ML17334B507

Submits Response to NRC 940422 Ltr,Supplying Sets of Summary Tables Containing Pressurized Thermal Shock & Upper Shelf Energy Info for Plant,Per GL 92-01

ML17334B507
Person / Time
Site:	Cook
Issue date:	05/20/1994
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	RUSSELL W T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1173C, GL-92-01, GL-92-1, TAC-M83453, TAC-M83454, NUDOCS 9405310207
Download: ML17334B507 (27)

Text

-ACCELERATEDDISTRIBUTIONDEMONSTIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)

SUBJECT:

SubmitsresponsetoNRC940422ltr,supplyingsetsofsummarytablescontainingpressurizedthermalshock6uppershelfenergyinfoforplant,perGL92-01.DSIZE.$0P~$tructuralIntegrity1/DISTRIBUTIONCODE:A028DCOPIESRECEIVED:LTRENCLTITLE:GenericLetter92-01Responses(ReactorVesselNOTES:RECIPIENTCOPIESIDCODE/NAMELTTRENCL"PD3-1PD11RECIPIENTIDCODE/NAMEHICKMAN,JCOPIESLTTRENCL22DACCESSIONNBR:9405310207DOC.DATE:94/05/20NOTARIZED:NODOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana!!'ichiganEleRECIP.NAMERECIPIENTAFFILIATIONRUSSELL,W.T.DocumentControlBranch(DocumentControlDesk)INTERNAL:NRR/DE/EMCBNRR/DRPE/PDI-1NUDOCS-ABSTRACTOGC/HDS2RES/DE/MEBEXTERNAL:NRCPDR221111101111NRR/DORS/OGCBNRR/DRPWOC/LPJ3CBM322hOlNSIC1111101111DDNOTETOALL"RIDS"RECIPIENTS:DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR15ENCL13 4IkII~a IndianaMichiganPowerCompanyP.O.Box16631Columbus,OH43216ÃIMEMSlMASNCMMWNPWMAEP:NRC:1173CDonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74RESPONSETOREQUESTFORVERIFICATIONOFINFORMATIONSUPPLIEDFORGENERICLETTER92-01,REVISION1(TACNOS.M83453andM83454)U.S,NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Attn:W.T.RussellMay20,1994

References:

1)NRCletterfromJohnB.HickmantoMr.E.E.Fitzpatrickdated,April22,1994.2)LetterNo.AEP:NRC:1173fromMr.E.E.FitzpatricktoT.E.Murley(NRC)dated,July13,1992.3)LetterNo.AEP:NRC:1173AfromMr.E.E.FitzpatricktoT.E.Murley(NRC)dated,November29,1993.4)LetterNo.AEP:NRC:1173BfromMr.E.E.FitzpatricktoT.E.Murley(NRC)dated,January24,1994.ThisletterissubmittedinresponsetoyourApril22,1994,letterwhichsuppliedtwosetsofsummarytablescontainingpressurizedthermalshock(PTS)anduppershelfenergy(USE)informationforeachoftheDonaldC.CookNuclearPlantUnits.ThosesummarytablesweredevelopedbyyourStaffbasedonourresponsestoGenericLetter(GL)92-01,Revision1,"ReactorVesselStructuralIntegrity",andonpreviouslydocketedinformation.Specifically,inyourApril22,1994letter,yourequestedthatweverifythattheinformationwesuppliedinresponsetoGL92-01,Revision1,hasbeenaccuratelyenteredinthesubjectsummarytables.QAgg~~J'i'4053i0207.'.940520'<<-'.,,',,gPDP'"ADGtK,05000315'P"'"-"--~:,.'"PDR',~

Mr.W.T.Russell-2AEP:NRC:1173CAsrequested,wehavereviewedandverified,withtheexceptionsnotedinEnclosure1tothisletter,theaccuracyofthePTSandUSEsummarytables.Forclarity,acopyofthePTSandUSEtables,annotatedwithourcomments,isincludedasEnclosure2tothisletter.Sincerely,~~E.E.FitzpatrickVicePresidentdrEnclosurescc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRC'ResidentInspectorJ.R.Padgett

<OSgi020)ENCLOSURE1TOAEP:NRC'1173CCOMMENTSONPRESSURIZEDTHERMALSHOCKANDUPPERSHELFENERGYSUMMARYTABLES Enclosure1toAEP:NRC:1173CPage1DonaldC.CookUnit1SummaryFileforPressurizedThermalShockThe32EFPY/EOLIDneutronfluenceof1.41xE19n/cm~ishighfornozzleshellplatesB4405-1,-2,and-3,andthenozzle/intermediateshellaxialandcircumferentialwelds1-442A/C,and8-442respectivelysincetheplatesandweldsarelocatedabovethecoreaffectedheight.TheDonaldC.CookUnit1IDneutronfluenceat32EFPY/EOLfortheabovementionedplatesandweldshasbeenestimatedbyWestinghouseat1.10xE18n/cm~.Westinghouseusedthe1.1xE18n/cm~fluencevalueindevelopingtheDonaldC.CookUnit1USEspresentedinWCAP-13587"ReactorVesselUpperShelfEnergyBoundingEvaluationforWestinghousePressurizedWaterReactors."WCAP-13587hasbeenreviewedbytheNRCOfficeofNuclearReactorRegulation,andisthesubjectoftheirsafetyassessment,datedApril21,1994(seeAttachment1toEnclosure1).Fortheaboveplatesandwelds,thevalueof1.41xE19shouldbereplacedwith1.10xE18.2.Asidentifiedonpage2-9oftheDonaldC.CookUnit1PTSevaluation,datedMarch1990(seeAttachment2toEnclosure1),the32EFPY/EOLIDneutronfluenceforthelongitudinalwelds2-442A/Cand3-442A/Cis0.95xE19n/cm~.TheUnit1PTSreportwasincludedasAttachment15totheGenericLetter92-01response,AEPletterNo.AEP:NRC:1173datedJuly13,1992.3.Asidentifiedonpage2-8oftheDonaldC.CookUnit1PTSevaluation,datedMarch1990(seeAttachment2toEnclosure1),thepercentCuforaxialwelds1-442A/C,2-442A/C,and3-442A/Candcircumferentialweld9-442isestimatedat0.28percent.Again,theUnit1PTSreportwasalsoincludedasAttachment15totheGenericLetter92-01response,AEPletterNo.AEP:NRC:1173datedJuly13,1992.The0.28percentCuvaluemaychangeasadditionalinformationbecomesavailable;however,thepercentCuvalueof.27shouldbereplacedwith.28fortheabovewelds.4,TheUnirradiatedUpperShelfEnergyvaluesarenotincludedinthePTSTable,andassuch,thefootnoteshouldberemoved.

