ML17331A465
| ML17331A465 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/30/1980 |
| From: | CARFAGNO S P FRANKLIN INSTITUTE |
| To: | BUTCHER E J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17326A752 | List: |
| References | |
| CON-NRC-03-79-118, CON-NRC-3-79-118 NUDOCS 8010080417 | |
| Download: ML17331A465 (22) | |
Text
REGULAT~INFORMATIONDISTRIBUTION~i'STEM(RIDS)*'tACCESSIONNBR:8010080417DOC~DATE;80/09/30NOTARIZED:NODOFACIL:50315DonaldC,CookNuclearPowerPlantgUnitlrIndianaS50003150316DonaldC.CookNuclearPowerPlantgUnit2gIndiana8056AUTHBYNAMEAUTHORAFFILIATIONCARFAGRO~S.P.FranklinInstitute/Frankl.inResearch.CenterRECIP~NAMERECIPIENTAFFILIATIONBUTCHER~K,J~Assistant'irectorforPlantSystems
SUBJECT:
Forwards"FractureToughnessofSteamGenerator8Reacto,rCoolantPumpSuppo,rts."Reptdescr,ibescriteriafor'reviewi.procedureLbasisforconclusionsupportingNUREG0577GtoupIIIplantrankingforfracturetoughnessadequacy.'ISTRIBUTIONCODE:X004SCOPIESRECEIVED!L(TRENCL1.SIZE!TITLE:FranklinResearchCenterContractReportNOTES:ILE;3copiesallmaterial05000315>>05000316RECIPIENTIDCOOK/NAME>>INTERNAL:A/DMATLlLQUALBECKHITHCCONTSYSADIRgL'ICENSING03GLAGOI.AACOPIESLITTRENCL1~11110111-1RECIPIENTIDCODE/NA>>MKA/DSFTYASSESSBUTCHEReE"i.15-DIRgHUMFACtSFYUAL~BRREGF01COPIKSLTTRENCL':113101011OCp9jggpTOTAL'UMBEROF>>COPIESREQUIRED!LTTRENCL<
~t1AI'~'ll1rA'I"i,01P~vAiiiAA,af.A,i4A'AAtllfirvas>AAI (l(FranklinResearchCenterADivisionofTheFranklininstituteSep'tember30,1980I'UnitedStatesNuclearRegulatoryCommissionWashington,D.C.20555Attention:
Reference:
Mr.EdwardJ.Butcher,Jr.ProjectOfficerFRCProjectC5257NRCContractNRC-03-79-118NRCTACNo.08479and08486,FRCTaskNo.167and168Title:FRCTER:FractureToughnessofSteamGeneratorandReactorCoolantPumpSupports-D.C.CookUnits1and2
DearMr.,
Butcher:EnclosedisaTechnicalEvaluationReportwhichaddressesthefracture-toughnessadequacyofsteamgeneratorandreactorcoolantpumpsupportsinD.C.CookUnits1and2.ThereportdescribesthecriteriaestablishedbyNRCforthisreview,thereviewprocedureusedtoevaluateplantcompliancewiththecriteria,andthebasisforFRC'sconclusionsupportingaNUREG0577GroupIII(relativelysuperior)plantrankingforfracture-toughnessadequacyofthesesupportstructures~Verytrulyyours,S.P.CarfagoProjectManager'SPC/mhjEnclosurecc:J.R.Fair(alsoreproduciblecopy)K.R.WichmanA.F.Glagola(letteronly)$0q80ZO0804Ztg)SISg)(tnTheBenjaminFranklinParkway,Philadelphia.Pa.19103(215)448-1000TWX-7106701889 t0TVno=!voa'one>f:n.lg1'lA'illA/1tPk)8P~tdlt5<~lf'l'p4t43VRls' 