ML17326A092
| ML17326A092 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/17/1999 |
| From: | POWERS R P AMERICAN ELECTRIC POWER CO., INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17326A093 | List: |
| References | |
| C0799-05, NUDOCS 9908250194 | |
| Download: ML17326A092 (30) | |
Text
CATEGORY1REGULARYINFORMATIONDISTRIBUTIi4SYSTEM(RIDS)r',ACCESSIONNBR:9908250194DOC.DATE:99/08/17NOTARIZED:YES(ACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaMAUTH;MMEAUTHORAFFILIATIONPOWERS,R.P.AmericanElectricPowerCo.,Inc.RECIE'.NA;K'"RECIPIENTAFFILIATIONRecordsManagementBranch(DocumentControlDesk)DOCKET05000315
SUBJECT:
ApplicationforamendtolicenseDPR-58,tochangeTS3/4.4.5&.basesforTS3/4.4.5,3/4.4.6.2&3/4.4.8toremovevoltage-basedrepaircriteria,F*repaircriteriaSsleevingmethodologiesfromUnit1TS&clarifybasessections.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENT.IDCODE/NAMELPD3-1LACOPIESLTTRENCL1111RECIPIENTIDCODE/NAMESTANG,JCOPIESLTTRENCL11G0INTERN~CENSENRR/DSSA/SRXBOGC/RP111,110NRR/DSSA/SPLBNUDOCS-ABSTRACT111.1EXTERNAL:NOAC11NRCPDRD'ENOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE~'TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR10ENCL9
~~I(I PmericenElectricP~er'ookNUotearPtanli@it1SteaineneratorRe~iotaPrrjectOneCookPrxeMl4910661646%72ANERICAN'IECIICPOWERAugust17,1999C0799-0510CFR50.90DocketNo:50-315U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskMailStop0-P1-17Washington,D.C.20555-0001DonaldC.CookNuclearPlantUnit1TECHNICALSPECIFICATIONCHANGEREQUESTTECHNICALSPECIFICATION3/4.4.5rANDBASES3/4.4.5,3/4.4.6.2,AND3/4.4.8Pursuantto10CFR50.90,IndianaMichiganPowerCompany(I&M),theLicenseeforDonaldC.CookNuclearPlantUnit1,proposestoamendAppendixA,TechnicalSpecifications(T/S),ofFacilityOperatingLicenseDPR-58.I&M'proposestoamendUnit1T/S3/4.4.5andthebasesforT/S3/4.4.5,T/S3/4.4.6.2,andT/S3/4.4.8.Thisproposedamendmentremovesthevoltage-basedrepaircriteria,F*repaircriteria,andsleevingmethodologiesfromtheUnit1T/Sandclarifiesthebasessectionsaccordingly.ThisproposedchangeispartoftheUnit1steamgenerator(SG)replacementeffort.TheamendmentistobeimplementeduponcompletionoftheSGreplacement.I&MwillbereplacingtheoriginalUnit1Westinghousemodel51SGswithBabcockandWilcox(B&W)SGshavingimprovedmaterialsandenhanceddesignfeatures.Thereplacementeffortisscheduledtooccurduringthecurrentoutage,priortoUnit1restart.Thecurrentvoltage-basedandF*repaircriteriaandsleevingmethodologies,intheUnit1T/S,incorporatedviapastamendmentstospecificallyaddressvariousSGtubedegradationmechanismsassociatedwiththeWestinghouseModel51SGs,arenotapplicabletothereplacementSGs.Attachment1providesthebackgroundandreasonfogthechange,adescriptionoftheproposedchange,thejustificationforthechange,andouranalysisconcerningsignificanthazardsconsiderations'ttachment2providesthecurrentT/Spages,marked-uptoreflecttheproposedchanges.Attachment3providestheproposed'evisedT/Spages.Attachment4providesanenvironmentalassessmentoftheproposedchange.r9908250i949908i7PDRADQCK050003l5t,PPDRAEP:America'sEnergyPartner" II7WlZ+y~I' U.S.NuclearRegulatoryCommissionPage2C0799-05Inaccordancewiththerequirementsof10CFR50.91,copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtheMichiganDepartmentofPublicHealth.Shouldyouhaveanyquestions,pleasecontactMr.GordonP.Arent,ActingDirectorofRegulatoryAffairs,at(616)465-5901,extension1575.Sincerely,R.P.PowersVicePresidentSRTOANDSUBSCRIBEDBEFOREMEzzsItv1999NotarybicMyCommissionExpiresAttachments)rZKRCQA.EGOlEGÃQSQ.5i2000/jmcc:A.C.Bakken,XII,w/attachmentsJ.E.Dyer,w/attachmentsMDEQ-DWSRPDNRCResidentInspector,w/attachmentsREWhale I+y7HXQ.ClCtKKI~QC3~ZNNQggRoC$587)tCiOMQNO