I Enclosure1toAEP:NRC:1173CPage2DonaldC.CookUnit2SummaryFileforPressurizedThermalShock5.Asidentifiedonpage8oftheDonaldC.CookUnit2PTSevaluationdatedFebruary1993(seeAttachment3toEnclosure1),the32EFPY/EOLIDneutronfluenceforthelowershellplatesC5540-2andC5592-1is1.71xE19n/cm~.Fortheaboveplates,thevalueof1.71xE18shouldbereplacedwith1.71xE19.TheUnit2PTSevaluationwasnotincludedwiththeGenericLetter92-01response;however,itwassubmittedperAEPletterNo.AEP:NRC:0561FdatedApril12,1993.Asidentifiedonpage7oftheDonaldC.CookUnit2PTSevaluationdatedFebruary1993(Attachment3toEnclosure1),thepercentNivalueforintermediateshellplateC5556-2is0.57,thepercentCuvalueforintermediateshellplateC5521-2is0.125,andthepercentNicontentforlowershellplateC5592-1is0.59.TherespectivepercentCuandNivaluesfortheseplatesshouldbereplacedwiththevaluesspecifiedinthisparagraph.D.C.CookUnit1SummaryFileforUpperShelfEnergyThechangeinthepercentCucontentoftheaxialandlongitudinalwelds,identifiedinCommentNo.3,resultsintheneedfortheNRCtore-calculate1/4TUSEatEOL.Usingeitherthe0.27or0.28percentCuvalue,therevised1/4TUSEexceedstheminimumUSEEnergycriteriaof50FT-Lbs.ThepercentCuvaluesdonotappearintheUSETables,andassuchthefootnoteshouldberemoved.9.Itshouldbenotedthat,withthecorrectionoftheIDneutronfluencevaluesforthenozzleshellplatesandthenozzle/intermediateshellaxialandcircumferentialweldsasindicatedincommentNo.labove,the1/4TneutronfluenceatEOLshouldalsobere-calculatedbytheNRC.Westinghousehasdeterminedthatthe1/4TneutronfluencesatEOLforthenozzleshellplatesandthenozzle/intermediateshellaxialandcircumferentialweldsare5.77xE17n/cm~.

lA.~

~gAREJIGktt44$~~c4~eUNITEDSTATESNUCIFARREGULATORYCOMMISSIONygp,sHINGTON.D.C.2055~<gqp>1$Hr.WilliamH.RasinVicePresidentandDirectorTechnicalDivisionNuclearHanagementandResourcesCouncil1776EyeStreet,N.W.,Suite300Washington,DC20006-3706

SUBJECT:

SAFETYASSESSHENTOFREPORTWCAP-13587,REVISION1,"ReactorVesselUpperShelfEnergyBoundingEvaluationforWestinghousePressurizedWaterReactors,"September1993

DearHr.Rasin,

ByletterdatedHarch16,1993,theNuclearHanagementandResourcesCouncil(NUHARC)submittedareportpreparedbytheWestinghouseElectricCorporationfortheWestinghouseOwners'roup(WOG)entitled,"ReactorPressureVesselUpperShelfEnergyBoundingEvaluationForWestinghousePressurizedWaterReactors,"WCAP-13587,Revision0.ThereportwasprovidedtoNRCassupplementalinformationinresponsetoGenericLetter(GL)92-01.Noreviewandapprovalwasrequested.ThereportisintendedtodemonstratethroughfracturemechanicsanalysesthatthereexistmarginsofsafetyagainstfractureequivalenttothoserequiredbyAppendixGofASHECodeSectionIIIforbeltlinematerialshavinguppershelfenergy(USE)valuesbelowthescreeningcriteriaof50ft-lb.ByletterdatedJuly1,1993,theNRCissuedarequestforadditionalinformation(RAI)concerningthereport.ThereplytotheRAIwasreceivedbyNRConAugust20,1993andtheNRCwasnotifiedthatthereportwouldberevisedbasedontheRAI.WCAP-13587,Revision1,wassubsequentlysubmittedtoNRCthroughNUHARCbyletterdatedSeptember30,1993.TheHaterialsandChemicalEngineeringBranchhascompletedasafetyassessmentofRevision1ofthereport.Theenclosurecontainsthesafetyassessment.ThestafffindsthemethodologyemployedandtheanalysisperformedfortheWOGtobeacceptableexceptasnotedintheenclosure.ThereportdidnotcontainanequivalentmarginsanalysisbasedonweldmentpropertiesbecausetheWOGconcludedthatallofthebeltlineweldswouldbeabove50ft-lbatendoflicense(EOL).AspartoftheGL92-01review,thestaffwillbeevaluatingeachbeltlineweldfortheWOGplantstodetermineifthescreeningcriterionwillbemetatEOL.IndividuallicenseesdesiringtoreferenceWCAP13587,Revision1,asthebasisforaddressingtheUSErequirementsof10CFR50,AppendixGmustconfirmthespecificplantapplicabilitybyeitherdemonstratingthatallbeltlineweldswillhaveEOLCONTACT:E.Hackett,301-504-2751 USEabove50ft-lborthattheboundingplateusedinthereporthasalowerJ-Rcurvethananyotherbeltlinematerialinthevessel.Further,individual.licenseesmustrequestapprovalinaccordancewith10CFR50,AppendixG.Thestaffalsoconcludedthatcomparisonofappliedfracturedrivingforcewithmaterialfractureresistancewasoverlyconservativeforsomeofthecasesanalyzed.Thisissue.wasaddressedforalimitingplantspecificcasebyletterdatedDecember21,1993,andtheWOGispreparingarevisiontothereportwhichaddressesallofthecasesconsidered.'fyouhaveanyquestions,pleasecontactEdHackettofmystaffat301-504-2751.H.WayneHodges,ActingDirectorDivisionofEngineeringOfficeofNuclearReactorRegulation

