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'ATINFORMATION DISTRIBUTIO YSTEM(RIDS)ACCESSION NBR:9711120292 DOC.DATE:
97/11/07NOTARIZED:
NOFACIL:50-335 St.LuciePlant,Unit1,FloridaPowerELightCo.AUTH.NAMEAUTHORAFFILIATION STALL,J.A.
FloridaPowerSLightCo.RECIP.NAME RECIPXENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000335
SUBJECT:
Verifiesthatcontainment structural integrity Scontainment leakageratesareacceptable byTSSRs4.6.1.6R4.6.1.2,respectively.
NextperiodicILRTisduebeforeMay2003.Basisofutil'sdecisionenclforinfo.DISTRIBUTION CODE:A017DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
AppendJContainment LeakRateTestingNOTES:ATERECIPIENT IDCODE/NAME PD2-3LAWIENS,L.INTERNAL:
ACRSNRR/DE/ECGB OGC/HDS3EXTERNAL:
NOACCOPIESLTTRENCL101'111111111RECIPIENT IDCODE/NAME PD2-3PDFILECENTER0RES/DE/SEB NRCPDRCOPIESLTTRENCL11111111RD0ENOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
LTTR11ENCL10 FloridaPower&LightCompany.6351S.OceanDrive,JensenBeach,FL34957-November7,1997I97-28710CFR50.4U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555RE:St.LucieUnit1DocketNo.50-335Integrated LeakTest-DeferralAtmeetingsbetweenFloridaPowerandLightCompany(FPL)andtheNRCStaffonJune17,1997andSeptember 23,1997,FPLpresented thescheduleforthesteamgenerator replacement (SGR)outage.Thescheduleincludedtheplannedperformance ofacontainment integrated leakratetest(ILRT).FPLverifiescontainment structural integrity andcontainment leakageratesareacceptable byTechnical Specification (TS)surveillance requirements, 4.6.1.6and4.6.1.2,respectively.
Thesespecifications relyoninspections andleakagetestingperformed inaccordance withtheContainment LeakageRateTestingProgramdescribed inTS6.8.4(h).FPLwillbeperforming thestructural integrity inspections requiredbyTS4.6.1.2.However,FPLhasdetermined thatthecontainment leakagetestingcanbeaccomplished bytheperformance ofalocalleakratetestforthecontainment construction hatchweldandtheASMESectionXIpressuretestofthesecondary sideofthereplacement steamgenerators.
Therefore, anILRTisnotrequiredfortheSGRandtheplannedILRTcanbeconducted atthenextregularly scheduled ILRT.ThenextperiodicILRTisduebeforeMay2003.ThebasisofFPL'sdecisionisattachedforyourinformation.
FPLispreparedtodiscussanystaffquestions onthisdetermination.
Vertyours,/.A.StallVicePresident St.LuciePlantAttachment JAS/GRMcc:RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St,LuciePlant97iiiM292 97i107PQRADQCK05000335pPDRanFPLGroupcompanyII!Illlllllllllllllllllllllllill/IIIIIII
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St.LucieUnit1DocketNo.50-335L-97-287Attachment Page1ST.LUCIEUNIT1STEAMGENERATOR REPLACEMENT EVALUATION FORCONTAINMENT TESTINGREQUIREMENTS
1.0 DESCRIPTION
ANDPURPOSEThisevaluation willservetodocumentthetestingrequirements, asrequiredby10CFR50AppendixJ,whichareapplicable totheUnit1steelcontainment pressurevesselfollowing thereplacement ofthetwosteamgenerators scheduled fortheFall1997refueling/steam generator replacement outage(SL1-15).
ThetestingapproachfortheUnit1containment hasbeenevaluated againstthefacilitychangecriteriaestablished by10CFR50.59.MetwoUnit1steamgenerators arebeingreplacedduringtheFall1997refueling outage(SL1-15).