Attachment1toC0799-05Page1BACKGROUNDANDREASONFORCHANGE;DESCRIPTIONOFCHANGE;JUSTIFICATIONFORCHANGE;AND10CFR50.92ANALYSISFORCHANGETOUNIT1TECHNICALSPECIFICATIONSA.BACKGROUNDANDREASONFORCHANGEIndianaMichiganPowerCompany(I&M),theLicenseeforDonaldC.CookNuclearPlant,Units1and2;planstoreplacetheUnit1steamgenerators(SGs)duringthecurrentoutagepriortoUnit1restart.Thecurrentsurveillancerequirementsforsampleselection,inspectionfrequency,acceptancecriteria,repairmethods,andrequiredreportswerespecificallydevelopedforapplicationtothedegradedWestinghousemodel51SGs(OSGs)installedinUnit1.Theserequirementsweredeveloped,inpart,topermittubestoremaininservicethatwereexperiencingvarioustubedegradationmechanisms.AfterreplacementoftheOSGs,thecurrentvoltage-basedrepaircriteria,F*repaircriteria,andsleevingmethodswillnolongerbeapplicableduetomaterialanddesignchangesincorporatedintothereplacementsteamgenerators(RSGs).Theanalysesperformedtosupportapplicationofthevoltage-basedandF*repaircriteriawerespecificallybasedontheOSGs.These.analyseswillnolongerapplytotheRSGsfollowingreplacementoftheOSGs.Inaddition,thecurrentlyapprovedWestinghousemechanical,Westinghouselaser-welded,andCombustionEngineeringleaktightweldedsleevingprocesseswillnolongerbeapplicabletoUnit1.ThesesleevingprocessesweredevelopedspecificallyforWestinghouseSGmaterialsanddesignandare,therefore,notapplicabletotheBaWRSGs.B.DESCRIPTIONOFCHANGEIntroductionChangesareproposedtoamendTechnicalSpecification(T/S)3/4.4.5,"SteamGenerators,"T/SBases3/4.4.5,"SteamGeneratorsTubeIntegrity,"T/Sbases3/4.4.6.2,"OperationalLeakage,"andT/Sbases3/4.4.8,"SpecificActivity,"forUnit1tosupportSGreplacement.Thereplacementeffortisscheduledtooccurduringthecurrentoutage,priortoUnit1restart.TheRSGmaterialsanddesignfeaturesfortubingandtubesupportsaredifferentfromtheOSGs.Inlightofthedesigndifferences,theanalysesperformedforuseofvoltage-basedandF*repaircriteriaandsleevingmethodologiesforUnit1tubesdonotapplytotheRSGs.Therefore,referencetothesecriteriaandmethodologieswillnolongerbeappropriateintheT/S.
Iy7tg))Ct4I'$1 Attachment1toC0799-05Page2DescritionandBasisforCurrentReuirementsThesurveillancerequirementsspecifiedinT/S3/4.4.5forinspectionofSGtubesareintendedtoprovidereasonableassurancethatthestructuralandleakageintegrityofthetubesisacceptableforcontinuedserviceandwillwithstandthepeakpressuresthatcoulddevelopfollowingapostulatedaccident.Themostsevereaccidentforpeakdifferentialpressureonthetubesisthemainsteamlinebreak(MSLB)accident.Priortodevelopmentofspecializedrepaircriteria(voltage-basedandF*),thepluggingcriteriaforUnit1werebasedonatubeintegrityminimumwallthicknessrequirementestablishedfortheplantaspartoftheoriginallicensingbasis.ThespecializedcriteriaforSGtubesandsleevesinthecurrentT/Sarebasedonanalysesperformedtorequirementsofregulatoryguide(RG)1.121andgenericletter(GL)95-05.Fortubesleftinserviceduetoapplicationofvoltage-basedorF*repaircriteria,analyseshavebeenperformedtodemonstrateacceptableprobabilityoftubeburst,andtoprovideassurancethatMSLBleakageiswithinsite-specificlimits.Thecurrentrepairmethodsofsleevingprovideaprocesstore-establishtheprimarysystempressureboundaryofatubecontainingdegradationexceedingtherepairlimit.InstallationofthesleeveprovidesaleaktightboundarythatspansthedefectiveareaandrestoresthestructuralintegrityofthetubingtosatisfyRG1.121requirements.Thecurrentprogramforin-serviceinspectionofSGtubesisbasedonamodificationofRG1.83,revision1,GL95-05,andF*criteria.In-serviceinspectionofSGtubingisnecessarytomaintainsurveillanceoftheconditionsofthetubesintheeventthatthereisevidence'fmechanicaldamageorprogressivedegradationduetodesign,manufacturingerrors,orin-serviceconditionsthatcouldleadtocorrosion.In-serviceinspectionofSGtubingalsoprovidesameansofcharacterizingthenatureandcauseoftubedegradationsothatcorrectivemeasurescanbetaken.T/Sreportingrequirementsassociatedwithapplicationofvoltage-basedrepairandF*repaircriteriaprovideassurancethattheNRCisawareofanyabnormalitiesdetectedduringaninspectionandprovidenotificationastotheextentofapplicationofthecriteria.T/S4.4.5providesthesurveillancerequirementsforsampleselection,inspectionfrequency,acceptancecriteria,repairmethods,andrequiredreportstotheNRC.ProvisionsofT/S4.4.5thatareaffectedbythisproposedT/Samendmentaresummarizedasfollows:
t~a41 Attachment1toC0799-05Page3T/Ssurveillancerequirement4.4.5.2providestherequirementforSGtubesampleselectionandinspectionandprefacethelistofexceptionstotherandomselectionofSGtubes.Thissectionalsostatesthattubesrepairedbysleevingdonotconstituteareasofpreviousdefectsorimperfections.T/Ssurveillancerequirement4.4.5.2.b.lrequiresalltubesnotpluggedorrepairedthatpreviouslyhaddetectablewallpenetrationsbeincludedinthefirstsample.T/Ssurveillancerequirement4.4.5.2.b.4requiresthat,forallindicationsleftinserviceasaresultofapplicationofthe-tubesupportplate(TSP)voltage-basedrepaircriteria,the,indicationsshallbeinspectedbybobbincoilprobeduringfuturerefuelingoutages.T/Ssurveillancerequirement4.4.5.2.crequiresthattubesthatremaininserviceduetotheapplicationoftheF*repaircriteriawillbeinspectedintherollexpandedregionduringfutureoutages.T/Ssurveillancerequirement4.4.5.2.erequiresthedeterminationofTSPintersectionshavingoutsidediameter,stresscorrosioncracking(ODSCC)indicationsbebasedonarandomsampleinspectionofatleast20%ofthetotalnumberoftubesinspectedovertheirfulllength.ImplementationoftheSGtube/TSPpluggingcriteriarequiresa100%bobbincoilinspectionforhotlegsupportplateintersectionsandcoldlegintersectionsdowntothelowestcoldlegTSPwithknownODSCCindications.T/Ssurveillancerequirement4.4.5.2.frequiresthatinspectionofsleevesfollowthecriteriaforfirstsampleselectionandsampleexpansionaccordingtotable4.4-2.T/Ssurveillancerequirement4.4.5.2alsospecifiesthecriteriatoclassifythesampleinspectionresultsintothreecategories.The"note"tothesecriteriastatesthatpreviouslydegradedtubesorsleevesmustexhibitsignificant(>10%)furtherwallpenetrationstobeincludedinthepercentagecalculationdefinedintheclassificationcriteria.T/Ssurveillancerequirement4.4.5.3.arequiresthefirstin-serviceinspectiontobeperformedwithinaspecifiedintervaloftimefollowinginitialcriticality.Frequenciesofsubsequentin-serviceinspectionsarealsoaddressed.
Attachment1toC0799-05Page4T/Ssurveillancerequirement4.4.5.4.a.1defines"imperfections"forbothtubesandsleevesasexceptionstodimensions,finishorcontourfromthatrequiredbyfabricationdrawingsorspecifications.T/Ssurveillancerequirement4.4.5.4.a.2defines"degradation"forbothtubesandsleevesasservice-inducedcracking,wastage,wear,orgeneralcorrosiononeithertheinsideoroutsideofthetubeorsleeve.T/Ssurveillancerequirement4.4.5.4.a.3defines"degradedtubeorsleeve"ashavinganimperfectionofgreaterthanorequalto20%ofthenominalwallthickness.T/Ssurveillancerequirement4.4.5.4.a.5defines"defect"asanimperfectionthatexceedsthedefinedrepairlimit.T/Ssurveillancerequirement4.4.5.4.a.6definesthe"repair/plugginglimit"fortubingorsleevedtubesastheimperfectiondepthequalto40%ofthenominaltubewallthickness.Theplugginglimitimperfectiondepthforlaserweldedsleevesisequalto23%ofthenominalsleevewallthickness.Theplugginglimitimperfectiondepthfornon-laserweldedsleevesisequalto29%ofthenominalsleevewallthickness.ThisdefinitiondoesnotapplytodefectsinthetubesheetthatmeetthecriteriaforanF*tube.T/Ssurveillancerequirement4.4.5.4.a.7defines"unserviceable"astheconditionfortubesandsleevesthatleakorwouldnotmaintaintheirstructuralintegrityundertheconditionsspecifiedin4.4.5.3.c.T/Ssurveillancerequirement4.4.5.4.a.8defines"inspection"asthemeansofdeterminingtheconditionoftheSGtubeorsleevefromthepointofentry(hotlegside)completelyaroundtheU-bendtothetopsupportofthecoldleg.ForatubeinwhichtheTSPelevationinterimplugginglimithasbeenapplied,the"inspection"willincludeallthehotlegintersectionsandcoldlegintersectionsdownto,atleast,thelevelofthelastcrackindication.T/Ssurveillancerequirement4.4.5.4.a.9definesandpermits"sleeving"oftwotypes.Tubesupportplatesleevesarecenteredaboutthetubesupportplateintersection.Tubesheetsleevesstartattheprimaryfluidtubesheetinterfaceandextendthroughtheentiretubesheet.T/Ssurveillancerequirement4.4.5.4.a.10definesthe"tubesupportplaterepairlimit"usedtodispositionalloy600SGtubesforcontinuedservicethatareexperiencingpredominatelyaxially-orientedODSCCconfinedwithinthe