Enclosure:

Asstated ENCLOSURESAFETYASSESSHENTBYTHEOFFICEOFNUCLEARREACTORREGULATIONREACTORVESSELUPPERSHFBOUNDINGEVALUATIONFORWESTINGHOUSEPRESSURIZEDMATERREACTORSMCAP-13587REVISION11.0REVIEWSUHHARYThestaffhasevaluatedtheequivalentmargihsanalysispresentedinreportMCAP-13587,Revision1,submittedbytheWestinghouseElectricCorporationfortheMestinghouseOwners'roup(WOG).ThestafffindsthemethodologyemployedandtheanalysisperformedfortheWOGtobeacceptableexceptasnotedherein.ThereportdidnotcontainanequivalentmarginsanalysisbasedonweldmentpropertiesbecausetheWOGconcludedthatallofthebeltlineweldswouldbeabove50ft-lbatendoflicense(EOL).AspartoftheGL92-01review,thestaffwillbeevaluatingeachbeltlineweldfortheWOGplantstodetermineifthescreeningcriterionwillbemetatEOL.IndividuallicenseesdesiringtoreferenceWCAP13587,Revision1,asthebasisforaddressingtheUSErequirementsof10CFR50,AppendixGmustconfirmthespecificplantapplicabilitybyeitherdemonstratingthatal.lbeltlineweldswillhaveEOLUSEabove50ft-lborthattheboundingplateusedinthetopicalreporthasalowerJ-Rcurvethananyotherbeltlinematerialinthevessel.Further,individuallicenseesmustrequestapprovalinaccordancewith10CFR50,AppendixG.Thestaffalsoconcludedthatcomparisonofappliedfracturedrivingforcewithmaterialfractureresistancewasoverlyconservativeforsomeofthecasesanalyzed.ThisissuewasaddressedforalimitingplantspecificcasebyletterdatedDecember21,1993[17],andtheMOGispreparingarevisiontothereportwhichaddressesallofthecasesconsidered.

2.0INTRODUCTION

ByletterdatedHarch16,1993,theNuclearManagementandResourcesCouncil(NUHARC)submittedareportpreparedbytheMestinghouseElectricCorporationfortheMOGentitled,"ReactorPressureVesselUpperShelfEnergyBoundingEvaluationforWestinghousePressurizedWaterReactors,"WCAP-13587,Revision0[1].ThereportwasprovidedtoNRCassupplementalinformationinresponsetoGL92-01[2].Noreviewandapprovalwasrequested.ThereportisintendedtodemonstratethroughfracturemechanicsanalysesthatthereexistmarginsofsafetyagainstfractureequivalenttothoserequiredbyAppendixGofASNECodeSectionIIIforbeltlinematerialshavingUSEvaluesbelowtheNRCscreeningcriteriaof50ft-lbin10CFR50,AppendixG.ByletterdatedJuly1,1993,theNRCissuedarequestforadditionalinformation(RAI)onthereport[3].ThereplytotheRAIwasreceivedbytheNRConAugust20,1993andtheNRCwasnotifiedthatthereportwouldberevisedbasedontheRAI.

