ML18026A218

Susquehanna Units 1 and 2 - SSES Design Assessment Report, Revision 1

ML18026A218
Person / Time
Site:	Susquehanna
Issue date:	04/14/1978
From:	Pennsylvania Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML18026A218 (21)

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SUSQUEHANNASTEAMELECTRICSTATIONDESIGNASSESSMENTREPORT(DAR)""-'";",:So-+6'tio'goIggV-lq.pS.=.Revision1

,~>'h)~h PREPACEThisReportcontainsdata,descriptionsandanaylsisrelativetotheadequacyoftheSusquehannaSteamElectricStationdesigntoaccommodateloadsresultinqfromsafetyreliefvalve(SRV)discharqeand/orloss-of-coolantaccident(LOCA)conditions.Rev.2,5/8p

DARTABLEOFCONTENTSChapter1GENERAL.INFORMATION1.1PurposeofReport1.2HistoryofProblem1.3SSESContainmentProgram1.4PlantDescription1.5Figures16TablesChapter2SUMMARY2.1LoadDefinitionSummary2.2DesignAssessmentSummaryIChapter3SRVDISCHARGEANDLOCATRANSIENTDESCRIPTION3.1DescriptionofSafetyReliefValve(SRV)Discharge3.2DescriptionofLoss-of-CoolantAccident(LOCA)Chapter4LOADDEFINITION4.1LoadsfromSafetyReliefValveDischarge4.2LoadsfromLoss-of-CoolantAccident4.3AnnulusPressurization4.4Figures4.5TablesChapter5LOADCOMBINATIONSFORSTRUCTURES~PIPING~A'NDEQUIPMENT5.1ConcreteContainmentandReactorBuildingLoadCombinations5.2StructuralSteelLoadCombinations5.3LinerPlateLoadCombinations5.4DowncomerLoadCombinations5.5Piping,Quencher,andQuencherSupportLoadCombinations5.6NSSSLoadCombinations5.7EquipmentLoadCombinations5.8ElectricalRacewaySystemLoadCombinations5.9HVACDuctSystemLoadCombinations5.10Figures5.11TablesChapter6DESIGNCAPABILITYASSESSMENT6.1ConcreteContainmentandReactorBuildingCapabilityAssessmentCriteria6.2StructuralSteelCapabilityAssessmentCriteria6.3LinerPlateCapabilityAssessmentCriteria'ev.2,5/80

TABLEOFCONTENTSfContinued)-6.4DowncomerCapabilityAssessmentCriteria6.5Piping,Quencher,andQuencherSupportCapabilityAssessmentCriteria6.6NSSSCapabilityAssessmentCriteria67EquipmentCapabilityAssessmentCriteriaChapter7DESIGNASSESSMENT7.1AssessmentMethodology7.2DesignCapabilityMargins7.3FiquresChapter8SSE~S-U~ECHERVERIFICATIONTEST8.1Introduction82TestFacilityandInstrumentation8.3TestParametersandMatrix8.4TestResults8.5DataAnalysis'andVerificationofLoadSpecification8.6Figures8.7TablesChapter9GKMIIMSTEAMBLOWDOWNTESTS9.1Introduction9.2TestFacilityandMatrix9.3TestParametersandMatrix9.4TestResults9.5DataAnalysis9.6VerificationoftheDesignSpecification9.7FiguresChapter10RESPONSESTONRC~UESTIONS10110210.310.4IdentificationofQuestionsUniquetoSSESQuestionsUniquetoSSESandResponsesTheretoQuestionsPertainingtotheNRC~sRevievoftheDARandResponseTheretoFiguresChapte'r11REFERENCESAppendixACONTAINMENTDESIGNASSESSMENTA.1ContainmentStructuralDesignAssessmentA.2SubmergedStructuresDesignAssessmentAppendixBCONTAINMENTRESPONSESPECTRADUETOSRVANDLOCALOADS'.1ContainmentModeShapesB.2ContainmentResponseSpectraAppendixCREACTORBUILDINGRESPONSESPECTRADUETOSRVANDXOCALOADSRev.2,5/80

