ML17229A519
| ML17229A519 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/07/1997 |
| From: | STALL J A FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-97-287, NUDOCS 9711120292 | |
| Download: ML17229A519 (23) | |
Text
CATEGORY1REGUL'ATINFORMATIONDISTRIBUTIOYSTEM(RIDS)ACCESSIONNBR:9711120292DOC.DATE:97/11/07NOTARIZED:NOFACIL:50-335St.LuciePlant,Unit1,FloridaPowerELightCo.AUTH.NAMEAUTHORAFFILIATIONSTALL,J.A.FloridaPowerSLightCo.RECIP.NAMERECIPXENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKET05000335
SUBJECT:
VerifiesthatcontainmentstructuralintegrityScontainmentleakageratesareacceptablebyTSSRs4.6.1.6R4.6.1.2,respectively.NextperiodicILRTisduebeforeMay2003.Basisofutil'sdecisionenclforinfo.DISTRIBUTIONCODE:A017DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:AppendJContainmentLeakRateTestingNOTES:ATERECIPIENTIDCODE/NAMEPD2-3LAWIENS,L.INTERNAL:ACRSNRR/DE/ECGBOGC/HDS3EXTERNAL:NOACCOPIESLTTRENCL101'111111111RECIPIENTIDCODE/NAMEPD2-3PDFILECENTER0RES/DE/SEBNRCPDRCOPIESLTTRENCL11111111RD0ENOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR11ENCL10 FloridaPower&LightCompany.6351S.OceanDrive,JensenBeach,FL34957-November7,1997I97-28710CFR50.4U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555RE:St.LucieUnit1DocketNo.50-335IntegratedLeakTest-DeferralAtmeetingsbetweenFloridaPowerandLightCompany(FPL)andtheNRCStaffonJune17,1997andSeptember23,1997,FPLpresentedthescheduleforthesteamgeneratorreplacement(SGR)outage.Thescheduleincludedtheplannedperformanceofacontainmentintegratedleakratetest(ILRT).FPLverifiescontainmentstructuralintegrityandcontainmentleakageratesareacceptablebyTechnicalSpecification(TS)surveillancerequirements,4.6.1.6and4.6.1.2,respectively.ThesespecificationsrelyoninspectionsandleakagetestingperformedinaccordancewiththeContainmentLeakageRateTestingProgramdescribedinTS6.8.4(h).FPLwillbeperformingthestructuralintegrityinspectionsrequiredbyTS4.6.1.2.However,FPLhasdeterminedthatthecontainmentleakagetestingcanbeaccomplishedbytheperformanceofalocalleakratetestforthecontainmentconstructionhatchweldandtheASMESectionXIpressuretestofthesecondarysideofthereplacementsteamgenerators.Therefore,anILRTisnotrequiredfortheSGRandtheplannedILRTcanbeconductedatthenextregularlyscheduledILRT.ThenextperiodicILRTisduebeforeMay2003.ThebasisofFPL'sdecisionisattachedforyourinformation.FPLispreparedtodiscussanystaffquestionsonthisdetermination.Vertyours,/.A.StallVicePresidentSt.LuciePlantAttachmentJAS/GRMcc:RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St,LuciePlant97iiiM29297i107PQRADQCK05000335pPDRanFPLGroupcompanyII!Illlllllllllllllllllllllllill/IIIIIII
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St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage1ST.LUCIEUNIT1STEAMGENERATORREPLACEMENTEVALUATIONFORCONTAINMENTTESTINGREQUIREMENTS1.0DESCRIPTIONANDPURPOSEThisevaluationwillservetodocumentthetestingrequirements,asrequiredby10CFR50AppendixJ,whichareapplicabletotheUnit1steelcontainmentpressurevesselfollowingthereplacementofthetwosteamgeneratorsscheduledfortheFall1997refueling/steamgeneratorreplacementoutage(SL1-15).ThetestingapproachfortheUnit1containmenthasbeenevaluatedagainstthefacilitychangecriteriaestablishedby10CFR50.59.MetwoUnit1steamgeneratorsarebeingreplacedduringtheFall1997refuelingoutage(SL1-15).TheStLucieUnit1containmentpressurevessel(Figure1)isafreestandingcarbonsteelvesselwithfourmajorpenetrations(Figure2):anescapelock;apersonnellock;amaintenancehatch;andaconstructionhatch.Accessforthenewreplacementsteamgenerators,aswellasremovaloftheoldsteamgenerators,willrequireopeningtheexistingconstructionhatch,whichisanintegrallyreinforcedpenetrationthroughthesteelcontainmentvesselwallwithaweldedclosurecap.Theconstructionhatchpenetration(Figure3)isa28-footdiametercylinderthathasaweldedellipsoidalclosurecover,whichextendsabout11feetinsidethesteelcontainmentpressurevessel.Thedouble-sidedfullpenetrationbuttweldattachingtheconstructionhatchcoverwillbecutandthecoverremovedduringtheoutage.Whentheoldsteamgeneratorshavebeenremovedfromcontainmentandthenewsteamgeneratorshavebeenplacedwithincontainment,theconstructionhatchcoverwillbeweldedbackinplaceontheendofthecylindricalconstructionhatch.TheremovalandweldingoftheconstructionhatchcoverwillbeperformedundertheSt.LucieASMESectionXIRepairandReplacementProgram.Repairandreplacementactivitieson,thecontainmentvesselwillbegovernedbyASMESectionXI,SubsectionIWE1992Edition,including1992Addendum.Unit1iscurrentlyinthesecondTenYearInServiceInspectionIntervalinaccordancewithASMESectionXI1983,includingtheSummer1983Addendum.Inadditiontothecuttingandweldingperformedontheconstructionhatch,allpiping,includingthereactorcoolantsystem(RCS)hotleg,RCSintermediateleg,mainsteam,feedwater,blowdownpiping,andinstrumentationlineswillbecutfreefromtheexistingsteamgeneratornozzlestofacilitatesteamgeneratorreplacement.Whenthesecondarysystempipingiswelded,attachingthemtothenewsteamgenerators,thenewweldjointsforthemainsteamandfeedwaterpipingwillformapartofthecontainmentpressureboundaryalongwiththeconstructionhatchclosurecover.Theremovalandweldingof St.LucieUnit1DocketNo.50-.335I97-287AttachmentPage2thesteamgeneratorsandassociatedpipingwillbeperformedundertheSt.LucieASMESectionXIprogramcoveringreplacementactivities.BasedontheoriginalrequirementsoftheSt.LucieplantTechnicalSpecifications,whichimplementedtherequirementsof10CFR50AppendixJforperiodicleakageratetesting,aperiodicIntegratedLeakRateTest(ILRT)wouldhavebeenscheduledduringtheFall,.1997refuelingoutage(SL1-15).ThattestwouldhaveservedtosatisfytheTechnicalSpecificationleakagetestsurveillancerequirementsaswellasserveasatestfortheconstructionhatchreinstallation.Thistestingwouldalsoinvolveothersteamgeneratorreplacementactivities:(a)installationofpadsonthecontainmentdome;and(b)closureweldsonthesecondarysidelineswheretheyattachtothenewsteamgenerators.However,basedonarecentrevisiontoSt.LucieUnit1TechnicalSpecificationsthatadopted10CFR50AppendixJ,OptionB,anormalsurveillanceILRTisnolongerrequireduntilMay2003.Accordingly,thisevaluationwilldocumentacceptablealternativestoanILRTforsteamgeneratorreplacementactivitiesinaccordancewiththeprovisionsof10CFR50AppendixJ,OptionB(Reference3),theSt.LucieUnit1TechnicalSpecifications(Reference2),andUpdatedFSAR(Reference1).2.0FPLevaluatedtheproposedalternativesfortestingofthecontainmentvesselandsecondary.systempipingasacceptablealternativestoafullILRT,andevaluatescompliancewiththeprovisionsof10CFR50AppendixJ,OptionB,plantTechnicalSpecifications,andtheUpdatedFSAR.Thistestingapproachwasev'aluatedagainstthecriteriaof10CFR50.59toensurethatitdoesnotconstituteanunreviewedsafetyquestion,orrequirechangestoTechnicalSpecifications.LICENSINGANDDESIGNBASISREQUIREMENTS2.1TECHNICALSPECIFICATIONREQUIREMENTSOnSeptember12,1995,theNRCapprovedarevisionto10CFRPart50,AppendixJ(Reference3),whichbecameeffectiveonOctober26,1995.Thisrevisionto10CFR50,AppendixJ,added"OptionB",whichaddressesperformancebasedrequirementstoallowlicenseestovoluntarilyreplacetheprescriptiverequirementsof10CFRPart50,AppendixJ,withtestingrequirementsbasedonbothpreviousoverallperformanceandperformanceofindividualcomponents.Performancebasedtestingintervalsarebasedonconsiderationoftheoperatinghistoryofacomponentandthepotentialriskassociatedwithitsfailure.OnOctober28,1996,FPLsubmittedaproposedlicenseamendmenttotheNRC(Reference4)requestingamodificationofPlantTechnicalSpecificationstoallowimplementationof10CFR50AppendixJ,OptionB.ThepurposeofthisamendmenttoTechnicalSpecificationswastoallowTypeA,B,andCcontainmentleakageteststobeconductedatintervalsdeterminedbyperformancebasedcriteria.FPLdevelopedtheSt,LucieAdministrativeProcedureADM68.01,"ContainmentLeakageRateTesting