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{{#Wiki_filter:Enclosure2TECHNICALEVAL'JAT)ONREPORTFRACTURETOUGHNESSOFSTEAMGENER4TORANDREACTORCOOLANTpUMPSUPPORTSINDIANAaHICHIGA')POgt":RCylP@y.DONALDCCOOKNUCLEARPOKERPLANTUNITS1AND2NRCDOCKETNO.$0-315and50-316NRCTACNO.08479and08486NRCCONTRACTNb.NRC43.79'ttbFRCPROJECTCSB7FRCTASK167and168PreparedbyFranklinResearchCenterTheParkwayatTwentiethStreetPhHadelphia,PA19163AuthOrS:T.C.S&lvel',h.G.hllCen,K.E.Dozschu,P.N.NoellFRCGroupLeadei:T.C.ScQ~lLPreparedforNuclearRegulatoryCommissionWashington,D,C.20%5LeadNREngineer:J.R.FairRevision1,Novemberl980ThisreportwaspreparedasanaccountofworksponsoredbyanagencyoftheUnitedStatesGovernment.NeithertheUnitedStatesGovernmentnoranyagencythereof,oranyoftheiremployees,makesanywarranty,expressedorimplied,'orassumesanylegalliabilityorresponsibilityforanythirdparty'suse,ortheresultsofsuchuse,ofanyinformation,apparatus,productorprocessdisclosedlnthisreport,orrepresentsthatitsusebysuchthirdpartywouldnotinfringeprivatelyownedrights,!F'ran}dinResearchCenterADivisionofTheFranklinInstituteThehnjstnnPronount'snowy.Phiii..Pal9I03(2JSi4ib)COO TER-C5257-167/168(Rev.1)CONTENTSSectionTitleParcae1SUMMARY~~t~~~~~~~~~2INTRODUCTION3BACKGROUND~/4CRITERIAAPPLIEDINTHEEVALUATION~4.1Fracture-ToughnessGroupingofMaterialsUsedinSupportConstruction.4.1.1Criterion4.1.2Interpretation.4.2PlantGroupingforFracture-ToughnessRankingofS/GandRCPSupportStructures4.2.1Criterion.4.2.2Interpretation.4.3CriteriaforFracture-ToughnessAdequacyofS/GandRCPSupports.4.3.1NDTCriteriaforScreening.4.3.2Interpretation.4.3.3AlternativeCriteria5TECHNICALEVALUATION5.1ReviewProcedureandImplementationofNRCCriteria775.2ExtentofFRC'sReview.105.3ReviewFindings5.3.1UseofGroupIMaterialsinApplicationsImportanttoStructuralIntegrityofSupports~~~~~~5.3.2ThickSectionUseofGroupIIMaterialsinApplicationsZmportanttoStructuralIntegrity.10,1010 TER-C5257-167/168(Rev.1)5.3.3ThinSectionUseofGroupIIMaterialsinApplicationsImportantToStructuralIntegrity.5.3.4UseofMaterialsClassifiedGroupIIIbyNUREG0577,UponCondition.5.3.5UseofMaterialsClassifiedGroupIIIbyNUREG0577<Outright6CONCLUSIONS101112crumbrTABLETitlePaae51COMPONENTSUPPORTSUMMARY~.~~~~~.8009FranklinResearchCenterAOesicnatTbaFranenhauteiv TER-C5257-167/168(Rev.1)1~SUMMARYInformationconcerningaspectsofthefracture-toughnessdesignofthesteamgenerator(S/G)andreactorcoolantpump(RCP)supportsfortheDonaldC.CookNuclearPowerPlantUnits1and2wassubmittedtotheActingDirectoroftheOfficeofNuclearRegulationbytheIndianaandMichiganPowerCompany(IMPC)byletterdatedNov.23,1977.ThisinformationwasreviewedattheFranklinResearchCenter(FRC)andevaluatedinaccordancewiththecriteriaoftheNuclearRegulatoryCommission(NRC)assetforthinNUREG0577-Draft(henceforthreferredtosimplyasNUREG0577).TheinformationhadpreviouslybeenreviewedaspartofthepreparationofNUREG0577,andD.C.CookUnits1and2hadbeenassignedaGroupZZZ(rela-tivelybest)plantrankingforfracturetoughnessofS/GandRCPsupports.Thisrankingwasregardedastentative.Subsequently,theNRCrequestedFRCtoconductanindependentreviewpriortofinalizingtheranking.sF((C'sreviewwasconfinedtofracture-toughnessissuesinsupportsabovetheembedment.ThereviewwasconductedinaccordancewithNRCcriteriaandtoaprocedurestandardizedfortheseverallicenseeswhosesupportdesignswerereviewedatFRC.Asaresultofitsreview,FRCconfirmedthattheGroupZIIplantrankingassignedtoDonaldC.CookNuclearPowerPlantsUnits1and2forfracturetoughnessofS/GandRCPsupportsisjustifiable.2INTRODUCTIONThisreportprovidesatechnicalevaluationofinformationsuppliedbyIMPCIwithitsletterofNov.23,1977,toMr.EdsonG.Case,ActingDirectorOfficeofNuclearRegulation.Theinformationconcernsthefracture-toughnessdesignofsupportsfortheS/GsandRCPsforD.C.CookUnits1and2.Theobjectiveoftheevaluationistorankthedesignforfracture-toughnessintegrityonarelativescaleinaccordancewiththegroupingschemeandcriteriaestablishedinNUREG0577.0llFranklinResearchCenterAOMsionofTheFlank&~
{{#Wiki_filter:Enclosure 2TECHNICALEVAL'JAT)ON REPORTFRACTURETOUGHNESS OFSTEAMGENER4TORANDREACTORCOOLANTpUMPSUPPORTSINDIANAaHICHIGA')
TER-C5257-167/168(Rev.1)3~BACKGROUNDDuringthecourseoftheNRClicensingreviewfortwopressurizedwaterreactors(PHR),NorthAnnaUnits1and2,questionsvereraisedregardingthefracture-toughnessadequacyofcertainmembersoftheS/GandRCPsupports.Thepotentialforlamellartearinginsomesupportmemberswasalsoquestioned.Thestaff'sconcernintheNorthAnnalicensingprocesswasthatperhapsnotenoughattentionhadbeengiventotheselectionofmaterialsfor,andfabricationof,theS/GandRCPsupports.Fracturetoughnessofamaterialisameasureofitscapabilitytoabsorbenergywithoutfailureordamage.Generally,amaterialisconsidered'tough"when,understatedconditionsofstressandtemperature,thematerialcanwithstandloadingtoitsdesignlimitinthepresenceofflaws.Toughnessalsoimpliesthat,undercertainconditions,thematerialhasthecapabilitytoarrestthegrowthofaflaw.Alackofadequatetoughness(accompaniedbyrthecombinationoflowoperatingtemperature>presenceofflaws>andnonredun-dancyofcriticalsupportmembers)couldresultinrailureofthesupportstructureunderpostulatedaccidentconditionsrspecificallyaloss-of-coolantaccident(LOCA)andsafeshutdownearthquake(SSE).Toaddressfracture-toughnessconcernsattheNorthAnnafacility,thelicenseeundertooktestsnotoriginallyspecifiedandnotincludedintherelevantASSNspecifications.Thesetestsindicatedthatmaterialusedincertainsupportmembershadrelativelypoorfracturetoughnessat804Pmetaltemperature.Inthiscase,thelicenseeagreedtoraise(byancillaryelectricalheat)thetemperatureoftheS/Gsupportbeamsinquestiontoaminimumof2254Feverytime,throughoutthelifeoftheplant,thatthereactorcoolantsystem(RCS)ispressurizedabove1,000psig.TheNRCstafffoundthistobeanacceptableresolution.Becausesimilarmaterialsanddesignswereusedinotherplantsandbe-causesimilarproblemswerethereforepossible,thismattervasincorporatedintotheNRCProgramforResolutionofGenericIssuesas"GenericTechnicalll00FranklinResearchCenterADivisiondIbcFranAnhshu TER-C5257-167/168(Rev.1)ActivityA-12PotentialforLowFractureToughnessandLamellarTearingonPWRSteamGeneratorandReactorCoolantPumpSupports."Sincetheoriginallicensingaction(NorthAnnaUnits1and2)involvedonlytheS/GandRCPsupportsofPWRs,thestaff'sinitialeffortsweredi-rectedtowardexaminationofthecorrespondingsupportsatotherPWRfacili-ties.However,thestaffhaskeptinmindthepossibilityofexpandingitsreviewtoincludeothersupportstructuresinPWRplantsandsupportstruc-turesinboilingwaterreactor(BWR)plants.TheintegrityofsupportembedmentswasnotquestionedduringtheNorthAnnalicensingaction;consequently,emphasiswasplacedonresolvingthemostimmediategenericissue-whetherornotproblemssimilartothoseuncoveredatNorthAnnaexistatotherfacilities.Itwasthestaff'sjudgmentthatinclusionofanevaluationofsupportembedmentsintheinitialreviewwouldrequiredetailed,plant-specificinvestigationsthatwerebeyondthescopeofthepreliminary,overallgenericreview.Suchconsiderationsweredeemedmoresuitecftoasubsequentphasewhenmoredetailedinvestigationsofindividualplantsmightbeundertaken.Requestsforinformationweresenttolicenseesinlate1977;responsestotheserequestswerereceivedduring1978.SandiaLaboratoriesinAlbuquerque,NewMexico,wasretainedtoassistthestaffinthereviewandanalysisoftheinformationreceivedfromlicenseesandapplicants.BasedonanalysisofthisinformationrthetechnicalstudiesperformedbySandiaLaboratories,andreviewoftheissuesbytheNRCstaff,theNRCdevelopedanNRCstafftechnicalpositionontheseissuesrwhichispresentedinNUREG0577,"PotentialforLowFractureToughnessandLamellarTearingonPWRSteamGeneratorandReactorCoolantPumpSupports."Inaddition,NUREG0577establishescriteriaforevaluationofthefracture-toughnessadequacyofS/GandRCPsupports.NUREG0577alsoappliescertainofthesecriteriatothesupportstructuresofanumberofPWRplantstoachieveplantgroupingsaccordingtotherelativefracture-toughnessinte-grityofthesesupports.tillFranklinResearchCenterADivwon81&iFrankhn~  
POgt":RCylP@y.DONALDCCOOKNUCLEARPOKERPLANTUNITS1AND2NRCDOCKETNO.$0-315and50-316NRCTACNO.
'li TER-C5257-167/168(Rev.1)Theplantratingsare:~GroupI(lowest)eGroupII(intermediate)~GroupIII(highest)Duringthegenericstudy,anumberofPWRplantswerereviewedforthefracture-toughnessadequacyoftheirRCPandS/Gdesigns.Asaresultofthesereviews,eachplantwasassignedatentativeplantrankingofeitherGroupI,II,orIII.SeveralPlants,D.C.CookUnits1and2amongthem,weretentativelyrankedGroupIII.IntheappendixtoNUREG0577preparedbySandiaLabora-tories,whoinitiallyestablishedtherankingswhichsubsequentlyreceivedNRCstaffendorsement,thesignificanceoftheGroupIIIrankingisdescribedas:consideredtobeasgoodascareful,reasonableengineeringpracticecanproduce."However,beforefinalizingthetentativeGroupIIIrankings,theNRCrequestedFRCtoconductanindependentreviewoftheGroupIIIplants(incon~unctionwithsimilarFRCtaskassignmentstoreviewthefracture-toughnessadequacyofcorrespondingsupportsincertainotherplants)andtoprepareaTechnicalEvaluationReportforeachplant,presentingthereviewfindings.ThetechnicalevaluationreportedhereinappliesthecriteriaofNUREG0577totheS/GandRCPsupportsforD.C.CookUnits1and2toprovideanassessmentofthefracture-toughnessadequacyofthesesupportsleadingtoaplantranking.4~CRITERIAAPPLIEDINTHEEVALUATION4~1FRACTURE-%)UGHNESSGROUPINGOFMATERIALSUSEDINSUPPORTCONSTRUCTION4.1.1CriterionTable4.6,MaterialGroups,ofAppendixCtoNUREG0577groupsmaterialsaccordingtotheirrelativefracturetoughnessas:~GroupI(poorest)oGroupII(intermediate)~GroupIII(best)JU~~LFrankjinResearchCenterA~dTheFranklinInseam  
