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{{#Wiki_filter:ATTACHMENT2TOAEP'NRC'1213AEXISTINGTECHNICALSPECIFICATIONPAGESMARKEDTOREFLECTPROPOSEDCHANGES9510310312951020PDRADOCK05000315PPDR 0
34.7SYSTEMS347.TGRBTNECYCLESAFETYVALVESNGCONDXTONFOROPERAON3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.ancC.v~lu~is>a~a.4With4reactorcoolantloopsandassociatesteamgeneratorsin'perationpandwithoneormoremainsteam1necodesafetyvalvesinop'arable,operation,naproceedprovidethatwithin4hours,eithertheinoperablerestoredtoOPlZstatus'rthePowerRangeNeutronFluxHighSetpointtripisreduced.perTable3.7-1;otherwise,beinae:-4e~HOTSTANDBYwithinthenext6hoursand.comply~~a@So%56cAAthAb.b.(Wi3reactorcoolantloopsandassociatedsteamgeneratorsinperation~andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operation4MGMMnayproceedprovidedgthatnirhin4honte,eitherthein'operable<~"+i~C~~s.restoredtoOPERABLEstatus~orthereactortripbreakersareopened;otherwise,bein~SHUTDOWNwithintheNext30hours.Hol-TheprovisionsofSpecification3.0.4arenotapp1.$cable.SURVEXLLANCEREUIREMENTS4.7.1.1.EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLE'naccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue~1Xwheneverfoundoutsidethe+1Ktolerance.qg~po,s-,~SogSq~Q~Otee~i~Wk>M.3~COOKNUCLEARPLANT-UNlT13/47-1~HENTNO.k@0,464
'TABLE3.7-lHAXlHUHALLOWABLEPOllERRAHGENEUTRONFLUXlllGIISETPOIHTMITllIHOPERAOLESTEAHEPIE~I'IKTEEEEPEPEIEWIE~HaxinemtiumberofInoperableSafetyValvesonAnOeratinSteamGeneratorHaximumAllowablePowerRangetleutronFluxilighSetpointPercentofRATEDTHERHALPOWER4I~~
/41VV<TheOPERABILITYofthemainsteamlinecodesafetyvalvesensureschatthesecondarysystempressurewillbelimitedcowt.thini.csdesignpressureof1085psigduringthemostsevereanticipatedsystemopera-tionalcransient.Themaximumrelievt.ngcapacityisassociatedwichacurbinetripfrom100%RATEDTHER.fALPOMERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosceambypasscothecondenser).Thespecifiedvalveli.ftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIofcheASMEBoi.lerandPressureCode,1971Edition.Thetotalrelievingcapacicyforallvalvesona11ofthe'steamli.nesis17,153,800lbs/hrwhichisapproximately121percentofthetocalsecondarysteamflowof14,120,000lbs/hrac100%RATEDTHERMALPOMER.Aminimumof2OPERABLEsafecyvalvesperoperabLesteamgeneratorensuresthatsufficientrelievt.ngcapacityi.savailableforcheallo~ableTHER.'iALPOWERrestri.ctioninTable3.7-1.STARTUPand/orPOMEROPERATIONinoperablewithinthelimitationsofofchereductioninsecondarysystembythereducedreactortripseccingschannels.Thereactortripsetpoincfollowingbases:isallowablewithsafetyaalvestheACTIONrequiremencsonthebasissteamflowandTHLq.KLPOt:ERrequiredofthePowerRangeNeutronFluxreductionsarederivedonthe.SPx(109)'XFor4loopoperaci.onQplam..a.Harkr8%here:SPreducedreacctripsetpoinj.npercencofRATEDTHERMALPOPERVmaximumnumberofinablesafecyval.vespersceamline<<1,2or3.X-Totalreli.ev'ngcapacityofalsafecyvalvespersteamline48,450lbs/hour.YNaxumrelievingcapacityofanyonesecyvalve57,690lbs/hour.(10PowerRangeNeutronFlux-HighTripSecpoincforloopoperaci.on.D.C.COOK-UNIT1B3/47-1AHENDHENTNO.120 Relacementtextfor3/4.7.1.1BasesHi<5=(100/Q)(4wpgZwhere:HiC=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Conversionfactor,947.82Q3tu/~SecMwtw,=MinimumtotalstcamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.h,,=HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.
34.7PLANTSYSTEMS34.7.1XNECYCLESFVALVESNGCONDONFOOPERAON3.7.1.1AllnsdnsteanlinecodesafetyvalvesssscclatedvdeheachsteangeneratorshallbeOPERABLE.APPLXCABXLXY:Modes1,2and3.~OTXON:moog'.CZ:Valve@o~a.Wi.th4reactorcoolantloopsandassociatesteamgeneratorsinoperationandwithoneormoremainsteam1necodesafetyvalvesinoperablL,operationmaproceedprovidedgthatwithin4hours,eithertheinoperablerestoredtoOPLEstatus>orthePowerRangeNeutronFluxHigh'ipetpoint'sreducedperTable3.7-1;otherwise,beinae-~~HOTSTANDBYwithinthenext6hoursand.Complot,40~clog~~4~ta4S.b.4Wi3reactorcoolantloopsandassociatedsteamgeneratorsin'perationyandwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operation~BOYImayproceedprovidedgthatwithin4hours,eitherthe'noperableV<QclS)oVC~o-kerestoredtoOPERABLEstatus/orthereactortripbreakersareopened;otherwise,beinCGASHUTDOWNwithinthe'ext30hours.HoT'-Theprovisions'fSpecification3.0.4arenotapplicable.SURVEXLLANCEREEMENTS4.7.1..1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvaluepl%wheneverfoundoutsidethe+1Ktolerance.~P~g,sy~gQQ~>Q,~~9.0.9o~VO+aPP4cab4~f~iceieiODE3.COOKNUCLEARPLANT-UNIT.23/47-1AMENDMENTNO.Sa,167 TABLE3-1LLOWABLEOWNGEEURONGHSETPOINTWITINOPERABLESESAFVALVESDURING4LOOPOPERA0MaximumNumberofInoperableSafetyValveso0eatnSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpointPercentoRATEDERMALPOWECOOKNUCLEARPLANT-UNIT23/CI.7-2 34.7PIANTSYSTEMSBASES34.7.1TURBINECYCLE34.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteamlinecodasafetyvalvesensureschacthesecondarysystempressurevillbelimitedtovithin110iofi,tsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationalczansient.Th>>maximumreueving'capacityisassociatedvithacuzbinetzipfrom100%RATEDTHERMALPOMERcoincidentvithanassumedlossofcondensezheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveltfcsettingsandrelievingcapacitiesareinaccordancevithcherequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.Thetotalrelievtngcapacityofallsafetyvalvesonallofthesteamlinesis17,153,800lbs/hrvhichisatleast105percentofthemaximumsecondarysteamflovrateat100%RATEDTHERMALPOVER.hminimumof2OPERABLEsafetyvalvespersteamgeneratorensuresthatsufficientrelievingcapacityisavailableforcheallovableTHERMALPOVERrestrictioninTable3.7-1.STARTUPand/orPOVKROPERATIONisallovablevichsafetyvalvesinoperablevithinthelimitacionsoftheACTIONrequirementsonthebasisofthereductioninsecondarysyscemsteamflovandTHERMALPOMrequt.redbythereducedreactortripsettingsofthePoverRangeNeutronFluxchannels.Thereactortripsetpotntreductionsarederivedonthefollovingbases:For4loopoperationWhere:SPreducedreactzipsecpointinperntofRATEDTHECALPOVER@pe~a.~hahVmaximumnumberofinope~safetyvalvespersteamlineXtotalrelievtncapacityofallstyvalvespezsteamlineinlbours4,2&8,450Ymaxrelievingcapacityofanyonesafealvelbs./hour857,6909PoverRangeNeutronFlux-HighTripSecpointfor4loopoperationCOOKNUCLEARPLANT-UNIT2B3/47-1AMENDMENTNO.Sl.134 Relacementtextfor3/4.7.1.1BasesHil=(100/Q)~(4)vh)Kwhere:Hi4=Safe@AnalysispowerrangehighneutronfluxsetpointinpercentQ=NomaalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Contortionfactor,947.82~Bto/SecMwtw,=MimmxmtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSI'openingpressureincludingtoleranceandaccumulation,asappropriate,inIb/sec.Forexample,iftheaazimumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasumnarionofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,exclaKagthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhm-thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMS'peratingprcssure,excludingthethreehighestcapacityMSSVs.h<<=HeateiivaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappepriateinBtu/IbmI4=Numb'floopsinplantThevaluesahalatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforjumentandchanneluncertaintiesby9%.Thisrcduccsthcmaximumplantoperatingpowerlevelsothatitisloserthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.
ATTACHMENT3TOAEP:NRC:1213APROPOSEDREVISEDTECHNICALSPECIFICATIONPAGES 3/4LIMITINGCONDlTIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITIONFOROPERATION3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.APPLICABILITY:MODES1,2and3.ACTION:aoMODES1&2:With4reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise,beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatementb.b.MODE3:Withaminimumof3reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s}atbrestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise,beinHOTSHUTDOWNwithinthenext30hours.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.1.1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.4.7.1.2TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3.COOKNUCLEARPLANT-UNIT1Page3/47-1AMENDMENT420,444,4' 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLEPOWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLESTEAMLINESAFETYVALVESDURING4LOOPOPERATIONMaximumNumberofInoperableSafetyValvesonAn0eratinSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)65.146.528.0COOKNUCLEARPLANT-UNIT1Page3/47-2 3/4.nBASES3/4.7PLANTSYSTE<MS3/4.7.1TURBINECYCLE3/4.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteamlinecodesafetyvalvesensuresthatthesecondarysystempressurewillbelimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationaltransient.Themaximumrelievingcapacityisassociatedwithaturbinetripfrom100%RATEDTHERMALPOWERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveliftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingofJ3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidetheJ1%tolerance.Thetotalrelievingcapacityforallvalvesonallofthesteamlinesis17,153,800lbs/hrwhichisapproximately121percentofthetotalsecondarysteamflowof14,120,000Ibs/hrat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvesperoperablesteamgeneratorensuresthatsufficientrelievingcapacityisavailablefortheallowableTHERMALPOWERrestrictioninTable3.7-1.STARTUPand/orPOWEROPERATIONisallowablewithsafetyvalvesinoperablewithinthelimitationsoftheACTIONrequirementsonthebasisofthereductioninsecondarysystemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.Thereactortripsetpointreductionsarederivedonthefollowingbases:ffso=iannfffi~r(4w&Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=K=hfNominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtConversionfactor,947.82~Btu/SecMwtMinimumtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.COOKNUCLEARPLANT-UNIT1PageB3/47-1AMENDMENT420
 