TheStLucieUnit1containment pressurevessel(Figure1)isafreestandingcarbonsteelvesselwithfourmajorpenetrations (Figure2):anescapelock;apersonnel lock;amaintenance hatch;andaconstruction hatch.Accessforthenewreplacement steamgenerators, aswellasremovaloftheoldsteamgenerators, willrequireopeningtheexistingconstruction hatch,whichisanintegrally reinforced penetration throughthesteelcontainment vesselwallwithaweldedclosurecap.Theconstruction hatchpenetration (Figure3)isa28-footdiametercylinderthathasaweldedellipsoidal closurecover,whichextendsabout11feetinsidethesteelcontainment pressurevessel.Thedouble-sided fullpenetration buttweldattaching theconstruction hatchcoverwillbecutandthecoverremovedduringtheoutage.Whentheoldsteamgenerators havebeenremovedfromcontainment andthenewsteamgenerators havebeenplacedwithincontainment, theconstruction hatchcoverwillbeweldedbackinplaceontheendofthecylindrical construction hatch.Theremovalandweldingoftheconstruction hatchcoverwillbeperformed undertheSt.LucieASMESectionXIRepairandReplacement Program.Repairandreplacement activities on,thecontainment vesselwillbegovernedbyASMESectionXI,Subsection IWE1992Edition,including 1992Addendum.
Unit1iscurrently inthesecondTenYearInServiceInspection Intervalinaccordance withASMESectionXI1983,including theSummer1983Addendum.
Inadditiontothecuttingandweldingperformed ontheconstruction hatch,allpiping,including thereactorcoolantsystem(RCS)hotleg,RCSintermediate leg,mainsteam,feedwater, blowdownpiping,andinstrumentation lineswillbecutfreefromtheexistingsteamgenerator nozzlestofacilitate steamgenerator replacement.
Whenthesecondary systempipingiswelded,attaching themtothenewsteamgenerators, thenewweldjointsforthemainsteamandfeedwater pipingwillformapartofthecontainment pressureboundaryalongwiththeconstruction hatchclosurecover.Theremovalandweldingof St.LucieUnit1DocketNo.50-.335I97-287Attachment Page2thesteamgenerators andassociated pipingwillbeperformed undertheSt.LucieASMESectionXIprogramcoveringreplacement activities.
Basedontheoriginalrequirements oftheSt.LucieplantTechnical Specifications, whichimplemented therequirements of10CFR50AppendixJforperiodicleakageratetesting,aperiodicIntegrated LeakRateTest(ILRT)wouldhavebeenscheduled duringtheFall,.1997refueling outage(SL1-15).
ThattestwouldhaveservedtosatisfytheTechnical Specification leakagetestsurveillance requirements aswellasserveasatestfortheconstruction hatchreinstallation.
Thistestingwouldalsoinvolveothersteamgenerator replacement activities:
(a)installation ofpadsonthecontainment dome;and(b)closureweldsonthesecondary sidelineswheretheyattachtothenewsteamgenerators.
However,basedonarecentrevisiontoSt.LucieUnit1Technical Specifications thatadopted10CFR50AppendixJ,OptionB,anormalsurveillance ILRTisnolongerrequireduntilMay2003.Accordingly, thisevaluation willdocumentacceptable alternatives toanILRTforsteamgenerator replacement activities inaccordance withtheprovisions of10CFR50AppendixJ,OptionB(Reference 3),theSt.LucieUnit1Technical Specifications (Reference 2),andUpdatedFSAR(Reference 1).2.0FPLevaluated theproposedalternatives fortestingofthecontainment vesselandsecondary.
systempipingasacceptable alternatives toafullILRT,andevaluates compliance withtheprovisions of10CFR50AppendixJ,OptionB,plantTechnical Specifications, andtheUpdatedFSAR.Thistestingapproachwasev'aluated againstthecriteriaof10CFR50.59toensurethatitdoesnotconstitute anunreviewed safetyquestion, orrequirechangestoTechnical Specifications.
LICENSING ANDDESIGNBASISREQUIREMENTS 2.1TECHNICAL SPECIFICATION REQUIREMENTS OnSeptember 12,1995,theNRCapprovedarevisionto10CFRPart50,AppendixJ(Reference 3),whichbecameeffective onOctober26,1995.Thisrevisionto10CFR50,AppendixJ,added"OptionB",whichaddresses performance basedrequirements toallowlicensees tovoluntarily replacetheprescriptive requirements of10CFRPart50,AppendixJ,withtestingrequirements basedonbothpreviousoverallperformance andperformance ofindividual components.