08479and08486NRCCONTRACTNb.NRC43.79'ttbFRCPROJECTCSB7FRCTASK167and168PreparedbyFranklinResearchCenterTheParkwayatTwentieth StreetPhHadelphia, PA19163AuthOrS:T.C.S&lvel',
h.G.hllCen, K.E.Dozschu, P.N.Noell FRCGroupLeadei:T.C.ScQ~lL PreparedforNuclearRegulatory Commission Washington, D,C.20%5LeadNREngineer:
J.R.FairRevision1,Novemberl980Thisreportwaspreparedasanaccountofworksponsored byanagencyoftheUnitedStatesGovernment.
NeithertheUnitedStatesGovernment noranyagencythereof,oranyoftheiremployees, makesanywarranty, expressed orimplied,'or assumesanylegalliability orresponsibility foranythirdparty'suse,ortheresultsofsuchuse,ofanyinformation, apparatus, productorprocessdisclosed lnthisreport,orrepresents thatitsusebysuchthirdpartywouldnotinfringeprivately ownedrights,!F'ran}din ResearchCenterADivisionofTheFranklinInstitute ThehnjstnnPronount'snowy.Phiii..Pal9I03(2JSi4ib)COO TER-C5257-167/168 (Rev.1)CONTENTSSectionTitleParcae1SUMMARY~~t~~~~~~~~~2INTRODUCTION 3BACKGROUND
~/4CRITERIAAPPLIEDINTHEEVALUATION
~4.1Fracture-Toughness GroupingofMaterials UsedinSupportConstruction
.4.1.1Criterion 4.1.2Interpretation.
4.2PlantGroupingforFracture-Toughness RankingofS/GandRCPSupportStructures 4.2.1Criterion
.4.2.2Interpretation.
4.3CriteriaforFracture-Toughness AdequacyofS/GandRCPSupports.4.3.1NDTCriteriaforScreening.
4.3.2Interpretation.
4.3.3Alternative Criteria5TECHNICAL EVALUATION 5.1ReviewProcedure andImplementation ofNRCCriteria775.2ExtentofFRC'sReview.105.3ReviewFindings5.3.1UseofGroupIMaterials inApplications Important toStructural Integrity ofSupports~~~~~~5.3.2ThickSectionUseofGroupIIMaterials inApplications Zmportant toStructural Integrity
.10,1010 TER-C5257-167/168 (Rev.1)5.3.3ThinSectionUseofGroupIIMaterials inApplications Important ToStructural Integrity
.5.3.4UseofMaterials Classified GroupIIIbyNUREG0577,UponCondition.
5.3.5UseofMaterials Classified GroupIIIbyNUREG0577<Outright6CONCLUSIONS 101112crumbrTABLETitlePaae51COMPONENT SUPPORTSUMMARY~.~~~~~.8009FranklinResearchCenterAOesicnatTbaFranenhauteiv TER-C5257-167/168 (Rev.1)1~SUMMARYInformation concerning aspectsofthefracture-toughness designofthesteamgenerator (S/G)andreactorcoolantpump(RCP)supportsfortheDonaldC.CookNuclearPowerPlantUnits1and2wassubmitted totheActingDirectoroftheOfficeofNuclearRegulation bytheIndianaandMichiganPowerCompany(IMPC)byletterdatedNov.23,1977.Thisinformation wasreviewedattheFranklinResearchCenter(FRC)andevaluated inaccordance withthecriteriaoftheNuclearRegulatory Commission (NRC)assetforthinNUREG0577-Draft (henceforth referredtosimplyasNUREG0577).Theinformation hadpreviously beenreviewedaspartofthepreparation ofNUREG0577,andD.C.CookUnits1and2hadbeenassignedaGroupZZZ(rela-tivelybest)plantrankingforfracturetoughness ofS/GandRCPsupports.
Thisrankingwasregardedastentative.
Subsequently, theNRCrequested FRCtoconductanindependent reviewpriortofinalizing theranking.sF((C'sreviewwasconfinedtofracture-toughness issuesinsupportsabovetheembedment.
Thereviewwasconducted inaccordance withNRCcriteriaandtoaprocedure standardized fortheseverallicensees whosesupportdesignswerereviewedatFRC.Asaresultofitsreview,FRCconfirmed thattheGroupZIIplantrankingassignedtoDonaldC.CookNuclearPowerPlantsUnits1and2forfracturetoughness ofS/GandRCPsupportsisjustifiable.
2INTRODUCTION Thisreportprovidesatechnical evaluation ofinformation suppliedbyIMPCIwithitsletterofNov.23,1977,toMr.EdsonG.Case,ActingDirectorOfficeofNuclearRegulation.
Theinformation concernsthefracture-toughness designofsupportsfortheS/GsandRCPsforD.C.CookUnits1and2.Theobjective oftheevaluation istorankthedesignforfracture-toughness integrity onarelativescaleinaccordance withthegroupingschemeandcriteriaestablished inNUREG0577.0llFranklinResearchCenterAOMsionofTheFlank&~
TER-C5257-167/168 (Rev.1)3~BACKGROUND DuringthecourseoftheNRClicensing reviewfortwopressurized waterreactors(PHR),NorthAnnaUnits1and2,questions vereraisedregarding thefracture-toughness adequacyofcertainmembersoftheS/GandRCPsupports.
Thepotential forlamellartearinginsomesupportmemberswasalsoquestioned.
Thestaff'sconcernintheNorthAnnalicensing processwasthatperhapsnotenoughattention hadbeengiventotheselection ofmaterials for,andfabrication of,theS/GandRCPsupports.
Fracturetoughness ofamaterialisameasureofitscapability toabsorbenergywithoutfailureordamage.Generally, amaterialisconsidered
'tough"when,understatedconditions ofstressandtemperature, thematerialcanwithstand loadingtoitsdesignlimitinthepresenceofflaws.Toughness alsoimpliesthat,undercertainconditions, thematerialhasthecapability toarrestthegrowthofaflaw.Alackofadequatetoughness (accompanied byrthecombination oflowoperating temperature>
presenceofflaws>andnonredun-dancyofcriticalsupportmembers)couldresultinrailureofthesupportstructure underpostulated accidentconditionsr specifically aloss-of-coolant accident(LOCA)andsafeshutdownearthquake (SSE).Toaddressfracture-toughness concernsattheNorthAnnafacility, thelicenseeundertook testsnotoriginally specified andnotincludedintherelevantASSNspecifications.
Thesetestsindicated thatmaterialusedincertainsupportmembershadrelatively poorfracturetoughness at804Pmetaltemperature.
Inthiscase,thelicenseeagreedtoraise(byancillary electrical heat)thetemperature oftheS/Gsupportbeamsinquestiontoaminimumof2254Feverytime,throughout thelifeoftheplant,thatthereactorcoolantsystem(RCS)ispressurized above1,000psig.TheNRCstafffoundthistobeanacceptable resolution.
Becausesimilarmaterials anddesignswereusedinotherplantsandbe-causesimilarproblemsweretherefore
: possible, thismattervasincorporated intotheNRCProgramforResolution ofGenericIssuesas"GenericTechnical ll00FranklinResearchCenterADivisiondIbcFranAnhshu TER-C5257-167/168 (Rev.1)ActivityA-12Potential forLowFractureToughness andLamellarTearingonPWRSteamGenerator andReactorCoolantPumpSupports."
Sincetheoriginallicensing action(NorthAnnaUnits1and2)involvedonlytheS/GandRCPsupportsofPWRs,thestaff'sinitialeffortsweredi-rectedtowardexamination ofthecorresponding supportsatotherPWRfacili-ties.However,thestaffhaskeptinmindthepossibility ofexpanding itsreviewtoincludeothersupportstructures inPWRplantsandsupportstruc-turesinboilingwaterreactor(BWR)plants.Theintegrity ofsupportembedments wasnotquestioned duringtheNorthAnnalicensing action;consequently, emphasiswasplacedonresolving themostimmediate genericissue-whetherornotproblemssimilartothoseuncovered atNorthAnnaexistatotherfacilities.
Itwasthestaff'sjudgmentthatinclusion ofanevaluation ofsupportembedments intheinitialreviewwouldrequiredetailed, plant-specific investigations thatwerebeyondthescopeofthepreliminary, overallgenericreview.Suchconsiderations weredeemedmoresuitecftoasubsequent phasewhenmoredetailedinvestigations ofindividual plantsmightbeundertaken.
Requestsforinformation weresenttolicensees inlate1977;responses totheserequestswerereceivedduring1978.SandiaLaboratories inAlbuquerque, NewMexico,wasretainedtoassistthestaffinthereviewandanalysisoftheinformation receivedfromlicensees andapplicants.
Basedonanalysisofthisinformationr thetechnical studiesperformed bySandiaLaboratories, andreviewoftheissuesbytheNRCstaff,theNRCdeveloped anNRCstafftechnical positionontheseissuesrwhichispresented inNUREG0577,"Potential forLowFractureToughness andLamellarTearingonPWRSteamGenerator andReactorCoolantPumpSupports."
Inaddition, NUREG0577establishes criteriaforevaluation ofthefracture-toughness adequacyofS/GandRCPsupports.
NUREG0577alsoappliescertainofthesecriteriatothesupportstructures ofanumberofPWRplantstoachieveplantgroupings according totherelativefracture-toughness inte-grityofthesesupports.
tillFranklinResearchCenterADivwon81&iFrankhn~  
'li TER-C5257-167/168 (Rev.1)Theplantratingsare:~GroupI(lowest)eGroupII(intermediate)
~GroupIII(highest)
Duringthegenericstudy,anumberofPWRplantswerereviewedforthefracture-toughness adequacyoftheirRCPandS/Gdesigns.Asaresultofthesereviews,eachplantwasassignedatentative plantrankingofeitherGroupI,II,orIII.SeveralPlants,D.C.CookUnits1and2amongthem,weretentatively rankedGroupIII.IntheappendixtoNUREG0577preparedbySandiaLabora-tories,whoinitially established therankingswhichsubsequently receivedNRCstaffendorsement, thesignificance oftheGroupIIIrankingisdescribed as:considered tobeasgoodascareful,reasonable engineering practicecanproduce."However,beforefinalizing thetentative GroupIIIrankings, theNRCrequested FRCtoconductanindependent reviewoftheGroupIIIplants(incon~unction withsimilarFRCtaskassignments toreviewthefracture-toughness adequacyofcorresponding supportsincertainotherplants)andtoprepareaTechnical Evaluation Reportforeachplant,presenting thereviewfindings.
Thetechnical evaluation reportedhereinappliesthecriteriaofNUREG0577totheS/GandRCPsupportsforD.C.CookUnits1and2toprovideanassessment ofthefracture-toughness adequacyofthesesupportsleadingtoaplantranking.4~CRITERIAAPPLIEDINTHEEVALUATION 4~1FRACTURE-%)UGHNESS GROUPINGOFMATERIALS USEDINSUPPORTCONSTRUCTION 4.1.1Criterion Table4.6,MaterialGroups,ofAppendixCtoNUREG0577groupsmaterials according totheirrelativefracturetoughness as:~GroupI(poorest) oGroupII(intermediate)
~GroupIII(best)JU~~LFrankjinResearchCenterA~dTheFranklinInseam  