Attachment1toC0799-05Page5thicknessofthetubesupportplates.Attubesupportplateintersections,theplugginglimitisbasedonmaintainingSGtubeserviceabilityasdeterminedbyvariousbobbinvoltagecriteria.Mid-cyclerepairlimitsarealsodefined.T/Ssurveillancerequirement4.4.5.4.a.lldefinestheF*"distance"asthedistancefromthe'ottomofthehardrolltransitiontowardthebottomofthetubesheetthathasbeenconservativelydeterminedtobe1.11inches(notincludingeddycurrentuncertainty).T/Ssurveillancerequirement4.4.5.4.a.12definesthe"F*tube"asaSGtubewithdegradation,belowtheF*distance,equaltoorgreaterthan40%,butthathasnoindicationsofdegradation(i.e.,noindicationofcracking)withintheF*distance.T/Ssurveillancerequirement4.4.5.4.a.13defines"tuberepair"assleevingdescribedbyreportslistedinT/Ssurveillancerequirement4.4.5.4.c.Discussionallowsuseofsleevingaspreventivemeasuresandforamethodofreturningpreviouslypluggedtubestoservicefollowingappropriateinspections.T/Ssurveillancerequirement4.4.5.4.bstatesthataSGshallbedeterminedoperableaftercompletingthecorrespondingactionsrequiredbytable4.4-2.T/Ssurveillancerequirement4.4.5.4.cidentifiesthetopicalreportsforsleevingmethodologiesapprovedforuseonUnitl.T/Ssurveillancerequirement4.4.5.5.arequiresthatthenumberoftubespluggedorsleevedbereportedtotheNRCwithin15daysofthecompletionofeachin-serviceinspectionoftheSGtubes.T/Ssurveillancerequirement4.4.5.5.brequiresthatthenumberoftubesandsleevesinspectedbereportedandtubesthatarepluggedorsleevedbeidentifiedintheannualoperatingreport.T/Ssurveillancerequirement4.4.5.5.drequiresnotificationtotheNRCofimplementationofvoltage-basedrepairpriortoreturningtheSGstoserviceifanyofthefollowingconditionsarise.Theestimatedend-of-cycle(EOC)leakagelimitexceedsthatassumedinthelicensingbasisoffsitedosecalculationfortheMSLB.
)lg.5'l>>,~l Attachment1toC0799-05Page6Circumferentialdetectedatintersections.crack-likethetubeindicationsaresupportplateIndicationsareidentifiedthatextendbeyondtheconfinesofthetubesupportplate.Indicationsareidentifiedatthetubesupportplateelevationsthatareattributabletoprimarywaterstresscorrosioncracking.ThecalculatedconditionalburstprobabilitybasedonprojectedEOCvoltagedistributionexceeds1x10'.Thisdeterminationalsorequiresanassessmentofthesafetysignificanceoftheoccurrence.T/Stable4.4-2providestherequiredsamplesize,resultingcategory,andrequiredactionsforfirst,second,andthirdsampleSGtubeinspections.T/Sbases3/4.4.5addressesrequirementsofT/Ssurveillance4.4.5.Additionally,T/Sbases3/4.5.6.2addressestheanticipatedprimary-to-secondaryleakageassociatedwiththeMSLB,whichisbasedontheSGtubestructuralintegrityconditionrequiredbyT/Ssurveillance4.4.5.T/Sbases3/4.4.8addressesthelimitationsontheprimarycoolantactivitybasedonmaintainingacceptableoffsitedosesfollowingasteamgeneratortuberupture(SGTR)event.ThisbasessectionwaspreviouslymodifiedtoincludeaMSLBcaseforhighprimary-to-secondaryleakage(120gpm)ataprimarycoolantactivitylevelcorrespondingto1%failedfuel.DescritionofProosedModificationstoUnit1TechnicalSecificationsI&MproposestoreviseT/S3/4.4.5,T/Sbases3/4.4.5,T/Sbases3/4.4.6.2,andT/Sbases3/4.4.8.TheserevisionsremovethemodificationsthatweremadetotheUnit1T/StoaddressthevariousSGtubedegradationmechanismsthathaveoccurredontheUnit1OSGs.IncorporationoftheseproposedchangeswillcausetheUnit1T/Stoessentiallyrevertbacktotheoriginallicensingbases(exceptforoperationalleakagelimits)thatareconsistentwithboththeStandardTechnicalSecificationsforWestinhousePWRPlants(NUREG-0452)andtheUnit2requirements.TheproposedT/Schangesareasfollows.T/Ssurveillancerequirement4.4.5.2,SGtubesampleselectionandinspection.
