ML17261B032

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Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp
ML17261B032
Person / Time
Site: Ginna 
Issue date: 03/28/1990
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To: JOHNSON A R
Office of Nuclear Reactor Regulation
References
NUDOCS 9004130169
Download: ML17261B032 (11)
v • d • e


Text

ACCELERATED DISTjUBUTION DEMONSHRATION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9004130169 DOC.DATE:

90/03/28NOTARIZED:

NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.

Rochester Gas6ElectricCorp.RECIP.NAME RECIPIENT AFFILIATXON JOHNSON,A.R.

.ProjectDirectorate I-3

SUBJECT:

ForwardsannualreptofECCSmodelrevsasapplicable tofacility,per 10CFR50.46.

DISTRXBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).

DOCKET0500024405000244.SRECIPIENT IDCODE/NAME PDl-3LAJOHNSON,A INTERNAL:

NRR/DET/ECMB 9HNRR/DST8E2NRR/DST/SXCB 7ENUDOCS-ABSTRACT OGC/HDS2RES/DSIR/EIB EXTERNAL:

LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENT IDCODE/NAME PD1-3PDNRR/DOEA/OTS B11NRR/DST/SELB 8DNRR/DST/SRXB 8EEMBREGLE01NRCPDRCOPIESLTTRENCL1"1111111101111ANDDPs9~<rmo7 RANOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTElCONTACTTHE.DOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROM'DISTRIBUTION LISISFORDOCUMENTS YOUDON'TNEEDITOTALNUMBEROFCOPIESREQUIRED:

LTTR21,ENCL19S A~fg4,hg'l>>~)VIAle~IPJkCcf1~)~<,iJi/(*-P'(IJlfl 0i)l/IIIIIIIIIIIIII lillllllE/I i/ANO/jjIIIII/jjjjjIIII SZZZuIl(liltiiZikll IIIIIII/ROCHESTER GASANDELECTRICCORPORATION o89EASTAVENUE,ROCHESTER, NY.14649.0001 March28,1990TELEPNONEAREACOOK7ld546-2700U.S.NuclearRegulatory Commission DocumentControlDeskAttn:Mr.AllenR.JohnsonPWRProjectDirectorate I-3Washington, D.C.20555

Subject:

10CFR50.46 AnnualReportECCSEvaluation ModelRevisions R.E.GinnaNuclearPowerPlantDocketNo.50-244

Reference:

1)NS-NRC-89-3463, "10CFR50.46 AnnualNotification for1989ofModifications intheWestinghouse ECCSEvaluation Models",LetterfromW.J.Johnson(Westinghouse) toT.E.Murley(NRC),Dated.October5,1989.2)NS-NRC-89-3464, "Correction ofErrorsandModifications totheNOTRUMPCodeintheWestinghouse SmallBreakLOCAECCSEvaluation ModelWhichArePotentially Significant",

LetterfromW.J.Johnson(Westinghouse) toT.E.Murley(NRC),DatedOctober5,1989.

DearMr.Johnson:

ThisletterprovidestheannualreportofEmergency CoreCoolingSystem(ECCS)modelrevisions astheyapplytoR.E.Ginna.ZnReferences 1)and2),Westinghouse ElectricCorporation providedinformation regarding modifications totheirECCSevaluation modelstoNRCStaff.References 1)and2)describethegenericeffectsofthemodelrevisions forbothlargeandsmallbreakLossOfCoolantAccidents (LOCA).Theattachment tothisletterprovidesinformation regarding theeffectsoftheECCSevaluation modelmodifications ontheGinnaUFSARChapter15.6.4LOCAanalysis.

Modifications tothemodelcausethelargebreakLOCAPeakCladTemperature (PCT)toincreaseby2Fto1889F.9004i30i69 90032SPDRADOCK05000244RPDCip'gget5/44'/

Modifications tothemodelforsmallbreakLOCAdonotaffectcalculated.

peakcladtemperature.

