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~INFORMATION DISTRIBUTION~i'STEM (RIDS)*'tACCESSION NBR:8010080417 DOC~DATE;80/09/30NOTARIZED:
NODOFACIL:50315DonaldC,CookNuclearPowerPlantgUnitlrIndianaS50003150316DonaldC.CookNuclearPowerPlantgUnit2gIndiana8056AUTHBYNAMEAUTHORAFFILIATIONCARFAGRO~S.P.
FranklinInstitute/Frankl.in Research.CenterRECIP~NAMERECIPIENT AFFILIATION BUTCHER~K,J
~Assistant'irector forPlantSystems
SUBJECT:
Forwards"Fracture Toughness ofSteamGenerator 8Reacto,rCoolantPumpSuppo,rts."
Reptdescr,ibes criteriafor'reviewi.
procedure Lbasisforconclusion supporting NUREG0577GtoupIIIplantrankingforfracturetoughness adequacy.'ISTRIBUTION CODE:X004SCOPIESRECEIVED!
L(TRENCL1.SIZE!TITLE:FranklinResearchCenterContractReportNOTES:ILE;3copiesallmaterial05000315>>
05000316RECIPIENT IDCOOK/NAME
>>INTERNAL:
A/DMATLlLQUALBECKHITHCCONTSYSADIRgL'ICENSING03GLAGOI.AACOPIESLITTRENCL1~11110111-1RECIPIENT IDCODE/NA>>MK A/DSFTYASSESSBUTCHEReE"i.15-DIRgHUMFACtSFYUAL~BRREGF01COPIKSLTTRENCL':113101011OCp9jggpTOTAL'UMBER OF>>COPIESREQUIRED!
LTTRENCL<
~t1AI'~'ll1rA'I"i,01P~vAiiiAA,af.A,i4A'AAtllfirvas>AAI (l(FranklinResearchCenterADivisionofTheFranklininstitute Sep'tember 30,1980I'UnitedStatesNuclearRegulatory Commission Washington, D.C.20555Attention:
Reference:
Mr.EdwardJ.Butcher,Jr.ProjectOfficerFRCProjectC5257NRCContractNRC-03-79-118 NRCTACNo.08479and08486,FRCTaskNo.167and168Title:FRCTER:FractureToughness ofSteamGenerator andReactorCoolantPumpSupports-D.C.CookUnits1and2
DearMr.,
Butcher:
EnclosedisaTechnical Evaluation Reportwhichaddresses thefracture-toughness adequacyofsteamgenerator andreactorcoolantpumpsupportsinD.C.CookUnits1and2.Thereportdescribes thecriteriaestablished byNRCforthisreview,thereviewprocedure usedtoevaluateplantcompliance withthecriteria, andthebasisforFRC'sconclusion supporting aNUREG0577GroupIII(relatively superior) plantrankingforfracture-toughness adequacyofthesesupportstructures
~Verytrulyyours,S.P.CarfagoProjectManager'SPC/mhjEnclosure cc:J.R.Fair(alsoreproducible copy)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' 0TECHNlCAL EVALUATION REPORTFRACTURETOUGHNESS OFSTEAMGENERATOR ANDREACTORCOOLANTPUMPSUPPORTSINDIANARI'1ICHIGAN POWER.CONPANY.DONAlDCCOOKNUCLEARPOWERPLANTUNITS1'ND2'NRCDOCKETNO.50-315and50-316NRCTACNO.
08479and08486NRCCONTRACTNO.NRC43-79-118 FRCPROJECTC5257FRCTASK167and168PreparedbyFranklinResearchCenterTheParkwayatTwentieth StreetPhiladelphia, PA19103Authors:T.C.Stilwell,A.G.Allten, K;E.Dorschu, P.N.Noell FRCGroupLeader:T.C.Sti.lwellPreparedforNuclear'Regulatory Commission Washington, D.C.20555LeadNRCEngineer:
J.R.PairSeptember, 1980Thisreportwaspreparedasanaccountofworksponsored byanagencyoftheUnitedStatesGovernment.