0TECHNlCALEVALUATIONREPORTFRACTURETOUGHNESSOFSTEAMGENERATORANDREACTORCOOLANTPUMPSUPPORTSINDIANARI'1ICHIGANPOWER.CONPANY.DONAlDCCOOKNUCLEARPOWERPLANTUNITS1'ND2'NRCDOCKETNO.50-315and50-316NRCTACNO.08479and08486NRCCONTRACTNO.NRC43-79-118FRCPROJECTC5257FRCTASK167and168PreparedbyFranklinResearchCenterTheParkwayatTwentiethStreetPhiladelphia,PA19103Authors:T.C.Stilwell,A.G.Allten,K;E.Dorschu,P.N.NoellFRCGroupLeader:T.C.Sti.lwellPreparedforNuclear'RegulatoryCommissionWashington,D.C.20555LeadNRCEngineer:J.R.PairSeptember,1980ThisreportwaspreparedasanaccountofworksponsoredbyanagencyoftheUnitedStatesGovernment.NeithertheUnitedStatesGovernmentnoranyagencythereof,oranyoftheiremployees,makesanywarranty,,expressedorimplied,orassumesanylegalliabilityorresponsibilityforanythirdparty'suse,ortheresultsofsuchuse,ofanyinformation,apparatus,productorprocessdisclosedinthisreport,orrepresentsthatitsusebysuchthirdpartywouldnotinfringeprivatelyownedrights.IIIIFranklinResearchCenterADivisionofTheFranklinInstituteTheBenjaminFranMinPa~ay.Phiia..Po.)9)03Q)5)448)000 l~'TER-C5257-167/168CONTENTSSectionTitle~Pae1SUMMARY~~~~~~~~~~~2INTRODUCTION3BACKGROUND4CRITERIAAPPLIEDINTHEEVALUATION.~2~44.1Fracture-ToughnessGroupingofMaterialsUsedinSupportConstruction.4.1.1Criterion4.1.2Interpretation.4.2PlantGroupingforFracture-ToughnessRankingofS/GandRCPSupportStructures44554.2.1Criterion4.2.2Interpretation.4.3CriteriaforFracture-ToughnessAdequacyofS/GandRCPSupports4.3.1NDTCriteriaforScreening.4.3.2Interpretation.4.3.3AlternativeCriteria5TECHNICALEVALUATION5.1ReviewProcedureandImplementationofNRCCriteria5.2ReviewFindings555566~7~7105.2.15.2.25.2.3UseofGroupIMaterialsinApplicationsImportanttoStructuralIntegrityofSupportsThickSectionUseofGroupIIMaterialsinApplicationsImportanttoStructuralIntegrity.ThinSectionUseofGroupIIMaterialsinApplicationsImportantToStructuralIntegrity.10101000FranklinResearchcenterA!XvldonotTheFranklinInstate TER-C5257-167/1685.2e4UseofMaterialsClassifiedGroupNUREG0577,UponCondition.5.2.5UseofMaterialsClassified.GroupNUREG0577,Outright5.2.6IssuesNotCompletelyResolved.6CONCLUSIONSIIbyIIIby1111NumberTABLETitlePage5.1COMPONENTSUPPORTSUMMARY.........8(IlfFranklinResearchCenterADtvistonotTheFrontonInstitute TER-C5257-167/1681.SUMMARYInformationconcerningaspectsofthefracture-toughnessdesignofthesteamgenerator(S/G)andreactorcoolantpump(RCP)supportsfortheDonaldC.CookNuclearPowerPlantUnits1and2wassubmittedtotheActingDirectoroftheOfficeofNuclearRegulationbytheIndianaandMichiganPowerCompany(IMPC)byletterdatedNov.23,1977.ThisinformationwasreviewedattheFranklinResearchCenter(FRC)andevaluatedinaccordancewiththecriteriaoftheNuclearRegulatoryCommission(NRC)assetforthinNUREG0577-Draft(henceforthreferredtosimplyasNUREG0577).TheinformationhadpreviouslybeenreviewedaspartofthepreparationofNUREG0577andD.C.CookUnits1and2hadbeenassignedaGroupIII(rela-tivelybest)plantrankingforfracturetoughnessofS/GandRCPsupports.Thisrankingwasregardedastentative.Subsequently,theNRCrequestedFRCtoconductanindependentreviewpriortofinalizingtheranking.FRC'sreviewwasconfinedtofracture-toughnessissuesinsupportsabovetheembedment.ThereviewwasconductedinaccordancewithNRCcriteriaandtoaprocedurestandardizedfortheseverallicenseeswhosesupportdesignswerereviewedatFRC.Asaresultofitsreview,FRCconfirmedthattheGroupIIIplantrankingassignedtoDonaldC.CookNuclearPowerPlantsUnits1and2forfracturetoughnessofS/GandRCPsupportsisjustifiable.2.INTRODUCTIONThisreportprovidesatechnicalevaluationofinformationsuppliedbyIMPCwithitsletterofNov.23,1977,toMr.EdsonG.Case,ActingDirectorOfficeofNuclearRegulation.Theinformationconcernsthefracture-toughnessdesignofsupportsfortheS/GsandRCPsforD.C.CookUnits1and2.Theobjectiveoftheevaluationistorankthedesignforfracture-toughnessintegrityonarelativescaleinaccordancewiththegroupingschemeandcriteriaestablished"inNUREG0577.(illFranjdlnResearchCenterADivisiveofTheFrsnidinInsotuie TER-C5257-167/1683.BACKGROUNDDuringthecourseoftheNRClicensingreviewfortwopressurizedwaterreactors(PWR),NorthAnnaUnits1and2,questionswereraisedregardingthefracture-toughnessadequacyofcertainmembers,oftheS/GandRCPsupports.Thepotentialforlamellarteax'inginsomesupportmemberswasalsoquestioned.Thesta'ff'sconcernintheNorthAnnalicensingprocesswasthatperhapsnotenoughattentionhadbeengiventotheselectionofmaterialsfor,andfabricationof,theS/GandRCPsupports.Fracturetoughnessofamaterialisameasureofitscapabilitytoabsorbenergywithoutfailureordamage.Generally,amaterialisconsidered"tough"when,understatedconditionsofstressandtemperature,thematerialcanwithstandloadingtoitsdesignlimitinthepresenceofflaws.Toughnessalsoimpliesthat,undercertainconditions,thematerialhasthecapabilitytoarrestthegrowthofaflaw.Alackofadequatetoughness(accompaniedbythecombinationoflowoperatingtemperature,presenceofflaws,andnonredun-dancyofcriticalsupportmembers}couldresultinfailureofthesupportstructureunderpostulatedaccidentconditions,specificallyaloss-of-coolantaccident(LOCA)andsafeshutdownearthquake(SSE).Toaddressfracture-toughnessconcernsattheNorthAnnafacility,thelicenseeundertooktestsnotoxiginallyspecifiedandnotincludedintherelevantASTMspecifications.Thesetestsindicatedthatmaterial-usedincertainsupportmembershadrelativelypoorfracturetoughnessat80'Fmetaltemperature.Inthiscasethelicenseeagreedtoraise(byancillaryelectricalheat)thetemperatureoftheS/Gsupportbeamsinquestiontoaminimumof225'Feverytime,throughoutthelifeoftheplant,thatthereactorcoolantsystem(RCS)ispressurizedabove1,000psig.TheNRCstafffoundthistobeanacceptableresolution.Becausesimilarmaterialsanddesignswereusedinotherplantsandbe-causesimilarproblemswerethereforepossible,thismatterwasincorporatedintotheNRCProgramforResolutionofGenericIssuesas"GenericTechnicalt)llFranklinResearchCenterAOMshnofIbeFrankKnbatiste