Performance basedtestingintervals arebasedonconsideration oftheoperating historyofacomponent andthepotential riskassociated withitsfailure.OnOctober28,1996,FPLsubmitted aproposedlicenseamendment totheNRC(Reference 4)requesting amodification ofPlantTechnical Specifications toallowimplementation of10CFR50AppendixJ,OptionB.Thepurposeofthisamendment toTechnical Specifications wastoallowTypeA,B,andCcontainment leakageteststobeconducted atintervals determined byperformance basedcriteria.
FPLdeveloped theSt,LucieAdministrative Procedure ADM68.01,"Containment LeakageRateTesting tSt.LucieUnit1DocketNo.50-335L-97-287Attachment Page3Program,"
(Reference 5)whichFPLincorporated byreference intoplantTechnical Specifications.
ThisAdministrative Procedure references theuseofcriteriafromRegulatory Guide1.163(Reference 6),whichspecifies amethodacceptable totheNRCforcomplying with10CFR50AppendixJ,OptionB,andendorsesapplication ofanexception toRegulatory Guide1.163,whichspecifically allowstheuseofeitherBechtelTopicalReportBN-TOP-1orANSI/ANS56.8-1994 (Reference 8)forTypeAleakageratetesting.Regulatory Guide1.163approvedtheintervals established inNEI94-01(Reference 7),whichspecifies anextension inTypeAtestfrequency toatleastonetestin10yearsbasedupontwopreviousconsecutive successful tests.TheSt.LucieUnit1containment operating historyhasdocumented sevensuccessful ILRTswithnoassociated failurestomeetacceptance criteria.
Theuseof10CFR50,AppendixJ,OptionB,including theexception toallowuseofeitherBechtelTopicalReportBN-TOP-1orANSI/ANS56.8-1994 forTypeAleakageratetestingwassubsequently approvedbytheNRCinLicenseAmendment 149totheUnit1Operating License(Reference 2).CurrentSt.LucieUnit1Technical Specifications requireverification thatcontainment structural integrity andcontainment leakageratesareacceptable perTechnical Specifications 4.6.1.6and4.6.1.2,respectively.
Thesespecifications relyoninspections andleakagetestingperformed inaccordance withtheContainment LeakageRateTestingProgramdescribed inT.S.6.8.4(h).
2.2NRCSAFETYEVALUATION (SER)TheoriginalNRCevaluation forcontainment isdocumented inSections3.8.1and6.2.1oftheNRCSER(Reference 9)ofMarch1976.ThatSERevaluated thepeakcontainment transient pressurefortheworstcaseprimarypipebreak,whichwascalculated as38.4psig.TheNRCverifiedthisvaluethroughtheirowncalculation ofpeakcontainment pressure.
TheNRCconcluded thatthemaximumcontainment pressurewascorrectly calculated bytheapplicant andwasbelowthedesigninternalpressureof44psigbyanacceptable margin.2.3UPDATEDFSARDESIGNBASISREQUIREMENTS Section3.8,2.1oftheUnit1UpdatedFSARaddresses thedesign,designleakagecriteria, applicable codes,pressuretesting,andpost-operational testingandinspection requirements forthesteelcontainment vessel.Thecontainment vessel,including allofitspenetrations, isalowleakageshell,whichisdesignedtoconfineradioactive materials thatcouldbe
tSt.LucieUnit1DocketNo.50-335L-97-287Attachment Page4releasedfollowing accidental lossofintegrity ofthereactorcoolantpressureboundary.
Thecontainment vesselisacircularcylinderwithanintegralhemispherical domeandellipsoidal bottomwhichhousesthereactorpressurevessel,thereactorcoolantpipingandpumps,thesteamgenerators, thereactorcoolantpressurizer andpressurizer quenchtank,andotherbranchconnections, including thesafetyinjection tanks.Thecontainment structure incombination withengineered safetyfeaturessystemsensurethattheradiological exposuretothepublic,resulting fromalossofreactorcoolantaccident, willremainbelowtheguidelines established in10CFR100.Toaccomplish this,thecontainment structure isdesignedtowithstand themaximumcalculated peaktransient internalpressureandtemperature resulting fromtheworstcasedesignbasisaccidentscenario.