AppendixDpRgGRggVgRIFICQTIQND.1PoolsvellModelVerificationD.2VelpotProqramVerificationD.3FiquresD.4TablesAppendixF.REACTOQBUILDINGSTRUCTURALDESIGNASSL'SSMEPTAppendixFBOP-ANDNSSSGRIPINGDESIGNASSESSMFNTAppendixGVASSSQESIGNASSESSMENTQDELETFOQAppendixHEQUIPMENTDESIGNASSESSMENT/DELETED}AppendixISUPPRESSIONPOOLTFMPERATJJRERFSPONSETOSRVDISCHARGE-AppendixJVFRIFICATIONOFSRVSUBMERGEDSTRUCTUREDRAGLOAD(PRO'PRIETARY)AppendixKDBYMELLFLOORVACCUMBREAKERJVB}CYCLINGDURINGCHUGGINGAppendixL.SUppLEMEQTALDESIGN.ASSFSSMENTL.1AssessmentMethodoloqyL.2AssessmentResultsJ..3FiquresL.4TablesRev.8,2/83 ICHAPTER"'1GENERALINFORMATTIONTABLEOPCONTENTS1.11.2PURPOSEOFREPORTHISTORYOFPROBLEM1-3SSESCONTAINMENTPROGRAM'4PLANTDESCRIPTION1.41Primary'ontainment'.1.41.1Penetrations1.4.1.2InternalStructures",'~',,'"lI'5"FZGURES1.6TABLESI,wIIIIII>>Rev.2,.5/801-1 CHAPTER1FIGURESNumberTitle1-11-3CrossSectionofContainmentSuppressionChamber,PartialPlanSuppressionChamber,SectionVie@1-0QuencherDistributionRev.2,5/801-2

~O'XTACHAPTER1TABLES~umber1-3TitleSSESLicensingBasisSSESContainmentDimensionsSSESContainmentDesignParametersComparisonoftheSSESProgramforSRVandLOCA,loadingswiththeNUREG0487AcceptanceCriteria,LeadPlantProgramandGenericLongTermProgramRev.2,5/801-3 10GNRRALINFORMATION1.1PU'RPOSEANDORGANIZATIONOFREPORTThepurposeofthisreportistopresentevidencethattheSusquehannaSteamElectricStation(SSES)designmarginsareadequateshouldtheplantbesubjectedtotherecentlydefinedthermohydrodynamicloadswhichresultfromsafetyreliefvalve(SRV)operationsand/ordischargesduringaloss-of-coolantaccident(LOCA)inaGEhoilinqwaterreactor(BWR).Rev;2,5/801-4 12HISTORy'FPROBLEMInApril1972attheGermanAEG-KraftwerkUnionMurgassenNuclearPlant,aboilingwater,reactor(BMR)safetyreliefvalve(SRV)wasopenedduringstartuptestingandfailedtoclose.Thereactorremainedatfullpressure,'andthevalvedischargedreactorsteamintothecontainmentsuppressionchamberuntilthesuppressionpoolwaterheatedfromgustaboveambienttoalmost170~C{inapproximately30minutes).Pulsatingcondensationdevelopedandlargeimpulsiveforceswithsubstantialunderpressureamplitudesacteduponthecontainment,eventuallycausinqleakaqefromthebottomlinerplate.Therefore,concern'asexpressedthatthestructuralintegrityofotherBMRpressurecontainmentsystemscouldbesensitivetoSRVinduceddynamicloads.TheNuclearRegulatoryCommission(NRC)issuedBulletin74-14toallBWRownersonNovember14,1974toalertthemtothepotentialproblemsofcondensationinstability(Murgasseneffect)'uetoSRVoperationTheNRCrequestedverificationthatBMRsuppressionpoolshadbeendesignedtowithstandloadssimilartothosewhichwerebeingexperienced.InJanuary1975theGeneralElectric-NuclearEnergyProgramDivision(GE-NEPD)identifiedthefollcwingdynamicloadingconditionswhichhadnotbeenfullyconsideredinthedesigncriteriaofMarkIIBMRcontainments:a.HainsteamSRVdischargethermo-hydrodynamicphenomena.b.Desiqnbasisaccident(DBA):loss-of-coolantaccident(LOCA)hydrodynamicphenomenaFollowingtheGEannouncement,thecontainmentconstructionsequencefortheSSESwasalteredtoenablethePennsylvaniaPowerandLightCompany(PPSL)anditsarchitect-engineer,BechtelPowerCorporation,toascertaintheeffectofthesephenomenaontheexistingSSESdesign.AtaskforcewasformedinNarch1975withrepresentativesfromBechtel-SanFrancisco,GE-NEPD,PPGL,andPhiladelphiaElectricCompanytoevaluateexistinqdesigncriteriawithrespecttothenewlydefinedSRVandDBA-LOCAloadinqs.InNay1975BechtelcompletedapreliminarystudyincorporatinqtheeffectsofthenewphenomenainthedesigncriteriafortheSSESsuppressionchamberstructuresandsafetyrelatedequipmentAsaresultofthisinvestigation,itwasdecidedthatthefollowingcivil-structuralmodificationsweretobeincorporatedimmediatelyinthecontainmentdesigntoaidinloadtransferandaddadditionalconservatismtotheexistingdesign:a.Thenumberofreinforcingbarsinthesuppressionchamberverticalwallswasincreased.b.Thenumberofembedmentsinthesuppressionchamberwallsfordowncomer/pipingrestraintswasincreasedtoaccommodatefuturerequirements.1-5 