TER-C5257-167/168ActivityA-12PotentialforLowFractureToughnessandLamellarTearingonPWRSteamGeneratorandReactorCoolantPumpSupports."Sincetheoriginallicensingaction(NorthAnnaUnits1and2)involvedonlytheS/GandRCPsupportsofPWRs,thestaff'sinitialeffortsweredi-rectedtowardexaminationofthecorrespondingsupportsatotherPWRfacili-ties.However,thestaffhaskeptinmindthepossibilityofexpandingitsreviewtoincludeothersupportstructuresinPWRplantsandsupportstruc-turesinboilingwaterreactor(BWR)plants.TheintegrityofsupportembedmentswasnotquestionedduringtheNorthAnnalicensingaction;consequently,emphasiswasplacedonresolvingthemostimmediategenericissue-whetherornotproblemssimilartothoseuncoveredatNorthAnnaexistatotherfacilities.Itwasthestaff'sjudgmentthatinclusionofanevaluationofsupportembedmentsintheinitialreviewwouldrequiredetailed,plant-specificinvestigationsthatwerebeyondthescope.ofthepreliminary,overallgenericreview.Suchconsiderationsweredeemedmoresuitedtoasubsequentphasewhenmoredetailedinvestigationsofindividualplantsmightbeundertaken.Requestsforinformationweresenttolicenseesinlate1977;responsestotheserequestswerereceivedduring1978.ISandiaLaboratoriesinAlbuquerque,NewMexico,wasretainedtoassistthestaffinthereviewandanalysisoftheinformationreceivedfromlicenseesandapplicants.Basedonananalysis'oftheinformation,thetechnicalstud-iesperformedbySandiaLaboratories,andreviewoftheissuesbytheNRCstaff,theNRCdevelopedanNRCstafftechnicalpositionontheseissues,whichispresentedinNUREG0577,"PotentialforLowFractureToughnessandLamellarTearingonPWRSteamGeneratorandReactorCoolantPumpSupports."Inaddition,NUREG0577establishescriteriaforevaluationofthefracture-toughnessadequacyofS/GandRCPsupports.NUREG0577alsoappliescertainofthesecriteriatothesupportstructuresofanumberofPWRplantstoachieveplantgroupingsaccordingtotherelativefracture-toughnessinte-grityofthesesupports.00FranklinResearchCenterAbhteianatTheFtenMinIneetute3 TER-C5257-167/168Theplantratingsare:~GroupI(lowest)~GroupII(intermediate)~GroupIII(highest)Duringthegenericstudy,anumberofPWRplantswerereviewedforthefracture-toughnessadequacyoftheirRCPandS/Gdesigns.Asaresultofthesereviews,eachplantwasassignedatentativeplantrankingofeitherGroupI,II,orIII.SeveralPlants,D.C.CookUnits1and2amongthem,weretentativelyrankedGroupIII.IntheappendixtoNUREG0577preparedbySandiaLabora-tories,whoinitiallyestablishedtherankingswhichsubsequentlyreceivedNRCstaffendorsement,thesignificanceoftheGroupIIIrankingisdescribedas:"consideredtobeasgoodascareful,reasonableengineeringpracticecanproduce."However,beforefinalizingthetentativeGroupIIIrankings,theNRCreque'stedFRCtoconductanindependentreviewoftheGroupIIIplants(inconjunctionwithsimilarFRCtaskassignmentstoreviewthefracture-toughnessadequacyofcorrespondingsupportsincertainotherplants)andtoprepareaTechnicalEvaluationReportforeachplant,presentingthereviewfindings.ThetechnicalevaluationreportedhereinappliesthecriteriaofNUREG0577totheS/GandRCPsupportsforD.C.CookUnits1and2toprovideanassessmentofthefracture-toughnessadequacyofthesesupportsleadingtoaplantranking.i4~CRITERIAAPPLIEDINTHEEUALUATION4.1FRACTURE-TOUGHNESSGROUPINGOFMATERIALSUSEDINSUPPORTCONSTRUCTION4.1.1CriterionTable4.6,MaterialGroups,ofAppendixCtoNUREG0577groupsmaterialsaccordingtotheirrelativefracturetoughnessas:~GroupI(poorest)~GroupII(intermediate)~GroupIII(best)(illFranklinResearchCenterAOhfsfonofTheFfenkffnInsofufe