ML18041A034

Forwards NMP Unit 2 Safety Evaluation Summary Rept (Filed in Category P) & Rev 8 to Updated SAR for NMP Unit 2 (Filed in Category K)

ML18041A034
Person / Time
Site:	Nine Mile Point
Issue date:	11/29/1995
From:	ABBOTT R B NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059B010	List: ML17059B009 ML18041A034
References
NMP2L-1596, NUDOCS 9512060037
Download: ML18041A034 (1805)

Text

PRIORITY1<ACCI'.I.ERATEDRIBSPROCI:.SS!HAGIREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9512060037DOC.DATE:95/11/29NOTARIZED:YESDOCKETgFACIL:50-410NineMilePointNuclearStation,Unit2,NiagaraMoha05000410AUTH.NAMEAUTHORAFFILIATIONABBOTT,R.B.NiagaraMohawkPowerCorp.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)

SUBJECT:

Forwards"NMPUnit2SafetyEvaluationSummaryRept"&rev8to"UpdatedSARforNMPUnzt2."DISTRIBUTIONCODE:A053DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:UpdatedFSAR(50.71)andAmendmenNOTESP0RECIPIENTIDCODE/NAMEPD1-1PDINTERNAL:ALECENTER1EXTERNAL:IHSNRCPDRCOPIESLTTRENCL1022221111RECIPIENTIDCODE/NAMEEDISON,GAEOD/DOA/IRBRGN1NOACSAICATEFI,BCOPIESLTTRENCL1111111111DUME'YOTETOALL"RlDS"RECIPIENTS:PLEASEHELPUSTOREDUCEO'ASTE!COYTA(T'I'IIEDOCL'IIE."iTCO4TROLDESK,ROONIPl-37(EXT.504.20S3ITOELIXII%ATEYOI:RRAMIEPROIIDISTRI!IL'TIOY,LIS'I'SI:ORDOCUNIEN'ISYO!.'ON"I'EI:.I3!TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11

,I RICHARDB.ABBOTTVIaePresidentNudearGeneraIIon.,VNIA(SARA'MOHAWKNIAGARAMOHAWKPOWERCORPORATIONJNINEMILEPOINTNUCLEARSTATION,P.O.BOX63,LYCOMING,N.Y.13093/TEL(315)349-1812FAX(315)34&4417November29,1995NMP2L1596U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,DC2055510C.F.R.$50.71(e)10C.F.R.$50.59(b)RE:NineMilePointUnit2DocketNo.50-410NPF-Gentlemen:

Subject:

SUBMITTALOFREVISIONSTOTHENINEMILEPOINTNUCLEARSTATIONUNIT2UPDATEDSAFETYANALYSISREPORTANDTHEANNUAL10C.F.R.550.59SAFETYEVALUATIONSUMMARYREPORTPursuanttotherequirementsof10C.F.R.$50.71(e)and10C.F.R.$50.59(b),NiagaraMohawkPowerCorporationherebysubmitsRevision8totheNineMilePointNuclearStationUnit2UpdatedSafetyAnalysisReport(USAR)andtheannualSafetyEvaluationSummaryReport.One(1)signedoriginalandten(10)copiesoftheUSAR,Revision8,areenclosed.CopiesarealsobeingsentdirectlytotheRegionalAdministrator,RegionI,andtheNRCResidentInspectoratNineMilePoint.TheUSARrevisioncontainschangesmadesincethesubmittalofRevision7inOctober1994.Inaddition,numerousUSARsectionshavebeeneditedtoeliminateblankandpartialpages.TheeliminationofblankandpartialpagesiseditorialinnatureanddoesnotupdateorchangesubstantiveinformationpreviouslydescribedintheUSAR,ChangestotheNiagaraMohawkQualityAssuranceTopicalReport(NMPC-QATR-1)thatwerepreviouslysubmittedwithUnit1UFSAR(Updated)Revision13,datedJune1995,havebeenincorporatedinUnit2USARAppendixB.Thecertificationrequiredby10C.F.R.$50.71(e)(2)isattached.TheenclosedannualSafetyEvaluationSummaryReportcontainsabriefdescriptionofchanges,tests,andexperiments,andincludesasummaryofthesafetyevaluationofeach.Noneofthesafetyevaluationsinvolvedanunreviewedsafetyquestionasdefinedin10C.F.R.$50.59(a)(2).Verytrulyyours,I"~L"..I,'4,f'.~95120b0037951129PDRADOCK05000410~K.PDRRichardB.AbbottVicePresident-NuclearGenerationg5i'd

Page'2RBA/JJL/kapEnclosurespc:Mr.T.T.Martin,RegionalAdministrator,RegionIMr.L.B.Marsh,Director,ProjectDirectorateI-l,NRRMr.G.E.Edison,SeniorProjectManager,NRRMr.B.S.Norris,SeniorResidentInspectorRecordsManagement

UNITEDSTATESNUCI.EARREGULATORYCOMMISSIONIntheMatterofNiagaraMohawkPowerCorporation(NineMilePointNuclearStationVnit2)DocketNo.50-410ERTIFIATINRichardB.Abbott,beingdulysworn,statesthatheisVicePresident-NuclearGenerationofNiagaraMohawkPowerCorporation;thatheisauthorizedonthepartofsaidCompanytosignandfilewiththeNuclearRegulatoryCommissionthiscertification;andthat,inaccordancewith10C.F.R.$50.71(e)(2),theinformationcontainedintheattachedletterandupdatedFinalSafetyAnalysisReportaccuratelypresentschangesmadesincetheprevioussubmittalnecessarytoreflectinformationandanalysessubmittedtotheCommissionorpreparedpursuanttoCommissionrequirementandcontainsanidentificationofchangesmadeundertheprovisionsof$50.59,butnotpreviouslysubmittedtotheCommission.By:RichardB,AbbottVicePresident-NuclearGenerationSubscribedandsworntobeforemethisA~dayof,1995.NoPublicBEVERLYW.RIPKANotaryPublicStateotNewYorkQual.tnOswegoCrxNo.46t48MyCommissionEx~z

EnclosuretoNMP2L1596'INEMILEPOINT-UNIT2SAFETYEVALUATIONSUMMARYREPORT1995DocketNo.5OKIOLicenseNo.NPF-69

SafetyEvaluationSummaryReportPage1of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitieofChange:87-046Mod.PN2Y87MX063Figure10.1-5bCondensate(CND)AnAdditionofCycloneSeparatortoCondensateBoosterPumpSealWaterInjectionLinesDescriptionofChange:Thismodificationinstalledtwonewcycloneseparatorsonthesealinjectionwaterlinesofeachofthecondensateboosterpumps.Also,anewflowrestrictionorificewasinstalledupstreamofeachcycloneseparatorandassociatedvalves.SafetyEvaluationSummary:ThismodificationisinaccordancewithANSIB31.1-1973.ThisnewequipmentinterfacesonlywiththeCNDsystemandhasnoimpacttoanyothersystems.Thismodificationwillensurecondensateboosterpumpreliabilityandpreventcostlypumpdowntimeformaintenanceonmechanicalseals.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage2of131SafetyEvaluationNo.:implementationDocumentNo.:USARAffectedPages:89-075Rev.75,8Mod.PN2Y87MX038Figures9.5-8Sh1L2,9.5-10Sh1,9.5-24,9.5-29System:TitleofChange:DescriptionofChange:Communications(COJ,COP,COS)AdditionofCommunicationEquipmentModificationstotheGaitronicscommunicationssystemwerepreviouslyreportedwithUSARrevisionsdatedOctober30,1991,October29,1992,andOctober29,1993,underSafetyEvaluation89-075,Revisions3,4,5,6and7./Additionalmodificationstoadd/improvespeakers,jacks,andassociatedequipmenttotheGaitronicscommunicationssystemhavebeenmadeasevaluatedunderSafetyEvaluation89-075,Revisions7and8.SafetyEvaluationSummary:/-/.Thismodificationwilladd/improvecommunicationcapabilitiestomeettherequirementsinUSARSection9.5.2.Thesechangeswillimprovecommunicationcapabilitiesrequiredforsurveillancetesting,personneltorespondtoalarmsinareaswithhighnoiselevels,andaddcommunicationequipmentinareasthathavebeenidentifiedasneedingcommunicationcapabilities.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage3of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:91-003Rev.7,8,8c9CalculationES-269N/ASystem:TitleofChange:DescriptionofChange:SecondaryContainmentSecondaryContainmentDrawdownAnalysisRevisions7,8,and9ofthesafetyevaluationevaluatedplantoperationfortheremainderofthefourthfuelcycle.ThefollowingparameterswerechangedforthehTrequirementsforthefourthcycleascomparedwiththepreviouscycle.1.Sentfuelheatloads:Aspentfuelpoolheatloadof4.49x10Btu/hrcorrespondingto50daysafterreactorshutdown(DARS)wasusedtodefinethehTrequirementsforthefourthfuelcycle.lnordertoreducethe6Trequirementsand,hence,heatingofthe'buildingduringthesummermonths,alowerspentheatloadof2.31x10'tu/hrcorrespondingto180DARSwasusedtodefinethehTrequirementsfortheremainderofthefourthrefuelingcycle.2.Unitcoolererformance:Basedontheperformancetestsperformedduringthe1992-93timeperiod,a2/odegradationofunitcoolers2HVR"UC413A8cBandanaveragedegradationof30%(sameaspreviouscycle)fortheremainingdrawdownrelatedunitcoolerswasusedfordefiningthe6Trequirementsfortheentirefourthoperatingcycle.Thisprovidessufficientmargintoaccountforanyfurtherdegradationthatmayoccuroverthenextoperatingcycle.3.Piinhealoadreducons:ToreducethehTrequirements,pipingheatloadshavebeenreducedassumingaminimumtemperatureof80'F(Curve2)and90'F(Curves3and4)inthebuilding.

SafetyEvaluation'ummaryReportPage4of131SafetyEvaluationNo.:DescriptionofChange:(cont'd.)91-003Rev.7,8,L9(cont'd.)CubiclehT:Foradditionalflexibility,drawdownanalysisisdoneassumingemergencycorecoolingsystem,residualheatremovalheatexchangersandreactorcoreisolationcoolingcubiclesinsecondarycontainmentaremaintainedat8'Fabovetheservicewatertemperature.Thesecondarycontainmentin-leakagetestperformedonOctober27,1993,indicatedthatin-leakageislessthan90%ofthevalueusedinthedrawdownanalysis.Thisprovidesamarginofabout10%(sameasthepreviouscycle)foranypotentialdegradationofin-leakageoverthenextcycle.1NOTE:ThesechangesweresupersededbySafetyEvaluation94-049andassociatedLicenseAmendmentNo.56.SafetyEvaluationSummary:IThedrawdownanalysis(CalculationES-269andsubsequentdispositions)providesfourcurvesthatdefine6Trequirementsfortheentirefourthfuelcycle.Basedontheevaluationperformed,itisconcludedthattheuseofnewCRTcurvesdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage5of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:91-068Mod.PN2Y89MX080Figures9.3-12h,9.3-12k,10.1-8bTurbineBuildinglVliscellaneousDrainsReboilerSteamLineDrainValveInterlockTheturbineplantmiscellaneousdrainsystemremovescondensatebuildupfromthesteamsupplylineseitherthroughthedrainvalves2DTM-AOV128and2DTM-AOV144orthroughbypasslinesaroundthesedrainvalvesthroughrestrictingorificessizedtopasscondensate.Theoriginaldesignrequiredthedrainvalvestoopenwhenevertheauxiliarysteamsupplyvalves2ASS-STV112and/or2ASS-STV143close,orwheneverturbinefirst-stagepressureindicatedinsufficientextractionsteamwasavailable.Theinterlocksbetweentheauxiliarysteamsupplyvalvesandtheircorrespondingdrainvalvehavebeenremoved.Thismodificationallowsoperatorcontrolofthedrainvalvesirrespectiveofthesteamsupplytothecleansteamreboilersand/orthebuildingheatingintermediateheatexchangerswithintheboundariesallowedbytheturbinefirst-stagepressuresensor.SafetyEvaluationSummary:Thedrainvalvesarenonsafetyrelatedandarenotrequiredforsafeoperationorshutdownoftheplant.Thismodificationprovidesadditionalincreasedoperatorcontrolwhichwillresultinanenhancementtoplantefficiencythatwillnotimpactthesafeoperationorshutdowncapabilitiesoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage6of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:91-080Mod.PN2Y88MX1938.3-10Low-VoltageMolded-CaseCircuitBreakersforPowerDistributionTitleofChange:ReplacementofObsoleteITEMolded-CaseCircuitBreakersDescriptionofChange:Thismodificationreplacedsixdistributionpanelsintheirentiretyandvariousobsoletemolded-casecircuitbreakersinmotorcontrolcentersandotherdistributionpanels.Thesebreakersprovidecircuitprotectionforthelow-voltageIpowerdistributionatUnit2.SafetyEvaluationSummary:ThismodificationdoesnotincreasetheprobabilityofanaccidentormalfunctionofequipmentimportanttosafetypreviouslyevaluatedintheUSAR.Replac'ementbreakersareproperlycoordinatedandadequatelysizedtotheirapplicationinaccordancewiththestandardratingsforthemolded-casecircuitbreakers.Replacementofobsoletebreakersandpanelswillprecludesystemoutages,LCOs,andplantoutageduetounavailablesparesshouldanyofthesecomponentsfailin-serviceorsurveillancetesting.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage7of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:91-089SimpleDesignChangeSC2-0140-90Figures11.2-1d,11.2-1gLiquidRadwasteManagement(LWS).RetireNon-functionalConductivityMonitorsThissimpledesignchangeretiredinplaceconductivityelementsandconductivityindicatingtransmittersfromthefloordraincollectorsubsystemandtheregenerantwastesubsystem.Theseinstrumentsprovidedisplayinputonlyandhavenologicfunction.Sparingtheconductivitymonitoringequipmenteliminatesrepetitivemaintenanceandcalibration.Grabsamplesareusedfordeterminingeffluentconductivityinthoseareaswhereelectronicmonitoringisdisabled.SafetyEvaluationSummary:TheLWSsystemprovidesdiverseoptionsfortheprocessingofwastedependingonthequalityofthewaste.However,innocasecanthewastebypass;afiltrationorevaporationprocess.Theconductivityofthewasteisusedtoaidintheselectionofaprocessmethod.Althoughgrabsampleswillhavetobeusedinlieuofelectronicmonitoring,nosacrificetotheintegrityorfunctionoftheLWSwilloccurfromtheproposedchange.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.-