WCAP-13587,Revision1[4],incorporatingtheresponsestotheRAI,wassubsequentlysubmittedtotheNRCthroughNUMARCbyletterdatedSeptember30,1993.3.0APPCARGUATORYRURMNTSANUIDNSRegulatoryrequirementsforuppershelfsafetymarginsarecontainedinAppendixGofTheCodeofFederalRegulations,Title10,Part50(10CFR50).AppendixGrequiresthattheinitialunirradiatedCharpyV-Notch(CVN)uppershelfenergyatthestartofvessellifebenolessthan75ft-lbandthatthevesselmaintainanuppershelfenergylevelofnolessthan50ft-lbthroughouttheservicelife.Ifitisanticipatedthatavesselmightfallbelow50ft-lbbeforeEOL,ananalysismustbesubmittedwhichdemonstrates"marginsofsafetyagainstfractureequivalenttothoserequiredbyAppendixGoftheASMECode."ThisanalysisissubjecttotheapprovaloftheDirector,OfficeofNuclearReactorRegulation.GuidelinesthatthestafffindsacceptableforconductingequivalentmarginsanalysesarecontainedinASMECodeCaseN-512[5]anddraftRegulatoryGuideDG-1023,"EvaluationofReactorVesselswithCharpyUpperShelfEnergylessthan50ft-lb"[6].DG-1023incorporatesthecriteriaofCodeCaseN-512and.providesadditionalguidanceonmaterialpropertiesandtransientselection.-DG-1023wasreleasedbyNRCforpubliccommentonOctober1,1993.NUREG/CR-.6023[7]presentstheresultsofgenericboundingequivalentmarginsanalysesconducted.accordingtoCodeCaseN-512guidelinesforbothPWRsandBWRs.Asthemajorityoflicenseesdonothavefracturetoughness"informationfortheirlimitingvesselmaterials,CVNdataistypicallyusedtoestimatethefracturetoughness.RegulatoryGuide1.99,Revision2[8]providesaprocedureforestimatingthedecreaseinCVNuppershelfenergyasafunctionofcoppercontentandfluence.NUREG/CR-5729[9]providesempiricallyderivedmodelsforpredictingmaterialfracturetoughness(J-Rcurves)fromCVNdataorchemicalcontentandfluence.TheNUREG/CR-5729modelsareapplicabletothemajorityofRPVmaterials.NRCBranchtechnicalpositionMTEB5-2[10]providescriteriaforestimatingtheCVNtoughnessforthetransverseorientationfromlongitudinaldataforplatematerials.The50ft-lbcriterionin10CFR50,AppendixGisforCVNdatafromtransverselyorientedspecimensinplateorforwelds.Thetransverseorientationinplatematerialhaslowerimpactpropertiesthanthelongitudinalorientation.Theimpactpropertiesoftheweldmetalarenotdifferentiatedbasedonorientation.4.DMILJPIITheWOGemployedtheproceduresandcriteriaofASMECodeCaseN-512[5]toperformtheequivalentmarginsanalysis.ForservicelevelsAandB,theWOGperformedananalysisforthelimitingnormaloperationcooldownrate(100'F/hr).TheanalysisisconsistentwiththeguidelinesprovidedinCodeCaseN-512[5]andDG-1023[6].InaccordancewithboththeCodeCaseandDraftRegulatoryGuide,theWOGassumedaquarterthicknessdepthflawforLevelsAandBandaflawdepthofupto1/10ofthebasemetalwallthickness

't pluscladdingforLevelsCandD.Theflawgeometryconsideredforallserviceconditionswasasemi-ellipticalsurfaceflawwitha6:1aspectratio.AquestionraisedintheRAI[3jconcernedtheissueofwhetherbothaxialandcircumferentialflawshadbeenaddressedasrequiredbytheCodeCase.TheresponsetotheRAIt3]citedthatbothcaseswereconsideredandtheappliedfracturedrivingforcefortheaxialflawswasinallcasesgreaterthanthose,forthecircumferentialflaws.Consequently,theaxialflawcaseswereconsideredlimiting.TheRPVbeltlinebasematerialscoveredbytheWOGincluded:(1)A302GradeA(Plate)(2)A302GradeB(Plate)(3)A533GradeB,Class1(Plate)(4)A508Class2(Forging)(5)A508Class3(Forging)TheRPVbeltlineweldscoveredbytheWOGincludethoseproducedusingthefollowingfluxes:(1)Linde1092(2)Linde1091,(3)Linde0091(4)Linde124(5)UH89(6)ARCOSB5(7)GrauLo(8)SMIT89Linde80weldmentswerenotincludedintheWOGreport.TheWOGmaintainsthat"weldmentsfabricatedwithfluxesotherthanLinde80willnotexhibitlessthan50ft-lbduringservice."WeldmentswillbediscussedfurtherinSection4.2.Table1providestheWOGoverallminimumacceptableUSEvaluesbyplanttype(2,3or4loop)fromtheequivalentmarginsanalysis.ThevaluesinTab'le1arebasedonfracturepropertiesforplateandforgingmaterials.NoanalysiswasperformedbasedonweldmentpropertiessincetheWOGmaintainsthatalloftheir'weldmentswillexceed50ft-lbatEOL~TheequivalentmarginsanalysiscomparedtheEOLUSEvalueforeachplantwiththeminimumacceptableUSEvaluesshowninTable1:TABLE1MinimumAcceptableUSEValuesFromWCAP13587,Revision1CASELOWESTUSEft-lb2Loo3Loo4Loo294243

~f~'~Iw.'heEOLUSEvaluesforeachplantweredeterminedinaccordancewiththemethodologyprovidedinRegulatoryGuide1.99,Revision2[8].Theadequacyoftheequivalentmarginsanalysiscanbedeterminedfromthefollowingconsiderations:(I)selectionofmechanicalproperties,(2)thedeterminationofpredictedEOLUSEvalue,(3)selectionofthemodelforgeneratingthefracturetoughnessdata(J-Rcurves),(4)selectionofthelimitingtransients,(5)thecalculationforappliedfracturedrivingforce(J,~~)and,(6)theboundingnatureoftheanalysis.4.IMechanicalProertiesPlantspecificvaluesoftensilemechanicalpropertiesforalloftheWOGvesselmaterialswererequestedintheRAI[3].TheWOGinsteadchosetoboundthemechanicalpropertiesforalloftheplantsbyusingtheASHECodeminimum.allowablemechanicalpropertiesat600'F.Thestress-straincurveusedintheequivalentmarginsanalysiswasgeneratedusingtypicaldataforcarbonsteelandthenadjustingthecurvetomatchtheASHECodeminimumvalues.Thestafffindsthismethodologytobeacceptable.4.2PredictedSglueInitialuppershelfenergyvaluesweredeterminedfrommaterialcertificationandsurveillancetestreports.GL92-01responseswerealsousedtoobtainsupplementalCVNdata.TheEOLUSEvalueswereestimatedusingtheRegulatoryGuide1.99,Revision2methodology[8].UsingthisapproachthreeplantswerefoundtohaveEOLUSEvaluesbelow50ft-lbasshowninTable2:TABLE2WOGPLantswithUSELessThan50ft-lbatEOLandComparisonwithMinimumAcceptableUSEValuesFromTheEquivalentHa'rginsAnalysisPLANTI.D.No.CASESHELLCOURSEHATERIALPREDICTEDEOLUSEft-lbMINIHUHACCEPTABLEUSEft-lb3Loo3LooLowerA302GrBIntermed.A302GrA42374LooUerA508Cl249434LooIntermed.A508Cl3Thelimitingmaterialforallthreeplantswaseitherplate(A302,A533)orforging(A508).AcomparisonofthepredictedEOLUSEvalueswiththeWOGminimumacceptableUSEvaluesinTable,I,showsthatthepredictedplantdataisequaltoorboundedbytheminimumacceptablevaluesforallthreeplants.Thesubjectreportalsonotedanadditionalcase(Plant16)whereEOLUSE.above50ft-lbwasnotdemonstratedforanA533Bplate.ItwasnotedbytheWOGthattheUSEvaluesfortheuppershellcourseofPlant16werebasedon-datafromunirradiatedlongitudinalspecimenswithlessthan100Kshear