NeithertheUnitedStatesGovernment noranyagencythereof,oranyoftheiremployees, makesanywarranty,,expressed orimplied,orassumesanylegalliability orresponsibility foranythirdparty'suse,ortheresultsofsuchuse,ofanyinformation, apparatus, productorprocessdisclosed inthisreport,orrepresents thatitsusebysuchthirdpartywouldnotinfringeprivately ownedrights.IIIIFranklinResearchCenterADivisionofTheFranklinInstitute TheBenjaminFranMinPa~ay.Phiia..Po.)9)03Q)5)448)000 l~'TER-C5257-16 7/168CONTENTSSectionTitle~Pae1SUMMARY~~~~~~~~~~~2INTRODUCTION 3BACKGROUND 4CRITERIAAPPLIEDINTHEEVALUATION
.~2~44.1Fracture-Toughness GroupingofMaterials UsedinSupportConstruction
.4.1.1Criterion 4.1.2Interpretation.
4.2PlantGroupingforFracture-Toughness RankingofS/GandRCPSupportStructures 44554.2.1Criterion 4.2.2Interpretation.
4.3CriteriaforFracture-Toughness AdequacyofS/GandRCPSupports4.3.1NDTCriteriaforScreening.
4.3.2Interpretation.
4.3.3Alternative Criteria5TECHNICAL EVALUATION 5.1ReviewProcedure andImplementation ofNRCCriteria5.2ReviewFindings555566~7~7105.2.15.2.25.2.3UseofGroupIMaterials inApplications Important toStructural Integrity ofSupportsThickSectionUseofGroupIIMaterials inApplications Important toStructural Integrity
.ThinSectionUseofGroupIIMaterials inApplications Important ToStructural Integrity
.10101000FranklinResearchcenterA!XvldonotTheFranklinInstate TER-C5257-167/168 5.2e4UseofMaterials Classified GroupNUREG0577,UponCondition.
5.2.5UseofMaterials Classified
.GroupNUREG0577,Outright5.2.6IssuesNotCompletely Resolved.
6CONCLUSIONS IIbyIIIby1111NumberTABLETitlePage5.1COMPONENT SUPPORTSUMMARY.........8(IlfFranklinResearchCenterADtvistonotTheFrontonInstitute TER-C5257-167/168 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 ofNUREG0577andD.C.CookUnits1and2hadbeenassignedaGroupIII(rela-tivelybest)plantrankingforfracturetoughness ofS/GandRCPsupports.
Thisrankingwasregardedastentative.
Subsequently, theNRCrequested FRCtoconductanindependent reviewpriortofinalizing theranking.FRC'sreviewwasconfinedtofracture-toughness issuesinsupportsabovetheembedment.
Thereviewwasconducted inaccordance withNRCcriteriaandtoaprocedure standardized fortheseverallicensees whosesupportdesignswerereviewedatFRC.Asaresultofitsreview,FRCconfirmed thattheGroupIIIplantrankingassignedtoDonaldC.CookNuclearPowerPlantsUnits1and2forfracturetoughness ofS/GandRCPsupportsisjustifiable.
2.INTRODUCTION Thisreportprovidesatechnical evaluation ofinformation suppliedbyIMPCwithitsletterofNov.23,1977,toMr.EdsonG.Case,ActingDirectorOfficeofNuclearRegulation.
Theinformation concernsthefracture-toughness designofsupportsfortheS/GsandRCPsforD.C.CookUnits1and2.Theobjective oftheevaluation istorankthedesignforfracture-toughness integrity onarelativescaleinaccordance withthegroupingschemeandcriteriaestablished" inNUREG0577.(illFranjdlnResearchCenterADivisiveofTheFrsnidinInsotuie TER-C5257-167/168 3.BACKGROUND DuringthecourseoftheNRClicensing reviewfortwopressurized waterreactors(PWR),NorthAnnaUnits1and2,questions wereraisedregarding thefracture-toughness adequacyofcertainmembers,oftheS/GandRCPsupports.
Thepotential forlamellarteax'inginsomesupportmemberswasalsoquestioned.
Thesta'ff'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 bythecombination oflowoperating temperature, presenceofflaws,andnonredun-dancyofcriticalsupportmembers}couldresultinfailureofthesupportstructure underpostulated accidentconditions, specifically aloss-of-coolant accident(LOCA)andsafeshutdownearthquake (SSE).Toaddressfracture-toughness concernsattheNorthAnnafacility, thelicenseeundertook testsnotoxiginally specified andnotincludedintherelevantASTMspecifications.