TER-C5257-167/1684.1.2InterpretationIfnosupplementaryrequirementswerecalledoutinthematerialspecifi-cationaimedatprocuringaproductwithfracture-toughnesspropertiessupe-riortothoseroutinelysuppliedunderthematerialspecification,thenthematerialwasgroupedinaccordancewithTable4.6~Ifadditionalrequirementsaimedatprocuringaproductwithsuperiorfracture-toughnesspropertieswerespecified,considerationwasgiventocred-itingthisspecificmaterialorderwithanimprovedmaterial-grouprating.4.2PLANTGROUPINGFORFRACTURE-TOUGHNESSRANKINGOFS/GANDRCPSUPPORTSTRUCTURES4'.2.1CriterionPlantsareclassifiedonthebasisoftheconstructionmaterialsusedinthesupportsaftergivingconsiderationtotheimportanceoftheirlocationandfunctionwithinthestructure,andtheirconsequentimportancetosupport-structure.integrity.(Refertopages5and6ofNUREG0577,PartI~)4.2.2InterpretationPlantswereassignedaplant-grouprankingidenticaltothematerial-grouprankingoftheleastfracture-toughmaterialusedintheconstruction,pro-videdthisusageisimportanttosupportintegrity.I4.3CRITERIAFORFRACTURE-TOUGHNESSADEQUACYOFS/GANDRCPSUPPORTSItistheclearintentofNUREG0577thatlicenseesdemonstratethefracture-toughnessadequacyofthe"S/GandRCPsupportsorthattheytakeappropriatecorrectivemeasurestoassuretheirfracture-toughnessintegrity.NUREG0577providesguidanceforsuchdemonstrations'.3.1NDTCriteriaforScreening30FDT+.+o~T,ut,'0'FIFranklinResearchCenterhDMsionofTheFcanklWInsatute 0l TER-C5257-167/168where:~NDTisthemeannilductilitytransitiontemperatureappro-priatetothematerialasgivenbyTable4.4ofAppendixCtoNUREG0577'~tristhestandarddeviationforthedatausedtodetermineNDTaslistedinTable4.4.~Tsupportsisthelowestmetaltemperatur'ethatthesupportmemberwilleverexperiencethroughouttheplantlifewhent'eplantisinanoperationalstate.Intheabsenceofmeasured,plant-specificdata,Tsupportsistakenas75'F.~Thetemperatureterm,30'For60'F,isanallowanceforsec-tionsize(30'Fforthinsectionsand60'Fforthicksec-tions).4'.3.2InterpretationIfevidenceisfurnishedbythelicenseeprovingthatothervaluesofNDT,tr,orTareactuallyvalidfortheSlGorRCPsupportsandmateri-supportsalsinthelicensee'splant,suchdatamaybeused.Ifacceptablealternativeevidenceisnotavailable,theabove-stipulatedvaluesshouldbeused.4.3.3AlternativeCriteriaNUREG0577alsorecognizedthatfracture-toughnessintegrityisacomplexmatterinvolvinganumberofinterrelatedfactors,mostofwhichareplantspecific.Consequently,demonstrationofcompliancewiththescreeningcrite-riaisbutonemeansofprovidingsatisfactoryassuranceoffracture-toughnessadequacy.NUREG0577notonlyrecognizesthatothermeansofshovingcompliancewiththeintentofNUREG0577arepossible,butalsooffersextensiveguidancere-latingtoseveralapproachesbywhichsuchademonstrationmaybeachieved.Becauseoftheplant-specificcharacterthatsuchdemonstrationsmusttake,NUREG0577doesnotrestrictthelicenseestoanysingleapproachbut,instead,encourageseachlicenseetoreviewthefracture-toughnessadequacyofhisSFGandRCPsupportsandsubmitevidenceofhis.findings.ll(FranklinResearchCenterAOivislonorTheFsanMfnInsiitute