Thecontainment vesselanditspenetrations aredesignedinaccordance withtheASMECodeSectionIII,Class"B"1968.AslistedinUpdatedFSARTable6.2-1,thecontainment pressureboundaryisdesignedfora"designinternalpressure" (definedinASMECodeArticleNE-3112)of44psigandcoincident temperature of264'F.The"maximuminternalpressure" (ILRTpressure) forthecontainment vesselis39.6psigatacoincident temperature of264'F.Thecalculated loss-of-coolant-accident (LOCA)blowdowntransient analysisdetermined thepeakcontainment pressureandtemperature thatcontainment wouldbeexposedtofollowing adesignbasisaccident.
Thisinternalpressure, referredtoasthe"maximumcalculated peakinternalpressure" inArticleNE-3112,is37.2psigasidentified inUpdatedFSARTable6.2-1.Thecorresponding designtemperature forthemaximumcalculated peaktransient pressureis258.6'F.Thiscontainment peaktransient pressurewassubsequently reanalyzed andcalculated as37.5psigforthesteamgenerator replacement, whichisdiscussed belowwithinSection3.2.ThisvalueremainslessthantheoriginalSERvalueof38.4psigandILRTpressurespecified intheUFSARof39.6pslg.Following completion oftheoriginalcontainment vesselfabrication andpost-weld heattreatment, pneumatic testingwasperformed inaccordance withtheapplicable requirements oftheASMECodeandANS7.60-1971 todemonstrate thestructural integrity andleak-tightness ofthecompleted containment vessel.Following completion ofthecontainment overpressure testingandasecondsoapbubblevisualinspection test,aleakageratetestofthevesselwasperformed.
TheTypeAintegrated leakageratetestwasperformed inaccordance with10CFR50AppendixJ-1973andANSI45.4-1972.
Thestartingtestpressurewas41.3psigtoassureacontinuous testpressureabove39.6psig.Hourlyreadingsweretakenfor48hourstomonitorthedecayofthetestpressure.
Asummarytechnical reportofthistestingwasgenerated whichdocumented theanalysisandinterpretation oftheleakageratetestdatanecessary todemonstrate theacceptability oftheleakageratetestinginmeetingacceptance criteria.
St.LucieUnit1DocketNo.50-335L-97-287Attachment Page5Subsection 3.8.2.1.14 oftheUnit1UpdatedFSARdescribes thepost-operational testingandinspection ofthecontainment vesselandpenetrations asfollows:a.LeakageRateTesting"Periodic leakageratetestsofthecontainment vesselandleaktestsofthetestablepenetrations willbeconducted asdescribed inSection6.2toverifytheircontinued leak-tight integrity."
b.Surveillance ofStructural Integrity "Asteelshellpressurecontainment vessel,designed, fabricated, inspected andpressuretestedinaccordance withtheASMEBoilerandPressureVesselCodeandprotected bytheconcreteshieldbuildingwilloffercontinued structural integrity overthelifeoftheunit...Therefore itiscontemplated thattherewillbenoneedforanyspecialin-service testsurveillance requirement otherthanvisualinspection oftheexposedinteriorandexteriorsurfacesofthecontainment vessel."Section6.2.1.4.2 oftheUnit1UpdatedFSARdescribes theperiodictestingandinspection ofthecontainment vesselwhichstatesthefollowing:
a.Containment Vessel"Periodic
'TypeA,BandC'eakageratetestsareconducted asapplicable inaccordance withAppendixJ,"PrimaryReactorContainment LeakageTestingforWaterCooledPowerReactors,"
10CFR50,andunitTechnical Specifications toverifythecontinued leak-tight integrity ofthecontainment."