SafetyEvaluationSummaryReportPage8of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:92-006Rev.1,2,4L5Mod.PN2Y89MX0774A-2,5.2-21,5.2-21a;Tables3B-3Sh2,6.2-56Sh7,9.4-1Sh4;Figures1.2-7Sh2,1.2-11Sh3,5.4-2b,5.4-16a,9.3-5g,12.3-7,12.3%0System:TitleofChange:CrackArrestVerificationInstallationoftheCrackArrestVerificationSystemandRWCUExtensionTie-InDescriptionofChange:Thismodificationimplementedthefollowingchanges:Installationofthecrackarrestverificationsystem(CAVS)includedacracklengthmonitor,waterchemistrystation,electrochemicalpotentialmonitorandtubing.ThesuctionsideoftheCAVSwasconnectedtothereactorrecirculationsystem(RCS)sampleline,downstreamfromtheoutboardisolationvalve,2RCSSOV105,beyondtheClass2lineclassification(i.e.,connectionwillbemadewherethelineisdesignatedasClass4).ThereturnlineoftheCAVSwasconnectedtothereactorwatercleanup(RWCU)extensiontie-inwhichisdownstreamfromoutboardisolationvalve2WCSAMOV112.2.TheRWCUextensiontie-inbeginsatline2-WCS-008-88-3,whichisdownstreamofoutboardcontainmentisolationvalve2WCS"MOV112intheRWCUvalvecubiclelocatedonelevation240',secondarycontainment.Existingvalves2WCS-V45and2WCS-V46werereplacedwith3/4-inchpipe.Thetestconnection,whichisusedduringtheleakratetestingofvalve2WCS"MOV112,wasmaintainedbyaddingathreadedcapandtwonewvalves,2WCS-V431and2WCS-V432.TheRWCUextensiontie-inalsoincludedthe3/4-inchpiperun,includingoneisolationvalve,2WCS-V390,andacheckvalve,2WCS-V392,whichareinsidetheRWCUvalvecubicle,apenetration(i.e.,W-7512-C)throughthecubiclewall,andanisolationvalve,2WCS-V391,outsidethecubicle,whichwereaddedviaTemporaryModification90-054andarenowpermanentperthismodification.

SafetyEvaluationSummaryReportPage9of131.SafetyEvaluationNo.:SafetyEvaluationSummary:92-006Rev.1,2,4L5(cont'd.)TheCAVSisnotasafety-relatedsystemnordoesitperformanysafety-relatedfunction,anditsadditiontotheUnit2designdoesnotaffectthesafetyandreliabilityofUnit2.Thesystem'sfunctionistocollectdatatoprovideanindicationoftheperformanceofplantmaterialsintheboilingwaterreactorenvironment.TheClass3sectionofRWCUextensiontie-inisconsideredQandtheClass4sectionoftheRWCUextensiontie-inisnonsafetyrelated.Bothofthesesectionsareproperlydesignedandwillnotaffectthesafeoperationorsafeshutdowncapabilityoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'ummaryReportPage10of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TltfeofChange:DescriptionofChange:92-033Rev.2ProcedureN2-OSP-RHS-R5009N/AResidualHeatRemoval(RHS)ProcedureN2-OSP-RHS-R5009ThissafetyevaluationevaluatedchangestoprocedureN2-OSP-RHS-RQ009,whichallowsthetestingofthepressureisolationvalvesintheRHSsystemwhichisolate,theRHSheatexchangerfromthereactorcorecoolinginjectionsystem(ICS).ThestepsoftheproceduredelineatethemethodologyfortestingthesysteminordertocomplywithTechnicalSpecifications4.0.5ahd4.4.3.2.2.TestingofthevalvesintheRHSsystemwasconductedduringrefueloutages.SafetyEvaluationSummary:ThisprocedureandmethodoftestingwillhavenoimpactonthesafeoperationorcapabilitytokeeptheplantinthesafeshutdownconditionbecausetheICSfunctionsarenotrequiredinoperationalconditions4or5andtheRHSsystemsafetyfunctionsareunaffected.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage11of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:kSystem:TitleofChange:DescriptionofChange:.93-004TemporaryMod.93-008N/A4.16-kVand600-VNormalAcDistributionAlternatefeedtoTransformer2NJS-X1FThe600-Vunitsubdistributiontransformer2NJS-X1F(feedertounitsub2NJS-US5)wastemporarilypoweredfrom4.16-kVstubbus2NNS-SWG015insteadofitsnormalsource,2NNS-SWG014,whichwasoutofserviceforrepairofacrackedbushingincubicle14-6.SafetyEvaluationSummary:Thistemporarymodificationdoesnotaffectordealwithanysafety-relatedequipmentintheplant.AnEngineeringreviewoftheUSAR,TechnicalSpecificationsandrelateddocumentsindicatesthatthistemporarymodificationisacceptablewithproceduralcontrolsandlimitations.Withthis'changein.':place,thenormalacdistributionwillcontinueperformingitsintendedfunction.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage12of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-008SimpleDesignChangeSC2-0008-93Figure10.1-6cFeedwater(FWP)SealWaterInjectionStrainerDrainValveandPressureGageDescriptionofChange:Thissimpledesignchangeaddedadifferentialpressureindicatoranddrainvalvestothesealinjectionduplexstrainerstofacilitatedrainageforperiodicmaintenanceofthestrainers.SafetyEvaluationSummary:ThischangeisspecifictotheFWPsystem.Nosignificanteffectsonanyotherplantsystemsand/orinterlocksarebeingintroduced.Theadditionofthedifferentialpressuregageanddrainvalveswillimprovetheperformanceofmaintenanceonthesubjectstrainers.Therefore,thesystemmaintainability/availabilityisimprovedduetotheeaseinperiodicchangeoutofthestrainerbaskets.Thesystemstructuralintegritywillnotbesignificantlyaffectedbythischangebecausetheweightofthevalvesandthedifferentialpressuregagearenegligiblerelativetothepipingsizeandschedule.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage13of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-011TemporaryMod.93-015N/AAuxiliaryBoilerDefeatSealCoolingLowFlowTripforAuxiliaryBoilerRecirculationPumpsDescriptionofChange:Thistemporarymodificationjumperedtheauxiliaryboilerrecirculationpumpsealcoolingwaterflowswitchesinordertoallowthepumpstorunwhensealwaterflowisthrottledback.Throttlingthesealwaterisdonetoreducethefrequencyofrequiredboilerblowdowns./SafetyEvaluationSummary:Althoughthistemporarychangemayresultindamagetothepumpseals,thereisnonuclearsafetysignificancetotheproposedchangesincetheauxiliary,boilersarenotrequiredforthesafeshutdownofthereactor.Theriskassociatedwithoperatingtheboilerwiththelowflowtripdefeatedisacceptablesinceplantimpactwillbelimitedtoboileroperability.implementationoftheproposedchangedoesnotconstituteanunreviewedsafetyquestion.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage14of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-017Rev.2SimpleDesignChangeSC2-0375-91N/AStandbyLiquidControl(SLS)RRCSLogicChangetoPrecludeSLSInoperabilityDescriptionofChange:Thismodificationchangedthestoragetanklevelzerologicintheredundantreactivitycontrolsystem(RRCS)panelsfromdeenergize-to-triptoenergize-to-trip.Previously,ifaRRCSpanelw'astakenoutofservice,therespectiveSLSloopwouldbecomeinoperablebecauseSLSidentifiedtheRRCSout-of-servicesignalasaSLStanklevelzero.TheSLStanklevelzerointerlockdisablestheSLSpumpstoprotectthemfromdamageduetorunningthemdry.Previously,temporaryjumpersneededtobeinstallediftheRRCSpanelsweretakenoutofservicetomaintainSLSoperability.Thischangeeliminatestheneedforthesejumpersandprovidesannunciationinthemaincontrolroomtoalerttheoperatorsifthestoragetanklevelzeroalarmisactivated.ThismodificationwasincorporatedintoSLSandRRCSbychangingthelogicinRRCSpanels2CEC"P001and2CEC"P002fromdeenergize-to-triptoenergize-to-trip.Thiswasdonebyminorpanelwiringchangestotheacloaddriverprintedcircuitboardinwhichitwillnolongerinvertthealarmsignal.Becauseofthislogicchange,newprogrammablereadonlymemoryintegratedcircuitswereinstalledintheselftestcircuitryofRRCS.Minorwiringchangestothestoragetanklevelzerointerlockcircuitryweremadeinpanels2CEC"PNL618and2CEC"PNL629toaccommodatethislogicchangeintheRRCSpanelstoenergize-to-trip.SafetyEvaluationSummary:ThismodificationwillkeepSLSoperableregardlessofthestatusoftheRRCSpanelsandwithouttheneedfortemporaryjumpers.Thismodificationhasnoimpactonthesafeoperationorshutdownoftheplant.NuclearsafetyisenhancedinthattemporaryjumpersnowdonotneedtobeinstalledwhenaRRCSpanelisoutofservicetokeepSLSoperable.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage15of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-018Rev.0,1,253Mod.PN2Y91MX0545.4-44,5.4%5;Figure54-16fReactorWaterCleanup(WCS)RWCUF/DImprovementsDescriptionofChange:Thismodificationchangedthereactorwatercleanup(RWCU)filterdemineralizer(F/D)systemasfollows:2.ReplacedseptainF/DvesselsA,B,C,Dwithanewdesign.iRevisedresinfeedsystemtoincludereplacementofthemeteringfeedpumpswithaneductorarrangement.SafetyEvaluationSummary:ThechangestotheRWCUF/Dsystemwillenhancethesystembymakingiteasierfortheoperatortocontrolandprovidemoreoperatoroptionstherebyincreasingflexibility,andimproveprecoatingoftheF/Dvessels.Ultimately,thesystemruncycleswillincreaseandbetterutilizationofprecoatmaterialwillbeachieved.Theproposedchangesarenonsafetyrelatedandwillhavenoimpactonthesafeoperationorshutdownoftheplant.ReactorwaterchemistrylimitsoutlinedinRegulatoryGuide1.56Rev.1,Table1,andspecifiedinTechnicalSpecificationsTable3.4.4-1,willbemaintained.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage16of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:93-020SimpleDesignChangeSC2-0049-93Figure9.4-10eRadwasteBuildingVentilationRadwasteControlRoomNoiseImprovementSafetyEvaluation93-020waspreviouslyreportedinOctober1994whentheUnit2USARwasrevisedtoreflectreplacementofthe7.5hpreturn/exhaustairfanswithnew3.0hpfans.ThisrevisiontotheUSARrevisestheflowdiagramtoshoware'ducedflowof10,700cfm.SafetyEvaluationSummary:ThisdesignchangewillimproveenvironmentalandworkingconditionsintheRadwasteControlRoombyreducingnoiselevels.Theproposedchange.doesnotaffectorinvolveanysafety-relatedequipment.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage17of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-027Rev.2N/A9.1-25,9.1-44FNRFuel-PreparationMachineFull-Up-StopSettingsDescriptionofChange:Thissafetyevaluationaddresseschangingthepositionofthewestfuelpreparationmachine(FPM)full-up-stops.Thischangewillreducethetime/exposurespentduringthetransferofnewfueltothespentfuelpool.Additionally,thiswillreducethepotentialforpersonalcontaminationandplantcontamination.Thewest(2FNR"TL1B)FPMwillbechangedsothatitsnormalconfigurationwillbe:~Full-up-stopspermanentlyremoved~Motivepowerremoved(air-supplylinedisconnectedandblocked)~TobeactivatedandusedonlywithnewnonirradiatedfuelunderadministrativecontrolsandthendeactivatedaftercompletionofnonirradiatedfuelhandlingThewest(2FNR"TL1B)FPlVIwillhaveitsfull-up-stopsremovedsuchthatanewfuelassemblyloadedintoitscarriagewillhaveitsbailhandleabovethespentfuelpoolwaterlevel.PositivestoppingoftheFPMcarriageisperformedbytheendstopsonrollerchainmechanism.Afterthecraneisdisconnectedfromthenewfuelassembly,whichissittingintheFPIVl,theassemblywillbetransferredbytherefuelingplatformtoitstemporarystoragelocationinthespentfuelstoragerack.SafetyEvaluationSummary:Thefunctionofthefull-up-stopsistoprovideenoughwatershieldingwhenusingaFPMtohandleirradiatedfuelassemblies.WhenaFPMisusedtotransferanonirradiatedfuelassemblyintothespentfuelpool,aspecificfull-uplimitisnotrequiredbecauseitsspecificfunction(i.e.,providewatershielding)isnotrequired.