TER-C5257-167/1685.TECHNICALEVALUATIONTheinformationfurnishedtotheNRCregardingthefracturetoughnessof,andthepotentialforlamellartearingin,S/GandRCPsupportsatD.C.CookUnits1and2wasreviewedatFRC.ThisinformationwassuppliedinresponsetotheNRCstaff'sgenericlettertoPWRlicenseesconcerningtheseissues.Acopyofthestaff'srequest-for-informationletter(ingenericform)maybefoundinNUREG0577,AppendixB.OnlyfracturetoughnessissueswereaddressedintheFRCreview;thereviewprocedureisdescribedbelow.5.1REVIEWPROCEDUREANDIMPLEMENTATIONOFNRCCRITERIAThedrawingsandinformationsubmittedwerefirstexaminedtobecomefamiliarwiththestructuraldesign,materialselection,andconstructionpractices.KeyitemsfromthisinformationwerecondensedtotabularformandarepresentedinTable5.1.InaccordancewithareviewprocedurestandardizedforthelicenseeswhoseplantswereevaluatedatFRC,thefirststepwastocompilealistofmaterialsusedinallmemberssignificanttothestructuralintegrityoftheS/GandRCPsupports.ThelistedmaterialsweretakenfromthosereportedintheresponsetoItem1oftheNRC'srequestforinformation,supplementedbyasurveyofthesupportdrawingsforadditionalmaterialswhichmightbeindi-catedthere.Toeachofthematerialssoidentified,twocriteriatestsvereapplied:1.TheNDT-criteriaforscreening(paragraph4.3.1ofthisreport).2.ThematerialgrouprankinginaccordancewiththeproceduresofSection4.1.Forplantswhichusedthem,materialsvithanassignedGroupIorGroupIIfracture-toughnessratingwerefurthercategorizedasthickorthinusingtheformulashownonthefollowingpagetodeterminethesectionthicknessabovewhichbrittle(plainstrain)behaviormaybeanticipatedunderdynamicload.IFranMinResearchCenterAMelondTheFranklinInstitute TABLE5.1COHPONENTSUPPORTSU)DIARYPLANT:DonaldCDCookI62UTILITYIndiana&MichiganPoverHATEkIALSNESSMeetinghouseAEAmericanElectricPoverCompanySUPPORTSUPPLIERHAXIHUHALLOWABLEDESICNSTRESSTYPEConstructionHacerials:HILLCERTS.HEATAVAILABLETREATMENTNDEOHMATERIALFRACTURETOUGHNESSTESTHEHBRANE6BENDIHG(NORMAL)THROUGHTHICKNESSh-618Cr2A-36A-588BoltingMaterials:h-193B7h-194Cr7AISI4145A&90AISI4340MeldingHacerials:E60XX>E70XX8016-01,8018-01,8018-G8016-C2,8018-02,2-1/2Zor3-1/2ZNiContentsubarcconsumablesYesYesA-36tofine-grainpractice.Normalizedh-588inCriticalmembers.UTunderveldareasThru-'ThicknessReducedAreaTestsCVNforh-618,A-3&,h-588(15ft-lbs830'F).AlsoHAEandMeldHaterial~Normal-Upset:AISCHanualAllovablesEmergency:0.9SPaulceItlNon-LinearElascic-PlasticAnalysis0.65SyFABRICATIONMELDINGPkOCESSHanualHetalhrcSubarcMELDINGPROCEDUREAISCCode,SeccionIXQualifiedPro-ceduresPOST-MELDINGTREATHENTStressReliefMETHODSUSEDTOPREVENTLAHELLARTEARINGAISCCodeJointsNDEANDINSPECTIONSPERFORHEDllTorRTvherepossibleHPorLPDESIGNTYPEOFSUPPORTPin&ulnas>CODEUSEDLOADINGCONDITIONSNormal:DL+TLUpset:DL+TL+OBEEmergency:DL+TL+DBEFaulted:DL+TL+DBEsPRHINIHUHTEMPERATUREOFSUPPORT60F(Ambienttemperaturenearsupports)