UpdatedFSARSection10.1indicates thatthesecondary systempipingwasdesignedinaccordance withtherequirements ofANSI/ANSB31.7ClassII,1969.Postconstruction pressuretestingperformed onsecondary systempipingwasconsistent withtheoperating pressures forthesesystems,whichwouldbesignificantly inexcessofthecontainment testpressurerequiredbyAppendixJ.3.0ANALYSISOFEFFECTSONSAFETY3.1ENGINEERING ANALYSISOFTESTINGREQUIREMENTS Theremovalandreinstallation oftheconstruction hatchclosurecoverwillbeperformed undertheSt.LucieASMESectionXIProgram.ASMESectionXI,IWE-4000, establishes requirements forrepairandreplacement activities forthecontainment "1
.~St.LucieUnit1DocketNo.50-335L-97-287Attachment Page6construction hatchcover.TheseCoderequirements imposeanumberofweldingandnondestructive examination
- criteria, including pressuretestinginaccordance with10CFR50,AppendixJ,asapplicable forthetypeofrepairsinvolved.
ASMESectionXI,Subsection IWE-4000andNEI94-01(per10CFR50AppendixJ,OptionB)requirethatanymodification, component replacement (thatispartoftheprimarycontainment boundary),
ortheresealing ofaseal-welded doorthatwasperformed aftertheplantpre-operational leakageratetestshallbefollowedbyeitheraTypeA,TypeB,orTypeCtest.Theserequirements aredesignedtoensurethatanychanges,including removalandreplacement, areperformed inamannerthatwillnotaffecttheleak-tightness ofthecontainment boundary.
TheoriginalEbascoconstruction specification fortheconstruction hatchrequiredthattheoriginaldesignhavesufficient materialtoallowtheconstruction hatchcovertoberemovedandweldedsixtimesduringthedesignlifeoftheplant.Theoriginalconstruction specification forinstallation oftheconstruction hatch,aswellasthecurrentASMESectionXICode,requiresthatavolumetric examination beperformed forthecompleted weldingoftheconstruction hatchcover.Asmentioned above,theremovalandreinstallation oftheconstruction hatchcoverwillbeperformed inaccordance withASMESectionXI,Subsection IWE,whichimposesrepairorreplacement requirements onthisactivity(Reference 13),including thevolumetric examination ofthecompleted welding.TheASMESectionXICoderequiresapressuretestaftercompletion ofinstallation ofthesystemorcomponent part.TheSt.Lucieplantwillsatisfythepressuretestrequirements, aswellasthoseofAppendixJ,byperforming apneumatic testoftheconstruction hatch-to-cover-weldjointatorabovethecontainment vesselinternaldesignpressureof39.6psig.Thispressuretestfortheconstruction hatchweldingwillbeaccomplished byconstruction ofatestchamberaroundtheweldjointbetweentheconstruction hatchanditscover(Figure4).Thetestchamberwillbepressurized andasoapbubbletestwillbeutilizedtodemonstrate thatzeroleakageoccursintheweldjoint.Thetestpressureof39.6psigmeetsthecriteriafortestinginaccordance with10CFR50AppendixJ,OptionB,underthecriteriaofANSI/ANS56.8.ANSI/ANS56.8specifies someoftheacceptable methodsfortestingandrequiresthatthesetestsbeperformed atatestpressureatleastequaltothetestpressureofatleast39.6psigasspecified intheUFSAR.Containment structural integrity willbeverifiedacceptable bytheperformance ofTechnical Specification 4.6.1.6.Thisspecification reliesoninspections performed inaccordance withtheContainment LeakageRateTestingProgramthatisdescribed inT.S.6.8.4(h).
Asdescribed below,severalNRCandindustrydocuments provideguidanceoncompliance with10CFR50,AppendixJ.
St.LucieUnit1DocketNo.50-335L-97-287Attachment Page7aoAppendixJto10CFR50(Reference 3)specifies testrequirements toensurethat:a)leakagedoesnotexceedallowable ratesspecified inplantTechnical Specifications; andb)integrity ofthecontainment structure ismaintained duringitsServicelife.Twooptionsareprovided, "eitherofwhichcanbechosenformeetingtherequirements ofthisAppendix".