6fractureindicatingthatthetestsdidnotrepresentfulluppershelfbehavior.ThelicenseeforPlant16hassubmittedanadditionalanalysisoftheCharpydatafortheirbeltlineplates[18j.ThissubmittalshowsthattheuppershellcourseplateswillachieveanEOLfluenceofonly4.85E+17n/cmandthereforethepercentdropinUSEwithirradiationislow(approximately10K).WiththesmallpredicteddropinUSEaninitialvalueofonly56ft-lbsisrequiredfortheuppershellcourseplatestoremainabove50ft-lbtoEOL.Thesubmittaldemonstratesthat,althoughfullshearperformancewasnotachievedintheCVNtestsfortwooftheuppershellcourseplates,theextrapolationtoanEOLUSEgreaterthan56ft-lbsforfullshelfperformanceisreasonable.Thestafffindsthisanalysistobeacceptable.AstheMOGdidnotprovidealistingwhichidentifiedtheWOGplantsandtheircorrespondingUSEdatabyname,confirmationoftheinputdata(chemistryandfluence)andcalculationsonaplant-by-plantbasiswasnotpossible.AsstatedpreviouslyinSection4.0,theWOGmaintainsthat"weldmentsfabricatedwithfluxesotherthanLinde80willnotexhibitlessthan50ft-lbduringservice."Table2-2inthesubjectreportconfirmsthisstatementbyshowingalistingwithinitialUSEandprojectedEOLUSEvalues~foreachplant.ThelowestEOLUSEvaluereportedwas50ft-lbforPlant17withARCOSB5flux.Aswasthecasewiththebasematerials,theWOGdidnotprovidealistingwhichidentifiedtheWOGplantsandtheircorrespondingUSEdatabyname.Therefore,confirmationoftheinputdata(chemistryandfluence)andcalculationsonaplant-by-plantbasiswasnotpossible.Further,sincetheminimumacceptable"SEvaluesfromtheequivalentmarginsana'Iysiswerebasedonfracturetoughnessdataforplateorforgingmaterials,thesevalueswillnotapplytoweldments.However,calculationsperformedforNUREG/CR-6023[7jwiththeLinde80weldmodelhaveshownaminimumacceptableUSEof41ft-lbforaPMR.Thestaffconsidersthat,whileweldmentsfortheWOGplantsarenotlikelytobelimitingforUSE,thesubjectreportdoesnotprovidesufficientinformationtomakethisdeterminationconclusively.AspartoftheGL92-01review,thestaffwillbeevaluatingeachbeltlineweldfortheWOGplantstodetermineifthescreeningcriterionwillbemetatEOL.4.3SelectionoftheFractureTouhnessJ-RCurveModelTheJ-RcurveinformationrequiredfortheequivalentmarginsanalysiswasgeneratedfromtheboundingEOLUSEvaluescalculatedforeachplantcategory(2loop,3loopand4loop).TheJ-RcurvesforRPVbasematerialswereobtainedfromCYNdatausingtheCharpymodelofNUREG/CR-5729[9).Asstatedpreviously,theWOGmaintainsthatalloftheWOGweldswillbeabove50ft-lbatEOLandthereforedidnotdevelopJ-Rdataforwelds.ForlevelsAand8theJ-Rcurvesforatemperatureof390.5'Fwereused.Thisvaluerepresentsthegreatesttemperatureatthecracktipduringthe100'F/Hr.cooldownfora1/4Tflawbasedonpeakstressresultsfroma2-Dfiniteelementanalysis.ForLevelsCandDthetemperaturesusedfortheJ-Rcurveswerefromtheappropriatetransients(intherangeof400'F-500'F).Thestafffinds,theapproachtodevelopingtheJ-RcurvedataforalloftheWOGbasematerialsto.beacceptablewiththeexceptionofthemethodusedforA302B.ForA3028plate,theWOGconsidersthe6TC(T)J-RcurvedataofNUREGCR/5265[ll]tobealowerboundfora50ft-lbA3028plate.TheMOGadjustedthe6Tdata forlowerUSEvaluesbydecreasingJ,<by3Xperft-lbofCVNenergy.ThisrateofdecreasecorrespondstoTeeratedeterminedfromtheCharpymodelofNUREG/CR-5729[9].Thestaffalsoconsiderthe6TA302BdataofNUREG/CR-5265tobealowerboundforA302B.However,thestafffindstheoverallJ-RCurveadjustmentprocedureforA302Btobeunacceptableforthefollowingreasons:(1)ThepercentdecreaseinJ,;,calculatedtoEOLforthelimitingA3025materialassumedtRaf.thematerialinNUREG/CR-5265[11]hadaUSEof50ft-lb.However,theactualUSEfortheA302BmaterialinNUREG/CR-5265[ll]is53ft-lb.ThereforetheXdecreaseinJ<,<citedforA302Binthesubjectrepor'tshouldbeapproxImately33Xasopposedto24X.(2)TheresultingJ,.datawerenottemperaturecorrected.ThedatafromNUREG/CR-5F63[(1]weregeneratedatatemperatureof180'F.Thestaffmaintainsthatatemperaturecorrectionisnecessary.OnemethodthathasbeenproposedfordeterminingthedecreaseinJ,,,withtemperatureforNUREG/CR-5265[11]materialiscontainedinreference[12].Usingtheequationprovidedinthisreference,thedecreaseinJ<withtemperaturefrom180'Fto390'Fisapproximately34'.AdjustingtheanalysistoaccountfortheaboveyieldsaJ,,~<valueat0.1inchesofcrackextension(Jo)whichissignificantlyless~ChanthatobtainedbytheWOG.A'ethodologyforadjustingA302BJ-Rcurvedatawhichissimilartothatinreference[12]andhasbeenfoundacceptablebythestaffiscontainedintheBMROwnersGroupTopicalReportNEDO-32205[13].ItshouldbenotedthattheA302BplatetestedforNUREG/CR-5265[11]wasahighsulphurplatewhichreceivedaminimalamountofcrossrolling.Theresultantfracturepropertieswereseverelydegradedbythepresenceoflargemanganese-sulfide(HnS)inclusions.Forthesereasons,itisquestionablewhethertheplatecanbeconsideredrepresentativeofA302BwhichwouldhavebeenusedinRPVconstruction.However,untilrecently,NUREG/CR-5265representedtheonlylargescalefracturedatathatwereavailableforA302B.Hence,thestaffhaveconsideredthesedatatobealowerboundforA302Bplate.RecentpreliminaryfracturetestresultsfromtheOakRidgeNationalLaboratory(ORNL)onapotentiallymorerepresentativeA302BplateindicatevastlysuperiorpropertiestothoseobtainedinNUREG/CR-5265[11].Thest'affwillconsidertheORNLdataandotheravailablefracturedatainestablishingfuturepositionsforA302Bplatefractureresistance.44SeletioniitiTransientThesubjectreportusedthe100'F/hrheatup/cooldowncaseasboundingforLevelsAandB.ThisisconsistentwiththeevaluationperformedinNUREG/CR-6023[7].ForLevelsCandDtheWOGusedbothpeakstressandtheoverallmagnitudeofthethrough-wallstressasthecriteriatodeterminetheboundingtransients.Theresultingtemperaturesatthecracktip(10Kofwallthickness+cladding)were511FforPlant17and487'Ffortheremainingplants.Usingthesecriteria,itwasjudgedthatasmallsteamlinebreak(SLB)wasthelimitingLevelCtransientandlargelossofcoolantaccident