Verytrulyyours,RobertC.MecredyDivisionManagerNuclearPr'oduction RWEi088Enclosures xc:Mr.AllenR.Johnson(MailStop14D1)ProjectDirectorate I-3Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector ATT'O10CFR50.46ANNUALPORTEffectofWestinghouse ECCSEvaluation ModelModifications ontheLOCAAnalysisResultsFoundinChapter15.6.4oftheR.E.Ginna(RG&E)NuclearPowerPlantUpdated,FinalSafetyAnalysisReportand.WCAP-11609 Containing theSteamGenerator TubePluinReortforGinnaNuclearPowerStationTheOctober17,1988revisionto10CFR50.46 requiredapplicants andholdersofoperating licensesorconstruction permitstonotifytheNuclearRegulatory'ommission (NRC)oferrorsandchangesintheECCSEvaluation Modelsonanannualbasis,whentheerrorsandchangesarenot.significant.

Reference 1definesasignificant errororchangeasonewhichresultsinacalculated peakfuelcladdingtemperature differentbymorethan50'Ffromthetemperature calculated forthelimitingtransient usingthelastacceptable model,orisacumulation ofchangesanderrorssuchthatthesumoftheabsolutemagnitudes oftherespective temperature changesisgreaterthan50'F.InReferences 2and3,information regarding modifications totheWestinghouse largebreakandsmallbreakLOCAECCSEvaluation Modelswassubmitted totheNRC.Thefollowing presentsanassessment oftheeffectofthemodifications totheWestinghouse ECCSEvaluation ModelsontheLoss-Of-Coolant Accident(LOCA)analysesresultsfoundinWCAP-11609, "SteamGenerator TubePlugging(SGTP)ReportforGinnaNuclearPowerStation",

October1987andChapter15.6.4oftheR.E.Ginna(RG&E)NuclearPowerPlantUpdatedFinalSafetyAnalysisReport.LARGEBREAKLOCA-EVALUATION MODELCHANGESThelargebreakLOCAanalysisforR.E.Ginna(RG&E)wasexaminedtoassesstheeffectoftheapplicable modifications totheWestinghouse largebreakLOCAECCSEvaluation ModelonPeakCladdingTemperature (PCT)resultsreported.

inWCAP-11609.

TheLOCAsafetyanalysesreportedintheUFSARwereperformed forGinnawithauniformSteamGenerator TubePlugging(SGTP)levelof12'-o.Thelargebreakanalysiswassubsequently reanalyzed andlicensedfor15%tubepluggingand.theresultsweredocumented inWCAP-11609,"SteamGenerator TubePlugging(SGTP)ReportforGinnaNuclearPowerStation",

October1987.ThelargebreakLOCAanalysisresultswerecalculated.

usingthe1981versionoftheWestinghouse largebreakLOCAECCSEvaluation Modelwhichisdocumented inWCAP-9220-P-A (Reference 4).Thecurrentlicensing basisanalysisassumed.thefollowing information important tothelargebreakLOCAanalysisNSSSpowerlevel-102-oof1520MWtFuelType-,14X14OFAPelletEdgeConfiguration

-ChamferUniformSteamGenerator TubePluggingLevel-15%iNuclearPeakingFactorsof2.32fortheTotalPeakingFactorand1.66fortheEnthalpyRisePeakingFactor.

~~

r~~orR.E.Ginna(R),thelimitingbreakreslkedfromthedoubleended.guillotine ruptureofthecoldlegpipingwithadischarge coefficient ofCD=0.4.Thecalculated peakcladdingtemperature was1887'Fincluding theapplicable penalties.

ThePCTvalueof1887'Fincludesa6'enaltytoaccountforanupperplenuminjection and.acorecrossflow penalty'of 10'F.Thefollowing modifications totheWestinghouse ECCSEvaluation Modelwereevaluated todetermine iftheywouldaffectthecurrentlicensing basis-largebreakLOCAanalysisresultsforR.E.Ginnafor15%SGTPfound.'nWCAP-11609.