TER-C5257-167/168,Thecriticalthicknessisgivenby:"ID22.5[-]fryDwhere.'yDisthedynamicyieldstrengthofthesteel.KIDisthenominal,minimumassuredfracturetoughnessofthesteelinaccordancewithvaluessuppliedbyNUREG0577.tcisthecriticalthickness.Inmembersthickerthantc,brittle(i-e.,planestrain)behaviormaybeexpected.AsimilarcategorizationforGroupIIImaterialswasnotdeemednecessaryforpurposesofthereviewbecausesuchmaterialsaresanctionedforthick-~sectionusebyvirtueoftheirgrouprating.Structuraldrawingswerethenexamined'for:1~AllstructurallysignificantusesofGroupImaterials.2.All'tructurallysignificantusesofGroupIImaterialsinthicksections.3.Structurallysignificantapplicationsofmaterialsknowntobesensitivetostresscorrosioncrackingorotherspecialfailuremechanismswhichmightmakethempronetobrittlebehavior.Thecircumstancesassociatedwithsuchusagewerethenexamined.Consider-ationwasgiventofactorssuchas:directionofloadings(alwayscompressiveorsometimestensile),stresslevelsinthememberasindicatedinthelicensee'sresponse,thepresenceofstressraisersinmembergeometries,re-dundancyofloadpaths,andthelike.Applicationsjudgedtobeofproblematicfracturetoughnesswereidentifiedformoredetailedevaluationatafuturedate.Inaddition,informationfurnishedonweldingandonmaterialspecifica-tionswasexaminedforitsfracture-toughnessimplicationsbyaweldingengi-neerandametallurgist,respectively.-9-9tjFranklinResearchCenterhOnfafonof'ahaFrrrnwrnInrrfrrrre TER-C5257-167/168AsaresultofthereviewfindingsandinaccordancewiththecriteriaproceduredescribedinSection4.2ofthisreport,atentativeplantrankingforfracture-toughnessadequacyofS/GandRCPsupportswasassigned.5.2REVIEWFINDINGS5.2.1UseofGroupIMaterialsinApplicationsImportanttoStructuralIntegrityofSupportsNonefound.5.2.2ThickSectionUseofGroupIIMaterialsinApplicationsImportanttoStructuralIntegrityNone,found.5.2.3ThinSectionUseofGroupIIMaterialsinApplicationsImportantToStructuralIntegrityASTMA-618steelisindicatedonbothS/GandRCPsupportdrawingsasthematerialforthemainverticalcolumns.Theseareconstructedof12inchdia-meter,double-extra-strongpipe(i.e.,seamlesstubeof123/4incho.d.andwith1inchwalls)~NUREG0577classifiesASTMA-618asaGroupIIsteelwhenfurnishedasformedandwithoutadditionalspecificationrequirements.However,ASTMA-618Grade2wasspecifiedforthistubingandCharpyV-notchtestingwasrequired.SpecificationASTMA-618Grade2limitssilconcontenttoamaximumof0.30percent,andrequiresadditionofvanadium.Theactualsteelusedwasanalyzedtohaveonly0'19percentsilicon(sufficienttocompletelydeoxidethesteelaccordingtosilicon-killedpractice)andtocontain0.04percentvanadium(whichwouldtendtopromoteafinergrainsize)~/ThetestreportfurnishedintheinformationsuppliedtoNRCbyIMPCindicatedthatthesteelpossessedaCharpyV-notchimpactenergyof24ft-lbsat30'F.Thisvalue,iftypicalofallheats,qualifiesthissteeltobeofadequatequalityandtoughnessfor1inchsectionusage.fillFranMlnResearchCenterASvislondTheFranldlnhearne