JQ~~I~+(LOCA)'andlargeSLBwerethelimitingLevelDtransients.ForLevelD,thelargeSLBwasultimatelyselectedasthelimitingLevelDtransientasastressanalysisconductedbytheMOGshowedthatthelargeSLBproducedslightlylargerstressesatthecracktipfora1inchdeepflaw.InresponsetotheRAI,theWOGprovidedthepressureandtemperaturehistoriesforallofthetransientsconsideredintheirassessment.BasedonanexaminationofallofthetransientsthestaffconcludesthatthelimitingCandDtransientsselectedbytheWOGareacceptable.4.5CalculationofAliedFractureDrivinForceJTheMOGemployedtheproceduresofCodeCaseN-512[5]andDG-1023[6]inthedeterminationofthefracturedrivingforce(J.)forLevelsAandB.Thestaffperformedanindependentevaluationoftfie7,.~calculationsforthelimitingPlant7caseandwereabletoverifytheS(calculations.ForlevelsCandDthepressureandtemperaturehistoriesforallofthetransientsconsideredwereinputtoa2-Dfiniteelementmodelofthenuclearsteamsupplysystem(NSSS)usingtheWECAN[14]computercode.Theresultingstressdistributionsforthelimitingtransients,whichincludedthecontributionsofthecladdingtothethermalstress,wereusedtocalculateJ,~usingthePCFAD[15]computercode.ConsistentwiththeresultsoftlutefoundinganalysesperformedforNUREG/CR-6023,theMOGJ,,~valuesforLevelsAandBwerefoundtobecontrolling.ThestafffindsthemethodologyemployedbytheWOGforcalculationofthefracturedrivingforcetobeacceptable.However,thestaffdiscoveredthatthefinalanalysisforequivalentmargin;wasoverlyconservativewhencomparingthefracturedrivingforce(J<,~)withthematerialfractureresistance(J,-).ThiswillbediscusseP>nthenextsection.4.6BoundinNatureoftheAnalsisTheresultsoftheWOGequivalentmarginsanalysisarepresentedinTables3,4and5forLevelsA,8,CandD.TheseTablesshowacomparisonbetweentheapplieddrivingforceandmaterialresistancevaluesforthethreegenericcases(2,3,and4loop)andtwoplant-specificcases.TheMOGconcludedthatinallcasesthecriteriaofCodeCaseN-512weremet(J,,,>J,~).However,inexaminingthePlant7case(A302Bplate)inPetal),thestaffconcludedthatthematerialvalueforJpqdeterminedbytheWOGwasnotacceptable(seeSection4.3).ThematerialvaluethatthestaffestimatedforJ~,forPlant7waswellbelowtheappliedvaluecalculatedbytheMOG.FurtherexaminationofthiscaserevealedthattheactualreasonforexceedingtheCodeCaseN-512criteriawasthattheMOGhadconservativelycomparedtheapplieddrivingforcefortheaxialfl~wwiththematerialresistancefortheweakorientationwhichcorrespondstothecircumferentialflaw(i.e.,meetingthecriteriaundertheseconditionsassuresthatthecriteriawillalsobemetwhenthevaluesarecomparedassuggestedbytheCodeCase.)Aconferencecall[16]withtheMestinghouseElectricCorporationandthelicenseeforPlant7confirmedthatthisconservativeanalysiswasperformedforallofthecasesevaluated.Thestaffconsidersthisanalysistobeoverlyconservative.InarevisionletterdatedDecember21,1993[17]whichspecificallyaddressesthePlant7case,theWOGdemonstratedthattheappropriatecomparisonoftheappliedandmaterialvaluesshowsthattheCodeCaseN-512[5]criteriawere met.Theletter[17]alsoaddressedtheUSEadjustmentandtemperaturecorrectionconcernsforA302BplatethatwerediscussedpreviouslyinSection4.3,TheMOGispreparingamorecomprehensiverevisiontothereportwhichwilladdressallofthecasesconsidered.Thestaffconcludesthat,intheinterim,thesubjectreportandthealternativeevaluationprovidedintherevisionletterofDecember21,1993,demonstrateequivalentmarginsofsafetyasperCodeCaseN-512[5]forWOGplateandforgingmaterials.Forthecaseofwelds,asstatedpreviously,theWOGmaintainsthat"weldmentsfabricatedwithfluxesotherthanLinde80willnotexhibitlessthan50ft-lbduringservice."However,theWOGdidnotprovidealistingwhichidentifiedtheWOGplantsandtheircorrespondingUSEdatabyname.Therefore,confirmationoftheinputdata(chemistryandfluence)andcalculationsonaplant-by-plantbasiswasnotpossible.Further,sincetheminimumacceptableUSEvaluesfromtheequivalentmarginsanalysiswerebasedonfracturetoughnessdataforplateorforgingmaterials,thesevalueswillnotapplytoweldments.CalculationsperformedforNUREG/CR-6023[7]withtheLinde80weldmodelhaveshownaminimumacceptableUSEof41ft-lbforaPWR.Thereforethestaffconsidersthat,whileweldmentsfortheWOGplantsarenotlikelytobelimitingforUSE,thesubjectreportdoesnotprovidesufficientinformationtomakethisdeterminationconclusively.AspartoftheGL92-0Ireview,thestaffwillbeevaluatingeachbeltlineweldfortheMOGplantstodetermineifthescreeningcriterionwillbemetatEOL.Inthesubjectreport,theMOGcitedaminimumacceptableUSEvalueof29ft-lbforplatesandforgingsin2loopplants.Mhilenumbersthislowcanresultfromthecalculationsandhavebeencitedelsewhere['6],[7],theirsignificanceisnotclearatthistimeandtheyrepresentanextrapolationofthedatausedtodevelopthecorrelationsinNUREG/CR-5729[9].ThereisnotatpresentatechnicalconsensusontheCVNenergylowerlimitforequivalentmarginsanalyses.However,valuesbelow30ft-lbforreactorpressurevesselsteelsarehighlysuspectassuchlowenergiesarelikelytobeassociatedwithductiletearingincombinationwithotherfracturemodes(e.g.,intergranular,incipientcleavage)notconsideredinthedevelopmentofthelowuppershelfcriteria.