Aspreviously discussed, St.LucieUnit1hasadoptedtherulesspecified inOptionBforperformance basedtesting.OptionBreferences NRCRegulatory Guide1.163(Reference 6)forguidanceonmeetingOptionB.'.Regulatory Guide1.163,"Performance-Based Containment Leak-Test Program,"
(Reference 6)brieflydescribes theregulatory positiononperformance basedtestingandendorsesNuclearEnergyInstitute (NEI)documentNEI-94-01 Revision0,(Reference 7)formethodsacceptable tocomplywiththeprovisions ofOptionB,subjecttofourexceptions:
a)establishment oftestintervals tobebasedonNEI-94-01 andnotthereferenced ANSI/ANS56.81994standard; b)establishment ofTypeCtestingintervals forcertaincomponents mustbelessthan30monthsforpurgevalvesandnogreaterthan60monthsforothercomponents; c)visualexamination requirements ofthecontainment vesselarerequired; andd)certainalternatives toTypeCtestsarenotallowed.Thefirstexception providesthemethodtojustifyatenyearintervalfortheILRT,theremaining threeexceptions donotaffectthisevaluation.
C.NEI-94-01,"Industry Guideline forImplementing Performance-Based Optionof10CFRPart50,AppendixJ,"(Reference 7)wasdeveloped byanNEIWorkingGroupandTaskForceforimplementation ofAppendixJthealternative containment testingrule.Thepurposeofthisdocumentistoassistlicensees intheimplementation ofOptionBtominimizetheredundant andoverlapping engineering andevaluation effortsassociated withregulatory requirements.
Section9ofNEI-94-01 describes themethodology fordetermining TypeA,B,andCintervals.
Establishment ofintervals isdocumented intheContainment LeakageRateTestingProgramandisnotwithinthescopeofthisevaluation.
Asdiscussed inNEI94-01,Section9.2.4,testrequirements for"repairsandmodifications thataffectthecontainment leakageintegrity requireleakageratetesting(TypeAtestingorlocalleakageratetesting)priortoreturning thecontainment tooperation."
Theconstruction hatchcoverwastestedaspartoftheoriginalpostconstruction structural integrity testat49.5psigandinsevensubsequent ILRT's,Thefullpenetration buttweldwillbeexaminedinaccordance withASMESectionXIusingvolumetric examination methods.Basedonthesignificant sizeofthebuttweld(1-1/2")andtherequirednon-destructive examination (NDE),noleakagethroughthisweldedjointisexpectednorwillanyleakagebeacceptable.
Inaccordance withNEI94-01,Section9.2.4,"localleakageratetesting"willbeperformed.
Thelocalleakagetestingwillconsistofinstallation ofaleakchase, St.LucieUnit1DocketNo.50-335L-97-287Attachment Page8pressurizing toatleast39.6psig,andapplication ofasoapbubblesolution(snoop)totestthebuttweldfromtheoppositeside(Figure4).Thismethodoftestingisadvantageous becauseitdefinitively teststhespecificweldinquestionwithanacceptance criterion of"zeroleakage."
d.Generally, asoapbubble(snoop)testisnotconsidered anacceptable methodofquantifying leakage,asdiscussed inReference 10.Thisisbecausethecorrelation ofsoapbubblestoaleakagerateisnotwelldefined.Theexception tothisisiftheleakagecriterion issetto"zeroleakage",
thenthemethodprovidesquantifiable results-noleakageatall(Reference 10).Althoughleakageisacceptable intermsoftheoverallcontainment testingprogram(i.e.,sumofallleakagepaths),thisparticular testwillhaveastrictcriterion of"zeroleakage."
Basedontheabove,theuseofalocalleakchasemeetstherequirements 10CFR50AppendixJ,OptionB.Intermsofcontainment isolation
- features, thesecondary sidesystemconsisting ofmainfeedwater andmainsteampipingarenormallyconsidered partofthepassiveclosedsysteminsidecontainment whichisanextension ofthecontainment structure.
DuringanILRT,thesecondary sidesystemisventedtoatmosphere inordertoprovideapressuredifferential of39.6psigorgreaterfromthecontainment atmosphere totheoutsideatmosphere throughthemainsteampipingsystem.Thesecondary sideofthereplacement steamgenerators havebeenhydrotestedto1.25x1000=1250psiaaspartofthefabricator's program.Oncethepipingtoandfromthesteamgenerators isweldedinplace,theweldswillbeexaminedandapressuretestperformed inaccordance withASMESectionXI.Thistestwillbeatpressures approximately twentytimeshigherthanthatofanILRT.Althoughtheleaktestisinadirection reversetothatofaLOCAenvironment, thetestisacceptable becauseofthehighpressureduringtheleaktest.Section9.2.1ofNEI94-01andSection6.2ofANSI/ANS56.8allowlicensees toutilizereversetestingifjustified.