TER-C5257-167/1685.2.4UseofMaterialsClassifiedGroupIIIbyNUREG0577,UponConditionASTMA-588isthemajorcomponentsteelofboththeS/GandRCPsupportsandwassuppliedasA-588,GradeA.ThissteelisclassifiedinNUREG0577asaGroupIImaterialintheas-rolledorhot-workedcondition.However,insections1/2inchthickandover,thesteelwasorderednormalizedandCharpyV-notchimpacttestswererequired.Thetestdatafurnishedforreviewindi-cateadequatetoughnessat30'Finallthicknesses.Inviewoftheadditionalrequirementsspecified,theA-588steelusedinthisapplicationisdeemedtobeofsufficientqualityandtoughnesstomeritaGroupIIImaterialrating.5.2.5UseofMaterialsClassifiedGroupIIIbyNUREG0577,OutrightAllboltingandweldingmaterials.5.2.6IssuesNotCompletelyResolvedThetextandmaterialstableoftheIMPCletterofresponserefertouseofASTMA-36steelasamaterialofconstructionforS/GandRCPsupportsintheCookplants.ThesealsostatethatitwasorderedtofinegrainpracticeandrequiredtobesubjectedtoCharpyimpacttesting.WithsuchadditionalrequirementstheA-36steelwouldbeconsidered,underNUREG0577criteria,assanctionedforgeneraluseinS/GandRCPsupports.However,FRCdidnotfinditindicatedasamaterialofconstructiononanyofthedrawingsfurnishedforreviewnorcouldmilltestorothermaterialdataforthissteelbefoundamongtheextensiveinformationsupplied.Thisquestion,althoughunresolved,wouldnotappeartoaffectthefinalclassificationofthisplant.6.CONCLUSIONSThedesignandconstructionofsupportsforsteamgeneratorsandreactorcoolantpumpsatDonaldC.CookNuclearPowerPlantUnits1and2havebeenreviewedforfracture-toughnessadequacyattheFRC.(IllFranMinResearchCenterADivisionor%heFranl4nInsetst
-0 TER-C5257-167/168CriteriaforthesuitabilityofmaterialsandconstructionpracticesforS/GandRCPsupportswereprovidedbytheNRCstaffaspublishedinNUREG0577-Draft.Inthereview,generalcriteriaofNUREG0577werespecificallyappliedtoinformationfurnishedbyIndianaandMichiganPowerCompany(IMPC)concern-ingthesupportsinD.C.CookUnits1and2.Thereviewwasrestrictedtosupports(abovetheembedment)forsteamgeneratorsandreactorcoolantpumps.Conclusionsrelatingtothemdonotnecessarilyextendtothesup'portdesignofothercomponents.InthecaseofD.C.CookUnits1and2FRCconcludesthat:1~Engineeringmeasurestakeninsupportdesign,materialselection,materialspecification,materialacceptancetesting,fabricationmethods,andinspectionsprovidereasonableevidencethatthesteamgeneratorsupportstructurespossessadequatefracturetoughnesstomeetNRCcriteriaforaGroupIIIrating.2.EngineeringmeasurestakeninthedesignandconstructionofthereactorcoolantpumpsupportsprovidesimilarevidencetoqualifythemforaGroupIIIratingalso.3.TheGroupIII(relativelyhighest)plantratingforfracture-toughnessadequacyofsupportsassignedtoDonaldC.,CookNuclearPowerPlantUnits1and2inNUREG0577-Draftisjustifiable.I)9FranMinResearchCenterAOsvlslonerThefrenk5nInsdrute 0