tSt.LucieUnit1DocketNo.50-335L-97-287AttachmentPage3Program,"(Reference5)whichFPLincorporatedbyreferenceintoplantTechnicalSpecifications.ThisAdministrativeProcedurereferencestheuseofcriteriafromRegulatoryGuide1.163(Reference6),whichspecifiesamethodacceptabletotheNRCforcomplyingwith10CFR50AppendixJ,OptionB,andendorsesapplicationofanexceptiontoRegulatoryGuide1.163,whichspecificallyallowstheuseofeitherBechtelTopicalReportBN-TOP-1orANSI/ANS56.8-1994(Reference8)forTypeAleakageratetesting.RegulatoryGuide1.163approvedtheintervalsestablishedinNEI94-01(Reference7),whichspecifiesanextensioninTypeAtestfrequencytoatleastonetestin10yearsbasedupontwopreviousconsecutivesuccessfultests.TheSt.LucieUnit1containmentoperatinghistoryhasdocumentedsevensuccessfulILRTswithnoassociatedfailurestomeetacceptancecriteria.Theuseof10CFR50,AppendixJ,OptionB,includingtheexceptiontoallowuseofeitherBechtelTopicalReportBN-TOP-1orANSI/ANS56.8-1994forTypeAleakageratetestingwassubsequentlyapprovedbytheNRCinLicenseAmendment149totheUnit1OperatingLicense(Reference2).CurrentSt.LucieUnit1TechnicalSpecificationsrequireverificationthatcontainmentstructuralintegrityandcontainmentleakageratesareacceptableperTechnicalSpecifications4.6.1.6and4.6.1.2,respectively.ThesespecificationsrelyoninspectionsandleakagetestingperformedinaccordancewiththeContainmentLeakageRateTestingProgramdescribedinT.S.6.8.4(h).2.2NRCSAFETYEVALUATION(SER)TheoriginalNRCevaluationforcontainmentisdocumentedinSections3.8.1and6.2.1oftheNRCSER(Reference9)ofMarch1976.ThatSERevaluatedthepeakcontainmenttransientpressurefortheworstcaseprimarypipebreak,whichwascalculatedas38.4psig.TheNRCverifiedthisvaluethroughtheirowncalculationofpeakcontainmentpressure.TheNRCconcludedthatthemaximumcontainmentpressurewascorrectlycalculatedbytheapplicantandwasbelowthedesigninternalpressureof44psigbyanacceptablemargin.2.3UPDATEDFSARDESIGNBASISREQUIREMENTSSection3.8,2.1oftheUnit1UpdatedFSARaddressesthedesign,designleakagecriteria,applicablecodes,pressuretesting,andpost-operationaltestingandinspectionrequirementsforthesteelcontainmentvessel.Thecontainmentvessel,includingallofitspenetrations,isalowleakageshell,whichisdesignedtoconfineradioactivematerialsthatcouldbe
tSt.LucieUnit1DocketNo.50-335L-97-287AttachmentPage4releasedfollowingaccidentallossofintegrityofthereactorcoolantpressureboundary.Thecontainmentvesselisacircularcylinderwithanintegralhemisphericaldomeandellipsoidalbottomwhichhousesthereactorpressurevessel,thereactorcoolantpipingandpumps,thesteamgenerators,thereactorcoolantpressurizerandpressurizerquenchtank,andotherbranchconnections,includingthesafetyinjectiontanks.Thecontainmentstructureincombinationwithengineeredsafetyfeaturessystemsensurethattheradiologicalexposuretothepublic,resultingfromalossofreactorcoolantaccident,willremainbelowtheguidelinesestablishedin10CFR100.Toaccomplishthis,thecontainmentstructureisdesignedtowithstandthemaximumcalculatedpeaktransientinternalpressureandtemperatureresultingfromtheworstcasedesignbasisaccidentscenario.ThecontainmentvesselanditspenetrationsaredesignedinaccordancewiththeASMECodeSectionIII,Class"B"1968.AslistedinUpdatedFSARTable6.2-1,thecontainmentpressureboundaryisdesignedfora"designinternalpressure"(definedinASMECodeArticleNE-3112)of44psigandcoincidenttemperatureof264'F.The"maximuminternalpressure"(ILRTpressure)forthecontainmentvesselis39.6