Thesetestsindicated thatmaterial-usedincertainsupportmembershadrelatively poorfracturetoughness at80'Fmetaltemperature.
Inthiscasethelicenseeagreedtoraise(byancillary electrical heat)thetemperature oftheS/Gsupportbeamsinquestiontoaminimumof225'Feverytime,throughout thelifeoftheplant,thatthereactorcoolantsystem(RCS)ispressurized above1,000psig.TheNRCstafffoundthistobeanacceptable resolution.
Becausesimilarmaterials anddesignswereusedinotherplantsandbe-causesimilarproblemsweretherefore
- possible, thismatterwasincorporated intotheNRCProgramforResolution ofGenericIssuesas"GenericTechnical t)llFranklinResearchCenterAOMshnofIbeFrankKnbatiste TER-C5257-167/168 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 thatwerebeyondthescope.ofthepreliminary, overallgenericreview.Suchconsiderations weredeemedmoresuitedtoasubsequent phasewhenmoredetailedinvestigations ofindividual plantsmightbeundertaken.
Requestsforinformation weresenttolicensees inlate1977;responses totheserequestswerereceivedduring1978.ISandiaLaboratories inAlbuquerque, NewMexico,wasretainedtoassistthestaffinthereviewandanalysisoftheinformation receivedfromlicensees andapplicants.
Basedonananalysis'oftheinformation, thetechnical stud-iesperformed bySandiaLaboratories, andreviewoftheissuesbytheNRCstaff,theNRCdeveloped anNRCstafftechnical positionontheseissues,whichispresented inNUREG0577,"Potential forLowFractureToughness andLamellarTearingonPWRSteamGenerator andReactorCoolantPumpSupports."
Inaddition, NUREG0577establishes criteriaforevaluation ofthefracture-toughness adequacyofS/GandRCPsupports.
NUREG0577alsoappliescertainofthesecriteriatothesupportstructures ofanumberofPWRplantstoachieveplantgroupings according totherelativefracture-toughness inte-grityofthesesupports.
00FranklinResearchCenterAbhteianatTheFtenMinIneetute3 TER-C5257-167/168 Theplantratingsare:~GroupI(lowest)~GroupII(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, theNRCreque'sted FRCtoconductanindependent reviewoftheGroupIIIplants(inconjunction withsimilarFRCtaskassignments toreviewthefracture-toughness adequacyofcorresponding supportsincertainotherplants)andtoprepareaTechnical Evaluation Reportforeachplant,presenting thereviewfindings.
Thetechnical evaluation reportedhereinappliesthecriteriaofNUREG0577totheS/GandRCPsupportsforD.C.CookUnits1and2toprovideanassessment ofthefracture-toughness adequacyofthesesupportsleadingtoaplantranking.i4~CRITERIAAPPLIEDINTHEEUALUATION 4.1FRACTURE-TOUGHNESS GROUPINGOFMATERIALS USEDINSUPPORTCONSTRUCTION 4.1.1Criterion Table4.6,MaterialGroups,ofAppendixCtoNUREG0577groupsmaterials according totheirrelativefracturetoughness as:~GroupI(poorest)
~GroupII(intermediate)
~GroupIII(best)(illFranklinResearchCenterAOhfsfonofTheFfenkffnInsofufe TER-C5257-167/168 4.1.2Interpretation Ifnosupplementary requirements werecalledoutinthematerialspecifi-cationaimedatprocuring aproductwithfracture-toughness properties supe-riortothoseroutinely suppliedunderthematerialspecification, thenthematerialwasgroupedinaccordance withTable4.6~Ifadditional requirements aimedatprocuring aproductwithsuperiorfracture-toughness properties werespecified, consideration wasgiventocred-itingthisspecificmaterialorderwithanimprovedmaterial-group rating.4.2PLANTGROUPINGFORFRACTURE-TOUGHNESS RANKINGOFS/GANDRCPSUPPORTSTRUCTURES 4'.2.1Criterion Plantsareclassified onthebasisoftheconstruction materials usedinthesupportsaftergivingconsideration totheimportance oftheirlocationandfunctionwithinthestructure, andtheirconsequent importance tosupport-structure.
integrity.
(Refertopages5and6ofNUREG0577,PartI~)4.2.2Interpretation Plantswereassignedaplant-group rankingidentical tothematerial-group rankingoftheleastfracture-tough materialusedintheconstruction, pro-videdthisusageisimportant tosupportintegrity.