3/4'IMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITIONFOROPERATION3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.APPLICABILITY:MODES1,2and3.ACTION:MODES1&2:With4reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise,beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatementb.b.MODE3:Withaminimumof3reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise,beinHOTSHUTDOWNwithinthenext30hours.c.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.1.1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.4.7.1,2TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3.COOKNUCLEARPLANT-UNIT2Page3/47-1 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLEPOWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLESTEAMLINESAFETYVALVESDURING4LOOPOPERATIONMaximumNumberofInoperableSafetyValvesonAnyOperatingSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)61.643.926.2COOKNUCLEARPLANT-UNIT2Page3/47-2AMENDMENT 3/4'ASES3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLE3/4.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteainlinecodesafetyvalvesensuresthatthesecondarysystempressurewill'belimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationaltransient.Themaximumrelievingcapacityisassociatedwithaturbinetripfrom100%RATEDTHERMALPOWERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveliftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingof+3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.Thetotalrelievingcapacityofallsafetyvalvesonallofthesteamlinesis17,153,800lbs/hrwhichisatleast105percentofthemaximumsecondarysteamflowrateat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvespersteamgeneratorensuresthatsufficientrelievingcapacityisavailablefortheallowableTHERMALPOWERrestrictioninTable3.7-1.STARTUPand/orPOWEROPERATIONisallowablewithsafetyvalvesinoperablewithinthelimitationsoftheACTIONrequirementsonthebasisofthereductioninsecondarysystemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.Thereactortripsetpointreductionsarederivedonthefollowingbases:ffsto=taooft2t~r(4w&z)Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Conversionfactor,947.82~Bto/SecMwtw,=MinimumtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.h<<=HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.COOKNUCLEARPLANT-UNIT2PageB3/47-1AMENDMENT82,434 0I ATTACHMENT4TOAEP:NRC:1213AWESTINGHOUSENSAL94-001"OPERATIONATREDUCEDPOWERLEVELSWITHINOPERABLEMSSV'S" I
WestinghouseEnergySystemsBusinessUnitNUCLEARSAF1TYADVISORYLETTER'HISISANOTIHCATIONOFARECENTLYIDENTIFIEDPOTENTIALSAFETYISSUEPERTAININGTOBASICCOMPONENTS'UPPLIEDBYWESTINGHOUSE.THISINFORMATIONISBEINGPROVIDEDTOYOUSOTHATAREVIEWOFTHISISSUECANBECONDUCEDBYYOUTODETERMINEIFANYACTIONISREQUIRED.P.O.Box355,Pittsburgh,PA152304355
 
==Subject:==
OperationatReducedPowerLevelswithInoperableMSSVsNumbet:NSAL-944)01BasicComponent:LossofLoadfi'urbincTripAnalysisforPlantLicensingBasisDatesOII20$4Plants:SecEnclosedListSubstantialSafetyHazardorFailuretoComplyPursuantto10CFR21.21(a)TransferofInformationPursuantto10CFR21.21(b)AdvisoryInformationPursuantto10CFR21.21(c)(2)SUMMARYYesCiNotlYcs0Ycs0WestinghousehasidentifiedapotentialsafetyissueregardingplantoperationwithinTechnicalSpecificationTable3.7-1.Thisissuedoesnotrepresentasubstantialsafetyhazardforyourplantpursuantto10CFR21.However,thisissuedoesrepresentaconditionwhichmayimpactyourplant'slicensingbasis.ITable3.7-1allowsplantstooperatewithareducednumberofoperableMSSVsatareducedpowerlevel,asdeterminedbythehighneutronQuxtripsetpoint.ThcFSARlossofload/turbinetrip(LOIJIT)analysisfromfullpowerboundsthecasewhereailMSSVsareoperable.TheFSAR(LOLfIT)eventmaynotbeboundingfortheallowableoperatingconfigurationsofTable3.7-1sincethehighneutronfiuxtripsetpojnt,whichisidentifiedinTable3.7-1foracorrespondingnumberofinoperableMSSVs,maynotbelowenoughtoprecludeasecondarysideoverpressurizationcondition.Asaresult,thebasisforTable3.7-1maynotbesuQicienttoprecludeoveipressurizationofthesecondatysideofthesteamgenerator.'Therefore,itisrecommendedthatyoureviewtheenclosedinformationtodeterininethcapplicabilityofthisissuetoyourplant.Theenclosedinfortnationcontainsamoredetaileddescriptionoftheissueandidentifiessolutionsthatyoumaywishtopursuetoaddressthisissue.Thesesolutionsinclude,butarenotlimitedto,areevaluationoftheLOIJITanalysisand/orachangeto~TechnicalSpecificationTable3.7-1.Additionalinformation,ifrequired,maybeobtainedfromthcoriginator.Tclephonc412-3746460.Originator..W.FasnachtStrategicLicensingIssuesH.A.Scpp,Manager,StrategicLicensingIssuesa%418.wpf:1b412094
 