TER-C5257-167/168(Rev.1)4.1.2InterpretationIfnosupplementaryrequirementswerecalledoutinthematerialspe'cifi-cationaimedatprocuringaproductwithfracture-toughnesspropertiessupe-riortothoseroutinelysuppliedunderthematerialspecification,thenthematerialwasgroupedinaccordancewithTable4.6.Ifadditionalrequirementsaimedatprocuringaproductwithsuperiorfracture-toughnesspropertieswerespecified,considerationwasgiventocred-/'tingthisspecificmaterialorderwithanimprovedmaterial-grouprating.4~2PLANTGROUPINGFORFRACTURE-TOUGHNESSRANKINGOFS/GANDRCPSUPPORTSTRUCTURES4.2.1CriterionplantsareclassifiedonthebasisoftheconstructionmaterialsusedinI~thesupportsaftergivingconsiderationtotheimportanceoftheirlocationandfunctionwithinthestructure,andtheirconsequentimportancetosupport-structureintegrity.(Refertopages5and.6ofNUREG0577,PartI.)4.2.2Interpretationplantswereassignedaplant-grouprankingidenticaltothematerial-grouprankingoftheleastfracture-toughmaterialusedintheconstruction,pro-videdthisusageisimportanttosupportintegrity.4~3CRITERIAFORFRACTURE-TOUGHNESSADEQUACYOFS/GANDRCPSUPPORTSZtistheclearintentofNUREG0577thatlicenseesdemonstratethefracture-toughnessadequacyoftheS/GandRCpsupportsorthattheytake1appropriatecorrectivemeasurestoassuretheirfracture-toughnessintegrity.NUREG0577providesguidanceforsuchdemonstrations.4.3.1NDTCriteriaforScreening30'FNDT+1~3o+or(F)supports60FI'!IIilFranklinResearchCenterADivaondTheFrabinhsacw TER-C5257-167/168(Rev.1)where:oNDTisthemeannilductilitytransitiontemperatureappro-'riatetothematerialasgivenbyTable4.4ofAppendixCtoNUREG0577'oisthestandarddeviationforthedatausedtodetermineNDTaslistedinTable4.4.0Tsupportsisthelowestmetaltemperaturethatthesupportmemberwilleverexperiencethroughouttheplantlifewhentheplantisinanoperationalstate.Intheabsenceofmeasured,plant-specificdata,Tsupportsistakenas75'F.oThetemperatureterm,30'For60'F,isanallowanceforsec-tionsize(30'Fforthinsectionsand60'Fforthicksec-tions).4.3.2InterpretationIfevidenceisfurnishedbythelicenseeprovingthatothervaluesofNDT,cr,orfareactuallyvalidfortheS/GorRCPsupportsandmateri-supportsalsinthelicensee'splant,suchdatamaybeused..Ifacceptablealternativeevidenceisnotavailable,theabove-stipulatedvaluesshouldbeused.4.3.3AlternativeCriteriaNUREG0577alsorecognizedthatfracture-toughnessintegrityisacomplexmatterinvolvinganumberofinterrelatedfactors,mostofwhichareplantspecific.Consequently,demonstrationofcompliancewiththescreeningcrite-riaisbutonemeansofprovidingsatisfactoryassuranceoffracture-toughnessadequacy.NUREG0577notonlyrecognizesthatothermeansofshowingcompliancewiththeintentofNUREG0577arepossible,butalsooffersextensiveguidancere-latingtoseveralapproachesbywhichsuchademonstrationmaybeachieved.Becauseoftheplant-specificcharacterthatsuchdemonstrationsmusttake,NUREG0577doesnotrestrictthelicenseestoanysingleappro'achbut,instead,encourageseachlicenseetoreviewthefracture-toughnessadequacyofhisS/GandRCPsupportsandsubmitevidenceofhisfindings.I)llFranklinResearchCenterAowoenorHie'r@@dinInNatc n
TER-C5257-167/168 (Rev.1)4.1.2Interpretation Ifnosupplementary requirements werecalledoutinthematerialspe'cifi-cationaimedatprocuring aproductwithfracture-toughness properties supe-riortothoseroutinely suppliedunderthematerialspecification, thenthematerialwasgroupedinaccordance withTable4.6.Ifadditional requirements aimedatprocuring aproductwithsuperiorfracture-toughness properties werespecified, consideration wasgiventocred-/'tingthisspecificmaterialorderwithanimprovedmaterial-group rating.4~2PLANTGROUPINGFORFRACTURE-TOUGHNESS RANKINGOFS/GANDRCPSUPPORTSTRUCTURES 4.2.1Criterion plantsareclassified onthebasisoftheconstruction materials usedinI~thesupportsaftergivingconsideration totheimportance oftheirlocationandfunctionwithinthestructure, andtheirconsequent importance tosupport-structure integrity.
TER-C5257-167/168(Rev.1)5~TECHNICALEVALUATIONTheinformationfurnishedtotheNRCregardingthefracturetoughnessof,andthepotentialfoxlamellartearingin,S/GandRCPsupportsatD.C.CookUnits1and2wasreviewedatFRC.ThisinformationwassuppliedinresponsetotheNRCstaff'sgenericlettertoPNRlicenseesconcerningtheseissues.Acopyofthestaff'srequest-for-informationletter(ingenericform)maybefoundinNUREG05771AppendixB.OnlyfracturetoughnessissueswereaddressedintheFRCreview;thereviewprocedureisdescribedbelow.5.1REVIEWPROCEDUREANDIMPLEHENTATIONOFNRCCRITERIAThedrawingsandinformationsubmittedwerefirstexaminedtobecome~~familiarwiththestructuraldesign,materialselection,andconstructionpractices.Keyitemsfromthisinformationwerecondensedtotabularformand0arepresentedinTable5.1.InaccordancewithareviewprocedurestandardizedforthelicenseeswhoseplantswereevaluatedatFRC,thefirststepwastocompilealistofmaterialsusedinallmemberssignificanttothestructuralintegrityoftheS/GandRCPsupports.ThelistedmaterialsweretakenfromthyrsereportedintheresponsetoItem1oftheNRC'srequestforinformation>supplementedbyasurveyofthesupportdrawingsforadditionalmaterialswhichmightbeindi-catedthere.Toeachofthematerialssoidentified,twocriteriatestswereapplied:1.TheNDTcriteriaforscreening(paragraph4;3.1ofthisreport).2.ThematerialgrouprankinginaccordancewiththeproceduresofSection4.1.Forplantswhichusedthem,materialswithanassignedGroupIorGroupIIfracture-toughnessratingwerefurthercategorizedasthickorthinusingtheformulashownonthefollowingpagetodeterminethesectionthicknessabovewhichbrittle(plainstrain)behaviormaybeanticipatedunderdynamicload.  
(Refertopages5and.6ofNUREG0577,PartI.)4.2.2Interpretation plantswereassignedaplant-group rankingidentical tothematerial-group rankingoftheleastfracture-tough materialusedintheconstruction, pro-videdthisusageisimportant tosupportintegrity.
4~3CRITERIAFORFRACTURE-TOUGHNESS ADEQUACYOFS/GANDRCPSUPPORTSZtistheclearintentofNUREG0577thatlicensees demonstrate thefracture-toughness adequacyoftheS/GandRCpsupportsorthattheytake1appropriate corrective measurestoassuretheirfracture-toughness integrity.
NUREG0577providesguidanceforsuchdemonstrations.
4.3.1NDTCriteriaforScreening 30'FNDT+1~3o+or(F)supports60FI'!IIilFranklinResearchCenterADivaondTheFrabinhsacw TER-C5257-167/168 (Rev.1)where:oNDTisthemeannilductility transition temperature appro-'riate tothematerialasgivenbyTable4.4ofAppendixCtoNUREG0577'oisthestandarddeviation forthedatausedtodetermine NDTaslistedinTable4.4.0Tsupports isthelowestmetaltemperature thatthesupportmemberwilleverexperience throughout theplantlifewhentheplantisinanoperational state.Intheabsenceofmeasured, plant-specific data,Tsupports istakenas75'F.oThetemperature term,30'For60'F,isanallowance forsec-tionsize(30'Fforthinsectionsand60'Fforthicksec-tions).4.3.2Interpretation Ifevidenceisfurnished bythelicenseeprovingthatothervaluesofNDT,cr,orfareactuallyvalidfortheS/GorRCPsupportsandmateri-supportsalsinthelicensee's plant,suchdatamaybeused..Ifacceptable alternative evidenceisnotavailable, theabove-stipulated valuesshouldbeused.4.3.3Alternative CriteriaNUREG0577alsorecognized thatfracture-toughness integrity isacomplexmatterinvolving anumberofinterrelated factors,mostofwhichareplantspecific.
Consequently, demonstration ofcompliance withthescreening crite-riaisbutonemeansofproviding satisfactory assurance offracture-toughness adequacy.
NUREG0577notonlyrecognizes thatothermeansofshowingcompliance withtheintentofNUREG0577arepossible, butalsooffersextensive guidancere-latingtoseveralapproaches bywhichsuchademonstration maybeachieved.
Becauseoftheplant-specific character thatsuchdemonstrations musttake,NUREG0577doesnotrestrictthelicensees toanysingleappro'ach but,instead,encourages eachlicenseetoreviewthefracture-toughness adequacyofhisS/GandRCPsupportsandsubmitevidenceofhisfindings.
I)llFranklinResearchCenterAowoenorHie'r@@din InNatc n
TER-C5257-167/168 (Rev.1)5~TECHNICAL EVALUATION Theinformation furnished totheNRCregarding thefracturetoughness of,andthepotential foxlamellartearingin,S/GandRCPsupportsatD.C.CookUnits1and2wasreviewedatFRC.Thisinformation wassuppliedinresponsetotheNRCstaff'sgenericlettertoPNRlicensees concerning theseissues.Acopyofthestaff'srequest-for-information letter(ingenericform)maybefoundinNUREG05771AppendixB.Onlyfracturetoughness issueswereaddressed intheFRCreview;thereviewprocedure isdescribed below.5.1REVIEWPROCEDURE ANDIMPLEHENTATION OFNRCCRITERIAThedrawingsandinformation submitted werefirstexaminedtobecome~~familiarwiththestructural design,materialselection, andconstruction practices.
Keyitemsfromthisinformation werecondensed totabularformand0arepresented inTable5.1.Inaccordance withareviewprocedure standardized forthelicensees whoseplantswereevaluated atFRC,thefirststepwastocompilealistofmaterials usedinallmemberssignificant tothestructural integrity oftheS/GandRCPsupports.
Thelistedmaterials weretakenfromthyrsereportedintheresponsetoItem1oftheNRC'srequestforinformation>
supplemented byasurveyofthesupportdrawingsforadditional materials whichmightbeindi-catedthere.Toeachofthematerials soidentified, twocriteriatestswereapplied:1.TheNDTcriteriaforscreening (paragraph 4;3.1ofthisreport).2.Thematerialgrouprankinginaccordance withtheprocedures ofSection4.1.Forplantswhichusedthem,materials withanassignedGroupIorGroupIIfracture-toughness ratingwerefurthercategorized asthickorthinusingtheformulashownonthefollowing pagetodetermine thesectionthickness abovewhichbrittle(plainstrain)behaviormaybeanticipated underdynamicload.  