cAnchor.boltswereplacedontheundersideofthediaphragmslabtoaccommodateadditionalsupportsfoz'heSRVdischargepipingforhorizontalrunsshouldtheybeneeded.d.e.Additionalanchorboltswereplacedwithinthedrywellwalltoallowinstallationofadditionalsnubbersandpiperestraints,ifrequiredThediaphragmslabshearreinforcementwaschangedfroma45~toa90~orientation{withrespecttothehorizontalplane)toaccommodatethemostconservativepoolswellupliftloadingsyetpredicted.Itbecameevidentthatacomplex,technicalissueexistedforallNarkIIplants,andPPGl.soughttocreateaunifiedutilitygrouptoaddressthematter.AMarkIIBMRcontainmentownersgroupwasformedinJune1975todefinepreciselythesuppressionpooldynamicloadsandexplorewaystoassesstheirimpact,.AsthedirectresultofactiontakenbytheMarkIIcontainmentownersorganization,agenericDynamicForcinqFunctionInformationReport,NEDE-21061PRev.1,whichwasalsoknownastheDFFIR,wasissuedjointlybyGE-NEPDandSargentandLundyfortheMarkIIownersinSeptember1975BasedontheanalyticaltechniquesincludedintheDFFIR,apreliminarySSESuniquecontainmentdesignassessmentwassubmittedbyPPGI.totheNuclearRegulatoryCommission{NRC)onNarch15,1976Asthebodyoftheusefulsupportivedataincreased,Revision2oftheDFFZHwasissuedjointlybyGE-NEPDandSargentandt.undyfortheMarkIIcontainmentownersgrouponSeptember1,1976,asNEDO/NEDE21061,Rev.2.Itwasatthistimerenamed.theDFFR.ThelicensingdocumentationconsideredfortheSSESissummarizedinTable1-1.1-6 1'SSES-CONTAINMENTPROGRAM.PPGLisamemberoftheHarkIIowners-groupthatvasformedinJune,1975todefineandinvestigatethedynamicloadsduetoSRVdischargeandLOCA.TheMarkIIovnersgroupcontainmentprogramconcentratedinitiallyonthetasksrequiredfo'rthelicensingoftheleadplants(Zimmer,LaSalle,andShoreham).Thisphaseofvork,calledtheshort'ermproqram,iscompleteandalongertermprogramisunderway.ThefinalgoaloftheHarkIIprogramistoevolveacompleteDFFRwhichvillsupporttheplant-uniqueDARssubmittedbye'achplantforitslicensetooperate.Aftergainingsomeunderstandingofthecontainment.loadsthroughtheinitialMarkIXwork,PPGLdecidedtofindaqualified,consultanttosupplementin-housetechnicalresourcesandassistinthedeterminationofarealisticcourseofactionforSusquehannaInNovember,1976,StanfordResearchInstitute,nowcalledSRIInternational(SRI),wasselected,andaninformationexchangebetweenSRZ.andPPGLensuedtodeterminewhatcausedthegreatestloadsonthecontainmentstructure.AfterconductingacompletereviewofknowndatafromtheMarkIIprogramandotherknowledgeablepersonsandorganizations,PPGLandSRIdecidedthattheloadsfrommainsteamsafetyreliefvalve(SRV)d'ischargeverethekeyloadstobecontrolled.AstudyofpossiblemethodsofcontrollingtheloadandareviewofvhatactivitiesvereoccurrinqinEuropeledPPGLandSRItotheconclusionthatanSRVdischargemitigatingdevice(quencher)shouldbeemployedtoreduce.thisloadinqontheSusquehannacontainment.AlthoughtheHarkIIownersgrouphadquencher-relatedtasksintheirprogram,thesetasksverenotsufficientlytimelytosatisfySSES-constructionscheduleneeds.PromreviewingthevorkdoneinEuropebysuchfirmsasASEATOMMARVIKEN,andKraftverkUnion,PPGLdiscoveredthatallknownquencher'designswerebasedondatafromKraftverkUnion(KWU).Thus,inMarch,1977,SRI,Bechtel(theSSESArchitect/Engineer)andPPGLvisitedKWUfordiscussionandtourofquencher-relatedfacilities.XnlateJuly,1977,PPGLemployedtheservicesofKWUtodesignaSSES-uniquequencherdevice.KraftworkUnionprovidedPPGLapackageofsignificantdesignandtestreportspertainingtothequencherdevelopmenttodemonstratedesignadequacyandqualityoftheirdevice(refertoTablel-l).ThesedocumentsweresubmittedtotheNRCinJanuary,1978.ThequencherloadspecificationvassubmittedtotheNRCinApril,1978.ToverifyKWU~sdesignapproach,afull-scaleSSESuniqueunitcelltest,asdescribedinChapter8,wasperformedbyKWUforPPGL.ThedocumentationofthistestseriesandverificationofthedesignspecificationvassubmittedinMarch,1979.SubsequentlythequencherdesignbyKWUforuseonSSEShasbeenadoptedastheSRVdischargeusedbysixofthesevenotherHarkIIownersandtheSSESprogramhasbecomethegenericMarkIIprogram.Rev.2,5/801-7 ThedefinitionofLOCAloads(Section4.2)isinbasicaccordancewiththeMarkIIprogram.Inadditionthough,'PSLhasdecidedtoconductaseriesoftransientsteamblowdowntestsinamodifiedGKMIItesttankinNannheim,Germany(refertoChapter9).ThesetestswillprovidedatatoresolveNRCconcernsonthedifferencesinventconfigurationbetweentheoriginalGE4TfacilityandaprototypicalMarkIIcontainmentand,toverifythecondensationoscillationloadspecificationusedontheSSESdesign.Tablel-lprovidesasummaryofthedocumentationsupportingtheSSESlicensing.Inaddition,Table1-4providesacomparisonoftheSSESprogramforSRV.andLOCAloadingwiththeNUREG0487acceptancecriteria,LeadPlantProgramandGenericLongTermProgram.I'naccordancewiththedirectionsoftheNRCstaffattheOctober19,1978meetingwiththeMarkIIOwnersGroupthesepositionsassumethattheuseoftheSRSSmethodofloadcombinationwillbeacceptedforuseontheMarkIIcontainments.Rev.2,5/800-8 1.4-Pl.M1TDESCRIPTIONTheSSES,Units1and2,isbeingbuiltinSalemTownship,LuzerneCountyabout5milesnortheastoftheBoroughofBerwick.Twogeneratingunitsofapproximately1,100megawattseacharescheduledforoperation:Unit1forNovember1,1980,andUnit2forMay1,1982.GeneralElectricissupplyingthenuclearsteamsupplysystems;BechtelPowerCorporationisthearchitect-engineerandconstructor.ThereactorbuildingcontainsthemajornuclearsystemsandequipmentThenuclearreactorsforUnits1and2areboilingwater,directcycletypeswitharatedheatoutputof11.2x10~Btu/hr.Eachreactorsupplies13.4x10~lb/hrofsteamtothetandemcompound,doubleflowturbines.1.4.1PrimarvContainmentThecontainmentisareinforcedconcretestructureconsistingofacylindricalsuppressionchamberbeneathatruncatedconicaldrywell.Figure1-1showsthegeometryofthecontainmentandinternalstructures.Theconicalportionoftheprimarycontainment(drywell)enclosesthereactorvessel,reactorcoolantrecirculationloops,andassociatedcomponentsofthereactorcoolantsystem.Thedrywelli.sseparatedfromthewetwell,ie,thepressuresuppressionchamberandpool,bythedrywellfloor,alsonamedthediaphragmslab.Majorsystemsandcomponentsinthecontainmentincludetheventpipesystem(downcomers)connectingthedrywellandwetwell,isolationvalves,vacuumreliefsystem,containmentcoolingsystems,andotherserviceequipment.Theconeandcylinderformastructurallyintegratedreinforcedconcretevessel,linedwithsteelplateandclosedatthetopofthedrywellwithasteeldomedhead.Thecarbonsteellinerplateisanchoredtotheconcretebystructuralsteelmembersembeddedintheconcreteandweldedtotheplate.Theentirecontainmentisstructurallyseparatedfromthesurroundingreactorbuildingexceptatthebasefoundationslab(areinforcedconcretemat,toplinedwithacarbonsteellinerplate)whereacoldjointbetweenthetwoadjoiningfoundationslabsisprovided.ThecontainmentstructuredimensionsandparametersarelistedinTables1-2and1-3.AdetailedplantdescriptioncanbefoundintheSSESFSAR,Section3.8.1.4.11'PenetrationsServicesandcommunicationbetweentheinsideandoutsideofthe.containmentaremadepossiblebypenetrationsthroughthecontainmentwall.Thebasictypesofpenetrationsarethedrywellhead,accesshatches(eguipmenthatches,personnellock,suppressionchamberaccesshatches,CRDremovalhatch),electricalpenetrations,andpipepenetrations.ThepipingRev.2,5/801-9 penetrationsconsistbasicallyofapipewithplateflangeweldedtoit.Theplateflangeisembeddedintheconcretewallandprovidesananchorageforthepenetrationtoresistnormaloperatinqandaccidentpipereactionloads.1.4.1.2InternalStructuresTheinternalstructuresconsistofreinforcedconcreteandstructuralsteelandhavethemajorfunctionsofsupportingandshieldingthereactorvessel,supportingthepipingandequipment,andformingthepressuresuppressionboundary.Thesestructuresincludethedrywellfloor(diaphragmslab),thereactorpedestal(aconcentriccylindricalreinforcedconcreteshellrestingonthecontainmentbasefoundationslabandsupportingthereactorvessel),thereactorshieldwall,thesuppressionchambercolumns(hollowsteelpipecolumnssupportingthediaphragmslab),thedrywellplatforms,theseismictrusses,thequenchersupports,andthereactorsteamsupplysystemsupports.SeeFigures1-1thr'ough1-4andTables1-2and1-3.Rev.2,5/801-10 ILOFPRIMARYCONTAINMENTISYM.ABT.(LMORYWELLHEAD48'OV"0D.CONC.I36'PSI"(OUTSIDEFACEIWP.W.PEL.791'.9"J.'Lr5'"9/:,'/.../;/SHIELDIANNULUS/::-/r2/4DOWNCOMER/'JETDEFLECTORSHIELDi29'.I"O.D.18'JI"I.O.'IX~~EL.723'4(X"I2(P-3"I.D.CONC.:86'3"I.D.CONCT.O.C.rEL,703'l",'I'~~~C.~rT.O.S.EL.778'.9"JIlr7REACTORSHIELDII25"7"I.D.hIII4~)"Jh~~'Ij',~4htTOC~'EL.729'.95/8"DIAPHRAGMSLABW.P87'.O.C.L.704'-0"lhEI'DRYWELLEL.701'-11"OOWNCOMER(87TOTALIQUENCHERDEVICE(16TOTALICONTAINMENTWALLWATEASTOPSBASEMATWATEASTOPI~Ij~tII'.~~rhCI1S0sSIII.D.CONCI12FT.'1'.6"'.,O'QII"'r~IQDECKANDSUPPORTBEAMIRP.V.PEDESTALIR.P.V.PEDESTALSTEELFOAMI19'.7"'Ar12,3'6"DIAM.STEELCOLUMNST,rhhig'~'~'1:~,III~I~I'".~I24FT.HIGHWATERLEVEL3'.6"~IhSUPPRESSIONCHAMBER7'41"COLDJOINT629'9".30'41"RO.O.CONC.I.D.CONC.MUDMATANDWATERPROOFING44'JY'.BOTTOMOFBASEMATEL.640'G"REACTORBUILDINGBASEMATCOLDJOINTSUSQUEHANNASTEAMELECTRICSTATIONtJNITS1AND2DESIGNASSESSMENTREPORTCROSSSECTIONOFCONTAINMENTFIGURE1-1 1064IgOi~4~Q'ICONTAINMENTVV~EgrOdy~r~e~013soSRVDIAPHRAGMSLABPENETRATIONFROMDIAPHRAGMSLABPENETRATIONOeC/03COLUMNOg30o>~~f0oo150oo>~o~'Ply+er~w~orOs..O~'EDESTALTOQUENCHERSSRVDIAPHRAGMSLABPENETRATIONNOTE:BRACINGISNOTSHOWNRev.2,5/80SUSQUEHANNASTEAMELECTRICSTATIONUNITS1AND2DESIGNASSESSMENTREPORTSUPPRESSIONCHAMBER"PARTIALPLANFIGURE1-2