PlantsAffectedD.C.Cook1&2J.M.FarleyI&2Byron1&2BraidwoodI&2V.C.SummerIZion1&2ShearonHarrisIW.B.McGuireI&2CatawbaI&2BeaverValleyI&2TurkeyPoint3&4VogtleI&2IndianPoint2&3SeabrookIMillstone3DiabloCanyonI&2WolfCreekCallawayIComanchePeakI&2SouthTexasI&2SequoyahI&2NorthAnnaI&2WattsBarI&2Size,wellBKori1,2,3&4YonggwangI&2SalemI&2@%418.wpf:1b411994II 04 IssueDescritionWestinghousehasidentifiedadeficiencyinthebasisforTechnicalSpecification3.7.1.1.ThisTechnicalSpecificationallowstheplanttooperateatareducedpowerlevelwithareducednumberofoperableMainSteamSafetyValves(MSSVs).ThedeficiencyisintheassumptionthatthemaximumallowableinitialpowerlevelisalinearfunctionoftheavailableMSSVreliefcapacity.ThelinearfunctionisidentifiedintheBasesSectionforTechnicalSpecification3/4.7.1.1andisprovidedasfollows:Sp=(X)aO(V)x(i(e)XSP=Reducedreactortripsetpointin%ofRATEDTHERMALPOWERV=MaximumnumberofinoperablesafetyvalvespersteamlineX=Totalrelievingcapacityofallsafetyvalvespersteamlineinibm/hour(109)=MaximumrelievingcapacityofanyonesafetyvalveinIbm/hourPowerrangeneutronflux-hightripsetpointforallloopsinoperationUndercerfainconditionsandwithtypicalsafetyanalysisassumptions,aLossofLoad/DrrbineTriptransientfrompart-powerconditionsmayresultinoverpressurizationofthemainsteamsystemwhenoperWnginaccordancewiththisTechnicalSpecification.'Ihefollowingdiscussiondescribestheissueinmoredetailandprovidesrecommendedalternativesforaddressingtheissue.TechnicalEvaluation'IheLossofLoad/TurbineTrip(LOLGT)eventisanalyzedintheFSARtoshowthatcorepro~onmarginsaremaintained(DNBR),theRCSwillnotoverpressurize,andthemainsteamsystemwillnotoveipressurize.Theanalysisassumesanimmediatelossofsteamrelievingcapabilitythroughtheturbineandcoincidentlossofallmainfeedwater.Nocreditistakenforthedirectreactortriponturbinetrip,sincethistripwouldnotbeactuatedforthecaseofalossofsteamload.Rather,thetransientisterminatedbyareactortriponhighpressurizerpressure,overtemperatureAT,orlowsteamgeneratorwaterlevel.Secondarysideov'erpressureprotectionisprovidedbyactuationoftheMainSteamSafetyValves(MSSVs),whicharedesignedtorelieveatleastfullpowernominalsteamflow.'IlieanalysisverifiesthattheMSSVcapacityissufficienttopreventsecondarysidepressurefimm.exceeding110percentofthedesignpressure.0%418.vq>f:tb411994
 
TheFSARonlyanalyzestheLOIJITtransientGomtheMpowerinitialcondition,withcasesexaminingtheeffectsofassumingprimarysidepressurecontrolanddifferentreactivityfeedbackconditions.WithfullyoperationalMSSVs,itcanbedemonstratedthatoverpressureprotectionisprovidedforallinitialpowerlevels.However,formostplants,TechnicalSpecification3.7.1.1allowsoperationwithareducednumberofoperableMSSVsatareducedpowerlevelasdeterminedbyresettingthepowerrangehighneutronfiuxsetpoint.ThisTechnicalSpecificationisnotbasedonadetailedanalysis,butratherontheassumptionthatthemaximumallowableinitialpowerlevelisalinearfunctionoftheavailableMSSVreliefcapacity.Recently,ithasbeendeterminedthatthisassumptionisnotvalid.'Iheproblemisthatifmainfeedwaterislost,areactortripisnecessarytopreventsecondarysideoverpressurizationforallpostulatedcoreconditions.Athighinitialpowerlevelsareactortripisactuatedearlyinthetransientas.aresultofeitherhighpressurizerpressureorovertemperaturehT.ThereactortripterminatesthetransientandtheMSSVsmaintainsteampressurebelow110%ofthedesignvalue.Atlowerinitialpowerlevelsareactortripmaynotbeactuatedearlyinthetransient.AnovertempeiaturehTtripisn'tgeneratedsincethecorethermalmarginsareincreasedatlowerpowerlevels.Ahighpressurizerpressuretripisn'tgeneratediftheprimarypressurecontrolsystemsfunctionnormally.Thisresultsinalongertimeduringwhichprimaryheatistransferredtothesecondaryside.'Ihereactoreventually,tripsonlowsteamgeneratorwaterlevel,butthismaynotoccurbeforesteampressureexceeds110%ofthedesignvalueifoneormoreMSSVsareinoperableinaccordancewiththeTechnicalSpecification.DuetothewidevarietyofplantdesignfeaturesthatareimportanttotheLOIJITanalysis,itisdifficulttoperformagenericevaluationtoshowthattheissuedoesnotapplytocertainplants.ThefollowingkeyparametershaveasignificanteffectonthesecondarysidepressuretransientMSSVreliefcapacityModeratorTemperatureCoefficient(MTC)MarginbetweentheMSSVsetpressures(includingtolerance)andtheoverpressurelimitLow-lowsteamgeneratorwaterlevelreactortripsetpointSafetSinificanceTheTechnicalSpecificationsformostplantsallowoperationatareducedpowerlevelwithinoperableMSSVs.Fromalicensingbasisperspective,thisconditionmayresultinsecondarysideoverpressurizationintheeventofaLOIJITtransient.Thelicensingbasisforanticipatedoperationaloccurrences(ANSConditionIIevents)typicallyrequiresthatthesecondarysideprcssureremainbelow110%ofthedesignvalue.a%418.wpf:Ib411994 Westinghousehasdeterminedthatthisissuedoesnotrepresentasubstantialsafetyhazard.Thereareseveralmitigatingfactorswhichprovideassurancethatthereisnolossofsafetyfunctiontotheexteatthatthereisamajorreductioninthedegreeofprotectionprovidedtothepublichealthandsafety.Theseinclude,butarenotlimitedto,thefollowing:1.AdequateoverpressureprotectionisprovidedatallpowerlevelsifalloftheMSSVsareoperable.2.Ifareactortripdoesnotoccurbutmainfeedwaterfiowismaintained,operationinaccordancewiththeTechnicalSpecificationTable3.7-1willnotresultinanoverpressurecondition.3.InanyLOIJITtransient,theatmosphericsteamdumpvalvesand/orcondensersteamdumpvalvesactuatetorelieveenergyiromthesteamgeneratorspriortotheopeningoftheMSSVs,andcontinuetorelievesteamiftheMSSVsdoopen.Sinceitisnotasafety-gradefunction,steamdumpisnotassumedtooperateinthesafetyanalysis;however,inrealityitisthefirstlineofdefenseinprotectingthesecondarysystemagainstoverpressurizatioa.ItisveryimprobablethatallthesecompoaentswouldbeinoperablecoincidentwithinoperableMSSVs.4.EvennearthebeginningofcorelifewithapositiveorzeroMTC,theprimaryvolantheatupresultingfromthetransientwouldtendtodrivethehGCnegative,whichwould.reducethecorepoweraadheatinputtothecoolaat.Thiswouldresultin'alowerrequiredMSSVcapacitytopreventsecondaryovegressurization.ThesafetyanalysisdoesnotcreditthereductionofMTCduringthetransient.NRCAwarenessIReortabilitWestinghousehasnotnotifiedtheNRCofthisissue,baseduponthedeterminationthatitdoesaotrepresentasubstantialsafetyhazardpursuantto10CFR21.However,WestinghousewillsendacopyofthislettertotheNRCsincethisissueimpactsinformationcontainedinNUREG-1431,"StandardTechnicalSpecifications,WestinghousePlants".RecommendationsToaddressthisissue,thefollowingactionsmaybeconsidered:(1)ModifyTechaicalSpecificatioa3.7.1.1(orequivalent)andtheassociatedbasissuchthatthemaximumpowerlevelallowedforoperationwithinoperableMSSVsisbelowtheheatremovingcapabilityoftheoperableMSSVs.Aconservativewaytodothisistosetthepowerrangehighaeutmnfiuxsetpointtothispowerlevel,thusensuringthattheactualpowerlevelcannotexceed@%418.wpf:1b411994
 