IsueTASKSSolCOMPONENTSUPtORTSUHHAkYtLAllflDonaldC.CoolII62Ul'ILITTIndiana6HichlkantonerNESSNeatlngouaeAEAnerleanElectr1<<touerConpenySIITIORT~OT~LIERHAT'LRIALSMAXIHUHALLOUAILEDESIGNSTRESSTIPSHILLCKRTS.NEATAVAILASLEIREAINCNTtRACllliEIOUCN!lCSSTOSTHCMIaANC6ECNUINC(NORMAL)INROIX:NTIIITTORSSCOIIstcuccconHeccrlalalA-6IUCc2A-36A-SSSkoltlnkHatcrlalalA-I&3SlAI'JbC[)AISI414$A-430AISI4340UeldinkHetcrlelelE6UXX~KIOXXSOI6-CI~ROIS-CI~SOIR-C0016C2~SOIRC2~2I/22or3-I(22NiContent~ubarcconeuuablcsTeeIesA36CoflueSralnpractice.Hocus1leadA-5SSInCritlealncubcrs.UTunderucllt'locu-Ihlcbnese~reaskeduccdAreaTesteCVNforA-SIS,A-36,A-5SSII5lt-lba030F).AlsoNAZendHeldHaterlal~Noruel-UpsetlAISCHasIueIAllousblcaKooeckencyl0.9SFaulteflHonl.IncorClastic-plasticAnalysI~0.65SytASRICATIONNKLDIMOtRUCLSSHenualMetalArcSubeccUCLDINC~lOTTOIIRSAISCCode,SectionIXQualifiedtro-'cduccstOSTUKLDINCTRCAIHCHTStcessReliefHKIINNSUSCDTOPRKVKNTLAMELLARICARINCAISCCodeJointsHUEAN>INSPCCTIONS~LRTOROTOUTorRTubccepoaalbleHPorLtULSICNlTPKOFSUl'PORTtinmolunnCODEUSCDLOAD!IKlCONDITIONSNofueloDLUpsctlDl.eTI,+OSEKsoeckencylDLeTLeDSEteulCedlDL+TL~DRCetkOMINIMUMIKMPCRATUkCOFRUPtORT60F(AnblcntCeoperatuceneer~uppocts) cC TER-C5257-167/168(Rev.1)Thecriticalthicknessisgivenby:"ZO225f)eyDwhere:tryDisthedynamicyieldstrengthofthesteel.K~Disthenominal,minimumassuredfracturetoughnessofthesteelinaccordancewithvaluessuppliedbymREG0577.tcisthecriticalthickness.Znmembersthickerthant,brittle(i.e.,planestrain)behaviormaybeexpected.AsimilarcategorizationforgroupZZlmaterialswasnotdeemednecessaryforpurposesofthereviewbecausesuchmaterialsaresanctionedforthick-sectionusebyvirtueoftheirgrouprating.Structuraldrawingswerethenexaminedfor:1.Allstructurallysignificantusesoft;roupImaterials.2.AllstructurallysignificantusesofGroupEImaterialsinthicksections.3.Structurallysignificantapplicationsofmaterialsknowntobesensitivetostresscorrosioncrackingorotherspecialfailuremechanismswhichmightmakethempronetobrittlebehavior.Thecircumstancesassociatedwithsuchusagewerethenexamined.Consider-IIationwasgiventofactorssuchas:directionofloadings(alwayscompressiveorsometimestensile),stresslevelsinthememberasindicatedinthelicensee'sresponse,thepresenceofstressraisersinmembergeometries,re-Idundancyofloadpaths,andthelike.Applicationsjudgedtobeofproblematicfracturetoughnesswereidentifiedformoredetailedevaluationatafuturedate.Xnaddition,informationfurnishedonweldingandonmaterialspecifica-tionswasexaminedforitsfracture-toughnessimplicationsbyaweldingengi-neerandametallurgist,respectively.IllFranklinResearchCenter-9-ADe!sionofTheFanklnInseue fill TERM5257-167/168(Rev.1)AsaresultofthereviewfindingsandinaccordancewiththecriteriaproceduredescribedinSection4.2ofthisreport,atentativeplantrankingforfracture-toughnessadequacyofS/GandRCPsupportswasassigned.52EXTENTOFFRCREVZENFRC'sevaluationswererestrictedtoassessmentsofthefracturetoughnessofsupportsforsteamgeneratorsandreactorcoolantpumps.Assessmentofthefracture-toughnessa'dequacyofsupportsforothercomponentsandoftheembed-mentwasnot:includedinthescopeofFRC'sworkassignmentandwasnotinves-tigated.5~3REVIEWFINDINGS5.3.1UseofGroupIMaterialsinApplicationsImportanttoStructuralIntegrityofSupportsNonefound.5.3.2ThickSectionUseofGroupIZMaterialsinApplicationsZmportanttoStructuralIntegrityNonefound.5.3.3ThinSectionUseofGroupZIMaterialsinApplicationsImportantToStructuralIntegrityAS'IMA-618steelisindicatedonbothS/GandRCPsupportdrawingsasthematerialforthemainverticalcolumns.Theseare.constructedof12inchdia-meter,doubleextra-strongpipe(i.e.,seamlesstubeof123/4incho.d.andwith1inchwalls).NUREG0577classifiesASTMA-618asaGroupZZsteelwhenfurnishedasformedandwithoutadditionalspecificationrequirements.However,AS'IMA-618Grade2wasspecifiedforthistubingandCharpyV-notchtestingwasrequired.SpecificationAS'INA-618Grade2limitssiliconcontenttoamaximumof0.30percent,andrequiresadditionofvanadium.Theactualsteelusedwasanalyzedtohaveonly0.19percentsilicon(sufficienttocompletelydeoxideI)llFranklinResearchCenterADivandTbcFra@OnInane 0
IsueTASKSSolCOMPONENT SUPtORTSUHHAkYtLAllflDonaldC.CoolII62Ul'ILITTIndiana6HichlkantonerNESSNeatlngouae AEAnerleanElectr1<<touerConpenySIITIORT~OT~LIERHAT'LRIALSMAXIHUHALLOUAILE DESIGNSTRESSTIPSHILLCKRTS.NEATAVAILASLE IREAINCNT tRACllliEIOUCN!lCSS TOSTHCMIaANC6ECNUINC(NORMAL)INROIX:NTIIITTORSS COIIstcucccon Heccrlalal A-6IUCc2A-36A-SSSkoltlnkHatcrlalal A-I&3SlAI'JbC[)AISI414$A-430AISI4340UeldinkHetcrlelel E6UXX~KIOXXSOI6-CI~ROIS-CI~SOIR-C0016C2~SOIRC2~2I/22or3-I(22NiContent~ubarcconeuuablcs TeeIesA36CoflueSralnpractice.
TER-C5257-167/168(Rev.1)thesteelaccordingtosilicon-killedpractice)andtocontain0.04percentvanadium(whichwouldtendtopromoteafinergrainsize).ThetestreportfurnishedintheinformationsuppliedtoNRCbyIMPCindicatedthatthesteelpossessedaCharpyV-notchimpactenergyof24ft-lbsat30'F.Thisvalue,iftypicalofallheats<qualifiesthissteeltobeofadequatequalityandtoughnessfor1inchsectionusage.5.3.4UseofMaterialsClassifiedGroupZZIbyNUREG0577,UponConditionASTMA-588isthemajorcomponentsteelofboththeS/GandRCPsupportsandwassuppliedasA-588>GradeA.ThissteelisclassifiedinNUREG0577asaGroupZImaterialintheas-rolledorhot-workedcondition.However,insections1/2inchthickandover,thesteelwasorderednormalizedandCharpyV-notchimpacttestswererequired.Thetestdatafurnishedforreviewindi-cateadequatetoughnessat30'Finallthicknesses.Inviewoftheadditionalrequirementsspecified,theA-588steelusedinthisapplicationisdeemedtobeof-'sufficientqualityandtoughnesstomeritaGroupZZZmaterialrating.ThetextandmaterialstableoftheZMPCletterofresponserefertouseofASTMA-36steelasamaterialofconstructionforS/GandRCPsupportsintheCookplants.ThesealsostatethatitwasorderedtofinegrainpracticeandrequiredtobesubjectedtoCharpyimpacttesting.WithsuchhdditionalrequirementstheA-36steelwouldbeconsidered,underNUREG0577criteria,assanctionedforgeneraluseinS/GandRCPsupports.However,FRCdidnotfinditindicatedasamaterialofconstructiononanyofthedrawingsfurnishedforreviewnorcouldmilltestorothermaterialdata'forthissteelbefoundamongtheextensiveinformationsupplied.Thus<althoughthereasonforlistingA-36steelasamaterialofconstructionisnotclear;whenoideredtothestatedrequirementsA-36isaGroupZZIsteel,anditsusewouldnotaffectthefinalclassificationofthisplant.5.3.5UseofMaterialsClassifiedGroupIIZbyNUREG0577,OutrightAllboltingandweldingmaterials.!)I)FranklinResearchCenterADhsioncrTheFrank' TER-C5257-167/168(Rev.1)6~CONCLUSIONSThedesignandconstructionofsupportsforsteamgeneratorsandreactorcoolantpumpsatDonaldC.CookNuclearPowerPlantUnits1and2havebeenreviewedforfracture>>toughnessadequacyattheFRC.CriteriaforthesuitabilityofmaterialsandconstructionpracticesforS/GandRCPsupportswereprovidedbytheNRCstaffaspublishedinNUREG0577-Draft.Inthereview,generalcriteriaofNUREG0577werespecificallyappliedtoinformationfurnishedbyIndianaandMichiganPowerCompany(IMPC)concern-ingthesupportsinD.C.CookUnits1and2.Thereviewwasrestrictedtosupports(abovetheembedment)forsteam'eneratorsandreactorcoolantpumps.Conclusionsrelatingtothemdonotnecessarilyextendtothesupportdesignofothercomponents.'I~InthecaseofD.C.CookUnits1and2FRCconcludesthat:l.Engineeringmeasurestakeninsupportdesign,materialselection,materialspecification,materialacceptancetesting,fabricationmethods,andinspectionsprovidereasonableevidencethatthesteamgeneratorsupportstructurespossessadequatefracturetoughnesstomeetNRCcriteriaforaGroupIIIrating.2.EngineeringmeasurestakeninthedesignandconstructionofthereactorcoolantpumpsupportsprovidesimilarevidencetoqualifythemforaGroupIIIratingalso.3.TheGroupIII(relativelyhighest)plantratingforfracture-toughnessadequacyofsupportsassignedtoDonaldCCookNuclearPowerPlantUnits1and2inNUREG0577-Draftisjustifiable.