5.0CONCLUSION

SThestaffhasevaluatedtheequivalentmarginsanalysispresentedinreportWCAP-13587,Revision1,submittedbytheWestinghouseElectricCorporationfortheWOG.Thestaffevaluationsupportsthefollowingconclusions:(1)ThemethodologyemployedfortheWOGreportwasconsistentwiththeguidelinesinCodeCaseN-512[5]andDG-1023[6]andisthereforeacceptabletothestaff.(2)(3)ThesubjectreportdemonstratesmarginsofsafetyequivalenttothoseoftheASHECodeforWOGbeltlineplateandforgingmaterials.AnequivalentmarginsanalysisbasedonweldmentpropertieswasnotperformedbecausetheWOGconcludedthatalloftheWOGbeltlinewelds'ouldbeabove50ft-lbatEOL.AspartoftheGL92-01review,the

l410staffwillbeevaluatingeachbeltlineweldfortheWOGplantstodetermineifthescreeningcriterionwillbemetatEOL.(4)IndividuallicenseesdesiringtoreferenceWCAP13587,Revision1,asthebasisforaddressingtheUSErequirementsof10CFR50,AppendixGmustconfirmthespecificplantapplicabilitybyeitherdemonstrating'hatallbeltlineweldswillhaveEOLUSEabove50ft-lborthattheboundingplateusedinthereporthasalowerJ-Rcurvethananyotherbeltlinematerialinthevessel.Further,individuallicenseesmustrequestapprovalinaccordancewith10CFR50,AppendixG.(5)ThestafffindstheWOGapproachformodelingtheJ-RcurvebehavioroftheA302BplateinWCAP-13587,Rev.1,tobeunacceptable(seeSection4.3).However,theA302BJ-RcurvemethodologyemployedintheplantspecificrevisionletterofDecember21,1993[17]includesappropriateadjustmentsforUSEandtemperaturecorrectionsandisacceptabletothestaff.(7)Thestafffindsthatthefinalcomparisonofappliedfracturedrivingforcewithmaterialfractureresistancewasoverlyconservativeforallcasesanalyzed.ThisissuewasadequatelyaddressedforalimitingplantspecificcasebyletterdatedDecember21,1993[17],andtheWOGispreparingarevisiontothereportwhichaddressesallofthecasesconsidered.Calculatedminimum.acceptableUSEvaluesbelow30ft-lbforreactorpressurevesselsteelsarehighlysuspectassuchlowenergiesarelikelytobeassociatedwithductiletearingincombinationwithotherfracturemodes(e.g.,intergranular,incipientcleavage)notconsideredinthedevelopmentofthelowuppershelfcriteria.

