ML17264A866

Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements

ML17264A866
Person / Time
Site:	Ginna
Issue date:	04/24/1997
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A865	List: ML17264A863 ML17264A866 ML17264A867 ML17264A868
References
NUDOCS 9705020088
Download: ML17264A866 (18)

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UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPIICATIONFORAMENDMENT TPERATINGLICENEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RG&E),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatlicense,beamended.ThisrequestforchangeistorevisetheAdministrative ControlswithrespecttotheReactorCoolantSystem(RCS)RCSPressureandTemperature LimitsReporttomakethenecessary changesinorderplacethisdocumentunderlicenseecontrolandtorevisetheLTOPenabletemperature methodology.

Adescription oftheamendment request,necessary background information, justification oftherequested changes,andnosignificant hazardsandenvironmental considerations areprovidedinAttachment I.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

Theproposedchangesalsodonotinvolveasignificant hazardsconsideration.

'97050200SS 9704~+PDRADQCK05000244PPDR

AmarkedupcopyoftheGinnaStationTechnical Specifications whichshowtherequested changesissetforthinAttachment II.Theproposedrevisedtechnical specifications areprovidedinAttachment III.TherevisedPTLRisprovidedinAttachment IV.Attachment Vcontainsaredlinedversionofthelowtemperature overpressure protection (LTOP)setpointmethodology withrespecttothecurrently approvedversion.Attachment VIcontainsafinalversionoftheLTOPsetpointmethodology.

Attachment VIIcontainsthefirstuseoftheLTOPenabletemperature methodology whileAttachment VIIIcontainsacopyofWCAP-14684 asreferenced withinthePTLR.WHEREFORE, Applicant respectfully requeststhatFacilityOperating LicenseNo.DPR-18,andAttachment Atothatlicense,beamendedintheformattachedheretoasAttachment III.Rochester GasandElectricCorporation ByRobertC.MecredyVicePresident NuclearOperations Subscribed andsworntobeforemeonthis24thdayofApril1997.NotaryPublicDEBORAHA.PIPERNl NotaryPubiic)ntheStateofNewYorkONTARIOCOUNTYCouutuauon ExpiresNov.23,19.~

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Attachment IR.E.GinnaNuclearPowerPlantLicenseAmendment RequestRevisionofReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)Administrative ControlsRequirements Thisattachment providesadescription ofthelicenseamendment request(LAR)andthenecessary justifications tosupportarevisiontotheRCSpressureandtemperature (P/T)limitsandlowtemperature overpressure protection (LTOP)limitscontained inthePTLRasreferenced bytheAdministrative Controls.

Thisattachment isdividedintosixsectionsasfollows.SectionAsummarizes allchangestotheGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.

SectionCprovidesthejustifications associated withtheseproposedchanges.Anosignificant hazardsconsideration evaluation andenvironmental consideration oftherequested changestotheGinnaStationTechnical Specifications areprovidedinSectionsDandE,respectively.

SectionFlistsallreferences usedinthisattachment.

A.DESCRIPTION OFTECHNICAL SPECIFICATION CHANGESThisLARproposestorevisetheGinnaStationTechnical Specifications toreflectanewPTLRintheAdministrative Controlssection.Thechangeissummarized belowandshowninAttachment II,1.Administrative Controls5.6.6Itemcwillberevisedtoreplacethereference totheMay23,1996NRCletterwithanewreference thatapprovesthefirstuseofthePTLRmethodology includedasAttachment VItothisLAR.Inaddition, reference 1.isrevisedtoreference thisLARasthesourceforthePTLRmethodology whilereference 2.isrevisedtoreference thefinalNRCapprovedWCAP-14040-NP-A whichisthebasisforthenewP/Tcurves.Reference 3.isnolongerrequiredandistherefore deleted.Finally,atypographical errorinitemdiscorrected.