Hocus1leadA-5SSInCritlealncubcrs.UTunderucllt'locu-Ihlcbnese
~reaskeduccdAreaTesteCVNforA-SIS,A-36,A-5SSII5lt-lba030F).AlsoNAZendHeldHaterlal~Noruel-Upsetl AISCHasIueIAllousblca Kooeckencyl 0.9SFaulteflHonl.IncorClastic-plastic AnalysI~0.65SytASRICATIONNKLDIMOtRUCLSSHenualMetalArcSubeccUCLDINC~lOTTOIIRS AISCCode,SectionIXQualified tro-'cduccstOSTUKLDINCTRCAIHCHT StcessReliefHKIINNSUSCDTOPRKVKNTLAMELLARICARINCAISCCodeJointsHUEAN>INSPCCTIONS~LRTOROTOUTorRTubccepoaalbleHPorLtULSICNlTPKOFSUl'PORTtinmolunn CODEUSCDLOAD!IKlCONDITIONS NofueloDLUpsctlDl.eTI,+OSEKsoeckencyl DLeTLeDSEteulCedlDL+TL~DRCetkOMINIMUMIKMPCRATUkC OFRUPtORT60F(AnblcntCeoperatuce neer~uppocts) cC TER-C5257-167/168 (Rev.1)Thecriticalthickness isgivenby:"ZO225f)eyDwhere:tryDisthedynamicyieldstrengthofthesteel.K~Disthenominal,minimumassuredfracturetoughness ofthesteelinaccordance withvaluessuppliedbymREG0577.tcisthecriticalthickness.
Znmembersthickerthant,brittle(i.e.,planestrain)behaviormaybeexpected.
Asimilarcategorization forgroupZZlmaterials wasnotdeemednecessary forpurposesofthereviewbecausesuchmaterials aresanctioned forthick-sectionusebyvirtueoftheirgrouprating.Structural drawingswerethenexaminedfor:1.Allstructurally significant usesoft;roupImaterials.
2.Allstructurally significant usesofGroupEImaterials inthicksections.
3.Structurally significant applications ofmaterials knowntobesensitive tostresscorrosion crackingorotherspecialfailuremechanisms whichmightmakethempronetobrittlebehavior.
Thecircumstances associated withsuchusagewerethenexamined.
Consider-IIationwasgiventofactorssuchas:direction ofloadings(alwayscompressive orsometimes tensile),
stresslevelsinthememberasindicated inthelicensee's
: response, thepresenceofstressraisersinmembergeometries, re-Idundancyofloadpaths,andthelike.Applications judgedtobeofproblematic fracturetoughness wereidentified formoredetailedevaluation atafuturedate.Xnaddition, information furnished onweldingandonmaterialspecifica-tionswasexaminedforitsfracture-toughness implications byaweldingengi-neerandametallurgist, respectively.
IllFranklinResearchCenter-9-ADe!sionofTheFanklnInseue fill TERM5257-167/168 (Rev.1)Asaresultofthereviewfindingsandinaccordance withthecriteriaprocedure described inSection4.2ofthisreport,atentative plantrankingforfracture-toughness adequacyofS/GandRCPsupportswasassigned.
52EXTENTOFFRCREVZENFRC'sevaluations wererestricted toassessments ofthefracturetoughness ofsupportsforsteamgenerators andreactorcoolantpumps.Assessment ofthefracture-toughness a'dequacy ofsupportsforothercomponents andoftheembed-mentwasnot:includedinthescopeofFRC'sworkassignment andwasnotinves-tigated.5~3REVIEWFINDINGS5.3.1UseofGroupIMaterials inApplications Important toStructural Integrity ofSupportsNonefound.5.3.2ThickSectionUseofGroupIZMaterials inApplications Zmportant toStructural Integrity Nonefound.5.3.3ThinSectionUseofGroupZIMaterials inApplications Important ToStructural Integrity AS'IMA-618steelisindicated onbothS/GandRCPsupportdrawingsasthematerialforthemainverticalcolumns.Theseare.constructed of12inchdia-meter,doubleextra-strong pipe(i.e.,seamlesstubeof123/4incho.d.andwith1inchwalls).NUREG0577classifies ASTMA-618asaGroupZZsteelwhenfurnished asformedandwithoutadditional specification requirements.
However,AS'IMA-618Grade2wasspecified forthistubingandCharpyV-notchtestingwasrequired.
Specification AS'INA-618Grade2limitssiliconcontenttoamaximumof0.30percent,andrequiresadditionofvanadium.
Theactualsteelusedwasanalyzedtohaveonly0.19percentsilicon(sufficient tocompletely deoxideI)llFranklinResearchCenterADivandTbcFra@OnInane 0
TER-C5257-167/168 (Rev.1)thesteelaccording tosilicon-killed practice) andtocontain0.04percentvanadium(whichwouldtendtopromoteafinergrainsize).Thetestreportfurnished intheinformation suppliedtoNRCbyIMPCindicated thatthesteelpossessed aCharpyV-notchimpactenergyof24ft-lbsat30'F.Thisvalue,iftypicalofallheats<qualifies thissteeltobeofadequatequalityandtoughness for1inchsectionusage.5.3.4UseofMaterials Classified GroupZZIbyNUREG0577,UponCondition ASTMA-588isthemajorcomponent steelofboththeS/GandRCPsupportsandwassuppliedasA-588>GradeA.Thissteelisclassified inNUREG0577asaGroupZImaterialintheas-rolled orhot-worked condition.
However,insections1/2inchthickandover,thesteelwasorderednormalized andCharpyV-notchimpacttestswererequired.
Thetestdatafurnished forreviewindi-cateadequatetoughness at30'Finallthicknesses.
Inviewoftheadditional requirements specified, theA-588steelusedinthisapplication isdeemedtobeof-'sufficient qualityandtoughness tomeritaGroupZZZmaterialrating.Thetextandmaterials tableoftheZMPCletterofresponserefertouseofASTMA-36steelasamaterialofconstruction forS/GandRCPsupportsintheCookplants.Thesealsostatethatitwasorderedtofinegrainpracticeandrequiredtobesubjected toCharpyimpacttesting.Withsuchhdditional requirements theA-36steelwouldbeconsidered, underNUREG0577criteria, assanctioned forgeneraluseinS/GandRCPsupports.
However,FRCdidnotfinditindicated asamaterialofconstruction onanyofthedrawingsfurnished forreviewnorcouldmilltestorothermaterialdata'forthissteelbefoundamongtheextensive information supplied.
Thus<althoughthereasonforlistingA-36steelasamaterialofconstruction isnotclear;whenoideredtothestatedrequirements A-36isaGroupZZIsteel,anditsusewouldnotaffectthefinalclassification ofthisplant.5.3.5UseofMaterials Classified GroupIIZbyNUREG0577,OutrightAllboltingandweldingmaterials.
!)I)FranklinResearchCenterADhsioncrTheFrank' TER-C5257-167/168 (Rev.1)6~CONCLUSIONS Thedesignandconstruction ofsupportsforsteamgenerators andreactorcoolantpumpsatDonaldC.CookNuclearPowerPlantUnits1and2havebeenreviewedforfracture>>toughness adequacyattheFRC.Criteriaforthesuitability ofmaterials andconstruction practices forS/GandRCPsupportswereprovidedbytheNRCstaffaspublished inNUREG0577-Draft.Inthereview,generalcriteriaofNUREG0577werespecifically appliedtoinformation furnished byIndianaandMichiganPowerCompany(IMPC)concern-ingthesupportsinD.C.CookUnits1and2.Thereviewwasrestricted tosupports(abovetheembedment) forsteam'enerators andreactorcoolantpumps.Conclusions relatingtothemdonotnecessarily extendtothesupportdesignofothercomponents.
'I~InthecaseofD.C.CookUnits1and2FRCconcludes that:l.Engineering measurestakeninsupportdesign,materialselection, materialspecification, materialacceptance testing,fabrication methods,andinspections providereasonable evidencethatthesteamgenerator supportstructures possessadequatefracturetoughness tomeetNRCcriteriaforaGroupIIIrating.2.Engineering measurestakeninthedesignandconstruction ofthereactorcoolantpumpsupportsprovidesimilarevidencetoqualifythemforaGroupIIIratingalso.3.TheGroupIII(relatively highest)plantratingforfracture-toughness adequacyofsupportsassignedtoDonaldCCookNuclearPowerPlantUnits1and2inNUREG0577-Draft isjustifiable.
IJANES881}}
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Revision as of 08:22, 29 June 2018