~~thisvalue.Tocalculatethissetpoint,thegoverningequationistherelationshipq=mhh,whereqistheheatinputfmmtheprimaryside,misthesteamflowrateandhhistheheatofvaporizationatthesteamreliefpressure(assumingnosubcooledfecdwater).Thus,analgorithmforuscindefiningtherevisedTechnicalSpecificationtablesetpointvalueswouldbe:Hig=(100/Q)~(wPN)Kwhere:'ig=SafetyAnalysispowerrangehighneutronfluxsetpoint,percentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat),MwtK=Conversionfactor,947.82MwtwsMinimumtotalsteamlowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inib/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingprcssure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVsperstcamgeneratoristhreethenw,shouldbeasummationofthecapacityofthcoperableMSSVsatthehighestoperableMSSVoperatingprcssure,excludingthethreehighestcapacityMSSVs.h+=heatofvaporizationforstcamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,Btu/1bmN=NumberofloopsinplantThevaluescalculatedfromthisalgorithmmustthenbeadjustedlowerforuscinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertainties(typically9%power).Themaximumplantoperatingpowerlevelwouldthenbelowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.0%418.wpf:1b411994 kk
~y~0C~c.Itshouldbenotedthattheuscofthisequatioawillresolvetheissueideatifiedinthisletterbyeaablingyoutore~culateyourTechnicalSpecification3.7.1.1setpointswithoutfurthermodificationstothestructureoftheTcchnicalSpecification.There-calculatedsetpointsarelikelytobelowerthanthosecurrentlyallowedbytheTechaicalSpecification.However,youshouldbeawareofatleasttwoconscrvatismswiththeequationYoumaywishtoreviewtheseconservatismstoevaluatetheuseoftheequationrelativetoyourplantspecificoperatingobjectives.ItispossibletorelaxsomeoftheseconservatismsforuseintheTechnicalSpecificatioaHowever,relaxationoftheconservatismsarelikelytoresultinmoresignificantchangestothestructureoftheTechnicalSpccificatioaFirst,theaboveequatioa(andtheexistingTechaicalSpecification3.7.1.1)isconservativesinceitisbasedonthemaximumnumberofinoperableMSSVsperloop.Forexample,arepresentativefourloopplant,inaccordancewiththecurrentTechnicalSpecification,shouldreduce'heneutronfluxsetpointto87%ifithasuptooneinoperableMSSVoneachloop.Thismeansthattheplantshouldusethissetpointwhetherthereareone,two,threeorfourinoperableMSSVs,aslongasthereisonlyoneinoperableMSSVpcrloop.Thus,theexistingTechnicalSpecificationandtheaboveequationareconservativeandbounding.However,anyrelaxationofthisconservatismmustbeinterpretedwithcare.Thereasonisthatthesteamgeneratorsmustbeprotcctcd6'omanovcrpressurizationconditionduringalossofloadtransient.'I%ereareseveraleventsthatcouldleadtoalossofload,includingtheinadvertentclosureofoneorallMSIVs.TheaffectedsteamgeneratormusthaveasufficientnumberofoperableMSSVstoprotectitfromanoverpressurizatioacondition,iftheMSIV(orMSIVs)wasiaadvertentlyclosed.Anotherconservatismintheaboveequation(andtheexistingTechnicalSpecification3.7.1.1)isinwwhichistheminimumtotalsteamQowratecapabilityoftheoperableMSSVsonanyonesteamgenerator.ThisvalueisconservativesinceitassumesthatifoneormoreMSSVsareinoperableperloop,theinoperableMSSVsarethelargestcapacityMSSVs,regardlessofwhetherthelargestcapacityMSSVsorthesmallercapacityMSSVsareinoperable.TheassumptionhasbeenmadesothattheaboveequationisconsistentwiththecurrentstructureofTechnicalSpecification3.7.1.1.(2)Asanalternative,plant-specificLOIJITanalysescouldbeperformedtomaximizetheallowablepower.levelforagivennumberofinoperableMSSVs.Dependingonkeyspecificplantparameters,theseanalysesmaybeabletojustifythecoatinuedvalidityofthecurrentTechnicalSpecificatioa(3)Considermodifying,asrequired,theBasesSectionforTechaicalSpecification3/4.7.1.1sothat.itisconsistentwiththeplantsafetyanalysis.Thesafetyanalysiscriterionforpreventiagovciprcssurizationofthesecondarysideisthattheprcssuredoesnotexceed110%ofthedesignpessureforanticipatedtransients.However,inreviewingseveralplanttechaicalspecifications,a%418.wpf:tbsp11994 itwasnotedthatthebasesforsomeplantsstatethatthesafetyvalvesinsurethatthesecondarysystempressurewillbelimitedtowithin10Soreven100%%uoofdesignprcssure.Thisisnotconsistentwiththesafetyanalysisbasisandshouldberevisedtoindicate110%.@%418.vg)f:1b411994}}

Revision as of 04:24, 13 June 2018

Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV
ML17332A999
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/20/1995
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17332A998 List:
References
NUDOCS 9510310312
Download: ML17332A999 (34)


Text

ATTACHMENT2TOAEP'NRC'1213AEXISTINGTECHNICALSPECIFICATIONPAGESMARKEDTOREFLECTPROPOSEDCHANGES9510310312951020PDRADOCK05000315PPDR 0

34.7SYSTEMS347.TGRBTNECYCLESAFETYVALVESNGCONDXTONFOROPERAON3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.ancC.v~lu~is>a~a.4With4reactorcoolantloopsandassociatesteamgeneratorsin'perationpandwithoneormoremainsteam1necodesafetyvalvesinop'arable,operation,naproceedprovidethatwithin4hours,eithertheinoperablerestoredtoOPlZstatus'rthePowerRangeNeutronFluxHighSetpointtripisreduced.perTable3.7-1;otherwise,beinae:-4e~HOTSTANDBYwithinthenext6hoursand.comply~~a@So%56cAAthAb.b.(Wi3reactorcoolantloopsandassociatedsteamgeneratorsinperation~andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operation4MGMMnayproceedprovidedgthatnirhin4honte,eitherthein'operable<~"+i~C~~s.restoredtoOPERABLEstatus~orthereactortripbreakersareopened;otherwise,bein~SHUTDOWNwithintheNext30hours.Hol-TheprovisionsofSpecification3.0.4arenotapp1.$cable.SURVEXLLANCEREUIREMENTS4.7.1.1.EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLE'naccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue~1Xwheneverfoundoutsidethe+1Ktolerance.qg~po,s-,~SogSq~Q~Otee~i~Wk>M.3~COOKNUCLEARPLANT-UNlT13/47-1~HENTNO.k@0,464