SafetyEvaluationSummaryReportPage18of131.SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)93-027Rev.2(cont'd.)Therefore,thissafetyevaluationisintendedtoallowthewest(2FNR"TL1B)FPMtobeconfiguredtosupporttheapplicationappropriatefornewfuelreceipt/transferactivitiesanddoesnotinvolveanunreviewedsafetyquestion.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage19of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:93-037SimpleDesignChangeSC2-0251-927A.1-5ReactorBuildingHeatingandVentilation(HVR),ContainmentIsolation(ISC),MainSteam(MSS),ResidualHeatRemoval(RHS),ReactorProtection(RPS),StandbyLiquidControl(SLC),ServiceWater(SWP)TitleofChange:DescriptionofChange:ReplacePUBMDRRelaysThissimpledesignchangereplacedexistingPotterandBrumfield(PLB)ModelMDRrelaysthathavebeenusedasanisolationdevicetoisolatenonsafety-relatedcircuitsfromsafety-relatedcircuits,ortoisolateredundantsafety-relatedcircuits.SafetyEvaluationSummary:ThischangeenhancesthefunctionalityofPRBMDRrelaysusedasanis'olationdeviceinthesystemslistedabovebecausethenewP8cBMDRrelaysaredesignedtoprecludethefailuremodesoftheserelays.Replacementrelayswillbequalifiedtothesamerequirementsastheoldrelays.Thenewrelayswillbeofthesameformandfitsuchthattheycanreplacetheoldrelaysasoneforonereplacementwithoutrequiringanymajormodificationsduringtheinstallation.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryR'eportPage20of131SafetyEvaluationNo.:,ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-044SimpleDesignChangeSC2-0102-91N/ANeutronMonitoringSystem(NIVIS)APRMUpscaleAlarmandRodBlock(SDCSC2-0102-91)DescriptionofChange:Thischangereplacedtheneutronfluxinputsignaltotheaveragepowerrangemonitor(APRM)upscalealarmandrodblockcircuitwiththefilteredsimulatedthermalpowersignal.Thepurposewastofilteroutandreducethenoiselevelsoftheneutronfluxsignal,whichinturnallowsUnit2operationalentryintotheExtendedLoadLineLimitAnalysis(ELLLA)regionofthepowerflowmapalongwithareductioninnuisanceupscalealarmsandrodwithdrawalblocks.SafetyEvaluationSummary:ThismodificationallowsoperationalentryintotheELLLAregionofthepowerflowmapwhichwasprohibitedbynuisancerodblocks.Thismodificationwillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage21of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-055SimpleDesignChangeSC2-0342-929.5%,9A.3%6;Figure9.5-1bFireProtectionWater(FPW)InstallCurbBoxesfor2FPW-V1060and2FPW-V1061DescriptionofChange:Thischangeinstalledcurbboxes(valveboxes)fortwoundergroundsectionalisolationvalvesinthefiremain.SafetyEvaluationSummary:Thesubjectvalveswereaddedduringtheconstructionofthesitecafeteriabuilding.Duringfinalconstructionactivities,thevalveswereinadvertentlycoveredpriortotheinstallationofcurbboxesaswasintended.Thischangedoesnotaffectthepipingandwillallowforuseofthetwovalvesaskey-operated,sectionalisolationvalvesinaccordancewith10CFR50AppendixR,SectionIII.B..Normalconstructionactivitiesinvolvingexcavationandfillarerequiredforthisinstallation.Whilethischangewilldisruptnormaltrafficflowintheareaofinstallation,noimpacttosystemorsafeplantoperationwillresult,andtheabilitytosafelyshutdowntheplantintheeventofafireisnotimpacted.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'SummaryReportPage22of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:ASystem:TitleofChange:DescriptionofChange:93-056Rev.1,2&3SimpleDesignChangeSC2-0328-92-Figures1.2-1,2.4-1N/AConstructaSpareTransformerFacilityThesparetransformerfacilitywasconstructedsouthwestoftheUnit2345-kVswitchyard.ThisfacilitywillbeusedforthestorageoftheadditionalsparetransformerforUnit2.SafetyEvaluationSummary:Theconstructionofthesparetransformerfacilitydoesnotimpactthepertinentlicensingissuesthatareassociatedwithhydrologicalengineering;i.e.,flooding,localintenseprecipitation(probablemaximumprecipitation),andtheimpactontheairintakeaccidentX/Q(Chi/0),theatmosphericdispersioncoefficient./Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage23of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-058Rev.2CalculationH21C-0279.1-39FHSRemovalofReactorCavityShieldPlugsA,B,CandDat40~korLessReactorPowerDescriptionofChange:ThissafetyevaluationevaluatedtheremovalofreactorcavityshieldplugsA,B,CandDat40percentorlessreactorpower.SafetyEvaluationSummary:TheremovalofthereactorcavityshieldplugsA,B,CandDat40percentorlessreactorpowerdoesnotaffectthestructuralintegrityoftheshieldplugbarrier.Theradiologicaleffectsoftheproposedchangehavebeencalculatedanddeterminedtobenegligibleforradiologicalconsequencestotherefueling,operatorsduringnormalrefuelingoperations.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage24of131SafetyEvaluationNo.'.ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:93-060TemporaryMod.93-038N/AReactorBuildingVentilation(HVR)TemporaryCoolingforRWCUPumpRoomsThismodificationinstalledatemporaryairconditioningunitoutsidethereactorwatercleanup(RWCO)pumproomstoprovideadditionalcoolingtohelpalleviatehightemperatureconditionsintherooms.Theairconditioningunitispoweredfromaweldingreceptaclefedfromdistributionpanel2WPS-PNL200.!SafetyEvaluationSummary:Thismodificationdoesnotaffectanysafety-relatedequipment,system,buildingorstructurerequiredtoperformitssafetyfunctionduringnormaloperationorfollowingaloss-of-coolantaccident.Ananalysisofcalculationsindicatesthataslightincreaseinthegeneralareatemperatureisinsignificantenoughtocauseanyeffectontheperformanceortheresponsetimeofasafety-relatedequipmentorsystemtoperformitsintendedfunction.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage25of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TideofChange:DescriptionofChange:93-065TemporaryMod.93-043N/AVentilationChilledWatertHVN)TemporaryRemovalof2HVN-TC17CThethermocouplewellpipeconnectionforthethermocouplebulbfromtransmitter2HVN-TC17Cwasleaking.Thethermowellconnectionwastemporarilyremovedandreplacedwithanisolationvalveandpipecomponentsuntilpermanentreplacementandmaintenancewasperformed.SafetyEvaluationSummary:Thistemporarymodificationwillhavenoimpactonthesafeoperationorcapabilitytokeeptheplantinthesafeshutdowncondition.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage26of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-075Rev.05.1SimpleDesignChangeSC2-0014-938.3-72;Figure8.3-10Safety-Related125-VdcBatterySystemBatteryChargerOutputBifurcationDescriptionofChange:ThissimpledesignchangefacilitatesperiodictestingoftheDivisionIandIIbatterychargers,asrequiredbyTechnicalSpecificationsSection4.8.2.1,withminimalimpacttoplantoperations.Thissimpledesignchangerelocatedthebatterychargerelectricalconnectionstoseparatecubicleswithintheirassociatedswitchgear.Thisbifurcationwasdoneutilizingtheexistingelectricalpowercablingbetweenthebatterychargersandthe125-Vdcswitchgear,andreterminatingthecablingtoindividualcubicleloadstabswithintheswitchgear.Onlyonechargerwasconnectedtothe125-Vdcswitchgearbusatatime.Thiswasaccomplishedbyusingabreakeralternatelybetweenthebreakerchargerswitchgearcubiclesorinstallingabreakerinbothofthebatterychargerswitchgearbreakercubicles.Intheeventthe125-Vdcswitchgearbreakersareinstalledforbothchargers(ofthesameDivision),oneofthebreakersshallbeplacedinA/C"Disconnect"positionandlockedoutwhiletheotherbreakerisclosed.Althoughtherewillbeanadditionalswitchgearcubicle/breakerinterfaceforbatterychargerconnectionstotheswitchgear,alarmsandoff-normalstatusdisplayswillbemaintainedatthoselocationswhichcurrentlyprovidesuchindications.SafetyEvaluationSummary:Thissimpledesignchangeenhancesthetestabilityofthebatterychargersbyeliminatingtheneedforliftingleadstoperformthesurveillancetesting.Thisdesignchangewillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage27of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:93-081Rev.0,1,2h.3SimpleDesignChangeSC2-0022-934.6-14;Figures4.6-5c,9.3-9a,9.3-9bSystem:ControlRodDrive(RDS),ReactorBuildingEquipmentDrain(DER),ResidualHeat(RHS),ReactorBuildingVentilation(HVR),ReactorCoreIsolationCooling(ICS)TitleofChange:EliminationofSteamEmissionfromtheReactorBuildingEquipmentDrainsandRDSScramDischargeVolumeCollectionTankInstallationDescriptionofChange:Thissimpledesignchangeinvolvedthefollowingchanges:Isolatedthehotpressurizeddrainlinesfromthecoolgravitydrains.2.AddedapressurereliefdeviceineachoftheReactorBuildingdrainloopstopreventoverpressurizationofthedrainheaderintheeventthatthedraincoolerinletvalvesareinadvertentlyclosed.3.ReroutedtheRDSscramdischargeheaderventlinetotheHVRsystemvia2DER-TK2B.Thisbypassesdraincooler2DER-E2Bandeliminatesapossibleblockageoftheventwhichwouldinhibitthescramdischargevolume(SDV)drainflow.4.SeparatedtheRDSSDVdrainlinefromtheRHSandICSpressurizedsteam-condensingheader,andreroutedthedraintoanewventedcollectiontank.SDVwaterenteringthenewcollectiontankpost-scramiscooledbymixingwiththeexistingwaterinthetank.Thenewtankthendrains,viaanoverflowline,intothegravitydrainheadertotheequipmentdraintank,2DER-TK2A.Thehot,pressurizeddrainlineswithinthe"A"loop(i.e.,ICS,RHS,andSDVdrains)havebeenseparatedfromthecoolgravitydrains,solvingtheALARAconcern.The"B"loop,hotpressurizeddrainsfromRHSandthemain SafetyEvaluationSummaryReportPage28of131SafetyEvaluationNo.:DescriptionofChange:(cont'd.)93-081Rev.0,1,2&3(cont'd.)steamsystemwereseparatedfromtheDERsystem,theRDSventwasrerouted,andthepressurereliefdeviceswereinstalledduringRefuel.Outage4.SafetyEvaluationSummary:Allworkassociatedwiththischangewillbeperformedinthesecondarycontainmentelevations175'-0"and196'-0",inaccordancewithapprovedsiteWorkControlandRadiationProtectionprocedures.Theconstructibilityaspectsofthischangehavebeenreviewed,andappropriateworksequencinginstructionsincludedwithintheapplicableWorkOrders.Theuseofconstructionaids,i.e.,tankleveltygontube,pipebladder,catchcontainments,flexiblehose,etc.,tofacilitateinstallationofpermanentpipinghavebeenreviewedandfoundadequateforsystempressureretentionandstructuralintegrity.Temporaryremovalofpipespoolsisrequired;replacementbacktotheoriginaldesign,asrequired,willbecontrolledwithintheworkorderpackage.TemporarydiversionofReactorBuildingequipmentdraineffluenttotheReactorBuildingfloordrainsystemhasbeenapprovedandwillbemonitoredbytheRadwasteDepartment.Basedontheevaluationperformed,itisconcludedthatthischangedoes.notinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage29of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:93-097SimpleDesignChangeSC2-0078-93Tables9.3-1,11.5-2Sh2;Figures9.3-5c,10.1-9eSystem:TitleofChange:ProcessSamplingDeletionofProcessSamplePointsforURCEffluentsDescriptionofChange:Thissimpledesignchangedeletedprocesssamplepointsforthecondensatedemineralizersystem(CND)attheultrasonicresincleaner(URC)effluent,theURCresineffluent,andtheURCresinreceivertankeffluent.Theseprocesssamplelinesandassociatedvalvesarenonsafetyrelated.SafetyEvaluationSummary:EachoftheaboveprocesssamplepointsbeginsatarootvalveintheCNDsystemandproceedsvia1/4"tubingtosamplesinkSAS4.The1/4"tubingwasremoved(priortoissuanceoftheplant,OperatingLicense)bymodificationPN2Y86MX044inordertoreplaceitwith1/2"tubingtoalleviatepluggingofthesmallerdiametertubing.Themodificationwassubsequentlycanceledandclosedoutbeforeinstallingthe1/2"tubing.TheStandardReviewPlandescribessamplepointsforperformancemonitoringattheinletandoutletofthecondensatepolishingsystemandsamplepointsforradiologicalanalysisofURCwasteliquideffluentandbyresincapacityanalysisatpanelslocatedbetweenthedemineralizerandtheURCprocess.SamplepointsareprovidedforthecommoninfluentandcommoneffluentoftheCNDsystem.Inaddition,ChemistrymonitorsURCperformancebyconductivityanalysisattheresinmixandholdtankeffluentandbyresincapacityanalysisatpanelslocatedbetweenthedemineralizersandtheURCprocess.ThewastewaterfromtheURCissenttothelowconductivitywastetank,alongwithotherliquideffluentfromtheCNDsystem.Thedischargefromthelowconductivitywastetankisprovidedwithasamplepointbeforebeingsenttoeithertheanionregenerationtankorliquidradwaste.Therefore,asamplepointexistsforradiologicalanalysisofcommonCNDwasteeffluent,includingURCwastewater, SafetyEvaluationSummaryReportPage30of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)93-097(cont'd.)beforedischargefromthelowconductivitywastetank.Inaddition,thesamplerootvalvesstillremainsothattemporaryconnectionscouldbemadetomonitortheURCprocess.Therefore,eliminationoftheURCeffluent,URCresineffluentandtheURCresinreceivertankeffluentsamplepointsdoesnotviolateanydesignbasesorplantrequirements.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage31of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-113Unit1SimpleDesignChan'geSC1-0173-91Table2.3&aWeatherStationReplacementof30'evelDewpointMonitoringSystemattheMainMeteorologicalTowerDescriptionofChange:Thissimpledesignchangereplacedthe30'eveldewpointmonitoringsystematthemainmeteorologicaltower.AGeneralEasternModel'E1'onitorwitha1211HlVIPsensorand'175'finterconnectingcablewereprocuredforthischange.Thedewpointtemperaturemeasurementismadewithadirect-measuringsensorutilizingaPeltier-cooledmirror,automaticallyheldatthedewpointtemperaturebyaphoto-sensing,condensate-detecting,opticalsystemincorporatingasolidstateLEDlightsourceanddirectandbiasphotodetectors.Themirrortemperature,ifabovefreezing,measuresthetruedewpointtemperatureand,ifbelow,measuresthefrostpointtemperature.Thetemperatureismeasuredbyanembeddedlinearthermistorsensor.SafetyEvaluationSummary:Thefrequencyoftherepairsontheoldmodeldewpointhascausedtheneedtoreplacethemodel.Thenewmodeldewpointsystemisasaccurateastheoldsystemandmorereliable.Thelocationofthenewdewpointsensorisindependentofthe30-ft.levelboomandwasdeterminedtobelocatedonthesoutheastlegofthetower.Thislocationwaschosenbecauseofexistingboltholesinthetowersteel.Therelocationwillnotaffecttheaccuracyorvalidityofthedataprovided.Theholesarelocatedatthesamelevelastheboom.Puttingthedewpointsensoratthesamelevelastheboominstrumentsisrequiredforconsistencyininstrumentreadings.IVlaintainingthesurgeprotectionfactorisrequiredtoprotectthenewcontroller/monitor.Therefore,newsurgeprotectionboardswereprocuredandwillbeinstalledinthemonitoringsystemcircuit.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage32of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:93-129N/AFigures1.2-1,2.4-1,9A.3-1N/AConstructionoftheNewEngineeringServicesBuildingDescriptionofChange:TheEngineeringServicesBuildinghasbeenconstructedoutsidetheprotectedarea,northoftheP-BuildingwheretheR-BuildingandNorthOlympicBuildingstand.TheEngineeringServicesBuildingisatwo-story,nonsafety-relatedstructurewithaslabongrade.ThisfacilityprovidesadditionalspacerequirementsfordepartmentsrelocatedfromtheSalinaMeadowsfacility.Thisbuildinghasatotalareaofapproximately45,000squarefeetandprovidesofficespaceforabout250personnel.SafetyEvaluationSummary:Basedontheevaluationperformed,itisconcludedthatconstructionoftheEngineeringServicesBuildingdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage33of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-001SimpleDesignChangeSC2-0255-91Figure9.2-5eMakeupWaterTreatingSystem(WTS)EcolochemFilteredandPurgeWaterConnectionsDescriptionofChange:TocontinuetheuseoftheEcolochemportabledemineralizedtrailer,permanentfilteredandpurgewaterconnectionswereaddedtotheexistingWTSsystempiping.TemporaryModification91-093wasemployedprovidingaconnectionforthepurgewaterfromtheEcolochemtothemakeupwasteneutralizingtank(2WTS-TK1).Thischangemadetheconnectionpermanentasinstalled.Inaddition,anewconnectionwasinstalledfromthewatertreatingfilterdrainline,2-WTS-002-134-4,tosupplytheEcolochemtrailer.MakeupwaterfromtheEcolochemdemineralizedtraileriscontrolledinaccordancewithprocedureN2-OP-15.ISafetyEvaluationSummary:AnengineeringreviewofthechangefoundthatinstallingadditionalconnectionstofacilitatetheEcolochemdemineralizedwaterprocesswillimprovethesystemperformancewithoutcausinganysafetyoroperabilityissues.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage34of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-006DER2-910-171811.4-1through11.4-6;Table11A-4Sh1&.2System:TitleofChange:SolidRadwasteAbandonmentIn-PlaceofAsphaltSolidificationEquipmentDescriptionofChange:CThischangeabandonedin-placeselectedportionsoftheoriginalasphalt-basedsolidradwasteprocessingsystem.SafetyEvaluationSummary:Theoriginalplantdesignforradwastesolidification(i.e.,removaloffreewaterfrommiscellaneouswetwastes)utilizedtheWerner&.Pfleiderer(WasteChem)asphaltvolumereductionsystemaddressedbyTopicalReportsWPC-VRS-001andWPC-VRS-002.Duetovariousdeficiencies,processproblems,andoffsitedisposalfacilityburialcriteriaassociatedwiththeuseofthissystem,theoriginalasphalt-basedsolidificationsystemwas"abandonedin-place."Theabandonmentin-placeoftheasphalt-basedsolidificationsystemwillhaveminimalimpactonradwasteprocessing,sincearadwastedewateringprocessprovidinganacceptablemethodofvolumereductionutilizingmethodologyandequipmentaddressedinChemNuclearSystems,lnc.,TopicalReportRDS-25506-01-P/NP(reviewedandapprovedbytheNRC)willbeutilized.Abandonmentin-placewasaccomplishedinsuchamannertoassureproperpressureboundaryconfinementofallprocessapplications.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage35of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-009Rev.0,1,2L3SimpleDesignChangeSC2-0015-94104-33,10.4-34;Figure10.1-6cFeedwater(FWP)InstallThrottleValvesinFeedPumpsSealWaterInjectionLinesDescriptionofChange:Thischangeinstalledthrottlevalvesinfeedpumpssealwaterinjectionlines.Theadditionofthethrottlevalvesallowseachsealwaterinboardandoutboardinjectionlinetobeequallybalanced,providinggreaterreliabilityofthefeedpumpseals.SafetyEvaluationSummary:Anengineeringreviewofthischangehasbeenperformed.Thisreview,whichincludedtheeffectsofthechangeonthesystem'soperability,reliability,maintainability,structuralintegrity,andsysteminteractions,hasfoundthattheimplementationofthischangewillenhancesystemreliability/maintainabilitywithoutcausinganysignificantsafetyoroperabilityissues.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage36of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-012N/ATable9A.3-15Sh3;Figures1.2-1,2.4-1,9.5-1b,9A.3-1System:TitleofChange:DescriptionofChange:N/ANewUnit2IVlaintenanceBuildingTheUnit2MaintenanceBuildinghasbeenconstructedinsidetheprotectedarea,southoftheUnit2AccessControlBuildingandnorth.ofthenewOperationsBuilding.Thisbuildingconsolidatesmaintenancefacilitiesintoanewsinglestructurewhichislocatedclosertoexistingplantaccessways,enhancingteIVlaintenanceDepartment'soverallefficiency.Thebuildingisatwo-story,nonsafety-relatedstructurewithapproximately42,000squarefeetoffloorarea.ThestructurehasaslabongradeandprovidesshopareasforElectrical,IVlechanical,andInstrumentationandControlsMaintenanceGroups.Additionalareasforlockerrooms,materialissue,andofficespacesforMaintenanceIVlanagementandSupportpersonnelareprovided.Also,aportionofthebuildingprovideshighbayvehicularaccessequippedwithoverheadcranes.ThenewIVlaintenanceBuildingandAccessControlBuildingareconnected,andanelevatedwalkwaybetweentheIVlaintenanceBuildingandtheOperationsBuildinghasbeenconstructed.SafetyEvaluationSummary:ThepertinentsafetyissuesidentifiedinthisSafetyEvaluationarefloodingandtheimpactontheControlRoomfreshairintakeradiologicalatmosphericdispersioncoefficient.TheMaintenanceBuildinglocationprovidesadequateseparationfromsafety-relatedsystemsandstructurestoprecludeanyadverseimpactfromanycompressedgasesorchemicalsstoredinthebuilding.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage37of131SafetyEvaluationNo.:ImplementationDocumentNo.:94-013SimpleDesignChangeSC2-0035-94USARAffectedPages:Figures10.1-9a,10.1-9b,10.1-9c,10.4-9Sh7,8,9System:TitleofChange:CondensateDemineralizer(CND)CondensateDemineralizerFlowRecordersUpgradeDescriptionofChange:Thischangereplacedfivecondensatedemineralizerflowrecordersandtheresinstrainerdifferentialpressuremetersassociatedwitheachcondensatedemineralizerwithnewrecordersthataredesignedforimprovedreliability.Thischangealsoreplacedasixthrecorderwhichmonitorsthetotaldifferentialpressureacrossallofthecondensatedemineralizers,andanadditionalmeterwhichmonitorsresinrecyclestrainerdifferentialpressurewithanewrecorderthatperformsthesecombinedfunctions.SafetyEvaluationSummary:Uponimplementationofthissimpledesignchange,newrecorderswillhavebeeninstalledthatprovideimprovedreliabilityofmonitoringofflowthroughthecondensatedemineralizersaswellasadequatemonitoringofthestrainersdifferentialpressure.TheCNDsystemisnotrequiredtoeffectorsupportsafeshutdownofthereactorortoperformintheoperationofreactorsafetyfeatures.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage38of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-017SimpleDesignChangeSC2-0004-91Tables6.2-56Sh7,9A.3-15Sh5;Figures7.3-10Sh1,9.5-1gSystem:FireProtectionMonitoring(FPM),FireProtectionWater(FPW)TitleofChange:RemoveAbandonedFPWPipeSystemsfromFPMMonitoringDescriptionofChange:TwoabandonedwaterdelugepipingsystemsoriginallydesignedtosuppressfiresatthereactorrecirculationpumpswereremovedfromtheFPM'system.Thischangeremovednuisancespuriousalarms,troublesignals,horns,annunciations,andcomputerinputsfromtwopipingsystemswhichwereneverfunctionalandnotrequired.Thischangealsodisconnectedcablingtospareddevicesintheplant,removedfusesandrelaysinthelocalfirecontrolpanel,andincludedtheremovalofdeactivatedswitchesandindicationlightsintheMainControlRoom.,/SafetyEvaluationSummary:Sincethetwoaffectedwaterdelugepipingsystemshavebeeninactiveandcappedpriortoplantoperation,theassociatedcomponentsperformnousefulfunction.Theprimarycontainmentdoesnotrequirefireprotectionsystemsduringnormaloperationsinceitisinerted./Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage39of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-018TemporaryMod.94-020N/AHigh-PressureCoreSpray(CSH)JumperControlSignalfor2CSH"MOV118Atemporaryjumperwasinstalledinthecontrolcircuitofthehigh-pressurecorespray(HPCS)suppressionpoolsuctionvalve,2CSH"MOV118,tosimulateaclosedvalvesignalfromHPCStestreturnvalve2CSH"MOV112.Thisprovidedapermissivesignalfor2CSH"MOV118toopeneventhoughvalve2CSH"MOV112wasdeenergizedand/orbeingstrokedopen(notclosed).With,'2CSH"MOV118capableofopening,theHPCSwascapableoftransferringwaterfromthesuppressionpooltothereactorvesselandmettherequirementsofTechnicalSpecification3/4.5.1.c.TheHPCSwasdeclaredoperablewithout2CSH"MOV112functioning,whichallowedittoreceivemaintenanceandbeVOTEStestedpriortotherefuelingoutage./.ISafetyEvaluationSummary:TheHPCSsystemcanbeconsideredoperablesincethisjumperinstallationwillallowittoperformitsdesignedfunctionswithoutanyimpactfrom2CSH"MOV112onthesystem'sflowrates,pressures,responsetimes,flowpaths,orsetpoints.Thejumperwillnotaffectanyothercomponentsorsystems.Therepairsandtestingof2CSH"MOV112canbeperformedsafelypriortotherefuelingoutage.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'ummaryReportPage40of131SafetyEvaluationNo.:ImplementationDocumentNo.:VSARAffectedPages:System:TitleofChange:94-020SimpleDesignChangeSC2-0405-91Figure10.1-5bCondensate(CNM)CondensateBoosterPumpMechanicalSealCavityDrainsDescriptionofChange:Thissimpledesignchangeaddeddrainlinestotheexistinginboardandoutboardmechanicalsealcavityconnections.Inaddition,theexistingdrainfromtheskidwasremovedandtheconnectioncapped.SafetyEvaluationSummary:Alldrainlines,whetherneworexisting,arenonsafetyrelatedandwillnotimpactthesafeoperationoftheplant.ThechangedoesnotaffecttheoperationoftheCNIVIsystem,TurbineBuildingequipmentandfloordrainsystems{DET,DFT),nordoesitaffectthesafeshutdownoftheplant.Bothsystemsaredesigne'dtohandleinfluentfromoilyornonoilywastefromradioactiveandpotentiallyradioactivesources.Bothsystemspumpwastefromtheirrespectivecollectiontanksorsumpstoradwasteforprocessing.ThecondensatepumpswillcontinuetofunctionasdesignedbecausethischangeinvolvesroutingwaterthatmaypassthroughthemechanicalsealstotheDFTsystemwithoutimpactingpumpperformancecharacteristics.Theexistingskiddrainlines2-CNIVI-150-3304,2CNM-150-331-4and2CNM-150-3324willberemovedandashortnippleandcapwillbeinstalled.Anywateroroilthatmaycollectontheskidmaybedrainedthroughthecappedconnectionorwipedaway.Shouldawaterleakdeveloparoundthecondensateboosterpumpsandsaidflowwassufficienttooverflowthepumpskidcontainment,theDFTsystemwouldcollecttheaddedvolume.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage41of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-021Rev.051SimpleDesignChangeSC2-0031-94Table3.9A-12Sh12;Figure9.2-1fServiceWater(SWP)IST-SWPCheckValvelnterna)sRemovalThissimpledesignchangeremovedtheinternalsfromcheckvalves2SWP"V800A,BandV802A,B.Removaloftheinternalswillprecludesedimentationwithinthevalueandprecludetestfailuresduringin-servicetesting.SafetyEvaluationSummary:Thischangewillhavenoimpactonthesafeoperationorcapabilitytokeeptheplantinasafeshutdowncondition.DeletionofthecheckvalveinternalswillnotpreventtheSWPsystemfromperformingitsintendedsafetyfunction,norwillthesystempressureintegritybedegradedduringanymodeofsystemorplantoperation.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage42of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-023SimpleDesignChangeSC2-0174-93Table7.6-6NeutronMonitoringSystem(NMS).TitleofChange:ReviseAPRMFlow-BiasedRodBlockSetpointSDCSC2-0174-93DescriptionofChange:Thisdesignchangerevisedtheaveragepowerrangemonitor(APRM)flow-biasedsimulatedthermalpower(STP)scramsetpointfrom0.66(W-hW)+51%to0.58(W-hW)+59%(theAPRIVIflow-biasedSTPupscalescramsetpointwasanalyzedunderTechnicalSpecificationAmendmentNo.51),andtheAPRMflow-biasedrodblocksetpointfrom0.66(W-hW)+42%to0.58(W-hW)+50%.ThischangeallowsUnit2tobetterutilizetheextendedloadlinelimitanalysis(ELLLA)regionofthepower/flowmap.SafetyEvaluationSummary:IThischangeallowsOperationstoentertheELLLAregionofthepower/flowmap.OperationintheELLLAregionisrestrictedbecauseatlowerflowstheAPRMflow-biasedscramandtheAPRIVIflow-biasedrodblockencroachontheELLLAregion.Thischangewillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage43of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-024Rev.1SimpleDesignChangeSC2-0361-91Tables1.8-1Sh52,7.5-2Sh158RegulatoryGuide1.97Monitoringand.DisplayInstrumentationTitleofChange:Identification/MarkingofRegulatoryGuide1.97DisplayInstrumentationonPanelsintheControlRoomDescriptionofChange:ThischangeaddedtothepanelsintheMainControlRoomaredplastictrimplatearoundthecomponentidentificationlabeloftheRegulatoryGuide(RG)1.97Category1andCategory2displaydevicesforTypeA,B,andCvariables.ThischangewillassisttheControlRoomoperatorsandsupervisorsinquicklylocatingthemostimportantRG1.97.displayinstruments(i.e.,thoseexpectedtobethemostusefulformonitoring,assessing,andrespondingtopostaccidentconditions).ThischangeimplementsandconformstoarecommendationspecifiedinRG1.97withthefollowingexceptions:(1)thepositionindicatinglightsfortheprimarycontainmentisolationvalveswerenotmarkedwiththeredtrimplate,and(2)themethodusedtoidentifytheRG1.97displaydevicesisthesameasthatusedtoidentifyseveralotherimportantsystemcontrolswitchesanddisplayinstruments.SafetyEvaluationSummary:Thischangedoesnotmodifyinanywaytheoperationorperformanceofanyplantsystemsorstructures,nordoesitrequirethatanychangesbemadetoanyinstructionscurrentlyspecifiedinanyplantoperating,maintenance,orcalibrationprocedures.Thischangedoesnotrequirechangingthecurrentlyspecifiedsafetyclassificationorqualificationcriteriaofanysystemcomponent,andhasnoadverseimpactonthesafeoperationorshutdownoftheplant.Also,thestructuralintegrityofthereactorcoolantsystempressureboundary,theprimarycontainmentpressureboundary,andthesecondarycontainmentpressureboundaryisinnowayaffectedbytheinstallationoftheproposedchange.