Fracture Toughness of Steam Generator & Reactor Coolant Pump Supports,Dc Cook Units 1 & 2, Revised Technical Evaluation Rept
ML17331A613
Person / Time
Site: Cook  
Issue date: 11/30/1980
From: ALLTEN A G, DORSCHU K E, STILWELL T C
FRANKLIN INSTITUTE
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17331A610 List:
References
CON-NRC-03-79-118, CON-NRC-3-79-118 TER-C5257-167, TER-C5257-167-168-R1, NUDOCS 8102060575
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Text

Enclosure 2TECHNICALEVAL'JAT)ON REPORTFRACTURETOUGHNESS OFSTEAMGENER4TORANDREACTORCOOLANTpUMPSUPPORTSINDIANAaHICHIGA')

POgt":RCylP@y.DONALDCCOOKNUCLEARPOKERPLANTUNITS1AND2NRCDOCKETNO.$0-315and50-316NRCTACNO.

08479and08486NRCCONTRACTNb.NRC43.79'ttbFRCPROJECTCSB7FRCTASK167and168PreparedbyFranklinResearchCenterTheParkwayatTwentieth StreetPhHadelphia, PA19163AuthOrS:T.C.S&lvel',

h.G.hllCen, K.E.Dozschu, P.N.Noell FRCGroupLeadei:T.C.ScQ~lL PreparedforNuclearRegulatory Commission Washington, D,C.20%5LeadNREngineer:

J.R.FairRevision1,Novemberl980Thisreportwaspreparedasanaccountofworksponsored byanagencyoftheUnitedStatesGovernment.

NeithertheUnitedStatesGovernment noranyagencythereof,oranyoftheiremployees, makesanywarranty, expressed orimplied,'or assumesanylegalliability orresponsibility foranythirdparty'suse,ortheresultsofsuchuse,ofanyinformation, apparatus, productorprocessdisclosed lnthisreport,orrepresents thatitsusebysuchthirdpartywouldnotinfringeprivately ownedrights,!F'ran}din ResearchCenterADivisionofTheFranklinInstitute ThehnjstnnPronount'snowy.Phiii..Pal9I03(2JSi4ib)COO TER-C5257-167/168 (Rev.1)CONTENTSSectionTitleParcae1SUMMARY~~t~~~~~~~~~2INTRODUCTION 3BACKGROUND

~/4CRITERIAAPPLIEDINTHEEVALUATION

~4.1Fracture-Toughness GroupingofMaterials UsedinSupportConstruction

.4.1.1Criterion 4.1.2Interpretation.

4.2PlantGroupingforFracture-Toughness RankingofS/GandRCPSupportStructures 4.2.1Criterion

.4.2.2Interpretation.

4.3CriteriaforFracture-Toughness AdequacyofS/GandRCPSupports.4.3.1NDTCriteriaforScreening.

4.3.2Interpretation.

4.3.3Alternative Criteria5TECHNICAL EVALUATION 5.1ReviewProcedure andImplementation ofNRCCriteria775.2ExtentofFRC'sReview.105.3ReviewFindings5.3.1UseofGroupIMaterials inApplications Important toStructural Integrity ofSupports~~~~~~5.3.2ThickSectionUseofGroupIIMaterials inApplications Zmportant toStructural Integrity

.10,1010 TER-C5257-167/168 (Rev.1)5.3.3ThinSectionUseofGroupIIMaterials inApplications Important ToStructural Integrity

.5.3.4UseofMaterials Classified GroupIIIbyNUREG0577,UponCondition.

5.3.5UseofMaterials Classified GroupIIIbyNUREG0577<Outright6CONCLUSIONS 101112crumbrTABLETitlePaae51COMPONENT SUPPORTSUMMARY~.~~~~~.8009FranklinResearchCenterAOesicnatTbaFranenhauteiv TER-C5257-167/168 (Rev.1)1~SUMMARYInformation concerning aspectsofthefracture-toughness designofthesteamgenerator (S/G)andreactorcoolantpump(RCP)supportsfortheDonaldC.CookNuclearPowerPlantUnits1and2wassubmitted totheActingDirectoroftheOfficeofNuclearRegulation bytheIndianaandMichiganPowerCompany(IMPC)byletterdatedNov.23,1977.Thisinformation wasreviewedattheFranklinResearchCenter(FRC)andevaluated inaccordance withthecriteriaoftheNuclearRegulatory Commission (NRC)assetforthinNUREG0577-Draft (henceforth referredtosimplyasNUREG0577).Theinformation hadpreviously beenreviewedaspartofthepreparation ofNUREG0577,andD.C.CookUnits1and2hadbeenassignedaGroupZZZ(rela-tivelybest)plantrankingforfracturetoughness ofS/GandRCPsupports.

Thisrankingwasregardedastentative.

Subsequently, theNRCrequested FRCtoconductanindependent reviewpriortofinalizing theranking.sF((C'sreviewwasconfinedtofracture-toughness issuesinsupportsabovetheembedment.

Thereviewwasconducted inaccordance withNRCcriteriaandtoaprocedure standardized fortheseverallicensees whosesupportdesignswerereviewedatFRC.Asaresultofitsreview,FRCconfirmed thattheGroupZIIplantrankingassignedtoDonaldC.CookNuclearPowerPlantsUnits1and2forfracturetoughness ofS/GandRCPsupportsisjustifiable.

2INTRODUCTION Thisreportprovidesatechnical evaluation ofinformation suppliedbyIMPCIwithitsletterofNov.23,1977,toMr.EdsonG.Case,ActingDirectorOfficeofNuclearRegulation.

Theinformation concernsthefracture-toughness designofsupportsfortheS/GsandRCPsforD.C.CookUnits1and2.Theobjective oftheevaluation istorankthedesignforfracture-toughness integrity onarelativescaleinaccordance withthegroupingschemeandcriteriaestablished inNUREG0577.0llFranklinResearchCenterAOMsionofTheFlank&~

TER-C5257-167/168 (Rev.1)3~BACKGROUND DuringthecourseoftheNRClicensing reviewfortwopressurized waterreactors(PHR),NorthAnnaUnits1and2,questions vereraisedregarding thefracture-toughness adequacyofcertainmembersoftheS/GandRCPsupports.

Thepotential forlamellartearinginsomesupportmemberswasalsoquestioned.

Thestaff'sconcernintheNorthAnnalicensing processwasthatperhapsnotenoughattention hadbeengiventotheselection ofmaterials for,andfabrication of,theS/GandRCPsupports.