B.BACKGROUND Duringtheconversion toimprovedstandardtechnical specifications (ISTS)forGinnaStation,RG&EproposedtorelocatetheLTOPandRCSP/TlimitstothePTLR(Ref.1).Associated withthischangewastheadditionofareference totheAdministrative Controlssectionoftechnical specifications relatedtothePTLRdocumenting themethodology usedforallchangestotheselimits.However,theonlyNRCapprovedmethodology wouldbe"new"withrespecttodetermination ofboththeLTOPandRCSP/Tlimits.Duetotimeconstraints, RG&EinformedtheNRCthatuseofthisnewmethodology wouldbeburdensome andinstead,RG&Ewishedtoretaintheexistingvalues.TheNRCagreedwiththisconcernandallowedtheexistinglimitstoberelocated tothePTLRbutrequiredchangestotheselimitstobereviewedandapprovedbytheNRCasdocumented inReference 2.Subsequent totheconversion toISTS,theNRCcompleted itsreviewofthelatestreactorvesselcapsuledataandtheassociated impactonthepressurized thermalshockevaluation forGinnaStation(Ref.3).Incorporation ofthisinformation intothePTLRrequiredareassessment oftheP/TcurvesandLTOPsetpoints thatareincludedinthePTLR.However,thefluencefactormethodology usedfortheGinnaStationPTSevaluation wasanearlierversionthanthatrequiredbyWCAP-14040-NP-A (Ref.4)whichwastobethebasisfortheP/Tmethodology.

Sinceanupdateoftheassociated documents couldnotbecompleted inthetimeframerequiredtosupportstart-upfromthe1996refueling outage,theNRCapprovedaPTLRforuseatGinnaStationuntilDecember31,1996usinganestimated fluencefactorvalue(Ref.5).Subsequent tothis,whileattempting tocloseoutthefluencefactormethodologies, theNRCquestioned RG&E'sapproachfordetermining LTOPenabletemperature.

Specifically, theNRCidentified thatthedetermination oftheLTOPenabletemperature requiredconsideration ofRCSliquidtemperature measurement accuracyperthemethodology currently specified inSpecification 5.6.6.Uponfurtherevaluation, RG&Eagreedtoaddressthisconcernbyfirstsubmitting areliefrequest(Ref.6)andthenbyrequesting anexemption toregulations (Ref.7).Subsequently, theNRCidentified thattheliquidtemperature accuracyquestionshouldbeinsteadaddressed byanewLARwhichupdatedthemethodology inSpecification 5.6.6.ToallowRG&Esufficient timetoaddressthisissue,thePTLRexpiration datewaschangedtoJuly1,1997(Ref.8).

ThepurposeofthisLARistocompleteimplementation ofGenericLetter96-03forGinnaStationandtorespondtotheJuly1,1997timelimitontheexistingPTLR.GenericLetter96-03requiresthatlicensees reference theP/TandLTOPmethodologies inthetechnical specifications andprovideaproposedPTLRusingthemethodology forNRCreview.Sections1,2,and4ofWCAP-14040-NP-A (Ref.4)havebeengenerically approvedforusebytheNRCforP/TlimitsandisbeingproposedastheP/Tlimitmethodology.

ThecurrentLTOPmethodology forGinnaStation(Ref.1)replacedthatprovidedinSection3ofWCAP-14040 duetoRG&Especificissuesandwaspreviously reviewedbytheNRCandfoundtobeacceptable (Ref.5).However,theLTOPenabletemperature methodology isbeingrevisedtoclarifythespecificRCStemperature accuracyrequirements andallowtheuseofASMEXICodeCaseN-514.Aredlinedversionofthemethodology showingallchangesfromthepreviousNRCapprovedversionisprovidedinAttachment VwhileafinalversionisprovidedinAttachment VItothisLAR.Therefore, thisLARprovidesaproposedPTLR(andsupporting documentation asprovidedinWCAP-14684) andincludesareference toWCAP-14040-NP-A andthisLARintheAdministrative Controlsasthebasisforthemethodology.