psigatacoincidenttemperatureof264'F.Thecalculatedloss-of-coolant-accident(LOCA)blowdowntransientanalysisdeterminedthepeakcontainmentpressureandtemperaturethatcontainmentwouldbeexposedtofollowingadesignbasisaccident.Thisinternalpressure,referredtoasthe"maximumcalculatedpeakinternalpressure"inArticleNE-3112,is37.2psigasidentifiedinUpdatedFSARTable6.2-1.Thecorrespondingdesigntemperatureforthemaximumcalculatedpeaktransientpressureis258.6'F.Thiscontainmentpeaktransientpressurewassubsequentlyreanalyzedandcalculatedas37.5psigforthesteamgeneratorreplacement,whichisdiscussedbelowwithinSection3.2.ThisvalueremainslessthantheoriginalSERvalueof38.4psigandILRTpressurespecifiedintheUFSARof39.6pslg.Followingcompletionoftheoriginalcontainmentvesselfabricationandpost-weldheattreatment,pneumatictestingwasperformedinaccordancewiththeapplicablerequirementsoftheASMECodeandANS7.60-1971todemonstratethestructuralintegrityandleak-tightnessofthecompletedcontainmentvessel.Followingcompletionofthecontainmentoverpressuretestingandasecondsoapbubblevisualinspectiontest,aleakageratetestofthevesselwasperformed.TheTypeAintegratedleakageratetestwasperformedinaccordancewith10CFR50AppendixJ-1973andANSI45.4-1972.Thestartingtestpressurewas41.3psigtoassureacontinuoustestpressureabove39.6psig.Hourlyreadingsweretakenfor48hourstomonitorthedecayofthetestpressure.Asummarytechnicalreportofthistestingwasgeneratedwhichdocumentedtheanalysisandinterpretationoftheleakageratetestdatanecessarytodemonstratetheacceptabilityoftheleakageratetestinginmeetingacceptancecriteria.
St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage5Subsection3.8.2.1.14oftheUnit1UpdatedFSARdescribesthepost-operationaltestingandinspectionofthecontainmentvesselandpenetrationsasfollows:a.LeakageRateTesting"PeriodicleakageratetestsofthecontainmentvesselandleaktestsofthetestablepenetrationswillbeconductedasdescribedinSection6.2toverifytheircontinuedleak-tightintegrity."b.SurveillanceofStructuralIntegrity"Asteelshellpressurecontainmentvessel,designed,fabricated,inspectedandpressuretestedinaccordancewiththeASMEBoilerandPressureVesselCodeandprotectedbytheconcreteshieldbuildingwilloffercontinuedstructuralintegrityoverthelifeoftheunit...Thereforeitiscontemplatedthattherewillbenoneedforanyspecialin-servicetestsurveillancerequirementotherthanvisualinspectionoftheexposedinteriorandexteriorsurfacesofthecontainmentvessel."Section6.2.1.4.2oftheUnit1UpdatedFSARdescribestheperiodictestingandinspectionofthecontainmentvesselwhichstatesthefollowing:a.ContainmentVessel"Periodic'TypeA,BandC'eakageratetestsareconductedasapplicableinaccordancewithAppendixJ,"PrimaryReactorContainmentLeakageTestingforWaterCooledPowerReactors,"10CFR50,andunitTechnicalSpecificationstoverifythecontinuedleak-tightintegrityofthecontainment."UpdatedFSARSection10.1indicatesthatthesecondarysystempipingwasdesignedinaccordancewiththerequirementsofANSI/ANSB31.7ClassII,1969.Postconstructionpressuretestingperformedonsecondarysystempipingwasconsistentwiththeoperatingpressuresforthesesystems,whichwouldbesignificantlyinexcessofthecontainmenttestpressurerequiredbyAppendixJ.3.0ANALYSISOFEFFECTSONSAFETY3.1ENGINEERINGANALYSISOFTESTINGREQUIREMENTSTheremovalandreinstallationoftheconstructionhatchclosurecoverwillbeperformedundertheSt.LucieASMESectionXIProgram.ASMESectionXI,IWE-4000,establishesrequirementsforrepairandreplacementactivitiesforthecontainment "1