Fracturetoughness ofamaterialisameasureofitscapability toabsorbenergywithoutfailureordamage.Generally, amaterialisconsidered

'tough"when,understatedconditions ofstressandtemperature, thematerialcanwithstand loadingtoitsdesignlimitinthepresenceofflaws.Toughness alsoimpliesthat,undercertainconditions, thematerialhasthecapability toarrestthegrowthofaflaw.Alackofadequatetoughness (accompanied byrthecombination oflowoperating temperature>

presenceofflaws>andnonredun-dancyofcriticalsupportmembers)couldresultinrailureofthesupportstructure underpostulated accidentconditionsr specifically aloss-of-coolant accident(LOCA)andsafeshutdownearthquake (SSE).Toaddressfracture-toughness concernsattheNorthAnnafacility, thelicenseeundertook testsnotoriginally specified andnotincludedintherelevantASSNspecifications.

Thesetestsindicated thatmaterialusedincertainsupportmembershadrelatively poorfracturetoughness at804Pmetaltemperature.

Inthiscase,thelicenseeagreedtoraise(byancillary electrical heat)thetemperature oftheS/Gsupportbeamsinquestiontoaminimumof2254Feverytime,throughout thelifeoftheplant,thatthereactorcoolantsystem(RCS)ispressurized above1,000psig.TheNRCstafffoundthistobeanacceptable resolution.

Becausesimilarmaterials anddesignswereusedinotherplantsandbe-causesimilarproblemsweretherefore

possible, thismattervasincorporated intotheNRCProgramforResolution ofGenericIssuesas"GenericTechnical ll00FranklinResearchCenterADivisiondIbcFranAnhshu TER-C5257-167/168 (Rev.1)ActivityA-12Potential forLowFractureToughness andLamellarTearingonPWRSteamGenerator andReactorCoolantPumpSupports."

Sincetheoriginallicensing action(NorthAnnaUnits1and2)involvedonlytheS/GandRCPsupportsofPWRs,thestaff'sinitialeffortsweredi-rectedtowardexamination ofthecorresponding supportsatotherPWRfacili-ties.However,thestaffhaskeptinmindthepossibility ofexpanding itsreviewtoincludeothersupportstructures inPWRplantsandsupportstruc-turesinboilingwaterreactor(BWR)plants.Theintegrity ofsupportembedments wasnotquestioned duringtheNorthAnnalicensing action;consequently, emphasiswasplacedonresolving themostimmediate genericissue-whetherornotproblemssimilartothoseuncovered atNorthAnnaexistatotherfacilities.

Itwasthestaff'sjudgmentthatinclusion ofanevaluation ofsupportembedments intheinitialreviewwouldrequiredetailed, plant-specific investigations thatwerebeyondthescopeofthepreliminary, overallgenericreview.Suchconsiderations weredeemedmoresuitecftoasubsequent phasewhenmoredetailedinvestigations ofindividual plantsmightbeundertaken.

Requestsforinformation weresenttolicensees inlate1977;responses totheserequestswerereceivedduring1978.SandiaLaboratories inAlbuquerque, NewMexico,wasretainedtoassistthestaffinthereviewandanalysisoftheinformation receivedfromlicensees andapplicants.

Basedonanalysisofthisinformationr thetechnical studiesperformed bySandiaLaboratories, andreviewoftheissuesbytheNRCstaff,theNRCdeveloped anNRCstafftechnical positionontheseissuesrwhichispresented inNUREG0577,"Potential forLowFractureToughness andLamellarTearingonPWRSteamGenerator andReactorCoolantPumpSupports."

Inaddition, NUREG0577establishes criteriaforevaluation ofthefracture-toughness adequacyofS/GandRCPsupports.

NUREG0577alsoappliescertainofthesecriteriatothesupportstructures ofanumberofPWRplantstoachieveplantgroupings according totherelativefracture-toughness inte-grityofthesesupports.

tillFranklinResearchCenterADivwon81&iFrankhn~

'li TER-C5257-167/168 (Rev.1)Theplantratingsare:~GroupI(lowest)eGroupII(intermediate)

~GroupIII(highest)

Duringthegenericstudy,anumberofPWRplantswerereviewedforthefracture-toughness adequacyoftheirRCPandS/Gdesigns.Asaresultofthesereviews,eachplantwasassignedatentative plantrankingofeitherGroupI,II,orIII.SeveralPlants,D.C.CookUnits1and2amongthem,weretentatively rankedGroupIII.IntheappendixtoNUREG0577preparedbySandiaLabora-tories,whoinitially established therankingswhichsubsequently receivedNRCstaffendorsement, thesignificance oftheGroupIIIrankingisdescribed as:considered tobeasgoodascareful,reasonable engineering practicecanproduce."However,beforefinalizing thetentative GroupIIIrankings, theNRCrequested FRCtoconductanindependent reviewoftheGroupIIIplants(incon~unction withsimilarFRCtaskassignments toreviewthefracture-toughness adequacyofcorresponding supportsincertainotherplants)andtoprepareaTechnical Evaluation Reportforeachplant,presenting thereviewfindings.

Thetechnical evaluation reportedhereinappliesthecriteriaofNUREG0577totheS/GandRCPsupportsforD.C.CookUnits1and2toprovideanassessment ofthefracture-toughness adequacyofthesesupportsleadingtoaplantranking.4~CRITERIAAPPLIEDINTHEEVALUATION 4~1FRACTURE-%)UGHNESS GROUPINGOFMATERIALS USEDINSUPPORTCONSTRUCTION 4.1.1Criterion Table4.6,MaterialGroups,ofAppendixCtoNUREG0577groupsmaterials according totheirrelativefracturetoughness as:~GroupI(poorest) oGroupII(intermediate)

~GroupIII(best)JU~~LFrankjinResearchCenterA~dTheFranklinInseam

TER-C5257-167/168 (Rev.1)4.1.2Interpretation Ifnosupplementary requirements werecalledoutinthematerialspe'cifi-cationaimedatprocuring aproductwithfracture-toughness properties supe-riortothoseroutinely suppliedunderthematerialspecification, thenthematerialwasgroupedinaccordance withTable4.6.Ifadditional requirements aimedatprocuring aproductwithsuperiorfracture-toughness properties werespecified, consideration wasgiventocred-/'tingthisspecificmaterialorderwithanimprovedmaterial-group rating.4~2PLANTGROUPINGFORFRACTURE-TOUGHNESS RANKINGOFS/GANDRCPSUPPORTSTRUCTURES 4.2.1Criterion plantsareclassified onthebasisoftheconstruction materials usedinI~thesupportsaftergivingconsideration totheimportance oftheirlocationandfunctionwithinthestructure, andtheirconsequent importance tosupport-structure integrity.

(Refertopages5and.6ofNUREG0577,PartI.)4.2.2Interpretation plantswereassignedaplant-group rankingidentical tothematerial-group rankingoftheleastfracture-tough materialusedintheconstruction, pro-videdthisusageisimportant tosupportintegrity.

4~3CRITERIAFORFRACTURE-TOUGHNESS ADEQUACYOFS/GANDRCPSUPPORTSZtistheclearintentofNUREG0577thatlicensees demonstrate thefracture-toughness adequacyoftheS/GandRCpsupportsorthattheytake1appropriate corrective measurestoassuretheirfracture-toughness integrity.

NUREG0577providesguidanceforsuchdemonstrations.

4.3.1NDTCriteriaforScreening 30'FNDT+1~3o+or(F)supports60FI'!IIilFranklinResearchCenterADivaondTheFrabinhsacw TER-C5257-167/168 (Rev.1)where:oNDTisthemeannilductility transition temperature appro-'riate tothematerialasgivenbyTable4.4ofAppendixCtoNUREG0577'oisthestandarddeviation forthedatausedtodetermine NDTaslistedinTable4.4.0Tsupports isthelowestmetaltemperature thatthesupportmemberwilleverexperience throughout theplantlifewhentheplantisinanoperational state.Intheabsenceofmeasured, plant-specific data,Tsupports istakenas75'F.oThetemperature term,30'For60'F,isanallowance forsec-tionsize(30'Fforthinsectionsand60'Fforthicksec-tions).4.3.2Interpretation Ifevidenceisfurnished bythelicenseeprovingthatothervaluesofNDT,cr,orfareactuallyvalidfortheS/GorRCPsupportsandmateri-supportsalsinthelicensee's plant,suchdatamaybeused..Ifacceptable alternative evidenceisnotavailable, theabove-stipulated valuesshouldbeused.4.3.3Alternative CriteriaNUREG0577alsorecognized thatfracture-toughness integrity isacomplexmatterinvolving anumberofinterrelated factors,mostofwhichareplantspecific.

Consequently, demonstration ofcompliance withthescreening crite-riaisbutonemeansofproviding satisfactory assurance offracture-toughness adequacy.

NUREG0577notonlyrecognizes thatothermeansofshowingcompliance withtheintentofNUREG0577arepossible, butalsooffersextensive guidancere-latingtoseveralapproaches bywhichsuchademonstration maybeachieved.

Becauseoftheplant-specific character thatsuchdemonstrations musttake,NUREG0577doesnotrestrictthelicensees toanysingleappro'ach but,instead,encourages eachlicenseetoreviewthefracture-toughness adequacyofhisS/GandRCPsupportsandsubmitevidenceofhisfindings.

I)llFranklinResearchCenterAowoenorHie'r@@din InNatc n

TER-C5257-167/168 (Rev.1)5~TECHNICAL EVALUATION Theinformation furnished totheNRCregarding thefracturetoughness of,andthepotential foxlamellartearingin,S/GandRCPsupportsatD.C.CookUnits1and2wasreviewedatFRC.Thisinformation wassuppliedinresponsetotheNRCstaff'sgenericlettertoPNRlicensees concerning theseissues.Acopyofthestaff'srequest-for-information letter(ingenericform)maybefoundinNUREG05771AppendixB.Onlyfracturetoughness issueswereaddressed intheFRCreview;thereviewprocedure isdescribed below.5.1REVIEWPROCEDURE ANDIMPLEHENTATION OFNRCCRITERIAThedrawingsandinformation submitted werefirstexaminedtobecome~~familiarwiththestructural design,materialselection, andconstruction practices.

Keyitemsfromthisinformation werecondensed totabularformand0arepresented inTable5.1.Inaccordance withareviewprocedure standardized forthelicensees whoseplantswereevaluated atFRC,thefirststepwastocompilealistofmaterials usedinallmemberssignificant tothestructural integrity oftheS/GandRCPsupports.