SafetyEvaluationSummaryReportPage44of1310SafetyEvaluationNo.:SafetyEvaluationSummary:{cont'd.)94-024Rev.1(cont'd.)ThetwonoteddeviationsfromfullconformancewiththesubjectrecommendationsofRG1.97haveeachbeenevaluated,andbothhavebeendeterminedtobeacceptableonaplant-specificbasis.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage45of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-026SimpleDesignChangeSC2-0134-93Figure9.2-8bDomesticWater(DWS)TitleofChange:DomesticHotWaterRecirculationPumpAbandonmentDescriptionofChange:Thischangeabandonedinplacedomesticwatersystemrecirculationpump2DWS-P1andassociatedmotorandelectricalequipment.Theassociatedannunciatorinthecontrolroomwasalsoremoved.Continuingproblemsconcerningpumpleakageandmotoroverloadingwereresulting'.inannunciatorindicationinthecontrolroom.Pumpabandonmentincludednecessarychangestoassociatedequipment.SafetyEvaluationSummary:TheDWSsystemisnotsafetyrelated,isnotconnectedtoanypotentiallyradioactiveprocesssystems,andisnonseismicexceptintheControlBuilding,whereappropriatedesignmeasureshavebeenimplemented.Systemwaterpressureisprovidedbythenormalsourceofdomesticwater,OswegoCityWater,andisnotaffectedbytherecirculationpump.Byabandoningthepump/motorandassociatedequipmentin-place,anunnecessaryannunciatorwillberemovedandtheneedforpumprepair/maintenance,whichhasproventobequiteextensiveinthepast,willbeeliminatedwhilenotadverselyaffectingsystemoperation.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'ummaryReport.Page46of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-027DER2-94-01579.3-20TurbinePlantSampling(SST),Reactor.PlantSampling(SSR)TitleofChange:ToleranceChangeforlsobathTemperatureinSamplePanelsDescriptionofChange:Thetemperatureoftheconstantisothermalbathsismaintainedat77Fa1Thetighttoleranceforthetemperaturerequiresconstantchangeinrefrigerationmodeandthisresultsinexcessivewearandtear.ontherefrigerationunits.Thischangeprovidedforawidertemperaturerange(77Fs5)tobemaintainedatthesamplesinkconstantbaths,therebyreducingtheconstantswitchingofrefrigerationmodesandthewearandtearontheunits.SafetyEvaluationSummary:Theproposedchangewouldreducethewearandtearontherefrigerationunitsbyexpandingthetoleranceoftheallowableconstantbathtemperatureandnotsignificantlyaffecttheaccuracyoftheconductivitymeasuringinstrumentation.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage47of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-028SimpleDesignChangeSC2-0020-949.5-84;Figures9.5-52a,9.5-52cAuxiliaryBoilerSystems(ABD,ABF,and'BH)TitleofChange:AdditionofAuxiliaryBoilerChemicalInjectionPipingandBoilerFeedandBlowdownSampleConnectionsDescriptionofChange:Thischangeprovidedameansofaddingsodiumsulfitedirectlytotheauxiliaryboilerswhentheboilersareinahotstandbycondition.Inaddition,waterchemistrysampleconnectionswereaddedtofacilitateboilerfeedwaterandblowdownanalysis.Allsamplepipinghasbeenroutedtoanewsamplesinkforconvenience.Restrictingorifice2ABF-RO128boredimensionhasbeendecreasedtoeliminateexcessivesteamlossfromtheauxiliaryboilerdeaerator.SafetyEvaluationSummary:Thischangeupgradestheauxiliaryboilersystemtoimprovesystemreliabilityanditscapabilitytosupportplantoperations.Theauxiliaryboilersystemandtheimpactedboilersubsystemsareclassifiedasnonsafetyrelated.Thesechangeswillhavenoimpactonthesafeoperationorshutdownoftheplantsincethehardwarechangeshavebeendesignedinaccordancewiththeoriginalplantdesignbasis,andhavenoeffectonthefunctionalcapabilityoftheauxiliaryboilersystems.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage48of131SafetyEvaluationNo.:ImplementationDocumentNo.:94-029TemporaryMod.94-022USARAffectedPages:System:N/AMakeupWaterStorage(IVIWS),ChilledWaterVentilation(HVN)TitleofChange:TemporaryMakeupWatertotheHVNSystemDescriptionofChange:Thistemporarychangeprovidedanalternatesourceofmakeupwatertothechilledwaterventilationsystem.ThenewmakeupwaterisfromtheMWSsysteminlieuofthewatertreatment(WTS)system.TheWTSsystemisexperiencingareductionofflowduetopipingdegradationandisnotabletosupplytherequireddemand.MWSwaterwillberoutedfrom/toexistingconnectionsviatemporaryhoseandassociatedcomponents.SafetyfvaluationSummary:ThealternatemakeupfromtheIVIWSsystemwillbesufficientthroughahoseofequalsizeasaminimum.Thenewsourceofmakeupwaterisdemineralizedwaterinlieuoffilteredwater,waterqualityisenhanced,andsupplywillbeadequatetomeetdemand.Allhosesandassociatedcomponentsshallberatedfortheirintendedserviceconditionsandwillbeadequatelysecured.The60gphofwaterfromtheIVIWSsystemwillnotaffectthemakeupwatersystemcapacitytofeedwatertoitsoriginallyintendedsystems.TheuseofMWSwaterinlieuoftheexistingWTSwaterwillnotcauseanyadversesafetyoroperabilityissues.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage49of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-032NUREG-01239A.3-31,9A.3-53,9A.3-56,9A.3-58N/AChangestotheUFSAR/USARActionsRequiredforInoperableFireProtectionSystemsDescriptionofChange:ThischangemodifiedtheUFSAR/USARactionstatementsforinoperablefirebarriers,water-basedextinguishingsystems,Halonsystemsandcarbondioxidesystems.Inaddition,thedefinitionoffirewatchpatrolwaschangedintheUnit1UFSARtoreflecttheactionstatementchanges.SafetyEvaluationSummary:Thesafetyevaluationanalyzesthecurrentactionstatementsandaugmentstheoptionsforcompensatorymeasureswithadditionaloptionstoaccountforareaswherefiredetectionsystemsareinstalledandoperable.Further,theexpandeduseofengineeringevaluationforimpairments,whichiscurrentlyrecognizedwithintheUnit2USAR,isexpandedforapplicationwithintheUnit1andUnit2actionstatements.SuchimpairmentprovisionsallowgreaterflexibilityindealingwithsystemimpairmentswithoutadverselyaffectingtheFireProtectionProgram.Theexistingactionstatementoptionsalsoremainaspotentialcompensatorymeasures.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage50of131SafetyEvaluationNo.:implementationDocumentNo.:USARAffectedPages:I94-033SimpleDesignChangeSC2-0164-839C.8-5;Appendix9CTables3-1,3-4,4-1Sh2;Appendix9CFigure5-1.System:TitleofChange:MainSteam(MSS)ReplaceSRVCrane2MHR-CRN66DescriptionofChange:Thefollowingchangeswereimplementedbythissimpledesignchange:1.Retiredcrane2MHR-CRN66andprovidedareplacementcrane.Thisreplacementcraneisanelectricaltrolleyandchainhoist,andisdesignatedIascrane2MHR-CRN66X.h2.Reworkedandrepairedelectricaltrolleyandbus-barforreplacementcrane2MHR-CRN66X.3.Providedanadditionalweld(nonstructural)forSRVcrane2MHR-CRN65Xmonorailspliceatazimuth240'oimprovecranetrolleyperformance.SafetyEvaluationSummary:-Replacementcrane2MHR-CRN66XisbeingsuppliednonseismicandwillberemovedfromtheprimarycontainmentduringplantoperationstomeetcommitmentsmadeundertheGuidelinesfortheControlofHeavyLoads(NUREG-0612)andUSARAppendix9CatUnit2.Theloadpathhasnotchangedandhasbeenpreviouslyevaluatedsuchthatthefailureofthecraneduringaseismiceventwillnotaffectplantsafety.Replacementcrane2MHR-CRN66XisconsideredandincludedintheControlofHeavyLoadsAnalysis.Thereplacementcraneandinstallationconditionsmeetrequirementsforseismicevaluationofnonsafety-relatedcomponentsinsafety-relatedareas(insideprimarycontainment)anddoesnotaffectthesafetyandreliabilityofUnit2.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage51of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-034Rev.1N/A8.2-1,8.2-28;Figures8.1-1,8.2-1,8.2-1a,8.2-1b,8.2-9System:345-kVTransmissionOutput,115-kVOffsitePowerSourcesTitleofChange:Independence/Scriba345-kVTransmissionLineDescriptionofChange:Thischangeaddedasixth345-kVtransmissionlinetoScribaStationthroughtwonew345-kVcircuitbreakers.Thetwonew345-kVcircuitbreakersarethesameelectricalratingastheothereight345-kVcircuitbreakers.Constructionworkincludedtheelectricalinterconnectionofoneofthetwo345-kVcircuitbreakersintheSpringof1994whileUnit1andUnit2wererunning.Inadditiontotheenergizationofthisbreaker,relaytestingwasalsoperformed.TheelectricalinterconnectionofthesecondbreakerandassociatedrelaytestingtookplaceduringtheUnit2refueloutageintheSpringof1995.SafetyEvaluationSummary:ThissafetyevaluationaddressestheimpactsonUnit1andUnit2resultingfromScribaSubstationconstructionactivities.Italsoanalyzestheeffectonthetransmissionsystemduetoincreasedgeneration.Worst-casescenarioswereidentifiedandfoundtobeboundedbypreviousaccidentsandtransientsanalyzedinboththeUnit1andUnit2UFSARs.AProbabilisticRiskAssessmentwasperformedtoquantifytherisksassociatedwiththelineoutages,constructionactivitiesandoperationofthenewtransmissionlines.Theresultsshowtherelativechangeincoredamagefrequencyissmallandisconsideredacceptable.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'ummaryReportPage52of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-035Rev.2N/A8.1-3,8.2-2,8.2-7,8.2-24;Figures8.2-1,8.2-1b,8.2&a,8.2-6dthrough8.2-6uSystem:TitleofChange:115-kVOffsitePowerSourceAlternate115-kVTransmissionSupplyNMP2DescriptionofChange:ThismodificationallowstheUnit2115-kVtransmissionline,No.5orNo.6,tobeenergizedfromthe115-kVtransmissionsysteminsteadofScribaSubstation.Either115-kVtransmissionlineNo.5orlineNo.6wouldbeenergizedfromNMPC's115-kVtransmissionsystem'slineNo.2.EithertransmissionlinewillbeconnectedtotheScribaStation115-kVmainbus(Cfor5line,Dfor6line)andwillprovide115-kVoffsitesupplythroughexisting115-kVfeederbreakersR50orR60.NochangestoprotectivetripschemesatUnit2wouldberequired.Sinceexisting115-kVcircuitbreakerswouldstillbeenergized,relayprotective,,tripsignalsatUnit2willbefunctional.SafetyEvaluationSummary:ThissafetyevaluationaddressestheimpactsonUnit1andUnit2resultingfromprovidinganelectricaloffsitepowersupplytoUnit2fromthe115-kVtransmissionsystem.Italsoanalyzestheeffectonthetransmissionsystemduetotheincreaseinelectricalload.Worst-casescenarioswereidentifiedandfoundtobeboundedbypreviousaccidentsandtransientsanalyzedinboththeUnit1andUnit2USARs.Theanalysisperformedshowsthatthe115-kVtransmissionlineNo.2canbeusedasanalternatesupplytothe115-kVNo.5orNo.6lineunderworst-caseloadingconditionsaslongascertainadministrativecontrolsaremaintained.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage53of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-036SimpleDesignChangeSC2-0040-94Table10.2-1Sh2;.Figure10.2-3Sh1Electro-HydraulicControl(EHC)KeylockSwitchAdditiontotheTurbineBackupOverspeedTestCircuitDescriptionofChange:Thischangeaddedakeylockswitchtotheturbinebackupoverspeedtestcircuit.Redundantswitchcontactswerenecessarytopreventtheoriginalpotentiallyfaultytestpushbuttonfromtrippingtheturbineduringnormaltesting.Thenewswitch,inthetestposition,disablesthetriprelayandservesasapermissiveforthetest.Initiationofthetestcontinuestobecontrolledbythepushbuttononlyafterthenew'switchisplacedinthetestposition.Inthenormalpositionthenewswitchhasnoimpactonthebackupoverspeedtripcircuit.SafetyEvaluationSummary:Theturbinegenerator,designedtominimizethepossibilityofafailurethatcouldproducehigh-energymissiles,isnotrequiredtotripfornuclearsteamsupplyupsetsbutdoessotoprotectitselffromconditionsthatmaycausedamage.Theturbinegeneratorisnotrequiredtoeffectorsupportsafeshutdownofthereactorortoperformintheoperationofreactorsafetyfeatures.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage54of'131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-039SimpleDesignChangeSC2-0113-94Figure10.1-9cCondensateDemineralizer(CND)CondensateDemineralizerSystemImprovements:.ReplacementofValve2CND-PV188andRemovalof2CND-RV278DescriptionofChange:Thissimpledesignchangereplacedvalve2CND-PV188,a1-1/2",300¹flangedTuflineplugvalve,actuatorandpositionerwithaFisherControls2",300¹flangedglobecontrolvalvewithactuatorandpositioner.TheTuflineplugvalvewasnotadequateforpressurecontrolandcontrollederratically.Valve'2CND-RV278was.removedfromthesystem.Thevalveleaked,adverselyimpactingsystemperformance.ValveRV278isredundantandsystemoverpressurizationwasprovidedby2CND-RV352.Inaddition,pressureindicators2CND-PI282,PI303andPI304werereplacedwithalargerscalegauge.JJSafetyEvaluationSummary:Thischangedoesnotaffectanysystem,equipmentorcomponentoftheplantwhichperformsasafety-relatedfunction.Nuclearsafetywillnotbeaffectedasthechangeimpactsthenonsafety-relatedCNDsystem.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage55of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-043Rev.2NEP-POL-010113.1-4,13.1-5;Figure13.1-3N/AEngineeringTechnicalSupportOrganization,ChangesDescriptionofChange:ThefollowingchangesweremadeintheUnit2Engineeringorganization:1.GeneralSupervisorNuclearDesign-positionabolished.I,2.SiteEngineering-namechangedtoPlantSupport.3.SupervisorSafetyAnalysis-namechangedtoSupervisorAnalysis.4.SupervisorChemistry/RPSupport-positionabolished;RPSupportfunctionmovedunderSupervisorAnalysis(see3above)andthechemistryfunctionmovedtoSupervisorEnvironmentalProtection.5.LeadEngineerInspectionProgram-positionabolishedandthefunctionintegratedintoMechanicalDesign.6.LeadEngineerSpecialPrograms-positionabolishedandfunctionintegratedunderSupervisorAnalysis(see3above).7.GeneralSupervisorEngineeringPerformanceServices-functionintegratedunderManagerUnit2Engineering.8.SupervisorEngineeringPerformance-costestimatingandschedulingfunctionsintegratedunderSupervisorProjectManagementUnit2.9.SupervisorAdministrativeServices-positionabolished;eachEngineeringSupervisorwilloverseetheirownadministrativestaff.10.AssociateSeniorStaffTechBuildingServices-positionupgradedandmovedunderManagerInformationManagementas"SupervisorBuildingServices."