.~St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage6constructionhatchcover.TheseCoderequirementsimposeanumberofweldingandnondestructiveexaminationcriteria,includingpressuretestinginaccordancewith10CFR50,AppendixJ,asapplicableforthetypeofrepairsinvolved.ASMESectionXI,SubsectionIWE-4000andNEI94-01(per10CFR50AppendixJ,OptionB)requirethatanymodification,componentreplacement(thatispartoftheprimarycontainmentboundary),ortheresealingofaseal-weldeddoorthatwasperformedaftertheplantpre-operationalleakageratetestshallbefollowedbyeitheraTypeA,TypeB,orTypeCtest.Theserequirementsaredesignedtoensurethatanychanges,includingremovalandreplacement,areperformedinamannerthatwillnotaffecttheleak-tightnessofthecontainmentboundary.TheoriginalEbascoconstructionspecificationfortheconstructionhatchrequiredthattheoriginaldesignhavesufficientmaterialtoallowtheconstructionhatchcovertoberemovedandweldedsixtimesduringthedesignlifeoftheplant.Theoriginalconstructionspecificationforinstallationoftheconstructionhatch,aswellasthecurrentASMESectionXICode,requiresthatavolumetricexaminationbeperformedforthecompletedweldingoftheconstructionhatchcover.Asmentionedabove,theremovalandreinstallationoftheconstructionhatchcoverwillbeperformedinaccordancewithASMESectionXI,SubsectionIWE,whichimposesrepairorreplacementrequirementsonthisactivity(Reference13),includingthevolumetricexaminationofthecompletedwelding.TheASMESectionXICoderequiresapressuretestaftercompletionofinstallationofthesystemorcomponentpart.TheSt.Lucieplantwillsatisfythepressuretestrequirements,aswellasthoseofAppendixJ,byperformingapneumatictestoftheconstructionhatch-to-cover-weldjointatorabovethecontainmentvesselinternaldesignpressureof39.6psig.Thispressuretestfortheconstructionhatchweldingwillbeaccomplishedbyconstructionofatestchamberaroundtheweldjointbetweentheconstructionhatchanditscover(Figure4).Thetestchamberwillbepressurizedandasoapbubbletestwillbeutilizedtodemonstratethatzeroleakageoccursintheweldjoint.Thetestpressureof39.6psigmeetsthecriteriafortestinginaccordancewith10CFR50AppendixJ,OptionB,underthecriteriaofANSI/ANS56.8.ANSI/ANS56.8specifiessomeoftheacceptablemethodsfortestingandrequiresthatthesetestsbeperformedatatestpressureatleastequaltothetestpressureofatleast39.6psigasspecifiedintheUFSAR.ContainmentstructuralintegritywillbeverifiedacceptablebytheperformanceofTechnicalSpecification4.6.1.6.ThisspecificationreliesoninspectionsperformedinaccordancewiththeContainmentLeakageRateTestingProgramthatisdescribedinT.S.6.8.4(h).Asdescribedbelow,severalNRCandindustrydocumentsprovideguidanceoncompliancewith10CFR50,AppendixJ.
St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage7aoAppendixJto10CFR50(Reference3)specifiestestrequirementstoensurethat:a)leakagedoesnotexceedallowableratesspecifiedinplantTechnicalSpecifications;andb)integrityofthecontainmentstructureismaintainedduringitsServicelife.Twooptionsareprovided,"eitherofwhichcanbechosenformeetingtherequirementsofthisAppendix".Aspreviouslydiscussed,St.LucieUnit1hasadoptedtherulesspecifiedinOptionBforperformancebasedtesting.OptionBreferencesNRCRegulatoryGuide1.163(Reference6)forguidanceonmeetingOptionB.'.RegulatoryGuide1.163,"Performance-BasedContainmentLeak-TestProgram,"(Reference6)brieflydescribestheregulatorypositiononperformancebasedtestingandendorsesNuclearEnergyInstitute(NEI)documentNEI-94-01Revision0,(Reference7)formethodsacceptabletocomplywiththeprovisionsofOptionB,subjecttofourexceptions:a)establishmentoftestintervalstobebasedonNEI-94-01andnotthereferencedANSI/ANS56.81994standard;b)establishmentofTypeCtestingintervalsforcertaincomponentsmustbelessthan30monthsforpurgevalvesandnogreaterthan60monthsforothercomponents;c)visualexaminationrequirementsofthecontainmentvesselarerequired;andd)certainalternativestoTypeCtestsarenotallowed.ThefirstexceptionprovidesthemethodtojustifyatenyearintervalfortheILRT,theremainingthreeexceptionsdonotaffectthisevaluation.C.NEI-94-01,"IndustryGuidelineforImplementingPerformance-BasedOptionof10CFRPart50,AppendixJ,"(Reference7)wasdevelopedbyanNEIWorkingGroupandTaskForceforimplementationofAppendixJthealternativecontainmenttestingrule.ThepurposeofthisdocumentistoassistlicenseesintheimplementationofOptionBtominimizetheredundantandoverlappingengineeringandevaluationeffortsassociatedwithregulatoryrequirements.Section9ofNEI-94-01describesthemethodologyfordeterminingTypeA,B,andCintervals.EstablishmentofintervalsisdocumentedintheContainmentLeakageRateTestingProgramandisnotwithinthescopeofthisevaluation.AsdiscussedinNEI94-01,Section9.2.4,testrequirementsfor"repairsandmodificationsthataffectthecontainmentleakageintegrityrequireleakageratetesting(TypeAtestingorlocalleakageratetesting)priortoreturningthecontainmenttooperation."Theconstructionhatchcoverwastestedaspartoftheoriginalpostconstructionstructuralintegritytestat49.5psigandinsevensubsequentILRT's,ThefullpenetrationbuttweldwillbeexaminedinaccordancewithASMESectionXIusingvolumetricexaminationmethods.Basedonthesignificantsizeofthebuttweld(1-1/2")andtherequirednon-destructiveexamination(NDE),noleakagethroughthisweldedjointisexpectednorwillanyleakagebeacceptable.InaccordancewithNEI94-01,Section9.2.4,"localleakageratetesting"willbeperformed.Thelocalleakagetestingwillconsistofinstallationofaleakchase, St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage8pressurizingtoatleast39.6psig,andapplicationofasoapbubblesolution(snoop)totestthebuttweldfromtheoppositeside(Figure4).Thismethodoftestingisadvantageousbecauseitdefinitivelyteststhespecificweldinquestionwithanacceptancecriterionof"zeroleakage."d.Generally,asoapbubble(snoop)testisnotconsideredanacceptablemethodofquantifyingleakage,asdiscussedinReference10.Thisisbecausethecorrelationofsoapbubblestoaleakagerateisnotwelldefined.Theexceptiontothisisiftheleakagecriterionissetto"zeroleakage",thenthemethodprovidesquantifiableresults-noleakageatall(Reference10).Althoughleakageisacceptableintermsoftheoverallcontainmenttestingprogram(i.e.,sumofallleakagepaths),thisparticulartestwillhaveastrictcriterionof"zeroleakage."Basedontheabove,theuseofalocalleakchasemeetstherequirements10CFR50AppendixJ,OptionB.Intermsofcontainmentisolationfeatures,thesecondarysidesystemconsistingofmainfeedwaterandmainsteampipingarenormallyconsideredpartofthepassiveclosedsysteminsidecontainmentwhichisanextensionofthecontainmentstructure.DuringanILRT,thesecondarysidesystemisventedtoatmosphereinordertoprovideapressuredifferentialof39.6psigorgreaterfromthecontainmentatmospheretotheoutsideatmospherethroughthemainsteampipingsystem.Thesecondarysideofthereplacementsteamgeneratorshavebeenhydrotestedto1.25x1000=1250psiaaspartofthefabricator'sprogram.Oncethepipingtoandfromthesteamgeneratorsisweldedinplace,theweldswillbeexaminedandapressuretestperformedinaccordancewithASMESectionXI.ThistestwillbeatpressuresapproximatelytwentytimeshigherthanthatofanILRT.AlthoughtheleaktestisinadirectionreversetothatofaLOCAenvironment,thetestisacceptablebecauseofthehighpressureduringtheleaktest.Section9.2.1ofNEI94-01andSection6.2ofANSI/ANS56.8allowlicenseestoutilizereversetestingifjustified.Fortheseweldedconnections,noleakagewillbeacceptable.Thisisconsistentwithinterpretationsmadebyotherplants.Accordingly,asdiscussedinReference11,thistestingisconsideredacceptabletomeet10CFR50AppendixJ.Forpadsweldedtothecontainmentvessel,testrequirementssubsequenttorepairsandmodificationsareaddressedinNEI94-01,Section9.2.4.Forweldsofattachmentstothesurfaceofsteelpressure-retainingboundary,TypeA(ILRT)testingmaybedeferredtothenextscheduledILRT.Accordingly,theinstallationofpadstothecontainmentwithoutperformanceofanILRTthisoutagemeetstherequirementsofAppendixJtesting.