Fortheseweldedconnections, noleakagewillbeacceptable.
Thisisconsistent withinterpretations madebyotherplants.Accordingly, asdiscussed inReference 11,thistestingisconsidered acceptable tomeet10CFR50AppendixJ.Forpadsweldedtothecontainment vessel,testrequirements subsequent torepairsandmodifications areaddressed inNEI94-01,Section9.2.4.Forweldsofattachments tothesurfaceofsteelpressure-retaining
- boundary, TypeA(ILRT)testingmaybedeferredtothenextscheduled ILRT.Accordingly, theinstallation ofpadstothecontainment withoutperformance ofanILRTthisoutagemeetstherequirements ofAppendixJtesting.
4 PSt.LucieUnit1DocketNo.50-335L-97-287Attachment Page93.2STEAMGENERATOR REPLACEMENT EVALUATION Theevaluation oftheSteamGenerator Replacement Project(SGRP)activities isaddressed intheSGRPStandAloneSafetyEvaluation.
Thisreportcontainsthetwoseparate50.59evaluations forSGRPactivities.
FPL'sEvaluation (Reference 14)containsanevaluation ofconstruction activities andplantchangesasaresultoftheimplementation effort,ThesecondFPLevaluation (Reference 15)containsanevaluation ofthereplacement steamgenerator.
Thesetwoevaluations donotaddressthespecifictypeoftestingthatwouldberequiredtosatisfyAppendixJrequirements.
Theuseofalocalleakratetestforthecontainment construction hatchasdiscussed withinthisevaluation willnotaffecttheconclusions previously reachedinthetwoSGRPevaluations identified above.Acontainment transient responseevaluation fortheworstcaseLOCAwasperformed aspartoftheevaluations performed fortheSGRP.Thereplacement steamgenerators containslightly.
moreprimarysidemassthantheoriginalsteamgenerators.
Thisresultsinaslightincreaseinthepeakcontainment pressurefollowing theworstcaseLOCA.Calculations performed withanincreased primarysidemassandenergycorresponding tothereplacement steamgenerators showthattheblowdownresultsinapeakcontainment pressureof37.5psig.Thisisanincreaseof0.3psigoverthecurrentcontainment analysisofrecord(37.2psig)showninUpdatedFSARTable6.2-1.TheSGRPpeakcontainment transient pressureof37.5psigislessthanthepeakpressureof38.4psigoriginally acceptedbytheNRCintheoriginalplantSER(Reference 9)andremainsbelowtheoriginally specified ILRTtestpressureofatleast39.6psig.Therefore, theproposeduseofalocalleakratetestpressureof39.6psigwillstillboundthenewcontainment peaktransient pressurecalculated fortheSteamGenerator Replacement Project,4.0EFFECTONTECHNICAL SPECIFICATIONS Theconstruction hatchcoverwastestedaspartoftheoriginalpostconstruction structural integrity testat1.25X39.6=49.5psigandinsevensubsequent ILRTs.Thefullpenetration buttweldwillbeexaminedinaccordance withASMESectionXIusingvolumetric examination methods.Althoughsomeleakagewouldbeacceptable intermsoftheoverallcontainment testingprogram(thatis,thesumofallleakagepaths),thecontainment leakagetestproposedforthereinstallation oftheconstruction hatchwillhaveastrictcriterion ofzeroleakageinordertosatisfytherepairandreplacement requirements.
Basedontheabove,theuseofalocalleakchasemeetstherequirements ofAppendixJtesting.Consequently, thedesignmarginsidentified forcontainment intheSt.LucieContainment LeakageRateTestingProgram,referenced inplantTechnical Specifications (Reference 2),willberestoredaftertheweldrepairsarecompleted ontheconstruction hatchcoverandsecondary systempipingwithincontainment.