SafetyEvaluationSummaryReportPage56of131SafetyEvaluationNo.:DescriptionofChange:(cont'd.)S4-043Rev.2(cont'd.)11.ProgramDirectorIndependentSafetyEngineeringGroup-word"program"deletedfrom.thepositiontitle.Thefunction.remainsunchanged.12.SupervisorDocumentControl(site),SupervisorDocumentControl(Salina),SupervisorRecordsManagementandSupervisorResourceCenters-thesepositionshavebeenabolishedandtheirfunctionshavebeentransferredintoanewposition,"SupervisorDocumentControl/RecordsManagement."13.SupervisorSoftwareDevelopment-thisisanewpositionreportingtoManagerInformationManagement.SafetyEvaluationSummary:Afterimplementationofthesechanges,adequateresourceswillexisttoprovideEngineeringsupportforsafeoperationandmaintenanceofthefacilityunderbothnormalandoff-normalconditions.Consequently,thesafeoperationand,maintenanceofthefacilityisnotadverselyaffected.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage57of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-044'DER2-94-0036N/AN/ABoraflexCouponRemovalwithNETCOProcedureSEP-093-01DescriptionofChange:Avisualinspectionwasmadeandmeasurementstakenofthefull-lengthsurveillanceassembly(SA)atUnit2.Theboraflexsheets,orcoupons,fromtheshort-lengthSAwereremovedandsenttoaqualifiedlaboratory(PennState)fortestingandanalysis.Thisanalysiswasusedtoestablishabaseline(the"original"datadescribedintheUSAR)tocomparefuturecoupontestsagainst.ThecouponswillalsobecomparedtounirradiatedcouponstakenfromtheoriginallotofBoraflexusedtomanufactureUnit2'sSAs.SafetyEvaluationSummary:/PerformingabaselinecharacterizationoftheBoraflexcouponsinstalledinthespentfuelracksisnecessarytodevelopaBoraflexPoisonSurveillanceProgramtotrackborondepletion.Thelackofpreinstallationbaselinecharacterizationwillnothaveasignificantimpactonthedevelopmentofalong-termsurveillanceprogramandwillnotposeasafetyconcern.Standardindustrypracticeandstatisticalstudiesshowthatremovingalloftheshort-lengthcouponsfromthespentfuelracks,forthetimeperiodrequiredtotakethisbaselinedata,willnothaveasignificantimpactontheneutronandgammaexposuresseenbythesecoupons,andfuturecouponsurveillancewillbeaccurate.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage58of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-045N/A3.1-24,7.3-26,9.1-'18,9.3-16,9.4-54,9.5-73,and26.2-55,6.2-99,6.3-20,6.4-6,7.3-34,8.3-2,8.3~;8.3-75,9.2-6,9.2-16,9.3-8,9.3-11,~9.3-29,9.4-8,9.4-24,9.4~,94-64,9.5-32,9.5%9,9.5-61,9.5-81,11.5-13;FMEAVolumes1System:TitleofChange:N/ARemovaloftheFailureModesandEffectsAnalysis(FMEA),Book1and2,fromtheUSARDescriptionofChange:TheFMEAwasoriginallysubmittedtotheNRCin1983aspartoftheOperatingLicenseapplication,anditdocumentedthesingle-failureanalysesforsafety-relatedsystemsatthattime.TheFMEAisaverydetailed,component-level,computer-basedfaulttreeanalysis.ThetwoFMEAvolumeshavebeenremovedfromtheUSARandareretainedasaseparateengineeringdocumentwhichisreferencedintheUSAR.SafetyEvaluationSummary:Thisisadocumentation-onlychangewhichhasnoeffectontheplant,itssystemsorprocedures,anddoesnotaffectthesafeoperationorshutdownoftheplant,nordoesitaffecttherequirementtoconsidersingle-failurecriterionasanormalpartofthedesignprocess.RemovingtheFMEAfromtheUSAReliminatestherequirementtoupdatethisdocumentannuallywiththeUSAR.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage59of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-046Rev.1SimpleDesignChangeSC2-0099-9310.2%,10.2-5;Figure1.2%0GeneratorHydrogenSupply(GMH)BulkHydrogenControlCabinetThischangereplacedallpiping,valves,andcontrolsassociatedwiththeexistingbulkhydrogenstorageunit.Changesincludedthereplacementofallcylinderisolationvalves,fabricationofanewstainlesssteeldischargemanifold,installationofanewtubetrailerdischargestation,installationofavendor-supplied(AirProducts)standardpressurecontrolstation,andreplacementos'theexcessflowcheckvalvewithaproperly-sizedunit.Inaddition,thedischargeheightforsafetyreliefventswasincreased.SafetyEvaluationSummary:/Thischangewasmadetoaddressleakageandsafetyconcernswiththe;previouspipingarrangement,andtomodifythesystemtoprovideadequatemakeupflowrateforgeneratorreplenishmentwithoutdefeatingtheprotectivefeaturesoftheexcessflowcheckvalve.Thedesignflowrateoftheexcessflowcheckvalvewasnotchanged.Themaingeneratorhydrogensupplysystemisanonsafety-relatedsystem.thatisusedtoprovidehydrogentothemaingeneratorafteranoutageoronanas-neededbasistomakeupforhydrogenlossfromthegenerator.Thesystemconsistsofavendor-suppliedbulkhydrogenstorageunitwithpressure-reducingcontrolslocatedintheyardareabetweenUnit2andUnit1,andanetworkofdistributionpipingandcontrolswhichconveythehydrogenintotheturbinebuildingwhereitisusedforgeneratormakeup.Thesystem'spurpose,function,methodofperformingitsfunction,anddesignbasiswasnotchanged.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage60of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-048SimpleDesignChangeSC2-0062-9270733PlantProcessComputerSystem(PMS)RemoveBalanceofPlantPerformanceCalculations(BOPCALC)andVesselTemperatureRateofChange(VTC)SoftwarefromthePlantProcessComputerSystem(PMS)DescriptionofChange:ThischangedisabledthecurrentBOPCALCandVTCfunctions,byremovingtheassociatedsoftwareprogramsfromthePMScomputer.SafetyEvaluationSummary:RemovingtheBOPCALCandVTCsoftwarewillhavenoimpactonthesafeoperationorshutdownoftheplant.ThePMScomputerwillremainasasystemtoprovideoperatorswiththemeanstomonitornuclearsteamsupplysystem(NSSS)andBOPevents.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage61of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-049Rev.0L1lNod.PN2Y89MX1466.2-66through6.2-71;Table6.2-54;Figures6.2-77,6.2-95Athrough6.2-95DSystem:SecondaryContainmentandStandbyGasTreatment(SGTS)TitleofChange:DescriptionofChange:1-HourDrawdownAnalysisThissafetyevaluationsupportsplantoperationfor1-hourdrawdowntime.ThefollowingparametershavebeenchangedforthereducedhTrequirementsascomparedwiththefourthoperatingcycle.Theseparametersarediscussedbelow:2.SpentFuelHeatLoads:Adesignbasisspentfuelpoolheatload(16batchesoffuelwith12daysofcoolingandpoweruprate)isusedforthedTrequirements.Theuseofthedesignbasisheatloadisconservative.rI.EUnitCoolerPerformance:Fortypercentdegradationforallunitcoolersisassumed.Basedontheperformancetestsperformedduringthe1992-93timeperiod,theoveralldegradationofallunitcoolersincluding2HVR"UC413A8cBis13%.Thisprovidessufficientmargintoaccountforanyfurtherdegradationthatmayoccurinthefuture.3.SecondaryContainmentIn-leakageRate:Themaximumallowablesecondarycontainmentin-leakageis2,670cfmtosupport1-hourdrawdowntimeandreducedhTrequirement.Thisis17%higherthanthefourthoperatingcyclebutstillmeetstheSRPSection6.2.3guideline.DecayHeatRemovalFlowReduction:The2,670cfmin-leakageselectionwillbemadesuchthatitwillpermitaflowdiversionupto300cfmforthedecayheatcoolingafter5hoursintoanaccident.The300cfmflowdivisionismorethanthecoolingflowrequirementof145cfm.EliminationofhTAnnunciation:Existingfour-hoursurveillanceprogramissufficienttoensurethatthe6Trequirementwillbemet.ThehTannunciationisnolongerrequiredbecauseofsignificantlytowerCkTrequirement,andperiodicsurveillanceisadequate.Therefore,theATannunciationcanbeeliminated.