4 PSt.LucieUnit1DocketNo.50-335L-97-287AttachmentPage93.2STEAMGENERATORREPLACEMENTEVALUATIONTheevaluationoftheSteamGeneratorReplacementProject(SGRP)activitiesisaddressedintheSGRPStandAloneSafetyEvaluation.Thisreportcontainsthetwoseparate50.59evaluationsforSGRPactivities.FPL'sEvaluation(Reference14)containsanevaluationofconstructionactivitiesandplantchangesasaresultoftheimplementationeffort,ThesecondFPLevaluation(Reference15)containsanevaluationofthereplacementsteamgenerator.ThesetwoevaluationsdonotaddressthespecifictypeoftestingthatwouldberequiredtosatisfyAppendixJrequirements.TheuseofalocalleakratetestforthecontainmentconstructionhatchasdiscussedwithinthisevaluationwillnotaffecttheconclusionspreviouslyreachedinthetwoSGRPevaluationsidentifiedabove.AcontainmenttransientresponseevaluationfortheworstcaseLOCAwasperformedaspartoftheevaluationsperformedfortheSGRP.Thereplacementsteamgeneratorscontainslightly.moreprimarysidemassthantheoriginalsteamgenerators.ThisresultsinaslightincreaseinthepeakcontainmentpressurefollowingtheworstcaseLOCA.Calculationsperformedwithanincreasedprimarysidemassandenergycorrespondingtothereplacementsteamgeneratorsshowthattheblowdownresultsinapeakcontainmentpressureof37.5psig.Thisisanincreaseof0.3psigoverthecurrentcontainmentanalysisofrecord(37.2psig)showninUpdatedFSARTable6.2-1.TheSGRPpeakcontainmenttransientpressureof37.5psigislessthanthepeakpressureof38.4psigoriginallyacceptedbytheNRCintheoriginalplantSER(Reference9)andremainsbelowtheoriginallyspecifiedILRTtestpressureofatleast39.6psig.Therefore,theproposeduseofalocalleakratetestpressureof39.6psigwillstillboundthenewcontainmentpeaktransientpressurecalculatedfortheSteamGeneratorReplacementProject,4.0EFFECTONTECHNICALSPECIFICATIONSTheconstructionhatchcoverwastestedaspartoftheoriginalpostconstructionstructuralintegritytestat1.25X39.6=49.5psigandinsevensubsequentILRTs.ThefullpenetrationbuttweldwillbeexaminedinaccordancewithASMESectionXIusingvolumetricexaminationmethods.Althoughsomeleakagewouldbeacceptableintermsoftheoverallcontainmenttestingprogram(thatis,thesumofallleakagepaths),thecontainmentleakagetestproposedforthereinstallationoftheconstructionhatchwillhaveastrictcriterionofzeroleakageinordertosatisfytherepairandreplacementrequirements.Basedontheabove,theuseofalocalleakchasemeetstherequirementsofAppendixJtesting.Consequently,thedesignmarginsidentifiedforcontainmentintheSt.LucieContainmentLeakageRateTestingProgram,referencedinplantTechnicalSpecifications(Reference2),willberestoredaftertheweldrepairsarecompletedontheconstructionhatchcoverandsecondarysystempipingwithincontainment.TheproposedtestingactivitieswillhavenoeffectsonplantTechnicalSpecifications,andthetestingprogramusingthepressure tSt.LucieUnit1DocketNo.50-335L-97-287AttachmentPage10of39.6psigforthecontainmentvesselwillnotrequireanychangestoTechnicalSpecificationsinordertoimplementthetestingapproachoutlinedinthisevaluation.
5.0CONCLUSION
SThisevaluationservestodocumentthetestingrequirementsfrom10CFR50,AppendixJ,whichareapplicabletotheUnit1steelcontainmentpressurevesselfollowingthereplacementofthetwosteamgeneratorsscheduledfortheFall1997refueling/steamgeneratorreplacementoutage(SL1-15).ThetestingapproachfortheUnit1containmentthatisdiscussedabovehasbeenevaluatedagainstthefacilitychangecriteriaestablishedby10CFR50;59toensurecompliancewithNRCregulatorycriteria.ThisevaluationconcludesthattheproposedmethodologyfortestingthecontainmentvesselandsecondarysystempipingisanacceptablealternativestoafullILRTandcomplieswiththeprovisionsof10CFR50,AppendixJ,plantTechnicalSpecifications,andtheUpdatedFSAR.Thetestingapproachasevaluatedagainstthecriteriaof10CFR50.59determinedthattheproposedtestingapproachdoesnotinvolveanunreviewedsafetyquestion,orrequirechangestoTechnicalSpecifications.Therefore,thistestingapproachcanbeimplementedwithoutpriorNRCapprovalpursuanttotherequirementsof10CFR50.59.