1981ECCSEvaluation Model:(NotMax-SILimited,)

Inthe1981versionoftheWestinghouse ECCSEvaluation Model,amodification wasmadetodelaydowncomer overfilling.

Thedelaycorresponds tobackfilling oftheintactcoldlegs.Datafromtestssimulating coldleginjection duringthepost-large breakLOCArefloodphasewhichhaveadequatesafetyinjection flowtocondenseallofthe-available steamflowshowasignificant amountofsubcooled.

liquidtobepresentinthecoldlegpipetestsection.Thissituation corresponds totheso-called maximumsafetyinjection scenarioofECCSEvaluation Modelanalyses.

TheR.E.Ginna(RGGE)LOCAanalysisperformed withtheWestinghouse 1981largebreakLOCAECCSEvaluation Modelisnotaffected.

bytheWREFLOODcodemodifications sincethemaximumsafeguards safetyinjection flowassumption isnotlimiting.

1981ECCSEvaluation Model.:(Two-Loop Plants)Inthe1981'version oftheWestinghouse ECCSEvaluation Model,thepressurizer ismodeledasbeingattachedtothebroken(faulted) loopintheSATAN-VIcodeforcalculating largebreakblowdownbehavior.

Sensitivity studieswereperformed todetermine ifthispressurizer locationinthenodingschemewasthemostlimitingposition.

Theresultsindicated thattwo-loopWestinghouse PWRsaresensitive'to thepressurizer nodallocationandthatinsomecasesmodelingthepressurizer intheintact(non-faulted) loopresulted.

inaslightincreaseinthecalculated PeakCladdingTemperature (PCT).Foratwoloopplant,corecoolingisprovidedbynegativecoreflowand.thenegativecoreflowperiod.laststhroughmostoftheremaining blowdownperiod;Theconcernregarding pressurizer locationrelatestothenegativecoreflowperiodwhichiscrucialforcorecoolinginatwo-loopplant.Withthepressurizer onthebrokenloop,pressurizer flowisalargecontributor tobreakflow(pumpside),lessening thecontribution fromtheupperplenumandleavingalargeupperplenuminventory fornegativecoreflowlaterinblowdown.

ForGinna,apenaltyof2'Fduetomodelingthepressurizer intheintact(non-faulted) loopwasassessedtobeusedintrackingmargintothe10CFR50.46 limitonthecurrentlicensing basisanalysisfor15-oSGTPcontained.

inWCAP-11609.

ThePCTforthelimitingC=0.4breakis1887'Fwithapplicable penalties, andthusaddingthe2'FincreasebringsthePCT,to1889'Fwhichiswellbelowthe10CFR50.46 limit.

ksdiscussed abovmodifications totheNestgghouse largebreakLOCAECCSEvaluation Modelcouldaffecttheresultbyalteringthe~PCT.A.AnalysisCalculated ResultB.Modifications toWestinghouse ECCSEvaluation ModelC.ECCSEvaluation ModelModifications Resultant PCT1887'F2oF1889FSMALLBREAKLOCA-EVALUATION MODELCHANGESThesmallbreak.LOCAanalysisforR.E.Ginna(RG&E)wasalsoexaminedtoassesstheeffectoftheapplicable modifications totheWestinghouse ECCSEvaluation ModelsonPeakCladdingTemperature (PCT)resultsreportedinChapter15.6.4.1oftheUFSAR.TheLOCAsafetyanalysesreportedintheUFSARwereperformed forGinnawithauniformSteamGenerator TubePlugging(SGTP)levelof12%.ThesmallbreakLOCAanalysiswassubsequently evaluated andlicensedforaSGTPlevelincreasefrom12:to15%.ThesmallbreakLOCAeventwasnotreanalyzed becausetheresultsarenotsensitive toaSGTPlevelincreasefrom12%to15:.Theevaluation wasdocumented, andtransmitted inWCAP-11609, "SteamGenerator TubePlugging(SGTP)ReportforGinnaNuclearPowerStation",

