetermination) wasincomplete.
21AAct"'tttrt032i0226 cst603i5PDRADQCK05000244PPDR 0~ltgpss However,theNRC'sreviewofthelatestreactorvesselcapsuledataisnearingcompletion whichwouldallowuseofpreviously NRCapprovedmethodology.
Inaddition, GenericLetter96-03(Ref.(b))hasbeenreleasedbytheNRC.Thisgenericletterprovidesguidanceforlicensees torelocatetheP/TlimitsandLTOPlimitsfromtechnical specifications andtoprovideamechanism forlicensees tomakechangestothelimitsusingNRCapprovedmethodology.
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, item2isnotbeingprovidedatthistime.Noothertechnical specification changesarerequiredtoimplement GenericLetter96-03(item3)sincethiswasaddressed duringtheconversion totheimprovedtechnical specifications.
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