6.0REFERENCES
StLucieUnit1UpdatedFSAR,Section3.8.2,"ContainmentStructure,"andSection6.2.1,"ContainmentFunctionalDesign."2.StLucieUnit1TechnicalSpecifications3.6.1.1,3.6.1.2,3.6.1.3,3.6.1.6,3.6.6.3,and6.8.4,AmendmentNo.149,transmittedbyNRCletterdatedFebruary10,1997.3.Title10CodeofFederalRegulations(CFR)Part50,AppendixJ,"PrimaryReactorContainmentLeakageTestingforWater-CooledPowerReactors,"EffectiveDateOctober26,1995.4.FPLletterL-96-244,"St.LucieUnit1,ProposedLicenseAmendment-Implementationof10CFR50AppendixJ,OptionB,"datedOctober28,1996.5.St.LuciePlantAdministrativeProcedureADM68.01,"ContainmentLeakageRateTestingProgram,"Revision0.6.NRCRegulatoryGuide1.163,"PerformanceBasedContainmentLeak-TestProgram,"datedSeptember1995.7.NuclearEnergyInstituteGuidelineNEI94-01,"IndustryGuidelineForImplementingPerformance-BasedOptionOf10CFRPart50,AppendixJ,"Revision0,datedJuly26,1995.
St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage118.ANSI/ANS-56.8-1994,"AmericanNationalStandardForContainmentSystemLeakageTestingRequirements."9.AECSt.Lucie1SafetyEvaluation(SER),"SafetyEvaluationoftheSt.LuciePlantUnitNo.l,"datedNovember8,1974,May9,1975,andMarch1,1976.10.USNRC,NuclearReactorRegulation,letter(C.Y.Shiraki,DivReactorProjects-III/IV)toCommonwealthEdisonCo.(D.L.Farrar),"IssuanceofExemptionsFromtheRequirementsof10CFRPart50,AppendixJ-ZionNuclearPowerStation,UnitNos.1and2,"datedDecember28,1995.(Page6Item1)11.NRCNuclearReactorRegulation,InternalMemorandum(G.M.Holahan,Div.ofSystemTechnology,toJ.A.Zwolinski,DivisionofReactorProjectsIII,IV,andV),"RegionIIIRequestforPositiononLeakageOutofContainmentThroughPWRSteamGeneratorSecondarySideDuringContainmentIntegratedLeakageRateTest,"datedFebruary1,1991.(Page3ResponsetoQuestion3)12.NRCInformationNotice97-29,"ContainmentInspectionRule,"datedMay30,1997.13.SGRPSafetyEvaluationENG-PSL-SEMP-94-034,"CodeReconciliationforSGRP,"Revision3,datedSeptember3,1997.14.SGRPSafetyEvaluationENG-PSL-SEMP-94-033,"SafetyEvaluationforthePSL-1SteamGeneratorReplacementProject,"Revision6,datedJuly17,1997.15.SGRPSafetyEvaluationENG-PSL-SEMP-94-026,"StandAloneSafetyEvaluation(SASE)Volume2-SteamGeneratorEquivalencyReport(SGER),"Revision1,datedJune3,1997.
St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage12SHIELDBUILDNOCCHTANMEHTVESSELddCONST.HATCHQELEV.7SWdddd0000dqdq00d0d00dqdq0d0CROSSSECTIONOFCONTAINMENTVESSELAND'SHIELDBUILDINGFigure1 St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage13MAINTENANCEHATCHEOUIPMENTHATCH//ESCAPEAIRLOCK/r///I//PERSONNELAIRLOCKPLANVIEWOFUNIT1CONTAINMENTANDMAJORPENETRATIONSFigure2
St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage1411/2'UTSIDECONTAINMENTINSIDECONTAINMENTFIGLRE4ELUPSOlOALHEAD~LXV.ra'sr~7I15"51I4'ONSTRUCTIONHATCHTHROUGHCONTAINMENTVESSELFigure3
St.LucieUnit1DocketNo.50-335L-97-287AttachmentPage15LOCALLEAKCHASE{COHCEPTUAISABDETAILSBESIODEVELOPED)LEAKCHASEDETAILFigure4