October1987.ThesmallbreakLOCAanalysisresultswerecalculated usingtheWestinghouse smallbreakLOCAECCSEvaluation Modeldocumented inWCAP-8970 (Reference 12)whichutilizedtheWFLASHcomputercode.ForR.E.Ginna(RG&E),thelimitingsizesmallbreakresultedfroma6inchequivalent diameterbreakinthecoldleg.Thecalculated peakcladdingtemperature was1092F.Theanalysisassumedthefollowing information important tothesmallbreakanalyses:

NSSSpowerlevel-102%of1520MWtFuelType-14Z14OFAPelletEdgeConfiguration

-ChamferUniformSteamGenerator TubePluggingLevel-12-oNuclearPeakingFactorsof2e32fortheTotalPeakingFactorand1.66fortheEnthalpyRisePeakingFactor.600GPMTotalAuziliary Feedwater Flow.Thefollowing modification totheWestinghouse ECCSEvaluation Modelwereevaluated todetermine iftheywouldaffectthecurrentlicensing basissmallbreakLOCAanalysisresultsforR.E.Ginna.WFLASHECCSEvaluation ModelFollowing theaccidentatThreeMileIslandUnit2,additional attention wasfocusedonthesmallbreakLOCAand.Westinghouse submitted areport,WCAP-9600 (Reference 5),totheNuclearRegulatory Commission (NRC)detailing theperformance oftheWestinghouse smallbreakLOCAEvaluation ModelwhichutilizedtheWFLASHcomputercode.InNUREG-0611 (Reference 6),theNRCstaffquestioned thevalidityofcertainmodelsintheWFLASH,computer

~t1'Vcodeandrequiredcenseestojustifycontinacceptance ofthemodel.SectionII.K.3.30 ofNUREG-0737 (Reference 7),whichclarified theNRCPost-TMIrequirements regarding smallbreakLOCAmodeling, requiredthatthelicensees revisethesmallbreakLOCAECCSmodelsalongtheguidelines specified inNUREG-0611.

Following theissuanceofNUREG-0737, Westinghouse andtheWestinghouse OwnersGroupdecidedtodeveloptheNOTRUMP(Reference 9)computercodeforuseinanewsmallbreakLOCAECCSEvaluation Model(Reference 10).TheNRCapprovedtheuseofNOTRUMPforsmallbreakLOCAECCSanalysesinMay1985.SinceapprovaloftheNOTRUMPsmallbreakLOCAECCSEvaluation Modelin1985,theWFLASHcomputercodehasnotbeenmaintained as.partoftheWestinghouse ECCSEvaluation Modelcomputercodes.InsectionII.K.3.31 ofNUREG-0737, theNRCrequiredthateachlicenseesubmitanewsmallbreakLOCAanalysisusinganNRCapprovedsmallbreakLOCAEvaluation Model.whichsatisfied therequirements ofNUREG-0737 sectionII.K.3.30.

NRCGenericLetter83-35(Reference 8)relaxedtherequirements ofItemII.K.3.31 byallowingamoregenericresponseandproviding abasisforretention oftheexistingsmall,breakLOCAanalyses.

Providedthatthepreviously existingmodelresultsweredemonstrated tobeconservative withrespecttothenewsmallbreakLOCAmodelapprovedundertherequirements ofNUREG-0737 II.K.3.30 (NOTRUMP),

plantspecificanalysesusingthenewsmallbreakLOCAEvaluation Modelwouldnotberequired.

InWCAP-11145 (Reference 11),Westinghouse andtheWestinghouse OwnersGroupdemonstrated thattheresult'sobtainedfromcalculations withWFLASHwereconservative relativetothoseobtained.

withNOTRUMP.Compliance withItemII.K.3.31 ofNUREG-0737 couldbecompleted byreferencing WCAP-11145 andsupplying someplantspecificinformation.