Thelistedmaterials weretakenfromthyrsereportedintheresponsetoItem1oftheNRC'srequestforinformation>

supplemented byasurveyofthesupportdrawingsforadditional materials whichmightbeindi-catedthere.Toeachofthematerials soidentified, twocriteriatestswereapplied:1.TheNDTcriteriaforscreening (paragraph 4;3.1ofthisreport).2.Thematerialgrouprankinginaccordance withtheprocedures ofSection4.1.Forplantswhichusedthem,materials withanassignedGroupIorGroupIIfracture-toughness ratingwerefurthercategorized asthickorthinusingtheformulashownonthefollowing pagetodetermine thesectionthickness abovewhichbrittle(plainstrain)behaviormaybeanticipated underdynamicload.

IsueTASKSSolCOMPONENT SUPtORTSUHHAkYtLAllflDonaldC.CoolII62Ul'ILITTIndiana6HichlkantonerNESSNeatlngouae AEAnerleanElectr1<<touerConpenySIITIORT~OT~LIERHAT'LRIALSMAXIHUHALLOUAILE DESIGNSTRESSTIPSHILLCKRTS.NEATAVAILASLE IREAINCNT tRACllliEIOUCN!lCSS TOSTHCMIaANC6ECNUINC(NORMAL)INROIX:NTIIITTORSS COIIstcucccon Heccrlalal A-6IUCc2A-36A-SSSkoltlnkHatcrlalal A-I&3SlAI'JbC[)AISI414$A-430AISI4340UeldinkHetcrlelel E6UXX~KIOXXSOI6-CI~ROIS-CI~SOIR-C0016C2~SOIRC2~2I/22or3-I(22NiContent~ubarcconeuuablcs TeeIesA36CoflueSralnpractice.

Hocus1leadA-5SSInCritlealncubcrs.UTunderucllt'locu-Ihlcbnese

~reaskeduccdAreaTesteCVNforA-SIS,A-36,A-5SSII5lt-lba030F).AlsoNAZendHeldHaterlal~Noruel-Upsetl AISCHasIueIAllousblca Kooeckencyl 0.9SFaulteflHonl.IncorClastic-plastic AnalysI~0.65SytASRICATIONNKLDIMOtRUCLSSHenualMetalArcSubeccUCLDINC~lOTTOIIRS AISCCode,SectionIXQualified tro-'cduccstOSTUKLDINCTRCAIHCHT StcessReliefHKIINNSUSCDTOPRKVKNTLAMELLARICARINCAISCCodeJointsHUEAN>INSPCCTIONS~LRTOROTOUTorRTubccepoaalbleHPorLtULSICNlTPKOFSUl'PORTtinmolunn CODEUSCDLOAD!IKlCONDITIONS NofueloDLUpsctlDl.eTI,+OSEKsoeckencyl DLeTLeDSEteulCedlDL+TL~DRCetkOMINIMUMIKMPCRATUkC OFRUPtORT60F(AnblcntCeoperatuce neer~uppocts) cC TER-C5257-167/168 (Rev.1)Thecriticalthickness isgivenby:"ZO225f)eyDwhere:tryDisthedynamicyieldstrengthofthesteel.K~Disthenominal,minimumassuredfracturetoughness ofthesteelinaccordance withvaluessuppliedbymREG0577.tcisthecriticalthickness.

Znmembersthickerthant,brittle(i.e.,planestrain)behaviormaybeexpected.

Asimilarcategorization forgroupZZlmaterials wasnotdeemednecessary forpurposesofthereviewbecausesuchmaterials aresanctioned forthick-sectionusebyvirtueoftheirgrouprating.Structural drawingswerethenexaminedfor:1.Allstructurally significant usesoft;roupImaterials.

2.Allstructurally significant usesofGroupEImaterials inthicksections.

3.Structurally significant applications ofmaterials knowntobesensitive tostresscorrosion crackingorotherspecialfailuremechanisms whichmightmakethempronetobrittlebehavior.

Thecircumstances associated withsuchusagewerethenexamined.

Consider-IIationwasgiventofactorssuchas:direction ofloadings(alwayscompressive orsometimes tensile),

stresslevelsinthememberasindicated inthelicensee's

response, thepresenceofstressraisersinmembergeometries, re-Idundancyofloadpaths,andthelike.Applications judgedtobeofproblematic fracturetoughness wereidentified formoredetailedevaluation atafuturedate.Xnaddition, information furnished onweldingandonmaterialspecifica-tionswasexaminedforitsfracture-toughness implications byaweldingengi-neerandametallurgist, respectively.

IllFranklinResearchCenter-9-ADe!sionofTheFanklnInseue fill TERM5257-167/168 (Rev.1)Asaresultofthereviewfindingsandinaccordance withthecriteriaprocedure described inSection4.2ofthisreport,atentative plantrankingforfracture-toughness adequacyofS/GandRCPsupportswasassigned.

52EXTENTOFFRCREVZENFRC'sevaluations wererestricted toassessments ofthefracturetoughness ofsupportsforsteamgenerators andreactorcoolantpumps.Assessment ofthefracture-toughness a'dequacy ofsupportsforothercomponents andoftheembed-mentwasnot:includedinthescopeofFRC'sworkassignment andwasnotinves-tigated.5~3REVIEWFINDINGS5.3.1UseofGroupIMaterials inApplications Important toStructural Integrity ofSupportsNonefound.5.3.2ThickSectionUseofGroupIZMaterials inApplications Zmportant toStructural Integrity Nonefound.5.3.3ThinSectionUseofGroupZIMaterials inApplications Important ToStructural Integrity AS'IMA-618steelisindicated onbothS/GandRCPsupportdrawingsasthematerialforthemainverticalcolumns.Theseare.constructed of12inchdia-meter,doubleextra-strong pipe(i.e.,seamlesstubeof123/4incho.d.andwith1inchwalls).NUREG0577classifies ASTMA-618asaGroupZZsteelwhenfurnished asformedandwithoutadditional specification requirements.

However,AS'IMA-618Grade2wasspecified forthistubingandCharpyV-notchtestingwasrequired.

Specification AS'INA-618Grade2limitssiliconcontenttoamaximumof0.30percent,andrequiresadditionofvanadium.

Theactualsteelusedwasanalyzedtohaveonly0.19percentsilicon(sufficient tocompletely deoxideI)llFranklinResearchCenterADivandTbcFra@OnInane 0

TER-C5257-167/168 (Rev.1)thesteelaccording tosilicon-killed practice) andtocontain0.04percentvanadium(whichwouldtendtopromoteafinergrainsize).Thetestreportfurnished intheinformation suppliedtoNRCbyIMPCindicated thatthesteelpossessed aCharpyV-notchimpactenergyof24ft-lbsat30'F.Thisvalue,iftypicalofallheats<qualifies thissteeltobeofadequatequalityandtoughness for1inchsectionusage.5.3.4UseofMaterials Classified GroupZZIbyNUREG0577,UponCondition ASTMA-588isthemajorcomponent steelofboththeS/GandRCPsupportsandwassuppliedasA-588>GradeA.Thissteelisclassified inNUREG0577asaGroupZImaterialintheas-rolled orhot-worked condition.

However,insections1/2inchthickandover,thesteelwasorderednormalized andCharpyV-notchimpacttestswererequired.

Thetestdatafurnished forreviewindi-cateadequatetoughness at30'Finallthicknesses.

Inviewoftheadditional requirements specified, theA-588steelusedinthisapplication isdeemedtobeof-'sufficient qualityandtoughness tomeritaGroupZZZmaterialrating.Thetextandmaterials tableoftheZMPCletterofresponserefertouseofASTMA-36steelasamaterialofconstruction forS/GandRCPsupportsintheCookplants.Thesealsostatethatitwasorderedtofinegrainpracticeandrequiredtobesubjected toCharpyimpacttesting.Withsuchhdditional requirements theA-36steelwouldbeconsidered, underNUREG0577criteria, assanctioned forgeneraluseinS/GandRCPsupports.

However,FRCdidnotfinditindicated asamaterialofconstruction onanyofthedrawingsfurnished forreviewnorcouldmilltestorothermaterialdata'forthissteelbefoundamongtheextensive information supplied.

Thus<althoughthereasonforlistingA-36steelasamaterialofconstruction isnotclear;whenoideredtothestatedrequirements A-36isaGroupZZIsteel,anditsusewouldnotaffectthefinalclassification ofthisplant.5.3.5UseofMaterials Classified GroupIIZbyNUREG0577,OutrightAllboltingandweldingmaterials.

!)I)FranklinResearchCenterADhsioncrTheFrank' TER-C5257-167/168 (Rev.1)6~CONCLUSIONS Thedesignandconstruction ofsupportsforsteamgenerators andreactorcoolantpumpsatDonaldC.CookNuclearPowerPlantUnits1and2havebeenreviewedforfracture>>toughness adequacyattheFRC.Criteriaforthesuitability ofmaterials andconstruction practices forS/GandRCPsupportswereprovidedbytheNRCstaffaspublished inNUREG0577-Draft.Inthereview,generalcriteriaofNUREG0577werespecifically appliedtoinformation furnished byIndianaandMichiganPowerCompany(IMPC)concern-ingthesupportsinD.C.CookUnits1and2.Thereviewwasrestricted tosupports(abovetheembedment) forsteam'enerators andreactorcoolantpumps.Conclusions relatingtothemdonotnecessarily extendtothesupportdesignofothercomponents.

'I~InthecaseofD.C.CookUnits1and2FRCconcludes that:l.Engineering measurestakeninsupportdesign,materialselection, materialspecification, materialacceptance testing,fabrication methods,andinspections providereasonable evidencethatthesteamgenerator supportstructures possessadequatefracturetoughness tomeetNRCcriteriaforaGroupIIIrating.2.Engineering measurestakeninthedesignandconstruction ofthereactorcoolantpumpsupportsprovidesimilarevidencetoqualifythemforaGroupIIIratingalso.3.TheGroupIII(relatively highest)plantratingforfracture-toughness adequacyofsupportsassignedtoDonaldCCookNuclearPowerPlantUnits1and2inNUREG0577-Draft isjustifiable.

IJANES881

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