I4.3CRITERIAFORFRACTURE-TOUGHNESS ADEQUACYOFS/GANDRCPSUPPORTSItistheclearintentofNUREG0577thatlicensees demonstrate thefracture-toughness adequacyofthe"S/GandRCPsupportsorthattheytakeappropriate corrective measurestoassuretheirfracture-toughness integrity.
NUREG0577providesguidanceforsuchdemonstrations'.3.1 NDTCriteriaforScreening 30FDT+.+o~T,ut,'0'FIFranklinResearchCenterhDMsionofTheFcanklWInsatute 0l TER-C5257-167/168 where:~NDTisthemeannilductility transition temperature appro-priatetothematerialasgivenbyTable4.4ofAppendixCtoNUREG0577'~tristhestandarddeviation forthedatausedtodetermine NDTaslistedinTable4.4.~Tsupports isthelowestmetaltemperatur'e thatthesupportmemberwilleverexperience throughout theplantlifewhent'eplantisinanoperational state.Intheabsenceofmeasured, plant-specific data,Tsupports istakenas75'F.~Thetemperature term,30'For60'F,isanallowance forsec-tionsize(30'Fforthinsectionsand60'Fforthicksec-tions).4'.3.2Interpretation Ifevidenceisfurnished bythelicenseeprovingthatothervaluesofNDT,tr,orTareactuallyvalidfortheSlGorRCPsupportsandmateri-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 thatothermeansofshovingcompliance withtheintentofNUREG0577arepossible, butalsooffersextensive guidancere-latingtoseveralapproaches bywhichsuchademonstration maybeachieved.
Becauseoftheplant-specific character thatsuchdemonstrations musttake,NUREG0577doesnotrestrictthelicensees toanysingleapproachbut,instead,encourages eachlicenseetoreviewthefracture-toughness adequacyofhisSFGandRCPsupportsandsubmitevidenceofhis.findings.
ll(FranklinResearchCenterAOivislonorTheFsanMfnInsiitute TER-C5257-167/168 5.TECHNICAL EVALUATION Theinformation furnished totheNRCregarding thefracturetoughness of,andthepotential forlamellartearingin,S/GandRCPsupportsatD.C.CookUnits1and2wasreviewedatFRC.Thisinformation wassuppliedinresponsetotheNRCstaff'sgenericlettertoPWRlicensees concerning theseissues.Acopyofthestaff'srequest-for-information letter(ingenericform)maybefoundinNUREG0577,AppendixB.Onlyfracturetoughness issueswereaddressed intheFRCreview;thereviewprocedure isdescribed below.5.1REVIEWPROCEDURE ANDIMPLEMENTATION OFNRCCRITERIAThedrawingsandinformation submitted werefirstexaminedtobecomefamiliarwiththestructural design,materialselection, andconstruction practices.
Keyitemsfromthisinformation werecondensed totabularformandarepresented inTable5.1.Inaccordance withareviewprocedure standardized forthelicensees whoseplantswereevaluated atFRC,thefirststepwastocompilealistofmaterials usedinallmemberssignificant tothestructural integrity oftheS/GandRCPsupports.
Thelistedmaterials weretakenfromthosereportedintheresponsetoItem1oftheNRC'srequestforinformation, supplemented byasurveyofthesupportdrawingsforadditional materials whichmightbeindi-catedthere.Toeachofthematerials soidentified, twocriteriatestsvereapplied:1.TheNDT-criteria forscreening (paragraph 4.3.1ofthisreport).2.Thematerialgrouprankinginaccordance withtheprocedures ofSection4.1.Forplantswhichusedthem,materials vithanassignedGroupIorGroupIIfracture-toughness ratingwerefurthercategorized asthickorthinusingtheformulashownonthefollowing pagetodetermine thesectionthickness abovewhichbrittle(plainstrain)behaviormaybeanticipated underdynamicload.IFranMinResearchCenterAMelondTheFranklinInstitute TABLE5.1COHPONENT SUPPORTSU)DIARYPLANT:DonaldCDCookI62UTILITYIndiana&MichiganPoverHATEkIALS NESSMeetinghouse AEAmericanElectricPoverCompanySUPPORTSUPPLIERHAXIHUHALLOWABLE DESICNSTRESSTYPEConstruction Hacerials:
HILLCERTS.HEATAVAILABLE TREATMENT NDEOHMATERIALFRACTURETOUGHNESS TESTHEHBRANE6BENDIHG(NORMAL)THROUGHTHICKNESS h-618Cr2A-36A-588BoltingMaterials:
h-193B7h-194Cr7AISI4145A&90AISI4340MeldingHacerials:
E60XX>E70XX8016-01,8018-01,8018-G8016-C2,8018-02,2-1/2Zor3-1/2ZNiContentsubarcconsumables YesYesA-36tofine-grain practice.