'TABLE3.7-lHAXlHUHALLOWABLEPOllERRAHGENEUTRONFLUXlllGIISETPOIHTMITllIHOPERAOLESTEAHEPIE~I'IKTEEEEPEPEIEWIE~HaxinemtiumberofInoperableSafetyValvesonAnOeratinSteamGeneratorHaximumAllowablePowerRangetleutronFluxilighSetpointPercentofRATEDTHERHALPOWER4I~~

/41VV<TheOPERABILITYofthemainsteamlinecodesafetyvalvesensureschatthesecondarysystempressurewillbelimitedcowt.thini.csdesignpressureof1085psigduringthemostsevereanticipatedsystemopera-tionalcransient.Themaximumrelievt.ngcapacityisassociatedwichacurbinetripfrom100%RATEDTHER.fALPOMERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosceambypasscothecondenser).Thespecifiedvalveli.ftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIofcheASMEBoi.lerandPressureCode,1971Edition.Thetotalrelievingcapacicyforallvalvesona11ofthe'steamli.nesis17,153,800lbs/hrwhichisapproximately121percentofthetocalsecondarysteamflowof14,120,000lbs/hrac100%RATEDTHERMALPOMER.Aminimumof2OPERABLEsafecyvalvesperoperabLesteamgeneratorensuresthatsufficientrelievt.ngcapacityi.savailableforcheallo~ableTHER.'iALPOWERrestri.ctioninTable3.7-1.STARTUPand/orPOMEROPERATIONinoperablewithinthelimitationsofofchereductioninsecondarysystembythereducedreactortripseccingschannels.Thereactortripsetpoincfollowingbases:isallowablewithsafetyaalvestheACTIONrequiremencsonthebasissteamflowandTHLq.KLPOt:ERrequiredofthePowerRangeNeutronFluxreductionsarederivedonthe.SPx(109)'XFor4loopoperaci.onQplam..a.Harkr8%here:SPreducedreacctripsetpoinj.npercencofRATEDTHERMALPOPERVmaximumnumberofinablesafecyval.vespersceamline<<1,2or3.X-Totalreli.ev'ngcapacityofalsafecyvalvespersteamline48,450lbs/hour.YNaxumrelievingcapacityofanyonesecyvalve57,690lbs/hour.(10PowerRangeNeutronFlux-HighTripSecpoincforloopoperaci.on.D.C.COOK-UNIT1B3/47-1AHENDHENTNO.120 Relacementtextfor3/4.7.1.1BasesHi<5=(100/Q)(4wpgZwhere:HiC=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Conversionfactor,947.82Q3tu/~SecMwtw,=MinimumtotalstcamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.h,,=HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.

34.7PLANTSYSTEMS34.7.1XNECYCLESFVALVESNGCONDONFOOPERAON3.7.1.1AllnsdnsteanlinecodesafetyvalvesssscclatedvdeheachsteangeneratorshallbeOPERABLE.APPLXCABXLXY:Modes1,2and3.~OTXON:moog'.CZ:Valve@o~a.Wi.th4reactorcoolantloopsandassociatesteamgeneratorsinoperationandwithoneormoremainsteam1necodesafetyvalvesinoperablL,operationmaproceedprovidedgthatwithin4hours,eithertheinoperablerestoredtoOPLEstatus>orthePowerRangeNeutronFluxHigh'ipetpoint'sreducedperTable3.7-1;otherwise,beinae-~~HOTSTANDBYwithinthenext6hoursand.Complot,40~clog~~4~ta4S.b.4Wi3reactorcoolantloopsandassociatedsteamgeneratorsin'perationyandwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operation~BOYImayproceedprovidedgthatwithin4hours,eitherthe'noperableV<QclS)oVC~o-kerestoredtoOPERABLEstatus/orthereactortripbreakersareopened;otherwise,beinCGASHUTDOWNwithinthe'ext30hours.HoT'-Theprovisions'fSpecification3.0.4arenotapplicable.SURVEXLLANCEREEMENTS4.7.1..1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvaluepl%wheneverfoundoutsidethe+1Ktolerance.~P~g,sy~gQQ~>Q,~~9.0.9o~VO+aPP4cab4~f~iceieiODE3.COOKNUCLEARPLANT-UNIT.23/47-1AMENDMENTNO.Sa,167 TABLE3-1LLOWABLEOWNGEEURONGHSETPOINTWITINOPERABLESESAFVALVESDURING4LOOPOPERA0MaximumNumberofInoperableSafetyValveso0eatnSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpointPercentoRATEDERMALPOWECOOKNUCLEARPLANT-UNIT23/CI.7-2 34.7PIANTSYSTEMSBASES34.7.1TURBINECYCLE34.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteamlinecodasafetyvalvesensureschacthesecondarysystempressurevillbelimitedtovithin110iofi,tsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationalczansient.Th>>maximumreueving'capacityisassociatedvithacuzbinetzipfrom100%RATEDTHERMALPOMERcoincidentvithanassumedlossofcondensezheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveltfcsettingsandrelievingcapacitiesareinaccordancevithcherequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.Thetotalrelievtngcapacityofallsafetyvalvesonallofthesteamlinesis17,153,800lbs/hrvhichisatleast105percentofthemaximumsecondarysteamflovrateat100%RATEDTHERMALPOVER.hminimumof2OPERABLEsafetyvalvespersteamgeneratorensuresthatsufficientrelievingcapacityisavailableforcheallovableTHERMALPOVERrestrictioninTable3.7-1.STARTUPand/orPOVKROPERATIONisallovablevichsafetyvalvesinoperablevithinthelimitacionsoftheACTIONrequirementsonthebasisofthereductioninsecondarysyscemsteamflovandTHERMALPOMrequt.redbythereducedreactortripsettingsofthePoverRangeNeutronFluxchannels.Thereactortripsetpotntreductionsarederivedonthefollovingbases:For4loopoperationWhere:SPreducedreactzipsecpointinperntofRATEDTHECALPOVER@pe~a.~hahVmaximumnumberofinope~safetyvalvespersteamlineXtotalrelievtncapacityofallstyvalvespezsteamlineinlbours4,2&8,450Ymaxrelievingcapacityofanyonesafealvelbs./hour857,6909PoverRangeNeutronFlux-HighTripSecpointfor4loopoperationCOOKNUCLEARPLANT-UNIT2B3/47-1AMENDMENTNO.Sl.134 Relacementtextfor3/4.7.1.1BasesHil=(100/Q)~(4)vh)Kwhere:Hi4=Safe@AnalysispowerrangehighneutronfluxsetpointinpercentQ=NomaalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Contortionfactor,947.82~Bto/SecMwtw,=MimmxmtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSI'openingpressureincludingtoleranceandaccumulation,asappropriate,inIb/sec.Forexample,iftheaazimumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasumnarionofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,exclaKagthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhm-thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMS'peratingprcssure,excludingthethreehighestcapacityMSSVs.h<<=HeateiivaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappepriateinBtu/IbmI4=Numb'floopsinplantThevaluesahalatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforjumentandchanneluncertaintiesby9%.Thisrcduccsthcmaximumplantoperatingpowerlevelsothatitisloserthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.