)Ilg Attachment1toC079p-05Page7T/Ssurveillancerequirement4.4.5.2isrevisedtoremovereferencetopreviousdefectsorimperfectionsrepairedbysleeving.T/Ssurveillancerequirement4.4.5.2.b.1isrevisedtoremovethereferencetosleeving.T/Ssurveillancerequirements4.4.5.2.b.4,4.4.5.2.c,4.4.5.2.e,and4.4.5.2.faredeleted.T/Ssurveillancerequirement4.4.5.2.disrenumbered.T/Ssurveillancerequirement4.4.5.2isrevisedtoremovethereferencetosleeving.T/Ssurveillancerequirement4.4.5.3,inspectionfrequencies.T/Ssurveillancerequirement4.4.5.3.aisrevisedtoapplytothesameinitialintervalforin-serviceinspectiontoRSGsaswasdonefortheoriginalOSGs.T/Ssurveillancerequirement4.4.5.4,acceptancecriteria.T/Ssurveillancerequirement4.4.5.4.aitems1,2,3,6,7,and8arerevisedtoremovereferencestosleeving.T/Ssurveillancerequirement4.4.5.4.aitems5and6arerevisedtoremovereferencestorepairlimits.T/Ssurveillancerequirement4.4.5.4.a.5isrevisedtodefineadefectintermsoftheplugginglimit.T/Ssurveillancerequirement4.4.5.4.a.6isrevisedtoremovethediscussionofapplicabilitytoF+tubesandsleeves.T/Ssurveillancerequirement4.4.5.4.a.8isrevisedtoremovethereferencetointerimplugginglimit.T/Ssurveillancerequirement4.4.5.4.aitems9,10,11,12,and13aredeleted.T/Ssurveillancerequirement4.4.5.4.bisrevisedtoremovereferencestosleevesandrepairlimits.T/Ssurveillancerequirement4.4.5.4.cisdeleted.T/Ssurveillancerequirement4.4.5.5,Reports.T/Ssurveillancerequirements4.4.5.5.a,4.4.5.5.b.1,and4.4.5.5.b.3arerevisedtoremovereferencestosleeving.
I)~~ghL1ItIII, Attachment1toC0799-05Page8T/Ssurveillancerequirement4.4.5.5.disdeleted.T/STable4.4-2.Table4."4-2isrevisedtoremovereferencestosleeving.BasesT/S3/4.4.5,SteamGeneratorTubeIntegrity.T/Sbases3/4.4.5arerevisedtoremoveanyreferencestorepairofdefectivetubes,repairlimits,andsleeving.Detailsonthevoltage-basedrepairlimitsareremovedandallreferencestoapprovedmethodologiesforsleevingareremoved.BasesT/S3/4.4.6.2,OperationalLeakage.T/Sbases3/4.4.6.2arerevisedtoremovethedetailofcrackgrowthandexpectedmaximumprimary-to-secondaryleakageduringaMSLB.BasesT/S3/4.4.8,SpecificActivity.T/Sbases3/4.4.8arerevisedtoremovetheparagraphthatdiscussesMSLBoffsitePosesataprimary-to-secondaryleakrateof120gpm.C.JUSTIFICATIONFORCHANGEForUnit1operationaftersteamgeneratorreplacement,thevoltage-basedandF*requirementswillnolongerbeapplicable.TheT/Sacceptancelimitswillbebasedonthrough-wallcriteriathatrequiretubesbepluggedwhenimperfectionsexceedtheplugginglimitof40%ofthenominaltubewallthickness.Theproposedprogramforperiodicin-serviceinspectionofthereplacementSGsmonitorstheintegrityoftheSGtubingtoprovidereasonableassurancethatthereissufficienttimetotakeproperandtimelycorrectiveactionifanytubedegradationispresent.TheproposedprogramisconsistentwithNUREG-0452andwasthebasisfortheoriginalT/SissuedwiththeUnit1operatinglicense,DPR-58.ThepurposeoftheT/Splugginglimit,inconjunctionwithsurveillanceandmaintenanceprograms,istoprovidereasonableassurancethattheSGtubesacceptedforcontinuedservicewillretainadequatestructuralandleakageintegrityduringnormal,transient,andpostulatedaccidentconditions.AlthoughD.C.CookisnotaGDCplant,I&MhasdeterminedthattheRSGdesignisconsistentwithgeneraldesigncriteria(GDC)14,15,30,31,and32of10CFR50,appendixA.CompatibilitywiththeseGDCs,as lsaA)I Attachment1toC0799-05Page9discussedbelow,supportstheapplicationofT/Sacceptancelimitsbasedonthrough-wallcriteria.RSGdesign,surveillance,andmaintenancemeettherequirementsofGDC14.TheRSGportionsofthereactorcoolantpressureboundaryaredesigned,fabricated,erected,andtestedtohaveanextremelylowprobabilityofabnormalleakage,rapidlypropagatingfailure,orgrossrupture.TheRSGdesignmeetstheapplicableASMECoderequirementsandcomplieswith10CFR50.55a.RSGdesign,surveillance,andmaintenancemeettherequirementsofGDC15.TheRSGportionsofthereactorcoolantsystemaredesignedwithsufficientmargintoprovidereasonableassurancethattheapplicablestresslimitsarenotexceededduringanyconditionofnormaloperationoranticipatedoperationaloccurrences.TheRSGtubinghasbeenstructurallyevaluatedundertheapplicablerequirementsofASMESectionIII,1989Edition,forServiceLevelsA,B,C,"andD(normal,upset,emergency,andfaultedconditions,respectively).RSGdesignmeetstherequirementsofGDC30.TheRSGportionsofthereactorcoolantpressureboundaryaredesigned,fabricated,erected,andtestedtothehighestpracticalqualitystandardsbymeetingtheASMECodeand10CFR50,appendixB.DetectionandidentificationofthelocationofRSGleakageisthroughexistingplantinstrumentationandprocedures.RSGdesignmeetstherequirementsofGDC31.TheRSGportionsofthereactorcoolantpressureboundaryaredesignedwithsufficientmargintoassurethat,whenstressedunderoperating,maintenance,testing,andpostulatedaccident.conditions:(1)theboundarybehavesinanon-brittlemanner;and(2)theprobabilityofrapidlypropagatingfractureisminimized.Thedesignconsidersservicetemperaturesandotheroperatingmaintenance,testing,andpostulatedaccidentconditions;uncertaintiesindeterminingmaterialproperties;effectsofradiationonmaterialproperties;residual,steadystate,andtransientstresses;andsizeofindications.RSGdesign,surveillance,andmaintenancemeettherequirementsofGDC32.RSGportionsofthereactorcoolantpressureboundaryaredesignedtopermitperiodicinspectionandtestingofimportantareasandfeaturestoassessstructuralandleak-tightintegrity.TheRSGhastubingfabricatedfromthermallytreatedSB-163material(Alloy690)whichisexaminedbyeddycurrentmethodstotherequirementsofASMESectionIII,NB-2550.InaccordancewithNUREG-0452andconsistentwiththeoriginallicensingbasisforUnit1,thedesignrequiresthatthedepthofanallowableoutsidediameterflawshallnotexceed40%ofthenominaltubewallthickness.
Ilh,Itlf~n Attachment1toC0799-05Page10UponreplacementoftheSGs,thecurrentsleevingmethodologywillnolongerbeapplicable.TheproposedchangeisrequiredbecausethesleevingmethodologiesreferencedintheUnit1T/SarespecifictoWestinghousemodel51SGsandhavenotbeenanalyzedorapprovedbytheNRCforusewiththeRSGsmanufacturedbyBSW.ThischangeremovestheinterimSGtubepluggingcriteriafromtheT/SandreinstatestheoriginalT/ScriteriaconsistentwithUnit2(whichdoesnothavesignificantlydegradedsteamgenerators).ThesecriteriaareinaccordancewithNUREG-0452.ThecriterionfortubepluggingisbasedonaminimumwallthicknessduetowastageasdeterminedbyASMESectionXI.BecausetheproposedT/SsurveillancerequirementsdonotallowforcontinuedoperationwithvoltagebasedandF*indications,theprobabilityofaSGTRisnotincreased.Therefore,implementationofthisproposedT/SamendmentrequestwillprovidereasonableassurancethattheUnit1SGsmaintainadequatestructuralandleakageintegrityconsistentwithGDC14,15,30,31,and32*of10CFR50,appendixA.Unit1willcontinuetoapplytheT/Smaximumprimary-to-secondaryleakagelimitof'150gallonsperday(gpd)throughanyoneSGtominimizethepotentialforexcessiveleakageduringplantconditions.TheEPRIrecommended150gpdlimitprovidesforleakagedetectionandplantshutdownintheeventofanunexpectedtubeleakandminimizesthepotentialforexcessiveleakageortubeburstintheeventofMSLBorlossofcoolingaccident(LOCA)conditions.ThedesignbasisdosescalculatedforpostulatedaccidentsinvolvingdegradationofSGtubes,suchasSGTRandMSLBaccidents,aspresentedinUFSARchapter14accidentanalysishavebeenevaluated.TheSGTRconsequencescontinuetobeboundedbythedesignbasisduetotheallowableleakageratespecifiedbythischange.TheproposedT/Sleakagerateismaintainedat150gpdperSG.However,amaximumleakageof500gpdperSGandtotalleakageof1440gpdforallfourgeneratorswasusedfordeterminationofoffsitedoseinUFSARchapter14.TheMSLBconsequencesaredecreasedbyinstallationoftheRSGsduetothereductioninprimary-to-secondaryleakageduringtheMSLB.Undertheapprovedinterimpluggingcriteria,aleakrateof8.4gpmwasdeterminedtobetheupperlimitforprimary-to-secondaryleakageinthefaultedsteamgenerator.Thisleakage,combinedwiththe150gpdleakagefromthenon-faultedSGs,wasdeterminedtolimittheoffsitedoseto10%ofthe10CFR100limits.FollowingreplacementoftheSGs,theleakageislimitedduringtheMSLBto150gpdforboththefaultedandunfaultedSGs.Therefore,theUnit1MSLBdosewillbeboundedbythecurrentUnit2doseanalysis,whichislessthan10%of10CFR100limits.