Normalized h-588inCriticalmembers.UTunderveldareasThru-'Thickness ReducedAreaTestsCVNforh-618,A-3&,h-588(15ft-lbs830'F).AlsoHAEandMeldHaterial~Normal-Upset:
AISCHanualAllovables Emergency:
0.9SPaulceItlNon-Linear Elascic-Plastic Analysis0.65SyFABRICATION MELDINGPkOCESSHanualHetalhrcSubarcMELDINGPROCEDURE AISCCode,SeccionIXQualified Pro-ceduresPOST-MELDING TREATHENT StressReliefMETHODSUSEDTOPREVENTLAHELLARTEARINGAISCCodeJointsNDEANDINSPECTIONS PERFORHED llTorRTvherepossibleHPorLPDESIGNTYPEOFSUPPORTPin&ulnas>
CODEUSEDLOADINGCONDITIONS Normal:DL+TLUpset:DL+TL+OBEEmergency:
DL+TL+DBEFaulted:DL+TL+DBEsPRHINIHUHTEMPERATURE OFSUPPORT60F(Ambienttemperature nearsupports)
TER-C5257-167/168
,Thecriticalthickness isgivenby:"ID22.5[-]fryDwhere.'yD isthedynamicyieldstrengthofthesteel.KIDisthenominal,minimumassuredfracturetoughness ofthesteelinaccordance withvaluessuppliedbyNUREG0577.tcisthecriticalthickness.
Inmembersthickerthantc,brittle(i-e.,planestrain)behaviormaybeexpected.
Asimilarcategorization forGroupIIImaterials wasnotdeemednecessary forpurposesofthereviewbecausesuchmaterials aresanctioned forthick-~sectionusebyvirtueoftheirgrouprating.Structural drawingswerethenexamined'for:1~Allstructurally significant usesofGroupImaterials.
2.All'tructurally significant usesofGroupIImaterials inthicksections.
3.Structurally significant applications ofmaterials knowntobesensitive tostresscorrosion crackingorotherspecialfailuremechanisms whichmightmakethempronetobrittlebehavior.
Thecircumstances associated withsuchusagewerethenexamined.
Consider-ationwasgiventofactorssuchas:direction ofloadings(alwayscompressive orsometimes tensile),
stresslevelsinthememberasindicated inthelicensee's
- response, thepresenceofstressraisersinmembergeometries, re-dundancyofloadpaths,andthelike.Applications judgedtobeofproblematic fracturetoughness wereidentified formoredetailedevaluation atafuturedate.Inaddition, information furnished onweldingandonmaterialspecifica-tionswasexaminedforitsfracture-toughness implications byaweldingengi-neerandametallurgist, respectively. 9tjFranklinResearchCenterhOnfafonof'ahaFrrrnwrnInrrfrrrre TER-C5257-167/168 Asaresultofthereviewfindingsandinaccordance withthecriteriaprocedure described inSection4.2ofthisreport,atentative plantrankingforfracture-toughness adequacyofS/GandRCPsupportswasassigned.
5.2REVIEWFINDINGS5.2.1UseofGroupIMaterials inApplications Important toStructural Integrity ofSupportsNonefound.5.2.2ThickSectionUseofGroupIIMaterials inApplications Important toStructural Integrity None,found.5.2.3ThinSectionUseofGroupIIMaterials inApplications Important ToStructural Integrity ASTMA-618steelisindicated onbothS/GandRCPsupportdrawingsasthematerialforthemainverticalcolumns.Theseareconstructed of12inchdia-meter,double-extra-strong pipe(i.e.,seamlesstubeof123/4incho.d.andwith1inchwalls)~NUREG0577classifies ASTMA-618asaGroupIIsteelwhenfurnished asformedandwithoutadditional specification requirements.