ATTACHMENT3TOAEP:NRC:1213APROPOSEDREVISEDTECHNICALSPECIFICATIONPAGES 3/4LIMITINGCONDlTIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITIONFOROPERATION3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.APPLICABILITY:MODES1,2and3.ACTION:aoMODES1&2:With4reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise,beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatementb.b.MODE3:Withaminimumof3reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s}atbrestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise,beinHOTSHUTDOWNwithinthenext30hours.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.1.1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.4.7.1.2TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3.COOKNUCLEARPLANT-UNIT1Page3/47-1AMENDMENT420,444,4' 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLEPOWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLESTEAMLINESAFETYVALVESDURING4LOOPOPERATIONMaximumNumberofInoperableSafetyValvesonAn0eratinSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)65.146.528.0COOKNUCLEARPLANT-UNIT1Page3/47-2 3/4.nBASES3/4.7PLANTSYSTE<MS3/4.7.1TURBINECYCLE3/4.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteamlinecodesafetyvalvesensuresthatthesecondarysystempressurewillbelimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationaltransient.Themaximumrelievingcapacityisassociatedwithaturbinetripfrom100%RATEDTHERMALPOWERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveliftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingofJ3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidetheJ1%tolerance.Thetotalrelievingcapacityforallvalvesonallofthesteamlinesis17,153,800lbs/hrwhichisapproximately121percentofthetotalsecondarysteamflowof14,120,000Ibs/hrat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvesperoperablesteamgeneratorensuresthatsufficientrelievingcapacityisavailablefortheallowableTHERMALPOWERrestrictioninTable3.7-1.STARTUPand/orPOWEROPERATIONisallowablewithsafetyvalvesinoperablewithinthelimitationsoftheACTIONrequirementsonthebasisofthereductioninsecondarysystemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.Thereactortripsetpointreductionsarederivedonthefollowingbases:ffso=iannfffi~r(4w&Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=K=hfNominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtConversionfactor,947.82~Btu/SecMwtMinimumtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.COOKNUCLEARPLANT-UNIT1PageB3/47-1AMENDMENT420

3/4'IMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLESAFETYVALVESLIMITINGCONDITIONFOROPERATION3.7.1.1AllmainsteamlinecodesafetyvalvesassociatedwitheachsteamgeneratorshallbeOPERABLE.APPLICABILITY:MODES1,2and3.ACTION:MODES1&2:With4reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthePowerRangeNeutronFluxHighSetpointtripisreducedperTable3.7-1;otherwise,beinHOTSTANDBYwithinthenext6hoursandcomplywithactionstatementb.b.MODE3:Withaminimumof3reactorcoolantloopsandassociatedsteamgeneratorsinoperation,andwithoneormoremainsteamlinecodesafetyvalvesassociatedwithanoperatingloopinoperable,operationmayproceedprovidedthatwithin4hours,eithertheinoperablevalve(s)arerestoredtoOPERABLEstatus,orthereactortripbreakersareopened;otherwise,beinHOTSHUTDOWNwithinthenext30hours.c.TheprovisionsofSpecification3.0.4arenotapplicable.SURVEILLANCEREUIREMENTS4.7.1.1EachmainsteamlinecodesafetyvalveshallbedemonstratedOPERABLEinaccordancewithSpecification4.0.5andwithliftsettingsasshowninTable4.7-1.Thesafetyvalveshallberesettothenominalvalue+1%wheneverfoundoutsidethe+1%tolerance.4.7.1,2TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3.COOKNUCLEARPLANT-UNIT2Page3/47-1 3/4LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREMENTS3/4.7PLANTSYSTEMSTABLE3.7-1MAXIMUMALLOWABLEPOWERRANGENEUTRONFLUXHIGHSETPOINTWITHINOPERABLESTEAMLINESAFETYVALVESDURING4LOOPOPERATIONMaximumNumberofInoperableSafetyValvesonAnyOperatingSteamGeneratorMaximumAllowablePowerRangeNeutronFluxHighSetpoint(PercentofRATEDTHERMALPOWER)61.643.926.2COOKNUCLEARPLANT-UNIT2Page3/47-2AMENDMENT 3/4'ASES3/4.7PLANTSYSTEMS3/4.7.1TURBINECYCLE3/4.7.1.1SAFETYVALVESTheOPERABILITYofthemainsteainlinecodesafetyvalvesensuresthatthesecondarysystempressurewill'belimitedtowithin110%ofitsdesignpressureof1085psigduringthemostsevereanticipatedsystemoperationaltransient.Themaximumrelievingcapacityisassociatedwithaturbinetripfrom100%RATEDTHERMALPOWERcoincidentwithanassumedlossofcondenserheatsink(i.e.,nosteambypasstothecondenser).ThespecifiedvalveliftsettingsandrelievingcapacitiesareinaccordancewiththerequirementsofSectionIIIoftheASMEBoilerandPressureCode,1971Edition.ThesafetyvalveisOPERABLEwithaliftsettingof+3%aboutthenominalvalue.However,thesafetyvalveshallberesettothenominalvalueJ1%wheneverfoundoutsidethe+1%tolerance.Thetotalrelievingcapacityofallsafetyvalvesonallofthesteamlinesis17,153,800lbs/hrwhichisatleast105percentofthemaximumsecondarysteamflowrateat100%RATEDTHERMALPOWER.Aminimumof2OPERABLEsafetyvalvespersteamgeneratorensuresthatsufficientrelievingcapacityisavailablefortheallowableTHERMALPOWERrestrictioninTable3.7-1.STARTUPand/orPOWEROPERATIONisallowablewithsafetyvalvesinoperablewithinthelimitationsoftheACTIONrequirementsonthebasisofthereductioninsecondarysystemsteamflowandTHERMALPOWERrequiredbythereducedreactortripsettingsofthePowerRangeNeutronFluxchannels.Thereactortripsetpointreductionsarederivedonthefollowingbases:ffsto=taooft2t~r(4w&z)Kwhere:Hi4=SafetyAnalysispowerrangehighneutronfluxsetpointinpercentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat)inMwtK=Conversionfactor,947.82~Bto/SecMwtw,=MinimumtotalsteamflowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inlb/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVspersteamgeneratoristhree,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingpressure,excludingthethreehighestcapacityMSSVs.h<<=HeatofvaporizationforsteamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriateinBtu/ibm4=NumberofloopsinplantThevaluescalculatedfromthisalgorithmarethenadjustedlowerforuseinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertaintiesby9%.Thisreducesthemaximumplantoperatingpowerlevelsothatitislowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.COOKNUCLEARPLANT-UNIT2PageB3/47-1AMENDMENT82,434 0I ATTACHMENT4TOAEP:NRC:1213AWESTINGHOUSENSAL94-001"OPERATIONATREDUCEDPOWERLEVELSWITHINOPERABLEMSSV'S" I

WestinghouseEnergySystemsBusinessUnitNUCLEARSAF1TYADVISORYLETTER'HISISANOTIHCATIONOFARECENTLYIDENTIFIEDPOTENTIALSAFETYISSUEPERTAININGTOBASICCOMPONENTS'UPPLIEDBYWESTINGHOUSE.THISINFORMATIONISBEINGPROVIDEDTOYOUSOTHATAREVIEWOFTHISISSUECANBECONDUCEDBYYOUTODETERMINEIFANYACTIONISREQUIRED.P.O.Box355,Pittsburgh,PA152304355

Subject:

OperationatReducedPowerLevelswithInoperableMSSVsNumbet:NSAL-944)01BasicComponent:LossofLoadfi'urbincTripAnalysisforPlantLicensingBasisDatesOII20$4Plants:SecEnclosedListSubstantialSafetyHazardorFailuretoComplyPursuantto10CFR21.21(a)TransferofInformationPursuantto10CFR21.21(b)AdvisoryInformationPursuantto10CFR21.21(c)(2)SUMMARYYesCiNotlYcs0Ycs0WestinghousehasidentifiedapotentialsafetyissueregardingplantoperationwithinTechnicalSpecificationTable3.7-1.Thisissuedoesnotrepresentasubstantialsafetyhazardforyourplantpursuantto10CFR21.However,thisissuedoesrepresentaconditionwhichmayimpactyourplant'slicensingbasis.ITable3.7-1allowsplantstooperatewithareducednumberofoperableMSSVsatareducedpowerlevel,asdeterminedbythehighneutronQuxtripsetpoint.ThcFSARlossofload/turbinetrip(LOIJIT)analysisfromfullpowerboundsthecasewhereailMSSVsareoperable.TheFSAR(LOLfIT)eventmaynotbeboundingfortheallowableoperatingconfigurationsofTable3.7-1sincethehighneutronfiuxtripsetpojnt,whichisidentifiedinTable3.7-1foracorrespondingnumberofinoperableMSSVs,maynotbelowenoughtoprecludeasecondarysideoverpressurizationcondition.Asaresult,thebasisforTable3.7-1maynotbesuQicienttoprecludeoveipressurizationofthesecondatysideofthesteamgenerator.'Therefore,itisrecommendedthatyoureviewtheenclosedinformationtodeterininethcapplicabilityofthisissuetoyourplant.Theenclosedinfortnationcontainsamoredetaileddescriptionoftheissueandidentifiessolutionsthatyoumaywishtopursuetoaddressthisissue.Thesesolutionsinclude,butarenotlimitedto,areevaluationoftheLOIJITanalysisand/orachangeto~TechnicalSpecificationTable3.7-1.Additionalinformation,ifrequired,maybeobtainedfromthcoriginator.Tclephonc412-3746460.Originator..W.FasnachtStrategicLicensingIssuesH.A.Scpp,Manager,StrategicLicensingIssuesa%418.wpf:1b412094

PlantsAffectedD.C.Cook1&2J.M.FarleyI&2Byron1&2BraidwoodI&2V.C.SummerIZion1&2ShearonHarrisIW.B.McGuireI&2CatawbaI&2BeaverValleyI&2TurkeyPoint3&4VogtleI&2IndianPoint2&3SeabrookIMillstone3DiabloCanyonI&2WolfCreekCallawayIComanchePeakI&2SouthTexasI&2SequoyahI&2NorthAnnaI&2WattsBarI&2Size,wellBKori1,2,3&4YonggwangI&2SalemI&2@%418.wpf:1b411994II 04 IssueDescritionWestinghousehasidentifiedadeficiencyinthebasisforTechnicalSpecification3.7.1.1.ThisTechnicalSpecificationallowstheplanttooperateatareducedpowerlevelwithareducednumberofoperableMainSteamSafetyValves(MSSVs).ThedeficiencyisintheassumptionthatthemaximumallowableinitialpowerlevelisalinearfunctionoftheavailableMSSVreliefcapacity.ThelinearfunctionisidentifiedintheBasesSectionforTechnicalSpecification3/4.7.1.1andisprovidedasfollows:Sp=(X)aO(V)x(i(e)XSP=Reducedreactortripsetpointin%ofRATEDTHERMALPOWERV=MaximumnumberofinoperablesafetyvalvespersteamlineX=Totalrelievingcapacityofallsafetyvalvespersteamlineinibm/hour(109)=MaximumrelievingcapacityofanyonesafetyvalveinIbm/hourPowerrangeneutronflux-hightripsetpointforallloopsinoperationUndercerfainconditionsandwithtypicalsafetyanalysisassumptions,aLossofLoad/DrrbineTriptransientfrompart-powerconditionsmayresultinoverpressurizationofthemainsteamsystemwhenoperWnginaccordancewiththisTechnicalSpecification.'Ihefollowingdiscussiondescribestheissueinmoredetailandprovidesrecommendedalternativesforaddressingtheissue.TechnicalEvaluation'IheLossofLoad/TurbineTrip(LOLGT)eventisanalyzedintheFSARtoshowthatcorepro~onmarginsaremaintained(DNBR),theRCSwillnotoverpressurize,andthemainsteamsystemwillnotoveipressurize.Theanalysisassumesanimmediatelossofsteamrelievingcapabilitythroughtheturbineandcoincidentlossofallmainfeedwater.Nocreditistakenforthedirectreactortriponturbinetrip,sincethistripwouldnotbeactuatedforthecaseofalossofsteamload.Rather,thetransientisterminatedbyareactortriponhighpressurizerpressure,overtemperatureAT,orlowsteamgeneratorwaterlevel.Secondarysideov'erpressureprotectionisprovidedbyactuationoftheMainSteamSafetyValves(MSSVs),whicharedesignedtorelieveatleastfullpowernominalsteamflow.'IlieanalysisverifiesthattheMSSVcapacityissufficienttopreventsecondarysidepressurefimm.exceeding110percentofthedesignpressure.0%418.vq>f:tb411994

TheFSARonlyanalyzestheLOIJITtransientGomtheMpowerinitialcondition,withcasesexaminingtheeffectsofassumingprimarysidepressurecontrolanddifferentreactivityfeedbackconditions.WithfullyoperationalMSSVs,itcanbedemonstratedthatoverpressureprotectionisprovidedforallinitialpowerlevels.However,formostplants,TechnicalSpecification3.7.1.1allowsoperationwithareducednumberofoperableMSSVsatareducedpowerlevelasdeterminedbyresettingthepowerrangehighneutronfiuxsetpoint.ThisTechnicalSpecificationisnotbasedonadetailedanalysis,butratherontheassumptionthatthemaximumallowableinitialpowerlevelisalinearfunctionoftheavailableMSSVreliefcapacity.Recently,ithasbeendeterminedthatthisassumptionisnotvalid.'Iheproblemisthatifmainfeedwaterislost,areactortripisnecessarytopreventsecondarysideoverpressurizationforallpostulatedcoreconditions.Athighinitialpowerlevelsareactortripisactuatedearlyinthetransientas.aresultofeitherhighpressurizerpressureorovertemperaturehT.ThereactortripterminatesthetransientandtheMSSVsmaintainsteampressurebelow110%ofthedesignvalue.Atlowerinitialpowerlevelsareactortripmaynotbeactuatedearlyinthetransient.AnovertempeiaturehTtripisn'tgeneratedsincethecorethermalmarginsareincreasedatlowerpowerlevels.Ahighpressurizerpressuretripisn'tgeneratediftheprimarypressurecontrolsystemsfunctionnormally.Thisresultsinalongertimeduringwhichprimaryheatistransferredtothesecondaryside.'Ihereactoreventually,tripsonlowsteamgeneratorwaterlevel,butthismaynotoccurbeforesteampressureexceeds110%ofthedesignvalueifoneormoreMSSVsareinoperableinaccordancewiththeTechnicalSpecification.DuetothewidevarietyofplantdesignfeaturesthatareimportanttotheLOIJITanalysis,itisdifficulttoperformagenericevaluationtoshowthattheissuedoesnotapplytocertainplants.ThefollowingkeyparametershaveasignificanteffectonthesecondarysidepressuretransientMSSVreliefcapacityModeratorTemperatureCoefficient(MTC)MarginbetweentheMSSVsetpressures(includingtolerance)andtheoverpressurelimitLow-lowsteamgeneratorwaterlevelreactortripsetpointSafetSinificanceTheTechnicalSpecificationsformostplantsallowoperationatareducedpowerlevelwithinoperableMSSVs.Fromalicensingbasisperspective,thisconditionmayresultinsecondarysideoverpressurizationintheeventofaLOIJITtransient.Thelicensingbasisforanticipatedoperationaloccurrences(ANSConditionIIevents)typicallyrequiresthatthesecondarysideprcssureremainbelow110%ofthedesignvalue.a%418.wpf:Ib411994 Westinghousehasdeterminedthatthisissuedoesnotrepresentasubstantialsafetyhazard.Thereareseveralmitigatingfactorswhichprovideassurancethatthereisnolossofsafetyfunctiontotheexteatthatthereisamajorreductioninthedegreeofprotectionprovidedtothepublichealthandsafety.Theseinclude,butarenotlimitedto,thefollowing:1.AdequateoverpressureprotectionisprovidedatallpowerlevelsifalloftheMSSVsareoperable.2.Ifareactortripdoesnotoccurbutmainfeedwaterfiowismaintained,operationinaccordancewiththeTechnicalSpecificationTable3.7-1willnotresultinanoverpressurecondition.3.InanyLOIJITtransient,theatmosphericsteamdumpvalvesand/orcondensersteamdumpvalvesactuatetorelieveenergyiromthesteamgeneratorspriortotheopeningoftheMSSVs,andcontinuetorelievesteamiftheMSSVsdoopen.Sinceitisnotasafety-gradefunction,steamdumpisnotassumedtooperateinthesafetyanalysis;however,inrealityitisthefirstlineofdefenseinprotectingthesecondarysystemagainstoverpressurizatioa.ItisveryimprobablethatallthesecompoaentswouldbeinoperablecoincidentwithinoperableMSSVs.4.EvennearthebeginningofcorelifewithapositiveorzeroMTC,theprimaryvolantheatupresultingfromthetransientwouldtendtodrivethehGCnegative,whichwould.reducethecorepoweraadheatinputtothecoolaat.Thiswouldresultin'alowerrequiredMSSVcapacitytopreventsecondaryovegressurization.ThesafetyanalysisdoesnotcreditthereductionofMTCduringthetransient.NRCAwarenessIReortabilitWestinghousehasnotnotifiedtheNRCofthisissue,baseduponthedeterminationthatitdoesaotrepresentasubstantialsafetyhazardpursuantto10CFR21.However,WestinghousewillsendacopyofthislettertotheNRCsincethisissueimpactsinformationcontainedinNUREG-1431,"StandardTechnicalSpecifications,WestinghousePlants".RecommendationsToaddressthisissue,thefollowingactionsmaybeconsidered:(1)ModifyTechaicalSpecificatioa3.7.1.1(orequivalent)andtheassociatedbasissuchthatthemaximumpowerlevelallowedforoperationwithinoperableMSSVsisbelowtheheatremovingcapabilityoftheoperableMSSVs.Aconservativewaytodothisistosetthepowerrangehighaeutmnfiuxsetpointtothispowerlevel,thusensuringthattheactualpowerlevelcannotexceed@%418.wpf:1b411994