Itshouldbenotedthat'venthoughthetechnical specifications donotrequirereactorvesselmaterialinformation tobelocatedwithinthePTLR,thisinformation isprovidedconsistent withGenericLetter96-03.ThisincludesarevisedRT~valuebasedontheattachedWCAP-14684.

TherevisedRT~valuealsoincludeschangesmadeasaresultofadditional surveillance capsulechemistry analyses.

C.JUSTIFICATION OFCHANGESThissectionprovidesthejustification forallchangesdescribed inSectionAaboveandshowninAttachment II.Thejustifications areorganized basedonwhetherthechangeis:morerestrictive (M),lessrestrictive (L),administrative (A),ortherequirement isrelocated (R).Thejustifications listedbelowarealsoreferenced inthetechnical specification(s) whichareaffected(seeAttachment II).C.1~dAdministrative ControlsSection5.6.6.cisrevisedtoreplacereference totheMay23,1996submittal withanewreference thatapprovesthefirstuseofthePTLRmethodology.

Inaddition, theAdminstrative Controlscontentisrevisedconsistent withGL96-03andthereferences forPTLRmethodology withrespecttoRCSP/Tlimitsisupdated.Thesechangesareadministrative innaturesincetheRCSP/Tlimitswerepreviously relocated fromtechnical specifications tothePTLR.Theonlychangebeingrequested istoupdatethePTLRconsistent withgenerically approvedWCAP-14040-NP-A usedintheAdministrative Controlssection.

Spe4 2.Atypographical errorinAdministrative ControlsSection5.6.6.discorrected toprovideconsistency withNUREG-1431.

C.2Administrative ControlsSection5.6.6.cisrevisedtoreplacethepreviously approvedLTOPmethodology (Ref.1)withthatprovidedinAttachment VI(Attachment Vprovidesa"red-line" comparison tothepreviously approvedmethodology toshowalldifferences).

TheproposednewLTOPmethodology allowstheLTOPenabletemperature tobedetermined usingASMESectionXICodeCaseN-514.ThiscodecaseallowstheLTOPenabletemperature tobethehigherof:(1)aRCStemperature of200'F,or(2)attheRCStemperature corresponding toareactorvesselmetaltemperature atthe1/4thickness fromtheinsidevesselsurfaceofRT~Y+50'F.Thisdiffersfromthecurrentspecified methodology thatwasbasedonBranchTechnical PositionRSB5-2whichrequiresusingaLTOPenabletemperature ofeither:(1)aRCStemperature of200F,or(2)attheRCStemperature corresponding toareactorvesselmetaltemperature atthe1/4thickness fromtheinsidevesselsurfaceofRT~~+90'F,whichever ofthetwoisgreater.Effectively reducingtheLTOPenabletemperature by40'Fisacceptable duetothemargininherentintheASMESectionXI,AppendixGcalculations usedinthedetermination oftheRT~~value.Thiswasrecognized byASMEintheirapprovalofCodeCaseN-514onFebruary12,1992andincorporating itintothe1993AddendatoASMECodeSectionXI,AppendixG.Instrument errormuststillbeaddressed whendetermining theRCStemperature corresponding totheRT>>~+50Fenabletemperature setpoint.

Therearenotanymorerestrictive (M),orrelocated (R)changesassociated withthisLAR.D.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications asidentified inSectionAandjustified inSectionChavebeenevaluated withrespectto10CFR50.92(c)andshowntonotinvolveasignificant hazardsconsideration asdescribed below.Thissectionisorganized basedonSectionCabove.

eht'~i",iC}t~l.aOh D.1EvaluinofAdminirativehanTheadministrative changesdiscussed inSectionC.1donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

TheproposedchangesreviseAdministrative ControlsSection5.6.6.ctoupdatethereference totheNRC'sapprovalofthefirstuseofthePTLRmethodology, updatetheRCSP/Tmethodology tothefinalNRCapprovedversion,andtocorrectatypographical error.Thesechangescompleteimplementation ofGenericLetter96-03byreferencing NRCapprovedmethodology withintheAdministrative Controls.