6.0REFERENCES

[2][3][4][5][6][8]WCAP-13587,Revision0,"ReactorVesselUpperShelfEnergyBoundingEvaluation.for'estinghousePressurizedWaterReactors",S.TandonandT.R.Hager,WestinghouseElectricCorporation,February,1993.GenericLetter92-01,Revision1,ReactorVesselStructuralIntegrity,.10CFR50.54(f),U.S.NuclearRegulatoryComnission,March6,1992.RequestforAdditionalInformationonWCAP-13587,"ReactorVesselUpperShelfEnergyBoundingEvaluationforWestinghousePressurizedWaterReactors,"U.S.NuclearRegulatoryCommission,July1,1993.WCAP-13587,Revision1,"ReactorVesselUpperShelfEnergyBoundingEvaluationforWestinghousePressurizedWaterReactors",S.TandonM.J.HaloneandT.R.Mager,WestinghouseElectricCorporation,September,1993.CodeCaseN-512,"AssessmentofReactorVesselswithLowUpperShelfCharpyImpactEnergyLevels,"SectionXI,Division1,ASHEBoilerandPressureVesselCode,February12,1993.DraftRegulatoryGuideDG-1023,"EvaluationofReactorPressureVesselswithCharpyUpperShelfEnergyLessthan50ft-lb,"U.S.NuclearRegulatoryComaission,August,1993.NUREG/CR-6023,"GenericAnalysesforEvaluationofLowCharpyUpperShelfEnergyEffectsonSafety.MarginsAgainstFractureofReactorPressureVesselMaterials,"T.L.Dickson,USNRC,'ashington,DC,July1993.RegulatoryGuide1.99,Revision2,"RadiationEmbrittlementofReactorVesselMaterials,"U.S.NuclearRegulatoryComnission,Hay,1988.[9][10][12]NUREG/CR-5729,"MultivariableModelingofPressureVesselandPipingJ-RData,"E.D.Eason,J.E.WrightandE.E.Nelson,USNRC,Washington,DC,1991.NUREG-0800,"StandardReviewPlanfortheReviewofSafetyAnalysisReportsforNuclearPowerPlants,LWREdition,"BranchTechnicalPosition-MTEB5-2,FractureToughnessRequirements,Section5.3.2,USNRC,Washington,DC,1981.NUREG/CR-5265,"SizeEffectsonJ-RCurvesforA302-BPlate,"A.L.HiserandJ.B.Terrell,USNRC,Washington,DC,1989.Memorandum,A.L.HiserandS.N.M.HalikofUSNRCtoK.R.Wichman,USNRC,"J-RCurvesforLowToughnessA302BPlate,"USNRC,September9,1993.

12[13]NED0-32205,".10CFR50AppendixGEquivalentHarginAnalysisforLow'pperShelfEnergyinBWR/2ThroughBWR/6Vessels,"LicensingTopicalReportfortheBWROwners'roup,GENuclearEnergy,April,1993.[14]WestinghouseElectricComputerAnalysis(WECAN)Code,File87-1J7-WESAD-Rl,datedDecember1987.[15]Bloom,J.H.andD.R.Lee,"UsersGuidefortheFailureAssessmentDiagramComputerCodeFAD,"BabcockandWilcox,Rev.4,April1990.[16]ConferenceCall,NRC,CarolinaPowerELightandWestinghouse,December13,1993.[17]LetterfromD.B.Waters,CarolinaPower5LightCompanytoUSNRC,ofDecember21,1993,"CarolinaPower5.LightCompany,H.B.RobinsonSteamElectricPlant-UnitNo.2,DocketNo.50-261/LicenseNo.DPR-23,ReactorVesselUpperShelfEnergyForReactorVesselCoreRegionPlateHaterials."[18]LetterfromE.E.Fitzpatrick,IndianaHichiganPowertoT.E.Hurley,USNRC,AEP:NRC:11738,withAttachmententitled,"AmericanElectricPowerServiceCorporation,DonaldC.CookNuclearPlantUnit2,UpperShelfCharpyValues,"January24,1994.

13TABLE3J<.~vs.J,forLevelsA5.BfromMCAP13587,Revision1,(PnhsonJare>n-lbs/in)CASE2Loo384APPLIEDdJda318702MATERIALdJda2925METCRITERIA?Yes3Loo4LooPlant7Plant17500590525548321345222197585527614527614214059923305992330YesYesYesYes()-CalculationsbasedonJ-RCurvesfromReference11TABLE4J~.~vs.J<,forLe~elCfromMCAP13587,Revision1(PnhsonJaresn-lbs/in)CASE2Loo311APPLIEDdJ/da225702MATERIALdJ/da2925METCRITERIA?Yes3Loo4LooPlant7Plant17310311308319252225250240585527614527614214059923305992330YesYesYesYes()-CalculationsbasedonJ-RCurvesfromReferencell 14TABLE5J<,.~vs.J,,forLevelDfromWCAP13587,Revision1(Pn>tsonJare1n-lbs/in)CASE2Loo3Loo4LooPlant7Plant17APPLIEDdJda447447468MATERIALdJda2925214059923305992330METCRITERIA?YesYesYesYesYes()-CalculationsbasedonJ-RCurvesfromReferencell