~~thisvalue.Tocalculatethissetpoint,thegoverningequationistherelationshipq=mhh,whereqistheheatinputfmmtheprimaryside,misthesteamflowrateandhhistheheatofvaporizationatthesteamreliefpressure(assumingnosubcooledfecdwater).Thus,analgorithmforuscindefiningtherevisedTechnicalSpecificationtablesetpointvalueswouldbe:Hig=(100/Q)~(wPN)Kwhere:'ig=SafetyAnalysispowerrangehighneutronfluxsetpoint,percentQ=NominalNSSSpowerratingoftheplant(includingreactorcoolantpumpheat),MwtK=Conversionfactor,947.82MwtwsMinimumtotalsteamlowratecapabilityoftheoperableMSSVsonanyonesteamgeneratoratthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,inib/sec.Forexample,ifthemaximumnumberofinoperableMSSVsonanyonesteamgeneratorisone,thenw,shouldbeasummationofthecapacityoftheoperableMSSVsatthehighestoperableMSSVoperatingprcssure,excludingthehighestcapacityMSSV.IfthemaximumnumberofinoperableMSSVsperstcamgeneratoristhreethenw,shouldbeasummationofthecapacityofthcoperableMSSVsatthehighestoperableMSSVoperatingprcssure,excludingthethreehighestcapacityMSSVs.h+=heatofvaporizationforstcamatthehighestMSSVopeningpressureincludingtoleranceandaccumulation,asappropriate,Btu/1bmN=NumberofloopsinplantThevaluescalculatedfromthisalgorithmmustthenbeadjustedlowerforuscinTechnicalSpecification3.7.1.1toaccountforinstrumentandchanneluncertainties(typically9%power).Themaximumplantoperatingpowerlevelwouldthenbelowerthanthereactorprotectionsystemsetpointbyanappropriateoperatingmargin.0%418.wpf:1b411994 kk

~y~0C~c.Itshouldbenotedthattheuscofthisequatioawillresolvetheissueideatifiedinthisletterbyeaablingyoutore~culateyourTechnicalSpecification3.7.1.1setpointswithoutfurthermodificationstothestructureoftheTcchnicalSpecification.There-calculatedsetpointsarelikelytobelowerthanthosecurrentlyallowedbytheTechaicalSpecification.However,youshouldbeawareofatleasttwoconscrvatismswiththeequationYoumaywishtoreviewtheseconservatismstoevaluatetheuseoftheequationrelativetoyourplantspecificoperatingobjectives.ItispossibletorelaxsomeoftheseconservatismsforuseintheTechnicalSpecificatioaHowever,relaxationoftheconservatismsarelikelytoresultinmoresignificantchangestothestructureoftheTechnicalSpccificatioaFirst,theaboveequatioa(andtheexistingTechaicalSpecification3.7.1.1)isconservativesinceitisbasedonthemaximumnumberofinoperableMSSVsperloop.Forexample,arepresentativefourloopplant,inaccordancewiththecurrentTechnicalSpecification,shouldreduce'heneutronfluxsetpointto87%ifithasuptooneinoperableMSSVoneachloop.Thismeansthattheplantshouldusethissetpointwhetherthereareone,two,threeorfourinoperableMSSVs,aslongasthereisonlyoneinoperableMSSVpcrloop.Thus,theexistingTechnicalSpecificationandtheaboveequationareconservativeandbounding.However,anyrelaxationofthisconservatismmustbeinterpretedwithcare.Thereasonisthatthesteamgeneratorsmustbeprotcctcd6'omanovcrpressurizationconditionduringalossofloadtransient.'I%ereareseveraleventsthatcouldleadtoalossofload,includingtheinadvertentclosureofoneorallMSIVs.TheaffectedsteamgeneratormusthaveasufficientnumberofoperableMSSVstoprotectitfromanoverpressurizatioacondition,iftheMSIV(orMSIVs)wasiaadvertentlyclosed.Anotherconservatismintheaboveequation(andtheexistingTechnicalSpecification3.7.1.1)isinwwhichistheminimumtotalsteamQowratecapabilityoftheoperableMSSVsonanyonesteamgenerator.ThisvalueisconservativesinceitassumesthatifoneormoreMSSVsareinoperableperloop,theinoperableMSSVsarethelargestcapacityMSSVs,regardlessofwhetherthelargestcapacityMSSVsorthesmallercapacityMSSVsareinoperable.TheassumptionhasbeenmadesothattheaboveequationisconsistentwiththecurrentstructureofTechnicalSpecification3.7.1.1.(2)Asanalternative,plant-specificLOIJITanalysescouldbeperformedtomaximizetheallowablepower.levelforagivennumberofinoperableMSSVs.Dependingonkeyspecificplantparameters,theseanalysesmaybeabletojustifythecoatinuedvalidityofthecurrentTechnicalSpecificatioa(3)Considermodifying,asrequired,theBasesSectionforTechaicalSpecification3/4.7.1.1sothat.itisconsistentwiththeplantsafetyanalysis.Thesafetyanalysiscriterionforpreventiagovciprcssurizationofthesecondarysideisthattheprcssuredoesnotexceed110%ofthedesignpessureforanticipatedtransients.However,inreviewingseveralplanttechaicalspecifications,a%418.wpf:tbsp11994 itwasnotedthatthebasesforsomeplantsstatethatthesafetyvalvesinsurethatthesecondarysystempressurewillbelimitedtowithin10Soreven100%%uoofdesignprcssure.Thisisnotconsistentwiththesafetyanalysisbasisandshouldberevisedtoindicate110%.@%418.vg)f:1b411994