Assuch,thesechangesareadministrative innatureanddonotimpactinitiators oranalyzedeventsorassumedmitigation ofaccidentortransient events.Therefore, thesechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzed.

2.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent landofaccidentfromanyaccidentpreviously evaluated.

Theproposedchangesdonotinvolveaphysicalalteration oftheplant(i.e.,nonewordifferent typeofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation.

Theproposedchangeswillnotimposeanynewordifferent requirements.

Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Theproposedchangeswillnotreduceamarginofplantsafetybecausethemethodology havebeenshowntoensurethattheP/TandLTOPlimitsinthePTLRcontinuetomeetallnecessary requirements forreactorvesselintegrity.

Thesechangesareadministrative innaturesincethelimitswerepreviously relocated tothePTLRunderaseparateLAR.Assuch,noquestionofsafetyisinvolved, andthechangedoesnotinvolveasignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedadministrative changestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.

D.2vlinfRriivhnThelessrestrictive changesdiscussed inSectionC.2donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences of.anaccidentpreviously evaluated.

TheproposedchangerevisesAdministrative ControlsSection5.6.6toreplacetheLTOPenabletemperature methodology withuseofASMESectionXICodeCaseN-514.Thiscodecaseeffectively reducestheLTOPenabletemperature byupto40'Foverthecurrentmethodology.

However,asshowninSectionC.2,sufficient marginremainswithintheLTOPenabletemperature calculation toensurethatthereactorvesselremainsintactfollowing allanalyzedevents.Therefore, thesechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzed.

2.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Theproposedchangesdonotinvolveaphysicalalteration oftheplant(i.e.,nonewordifferent typeofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation.

Theproposedchangeswillnotimposeanynewordifferent requirements.

Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Theproposedchangeswillnotreduceamarginofplantsafetybecausethemethodology hasbeenshowntoensurethattheLTOPlimitsinthePTLRcontinuetomeetallnecessary requirements forreactorvesselintegrity.

TheASMECodespecifically recognizes thatCodeCaseN-514providesnecessary marginsuchthatthechangedoesnotinvolveasignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedlessrestrictive changetotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.

'Et\Ab E.ENVIRONMENTAL CONSIDERATION RG&Ehasevaluated theproposedchangesanddetermined that:1.Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionDabove;2.Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsitesincenospecifications relatedtooffsitereleasesareaffected; and3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincenonewordifferent typeofequipment arerequiredtobeinstalled asaresultofthisLAR.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).

Therefore, pursuantto10CFR51.22(b),

anenvironmental assessment oftheproposedchangesisnotrequired.

F.REFERENCES LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,

Subject:

Technical SpectJicationsImprovement Program,ReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR),datedDecember8,1995.2.LetterfromL.B.Marsh,NRC,toR.C.Mecredy,RG&E,

Subject:

R.E.Ginna-Acceptance forReferencing ofPressureTemperature LimitsReport(TACNo.M92320),datedDecember26,1995.3.LetterfromA.R.,Johnson, NRC,toR.C.Mecredy,RG&E,

Subject:

R.E.GinnaNuclearPowerPlant-Pressurized ThermalShockEvaluation (TACNo.M93827),datedMarch22,1996.4.WCAP-14040-NP-A, Methodology UsedtoDevelopColdOverpressure Mitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,January1996.5.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,

Subject:

IssuanceofAmendment No.64toFacilityOperating LicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.6.LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,

Subject:

RequesttoUseASMECodeCaseN-514intheDetermination ofLowTemperature Overpressure Protection (LTOP)EnableTemperature, datedDecember18,1996.

0 LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,

Subject:

RequestforExemption to10CFR50.60toUseAmericanSocietyofMechanical Engineers (ASME)CodeCaseN-514intheDetermination ofLowTemperature Overpressure Protection (LTOP)EnableTemperature, datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&E,Subject;R.E.Ginna-Acceptance ofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperature LimitsReport(PTLR)PACNo.M97313),datedDecember10,1996.-8-