Westinghouse, therefore, hasnotbeenmodifying, investigating, orevaluating proposedchangestotheWFLASH.smallbreakLOCAECCSEvaluation Model.Asdiscussed above,noneofthemodifications totheWestinghouse smallbreakLOCAECCSEvaluation ModelwouldaffectthesmallbreakLOCAanalysisresultsbyalteringthePCT.A.AnalysisCalculated ResultB.Modifications toWestinghouse ECCSEvaluation ModelC.ECCSEvaluation ModelModifications Resultant PCT1092'F+0oF1092'FCONCLUSION Anevaluation oftheeffectofmodifications totheWestinghouse ECCSEvaluation ModelasreportedinReferences 2and3wasperformed forboththelargebreakLOCAandsmallbreakLOCAanalysesresultsfoundinWCAP-11609 andChapter15.6.4oftheR.E.GinnaNuclearPowerPlantUpdatedFinalSafetyAnalysisReport.TheLOCAsafetyanalysesreportedintheUFSARwereperformed forGinnawithauniformSteamGenerator TubePlugging(SGTP)levelof12-o.ThelargebreakLOCAanalysiswassubsequently reanalyzed andlicensedforanincreaseto15:tubeplugging.

ThesmallbreakLOCAanalysiswasevaluated andwasnotimpactedbytheincrease inSGTPlevelto.Theresultsoftheanaesandevaluations fortheincreasein.SGTPlevelto15-oweredocumented inWCAP-11609,"SteamGenerator TubePlugging(SGTP)ReportforGinna.NuclearPowerStation".

WhentheeffectsoftheECCSmodelchangeswerecombinedwiththecurrentplantanalysisresults,itwasdetermined thatcompliance withtherequirements of10CFR50.46 wouldbemaintained.

REFERENCES 2.3.4.5.6.7.8.9.10.12."Emergency CoreCoolingSystems;Revisions toAcceptance Criteria",

FederalRegister, Vol.53,No.180,pp.35996-36005,datedSeptember, 16,1988.NS-NRC-89-3463, "10CFR50.46 AnnualNotification for1989ofModifications intheWestinghouse ECCSEvaluation Models,"LetterfromW.J.Johnson(Westinghouse) toT.E.Murley(NRC),dated.October5,1989.NS-NRC-89-3464, "Correction ofErrors.and Modifications totheNOTRUMPCodeintheWestinghouse SmallBreakLOCAECCSEvaluation ModelWhichArePotentially Significant",

LetterfromW.J.Johnson(Westinghouse) toT.E.Murley(NRC),datedOctober5,1989.WCAP-9220-P-A, Revision1(Proprietary),

WCAP-9221-A, Revision1(Non-Proprietary),

"Westinghouse ECCSEvaluation Model1981Version",

1981,Eicheldinger, C.WCAP-10924-P-A (Proprietary),

WCAP-12130-A (Non-Proprietary),

"Westinghouse LargeBreakLOCABestEstimateMethodology",

Hochreiter, L.E.,et.al.,January1987.ReportonSmallBreakAccidents forWestinghouse NuclearSteamSupplySystem",WCAP-9601 (Non-Proprietary),

June1979,WCAP-9600(Proprietary),

June1979."GenericEvaluation ofFeedwater Transients andSmallBreakLoss-of-Coolant Accidents inWestinghouse DesignedOperating Plants",NUREG-0611, January1980."Clarification ofTMIActionPlanRequirements",

NUREG-0737, November1980."Clarification ofTMIPlanItemII.K.3.31, "NRCGenericLetter83-85fromD.G.Eisenhut, November2,1983."NOTRUMP-ANodalTransient SmallBreakandGeneralNetworkCode",WCAP-10079-P-A (Proprietary),

WCAP-10081-A (Non-'Proprietary),

Lee,N.,et.al.,August1985."Westinghouse SmallBreakECCSEvaluation ModelUsingtheNOTRUMPCode",WCAP-10054-P-A (Proprietary),

WCAP-10081-A (Non-Proprietary),

Lee,N.,et.al.,August1985.WCAP-8970 (Proprietary) andWCAP-8971 (Non-Proprietary),

"Westinghouse Emergency CoreCoolingSystemSmallBreakOctober1975Model",April1977.

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