SafetyEvaluationSummaryReportPage62of131SafetyEvaluationNo.:DescriptionofChange:(cont'd.)94-049Rev.08c1(cont'd.)6.SurveillanceAcceptanceCriteria:ThesecondarycontainmentandSGTSsystemsurveillanceacceptancecriteriaarerevisedtoreflect2,670cfmin-leakagerate.Theanalysismethodsarethesameasthoseusedpreviously.7.UseofElectricHeaters:Upto45kWofelectricheaterscanbeusedtomaintainproperemergencycorecoolingsystemroomtemperature(high-pressurecoresprayroomexcluded).Thischangedoesnotadverselyaffect60minutesdrawdowncapacity.Useofadditionalheatersmaybeallowed,followingEngineeringevaluationandwithApplicabilityReview.NOTE:Revision1totheSafetyEvaluationevaluatedtheuseoftheelectricheatersasdescribedinitem7.TheelectricheaterswereprohibitedfromuseinRevision0.SafetyEvaluationSummary:Thedrawdownanalyses(Gale.ES-271,Rev.0andES-259,Rev.02)provideacurvethatdefineshTrequirementsbasedon1-hourdrawdowntimefortheremainderoftheplantlife.ThehTrequirementvariesfrom5to10~Fduringsummermonths.BecauseoflowhTrequirement,buildingheatingisnotanticipated.Duringwintermonths,theavailablehTwillbemorethanthemaximumhTrequirementof20'F.ThesafetyevaluationconcludesthatnosafetyconcernsareinvolvedandnounreviewedsafetyquestionsexistifthehTrequirementsofFigure1andotherrequirementsasstipulatedinthesafetyevaluationareadheredto.

SafetyEvaluationSummaryReportPage63of131SafetyEvaluationNo.:implementationDocumentNo.:USARAffectedPages:System:TitleofChange:84-050EDC2E10933Figures5.4-13d,5.4-13gResidualHeatSystem(RHS)ReviseSafetyClassofControlComponentsforRHSSteamCondensingPressureReducingValves2RHS"PV21A/BfromSRtoQDescriptionofChange:ThischangerevisedthesafetyclassfromSR(SafetyRelated)toQ(Quality)forcomponentsoftheRHS,steam-condensingpressure-reducingvalveinstrumentloopswhichperformnosafetyfunction.Thesafetyclassificationwaschangedforthepressureindicatingcontroller,pressureindicatorandthecurrenttopneumaticconverterfor2RHS"PV21Bandthecurrenttopneumaticconverterfor2RHS"PV21A.SafetyEvaluationSummary:Changingthesafetyclassification,fromSRtoQ,ofcomponentswhichperformnosafetyfunction,willhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage64of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-053Rev.1SimpleDesignChangeSC2-0283-91Figure7.4-1Sh1ICS-ReactorCoreIsolationCooling(RCIC)AddTimeDelayinRCICInitiatedTurbineTripDescriptionofChange:TheRCICsystematUnit2isdesignedinsuchawaythatRCICinitiationprovidesautomaticsignaltotripthemainturbineinstantaneously,regardlessofthecauseofRCICactuation.Therefore,anyinadvertentRCICactuationduetohumanerrororequipmentmalfunctionwillcauseanunnecessarytripofthe>mainturbine.Ifatthatmoment.thereactorisrunningat35/opowerorhigher,thereactorscramwillfollow.Toresolvethisdiscrepancy,atimedelaywasaddedtotheturbinetripsignalinitiatedbyRCIC.Thischangeallowstheoperatortoverifythecauseof,startingRCICpriortotheturbinetripandtakeappropriateactions.IIToprovidethistimedelay,thenonsafety-relatedauxiliaryAgastatrelaywasreplacedwithanonsafety-relatedtimedelayAgastatrelay.SafetyEvaluationSummary:'IGeneralElectric(GE)reportGE-NE-E51-00'171-01,datedJune1994,andGEletters,dated8/29/94,8/30/94,and9/13/94,providedrequestedanalysisoftheproposedchangebasedoncalculatedmoisturelevelinthesteamandsteampipingconfiguration.TheGEreportconcludedthatatimedelayofuptofiveminuteswillnotcompromisetheturbineprotectionandcanbeintroducedtotheRCICinitiatedturbinetrip,providingthetotalaccumulatedtimeofRCICoperationismonitoredanddoesnotexceedeightminutesperyear.Itisconcludedthatthischangewillnotalterthedesignorfunctionofthemainsteamsystemormainturbineperformanceinawaythatadverselyaffectstheturbineprotectionorsystemperformanceorplantnuclearsafety.TheadditionofthetimedelaywillnotaffecttheRCICperformance.