Attachment1toC0799-05PagellAmendment166toDPR-58addedadiscussioninthebasessectionsofT/S3/4.4.5andT/S3/4.4.8regardingtheMSLBoffsitedose,whichwascalculatedusingassumedSGleakageof120gpm.Subsequently,amendment178toDPR-58imposedamorelimitingconditionbasedona12.6gpmSGleakagefortheMSLBtolimitoffsitedosesto10%.ofthe10CFR100limits(thisvaluewaslaterrevisedto8.4gpm).Amendment178revisedT/Sbases3/4.4.5toremovethereferencetothe120gpmMSLBoffsitedoseevaluation,butinadvertentlydidnotreviseT/Sbases3/4.4.8.Becausethediscussionregaxdingthe120gpmSGleakratenolongerapplies,itwillberemovedfromT/Sbases3/4.4.8bythischange.D.BASESFORNOSIGNIFICANTHAZARDSDETERMINATION(10CFR50.92ANALYSIS)IndianaMichiganPowerCompany,theLicenseeforDonaldC.CookNuclearPlantUnit1,proposestoamendTechnicalSpecification(T/S)3/4.4.5,"SteamGenerators,"T/SBases3/4.4.5,"SteamGeneratorsTubeIntegrity,"T/SBases3/4.4.6.2,"OperationalLeakage,"andT/SBases3/4.4.8,"SpecificActivity,"tosupportsteamgenerator(SG)replacement.I&MwillbereplacingtheoriginalUni.t1Westinghousemodel51SGswithB&WSGs.Thereplacementeffortisscheduledtooccurduringthecurrentoutage,priortoUnit1restart.I&MhasevaluatedthisproposedT/Samendmentanddeterminedthatitdoesnotinvolveasignificanthazard.Accordingto10CFR50.92(c),aproposedamendmenttoanoperatinglicensedoesnotinvolveasignificanthazardifoperationofthefacilityinaccordancewiththeproposedamendmentdoesnot:involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;orcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or3.involveasignificantreductioninamarginofsafety.NoSinificantHazardsAnalsisCriterion1:Theproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.ThischangeremovestheinterimsteamgeneratortubepluggingcriteriafromtheT/SandreinstatestheoriginalT/ScriteriaconsistentwithUnit2(whichdoesnothavesignificantlydegraded IIIeq~dt,C Attachment1toC0799-05Page12steamgenerators).ThecurrentT/SallowforcontinuedoperationwithtubesthatdemonstxateindicationsperF*andvoltage-basedcriteria.ThebasisusedtojustifytheinterimcriteriaisspecifictotheUnit1originalsteamgenerators(OSGs)anddoesnotapplytothereplacementsteamgenerators(RSGs).Theproposedchangereturnsthepluggingcriteriaforthesteamgeneratortubestotheoriginallicensingbasis.ThecriteriaareinaccordancewithNUREG-0452,(old)"StandardTechnicalSpecifications."ThepluggingcriteriaarebasedonaminimumwallthicknessduetowastageasdeterminedbyASMESectionXI.TheproposedchangeisconservativeinnaturebecauseitdoesnotallowforcontinuedoperationwithF*andvoltage-baseddegradedtubes.Becauseofthis,theprobabilityofasteamgeneratortuberupture(SGTR)isnotincreased.ThepotentialforaSGTRisalsonotincreasedasdemonstratedinthequalificationanalysisandtestingfortheRSGs.Theprogramforperiodicin-serviceinspectionmonitorstheintegrityoftheSGtubingtoprovidereasonableassurancethatthereissufficienttimetotakeproperandtimelycorrectiveactionifanytubedegradationisdetected.ThetubeinspectionsthemselvesarenotinitiatorsofaSGTR.Therefore,thischangeisnotexpectedtoincreasetheprobabilityofaSGTRduringnormaloraccidentconditions.Unit1willcontinuetoapplytheT/Smaximumprimary-to-secondaryleakagelimitof150gallonsperday(gpd)throughanyoneSGtominimizethepotentialforexcessiveleakage.TheEPRI-recommended150gpdlimitprovidesforleakagedetectionandplantshutdownintheeventofanunexpectedtubeleakandminimizesthepotentialforexcessiveleakageortubeburstintheeventofmainsteamlinebreak(MSLB)orloss-of-coolantaccident(LOCA)conditions.Thislowerlimitismorerestrictivethanthelimit(500gpdperSGandtotalleakageof1440gpd)utilizedfordeterminationofoffsitedoseandalsoprovidesfurtherassurancethattheprobabilityofaSGTRisnotincreased.ThedesignbasisdosescalculatedforpostulatedaccidentsinvolvingdegradationofSGtubes,suchasSGTRandMSLBaccidents,aspresentedinUFSARchapter14accidentanalysis,havebeenevaluated.TheSGTRconsequencescontinuetobeboundedbythedesignbasisanalysesduetotheallowableleakageratespecifiedbythischange.TheproposedT/Sleakagerateismaintainedat150gpdperSG.However,themaximumleakageof500gpdperSGandtotalleakageof1440gpdforallfourgeneratorswasusedtodetermineoffsitedoseinUFSARchapter14.TheMSLBconsequencesaredecreasedbyinstallationoftheRSGsduetothereductioninprimary-to-secondaryleakageduring'theMSLB.Undertheapprovedinterimpluggingcriteria,aleakrateof8.4gpmwasdeterminedtobetheupperlimitforallowableprimary-to-Ilga' Attachment1toC0799-05Page13secondaryleakageinthefaultedsteamgenerator.Thisleakage,combinedwiththe150gpdleakagefromthenon-faultedSGs,wasdeterminedtolimittheoffsitedoseto10%ofthe10CFR100limits.FollowingreplacementoftheSGs,theleakageislimitedduringtheMSLBto150gpdforboththefaultedandunfaultedSGs.Therefore,theUnit1MSLBdosewillbeboundedbythecurrentUnit2doseanalysis,whichislessthan10%of10CFR100limits.Therefore,theproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Criterion2:Theproposedchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Removingapplicationofvoltage-basedrepaircriteria,F*repaircriteria,andsleevingmethodologiesuponinstallationoftheRSGswillnotintroducesignificantoradversechangestotheplantdesignbasisthatcouldleadtoanewordifferentkindofaccidentbeingcreated.Thischangedoesnotchangetheoverallobjectiveofsurveillanceactivities-maintainingthestructuralintegrityofthisportionofthereactorcoolantsystem.Thesurveillanceactivitiesareperformedduringoutages.Theproposedchangeinthesurveillanceprogramreturnstheprogramtotheinitiallicensingbasis.Nonewfailuresarecreated.Therefore,theproposedchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated.Criterion3:Theproposedchangedoesnotinvolveasignificantreductioninamarginofsafety.Removingtheapplicationofvoltage-basedandF*repaircriteriaandsleevingmethodologiesdoesnotinvolveareductioninamarginofsafety.TheRSGtubinghasbeenshowntoretainadequatestructuralandleakageintegrityduringnormal,transient,andpostulatedaccidentconditionsconsistentwithGDC14,15,30,31,and32of10CFR50appendixA.TheRSGtubinghasbeendesignedandevaluatedconsistentwiththeASMESectionIII,1989edition.TheproposedpluggingcriteriaarebasedonASMESection'IanddonotallowforoperationwithindicationsidentifiedbyF*andvoltage-basedcriteria.Theproposedprogramforperiodicin-serviceinspectionoftheRSGsmonitorstheintegrityoftheSGtubingtoprovidereasonableassurancethatthereissufficienttimetotakeproperandtimelycorrectiveactionifanytubedegradationispresent.Theproposedprogram
~l'lt' Attachment1toC0799-05Page14isconsistentwithNUREG-0452andwasthebasisfortheoriginalUnit1T/Ssurveillanceprogram.TheproposedchangemaintainstheT/Smaximumprimary-to-secondaryleakageat150gpdpergeneratortominimizethepotentialforexcessiveleakage.ThislimitprovidesforleakagedetectionandshutdownintheeventofanunexpectedtubeleakandminimizesthepotentialforexcessiveleakageortubeburstintheeventofaMSLBorLOCA.Becausethislimitismaintained,themarginofsafetyismaintained.Therefore,itisconcludedthatthischangedoesnotinvolveasignificantreductioninamarginofsafety.