However,ASTMA-618Grade2wasspecified forthistubingandCharpyV-notchtestingwasrequired.
Specification ASTMA-618Grade2limitssilconcontenttoamaximumof0.30percent,andrequiresadditionofvanadium.
Theactualsteelusedwasanalyzedtohaveonly0'19percentsilicon(sufficient tocompletely deoxidethesteelaccording tosilicon-killed practice) andtocontain0.04percentvanadium(whichwouldtendtopromoteafinergrainsize)~/Thetestreportfurnished intheinformation suppliedtoNRCbyIMPCindicated thatthesteelpossessed aCharpyV-notchimpactenergyof24ft-lbsat30'F.Thisvalue,iftypicalofallheats,qualifies thissteeltobeofadequatequalityandtoughness for1inchsectionusage.fillFranMlnResearchCenterASvislondTheFranldlnhearne TER-C5257-167/168 5.2.4UseofMaterials Classified GroupIIIbyNUREG0577,UponCondition ASTMA-588isthemajorcomponent steelofboththeS/GandRCPsupportsandwassuppliedasA-588,GradeA.Thissteelisclassified inNUREG0577asaGroupIImaterialintheas-rolled orhot-worked condition.
However,insections1/2inchthickandover,thesteelwasorderednormalized andCharpyV-notchimpacttestswererequired.
Thetestdatafurnished forreviewindi-cateadequatetoughness at30'Finallthicknesses.
Inviewoftheadditional requirements specified, theA-588steelusedinthisapplication isdeemedtobeofsufficient qualityandtoughness tomeritaGroupIIImaterialrating.5.2.5UseofMaterials Classified GroupIIIbyNUREG0577,OutrightAllboltingandweldingmaterials.
5.2.6IssuesNotCompletely ResolvedThetextandmaterials tableoftheIMPCletterofresponserefertouseofASTMA-36steelasamaterialofconstruction forS/GandRCPsupportsintheCookplants.Thesealsostatethatitwasorderedtofinegrainpracticeandrequiredtobesubjected toCharpyimpacttesting.Withsuchadditional requirements theA-36steelwouldbeconsidered, underNUREG0577criteria, assanctioned forgeneraluseinS/GandRCPsupports.
However,FRCdidnotfinditindicated asamaterialofconstruction onanyofthedrawingsfurnished forreviewnorcouldmilltestorothermaterialdataforthissteelbefoundamongtheextensive information supplied.
Thisquestion, althoughunresolved, wouldnotappeartoaffectthefinalclassificationofthisplant.6.CONCLUSIONS Thedesignandconstruction ofsupportsforsteamgenerators andreactorcoolantpumpsatDonaldC.CookNuclearPowerPlantUnits1and2havebeenreviewedforfracture-toughness adequacyattheFRC.(IllFranMinResearchCenterADivisionor%heFranl4nInsetst
-0 TER-C5257-167/168 Criteriaforthesuitability ofmaterials andconstruction practices forS/GandRCPsupportswereprovidedbytheNRCstaffaspublished inNUREG0577-Draft.Inthereview,generalcriteriaofNUREG0577werespecifically appliedtoinformation furnished byIndianaandMichiganPowerCompany(IMPC)concern-ingthesupportsinD.C.CookUnits1and2.Thereviewwasrestricted tosupports(abovetheembedment) forsteamgenerators andreactorcoolantpumps.Conclusions relatingtothemdonotnecessarily extendtothesup'portdesignofothercomponents.
InthecaseofD.C.CookUnits1and2FRCconcludes that:1~Engineering measurestakeninsupportdesign,materialselection, materialspecification, materialacceptance testing,fabrication methods,andinspections providereasonable evidencethatthesteamgenerator supportstructures possessadequatefracturetoughness tomeetNRCcriteriaforaGroupIIIrating.2.Engineering measurestakeninthedesignandconstruction ofthereactorcoolantpumpsupportsprovidesimilarevidencetoqualifythemforaGroupIIIratingalso.3.TheGroupIII(relatively highest)plantratingforfracture-toughness adequacyofsupportsassignedtoDonaldC.,CookNuclearPowerPlantUnits1and2inNUREG0577-Draft isjustifiable.
I)9FranMinResearchCenterAOsvlslonerThefrenk5nInsdrute 0