Theproposedtestingactivities willhavenoeffectsonplantTechnical Specifications, andthetestingprogramusingthepressure tSt.LucieUnit1DocketNo.50-335L-97-287Attachment Page10of39.6psigforthecontainment vesselwillnotrequireanychangestoTechnical Specifications inordertoimplement thetestingapproachoutlinedinthisevaluation.
5.0CONCLUSION
S Thisevaluation servestodocumentthetestingrequirements from10CFR50,AppendixJ,whichareapplicable totheUnit1steelcontainment pressurevesselfollowing thereplacement ofthetwosteamgenerators scheduled fortheFall1997refueling/steam generator replacement outage(SL1-15).
ThetestingapproachfortheUnit1containment thatisdiscussed abovehasbeenevaluated againstthefacilitychangecriteriaestablished by10CFR50;59toensurecompliance withNRCregulatory criteria.
Thisevaluation concludes thattheproposedmethodology fortestingthecontainment vesselandsecondary systempipingisanacceptable alternatives toafullILRTandcomplieswiththeprovisions of10CFR50,AppendixJ,plantTechnical Specifications, andtheUpdatedFSAR.Thetestingapproachasevaluated againstthecriteriaof10CFR50.59determined thattheproposedtestingapproachdoesnotinvolveanunreviewed safetyquestion, orrequirechangestoTechnical Specifications.
Therefore, thistestingapproachcanbeimplemented withoutpriorNRCapprovalpursuanttotherequirements of10CFR50.59.
6.0REFERENCES
StLucieUnit1UpdatedFSAR,Section3.8.2,"Containment Structure,"
andSection6.2.1,"Containment Functional Design."2.StLucieUnit1Technical Specifications 3.6.1.1,3.6.1.2,3.6.1.3,3.6.1.6,3.6.6.3,and6.8.4,Amendment No.149,transmitted byNRCletterdatedFebruary10,1997.3.Title10CodeofFederalRegulations (CFR)Part50,AppendixJ,"PrimaryReactorContainment LeakageTestingforWater-Cooled PowerReactors,"
Effective DateOctober26,1995.4.FPLletterL-96-244, "St.LucieUnit1,ProposedLicenseAmendment
-Implementation of10CFR50AppendixJ,OptionB,"datedOctober28,1996.5.St.LuciePlantAdministrative Procedure ADM68.01,"Containment LeakageRateTestingProgram,"
Revision0.6.NRCRegulatory Guide1.163,"Performance BasedContainment Leak-Test Program,"
datedSeptember 1995.7.NuclearEnergyInstitute Guideline NEI94-01,"Industry Guideline ForImplementing Performance-Based OptionOf10CFRPart50,AppendixJ,"Revision0,datedJuly26,1995.
St.LucieUnit1DocketNo.50-335L-97-287Attachment Page118.ANSI/ANS-56.8-1994, "American NationalStandardForContainment SystemLeakageTestingRequirements."
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St.LucieUnit1DocketNo.50-335L-97-287Attachment Page12SHIELDBUILDNOCCHTANMEHT VESSELddCONST.HATCHQELEV.7SWdddd0000dqdq00d0d00dqdq0d0CROSSSECTIONOFCONTAINMENT VESSELAND'SHIELD BUILDINGFigure1 St.LucieUnit1DocketNo.50-335L-97-287Attachment Page13MAINTENANCE HATCHEOUIPMENT HATCH//ESCAPEAIRLOCK/r///I//PERSONNELAIR LOCKPLANVIEWOFUNIT1CONTAINMENT ANDMAJORPENETRATIONS Figure2
St.LucieUnit1DocketNo.50-335L-97-287Attachment Page1411/2'UTSIDE CONTAINMENT INSIDECONTAINMENT FIGLRE4ELUPSOlOALHEAD~LXV.ra'sr~7I15"51I4'ONSTRUCTION HATCHTHROUGHCONTAINMENT VESSELFigure3
St.LucieUnit1DocketNo.50-335L-97-287Attachment Page15LOCALLEAKCHASE{COHCEPTUAI SABDETAILSBESIODEVELOPED)
LEAKCHASEDETAILFigure4