SafetyEvaluationSummaryReportPage65of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)84-053Rev.1(cont'd.)Basedontheanalysisperformed,itisconcludedthattheproposedchangedoesnotalterdesign,function,ormethodofperformingthefunctionofthesafety-relatedsystemandisincompliancewithNRCrequirements.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage66of'131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-055Rev.08a1Mod.PN2Y94MX004Figure6.2-71aContainmentAtmosphereMonitoring(CMS)EliminateMoistureFromH~/O~AnalyzersWaterintrusioninthesamplelineshashadaconsistentdeleteriouseffectontheperformanceofbothTrainAandTrainBhydrogen/oxygen(H~/O~)analyzerpanels(2CMS"PNL66Aand2CMS"PNL66B).Problemsrangefromwaterintheanalyzingcomponents(whichresultininaccurateoutputs)toequipmentfailures(samplepumps,analyzers,etc.).Thesourceofwaterintrusionwasdeterminedtobeduetothehighhumidity(intheprimarycontainmentandtheareaabovethesuppressionpool)beingcarriedintothesamplesuctionlines.Surveillancedurationshaveincreasedasaresultofhavingtorepair/replacevariouscomponentswhicharepronetowaterincursiondamage.Inaddition,a7-dayLCOisstartedwheneverasurveillance/maintenanceisinitiatedoneitherH~/O~train.SafetyEvaluationSummary:ThismodificationinstalledamoisturecollectorinboththesampleinletandreturnlinesforbothTrainsAandB.Whilethemoisturecollectorsareidentifiedassafetyrelated,theyhavenopermissiveorcontrolfunctions.TheyfunctiononlytopreventwaterintrusionintotheH~/O~analyzersystemcomponents.Themodificationwillincreasethesystems'eliabilityandavailabilityanddecreasemaintenance.MostofthemodificationwasinstalledpriortoRefuelingOutage4(RFO-4)withfinaltie-instothesystemduringRFOK.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage67of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-056DER2-94-02176.4-2N/AChangeinNMP2ControlRoomSuppliesRequirementDescriptionofChange:Thischangeallowsfortheprovisionoffood,sleepingfacilities,andotherpersonalcomfortsuppliesfromoutsidetheControlRoomvitalareaenvelopeonanas-neededbasis.ProvidingfoodandsleepingfacilitiesfromeitheronsiteoroffsitesourcescanbereadilyperformedwhenUFSAR-identifiedaccessroutesareconsidered.SafetyEvaluationSummary:ProvidingpersonalcomfortsuppliestotheControlRoomfromoutsidethevitalareaenvelopeduringdesignbasisaccident(DBA)conditionsisinaccordance'withpreviouslyevaluatedaccessroutesdescribedintheUSAR.HabitabilityoftheControlRoomenvelopewithoutthesesupplieshasbeenevaluatedasconsistentwiththeguidelinessetby10CFR50AppendixA,GeneralDesignCriteria19.ThischangedoesnotaffectanyequipmentimportanttosafetypreviouslyevaluatedintheUSARandhasnoimpactonthesafeoperationorshutdownoftheplant.Thischangehasnoimpactonradiologicaleffluentsornonradiologicalconsequencestotheenvironment.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage68of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-058DrawingEY-SSFigure1.2-1N/ANewStructurestoConnectUnit2AccessControlBuildingtothePlantDescriptionofChange:TheUnit2AccessControlBuilding(Phase1)wasconstructedin1993.ThisstructurewasconnectedtotheReactorBuildingviatemporarywoodenstructure.ThiswoodenstructurehasbeenreplacedwithapermanentstructureandanadditionalenclosedwalkwayfromthisstructuretotheCardoxRoom/AuxiliaryServicesBuilding.Thesestructuresprovideadditionalentrypathstoboththeradiologically-controlledareasandthenonradiologicallycontrolledareasofUnit2.ThenewpassagewaytotheCardoxRoomisoutsidetheradiologically-controlledzone.SafetyEvaluationSummary:ThepertinentsafetyissuesidentifiedinthissafetyevaluationareimpactontheControlRoomfreshairintake,impactontheFloodAnalysis,additionalloadsonAuxiliaryBayroof,ReactorBuildingandControlBuildingwalls,impactontheCO~tankruptureanalysis,andaccessibilityfortheremovaloftheAuxiliaryBayroofplugs.Basedontheevaluationperformed,itisconcludedthatconstructionoftheseinterconnectingstructuresbetweentheAccessControlBuildingandtheUnit2Plantstructuresdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage69of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-059Rev.0L1Mod.PN2Y93MX004N/ASystems:CommonElectrical(CES),MoistureSeparatorVents/Drains(DSM),MoistureSeparatorReheaterVents/Drains(DSR),FeedwaterPumpRecirculation(FWR),Feedwater(FWS),HighPressureFeedwaterHeaterDrains(HDH),LowPressureFeedwaterHeaterDrains(HDL),HotReheat(HRS),MeteorologicalMonitoring(MMS),MainSteam(MSS),ReactorWaterCleanup(WCS)TitleofChange:ModifiedASMEPTC6.1TurbineGeneratorPerformanceTestCapabilityforUnit2DescriptionofChange:AmodifiedASlVIEPTC6.1TurbineGeneratorPerformanceTest(ASMETest)wasrequiredinorderforGeneralElectric(GE)towarranteerecoveringtheelectricalmegawattslostduetotheremovaloftwoL-1stagewheelsinlow-pressureturbinesBandCbyreplacingrotorsforlow-pressureturbinesA,B,andC.Thismodificationinstalled50thermocouples,adataacquisitionterminal,and6condenser(baskettip)backpressuresensinglines(2percondenser).Theseitems,inadditiontoexistingplantinstrumentation,enabledtheASMEtesttobeperformed.Throughtheoutputsofthedataacquisitionterminal,themodificationalsoenabledthetemperatures(sensedbythethermocouples)tobemonitoredonthesitemeteorologicalcomputer(METVAX).SafetyEvaluationSummary:Thismodificationwilladdsupplementaryinstrument/pressureinputsinordertoenableamodifiedASMETesttobeperformedatUnit2.Thistestisrequiredinordertoevaluatetheefficiencyoftheturbinegeneratorbeforeandaftertheinstallationofthenewlow-pressureturbinemonoblockrotorsand,subsequently,theefficiencyduetoimplementingpoweruprate.Inaddition,thechangewillenableplantpersonneltopermanentlymonitortemperaturesatthepowercycle SafetyEvaluationSummaryReportPage70of131SafetyEvaluationNo.:94-069Rev.08c1(cont'd.)SafetyEvaluationSummary:(cont'd.)blockvalves(PCBV)close'tothecondensers.Significantincreaseintemperatures,whenthevalvesareclosed,wouldbeindicativeofPCBVleakage.Thechangeswillhavenoimpactonsafeoperationorshutdownoftheplant.ThemodifiedASMEtestisnotdiscussedintheUnit2USAR.TheUnit1USAR,Sectionll.C.,describesthemeteorologyrequirementsandwillnotbeimpactedbythedatalinkinputtedfromUnit2recorder2CES-TJR100.Unit2USARSection2.3.3.2.3describestheMETVAXasaweatherdataprocessingsystemanditwillnotbeimpacted.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage71of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-061PN2Y94MX008Figures9.2-1c,9.2-1e,9.2-1f,9.2-1g,9.2-1J,9.2-1pSystem:TitleofChange:ServiceWater{SWP)InstallationofServiceWater-SystemChemicalCleaningValveTie-lnsDescriptionofChange:Thismodificationprovidedtheisolationandinterfacetie-insnecessarytofacilitatechemicalcleaningofthesmalldiameterservicewaterpiping(I.e.,3-inchNPSandsmaller)intheReactorandControlBuildings.Thecleaningoperationwasimplementedtoremovecorrosionproductandsiltdepositionfromtheaffectedpipingandassociatedunitcoolercoils.Thecleaningprocesswasthefirststepinsuppressingfurtheraggressivecorrosionattackofthepipesurfaceduetomicrobiologicallyinfluencedcorrosion.Thisprecludesfuturecostlypipingrepairsduetoexcessivepitting.Thescopeofthissafetyevaluationaddressestheisolationvalvetie-insnecessarytoaccommodatefuturecleaning.Theactualcleaningoperationwillbeaddressedinseparatedocumentation.SafetyEvaluationSummary:Thisdesignprovidesin-lineisolationvalvesandfittingsforuseinafuturechemicalcleaningoperation.Theisolationvalvessegmenttheaffectedheadersintosixindependentcleaningloops.Duringnormaloperation,theisolationvalvesaremaintainedinthefullopenpositionandperformnoactivethrottlingorisolationfunction.Duringthecleaningoperationthevalvesareclosed,isolatingtheaffectedloopfromthemainheader.Considerationforcomponentaccesswasaddressedinthedesignandplacementofthenewvalvesandfittings.Thesystemchangeshavebeenreviewedagainsttheexistingsystemflowcalculationsandsystempipestresscalculations.Thesechangesdonotchangeorimpedethefunctionoftheoriginalinstallation.Thenewdesignprovidesisolationcapabilitiesnotincludedintheoriginalinstallation,enhancingtheoperabilityandmaintainabilityofthesystem.Thisinstallationdoesnotchangetheoperationofthesystemoritsfunction.Thecleaningvalvetie-insprovidethecapabilitytosupportafuturechemicalcleaningoperation.Theaddedisolationcapabilityenhancessystemmaintenance SafetyEvaluationSummaryReportPage72of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.}94-061(cont'd.}capabilities.TheseadditionstothesystemdonotchangeanylicensingordesignbasesrequirementsoftheSWPsystem.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage73of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-062PN2Y94MX009Figures9.2-1c,9.2-1e,9.2-1g,9.2-1L,9.2-1m,9.2-1pSystem:TitleofChange:DescriptionofChange:ServiceWater(SWP)Resize/RerouteSWPPipingThismodificationupsizedapproximately1,100ft.ofSWPpipingintheReactorBuildingandAuxiliaryBaystoimprovethehydraulicperformanceofselectedunitcoolers.SafetyEvaluationSummary:Thisprojectwillreplaceapproximately1,100ft.ofthesafety-relatedpipe.Thispipewasidentified,throughhydraulicanalysis,tobeundersizedforthedutyrequirementsofthesystem.Thisreviewidentifiedportionsofpipingfor.unitcoolers2HVR"UC401AthroughF,UC406,UC407A,BandC,UC408A:andB,UC410A,UC411CandUC414AandBashavingmarginalcleanpipehydraulicperformance.Thisdesignchangesthesizeofthecurrentlyinstalledpipingandinmostcasesconformstotheoriginalroutingoftheexistingpipe.Therearesomesectionsofthepipingthatwillrequireminorreroutesforgreateraccessibility.Thepipingchangeshavebeenreviewedagainsttheexistingsystemflowcalculationsandsystempipestresscalculations.Thesechangesdonotaffectthefunctionoftheoriginalinstallation.Thenewdesignprovidesisolationcapabilitiesnotincludedintheoriginalinstallation,enhancingtheoperabilityandmaintainabilityofthesystem.Portionsofthenewpipingwillbeinstalledinparallelwiththeexistingpiping.Theexistingpipewillbeabandonedinplacefollowingthesystemtie-ins.Mostpipinginstallationwilltakeplaceduringnormalpoweroperation.TheremainderofthepipeandalltherequiredsystemconnectionswillbeinstalledduringRefuelingOutage4.Precautionswillbetakentoinsurethatinstallationactivitieswillnotinterferewithplantoperationorendangertheabilityofplantsy'stemstoperformtheirnecessaryfunctions.Thepipingsizeincreaseenhancesthecapabilityofthesystemtorespondtoplantneeds.Thisisaccomplishedbyincreasingthecapabilityofthesystemtosupply SafetyEvaluationSummaryReportPage74of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)94-062(cont'd.)servicewatertothecoolers.Theincreasesinpipesizewillnotchangeorimpact'hefunctionofthesystem.ConsideringthedocumentsreviewedithasbeendeterminedthatthismodificationcomplieswithallofthedesignandlicensingrequirementsapplicabletotheUnit2SWPsystem.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage75of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-063SimpleDesignChangeSC2-0029-94Figure9.4-9Sh1,28a3ReactorBuildingVentilation(HVR).HVRFansRepeatedlyFailedtoStartReactorBuildingnormalventilationsystemspare/standbysupplyandexhaustfanshaverepeatedlyfailedtoautostartormanuallystart.Thestartcircuitsforthefanscontainapermissivelogicrequiringrespectivedischargedamperstobegreaterthan40loopen.Whenafanstartsignalisreceived,arelay/timerisinitiated.Also,thestartsignalinitiatestheopeningoftheassociateddischargedampers.lftheassociateddischargedampertakeslongerthan10secondstoopento40%openposition,the.timerwilltimeoutandsendasignaltoclosethedischargedamper;thefanwillnotautostart.Fieldtestingdemonstratedthestartsequencewasbetween7.3and9.2secondswiththerelay/timertrippingin10.1seconds;relay/timerrangewas1.5.to15seconds.Themarginallowedbetween"Start"and"FailtoStart"wastoorestrictiveanddidnotallowforanyanomalyorvarianceofoPeration.Therefore,therelay/timersetpointwasincreasedtoa12seconds.SafetyEvaluationSummary:Thischangewillenhancetheperformanceofthenonsafety-relatedportionoftheReactorBuildingnormalheating,ventilatingandairconditioningsystemandwillnotaffecttheoperationofanysystemsimportanttothesafeoperationandshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'ummaryReportPage76of131SafetyEvaluationNo.:ImplementationDocumentNo.:94-064SimpleDesignChangeSC2-01'l8-94USARAffectedPages:System:TitleofChange:9.5-33,9A.3-16,9A.3-'l7,9A.3-63;Table9A.3-7Sh2Ea3;Figure9A.3-5N/ADeletionofFireBarrierRating-DieselGeneratorDayTankRoomsDescriptionofChange:Thischangedeletedtherequirementforathree-hourratedfirebarrierseparatingeachdieselfueldaytankfromitsassociateddieselgenerator.SafetyEvaluationSummary:ThecurrentFireHazardsAnalysis,aspresentedinUSARSection9.A,postulatesafireineachdieselgeneratorareawhichincludestheentireinventoryofdieselfuelcontainedwithinthedaytank.Sincethedieselgeneratorwillnotfunctionwithoutthedaytanksupplyingfuelandthedaytankhasnovaluewithouttheavailabilityofadieselgenerator,theprovisionofafirebarriertoisolatethefuelsupplyfromthedieselgeneratorisoflittlevalue.Thepostulatedfiredoesnotcreditthefirebarrierwithisolatingthedaytankfromthedieselgenerator.Eliminationofthefirebarrierdoesnotplacetheareaoutsideofcompliancewithapplicablecriteriasincedikingandspillcontainment,inaccordancewithBTPCMEB9.5-1PositionC.7.i.(2),ismaintained.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage77of131SafetyEvaluationNo.:ImplementationDocumentNo.:94-065SimpleDesignChangeSC2-0034-94USARAffectedPages:Table3.9A-12Sh12&13;Figures9.2-1e,9.2-1f,9.2-1j,9.2-1LSystem:ServiceWater(SWP)TitleofChange:SWPCheckValveRemoval,RelocationorReplacementDescriptionofChange:TheSWPsystemwasreviewedbytheprojectteaminresponsetoindustryconcernsandUnit2performanceproblemsnotedduringSWPcheckvalveandunitcoolertests.Astudywasperformedwhichnotedseveralareasforimprovementofthesystemperformance.Thescopeofthisprojectaddressedoneaspectoftheproposedsystemimprovementsrecommendedbythestudy.Thisprojectaddressedcheckvalveperformanceenhancementswhichincluded:Removaloftheinternalsfromcheckvalves2SWP"V75Aand75B.Relocationofcheckvalves2SWP"V1024andV1025,and.theinstallationofblockingvalvesanddrainprovisions.Replacementofliftcheckvalves2SWP"V201Aand201Bwithnozzlecheckvalves,andreroutingtheassociatedpiping.Replacementofswingcheckvalves2SWP"V240Aand240Bwithnozzlecheckvalves.SafetyEvaluationSummary:Thecheckvalvechangesenhancethecapabilityofthesystemtorespondtoplantneeds.Thisisaccomplishedbyimprovingvalvereliability,eliminatingunnecessarymaintenanceandtesting,andincreasingthecapabilityofthesystemtosupplyservicewatertotheassociatedheatloads.ThesechangesdonotadverselychangeorimpactthefunctionofthesystemandcomplywithallofthedesignandlicensingrequirementsapplicabletotheUnit2SWPsystem.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage78of.131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-066TemporaryMod.94-039N/AReactorProtectionSystem(RPS),NuclearSteamSupplySystem(NSSS),MainSteamSystem(MSS)TitleofChange:DefeatofMainSteamLineRadMonitoringTripSignalChannelB1DescriptionofChange:ThistemporarymodificationinstalledaJumperinpanel2CEC"PNL633BayBinordertodefeatatripsignal(ChannelB1)whichwouldnormally,,beprovidedwheneverdetector2MSS"RE46Bisinoperable.SafetyEvaluationSummary:Thistemporarymodificationallowsforampletimeforthereplacementof,thefaultydetectorwithoutenteringaLCOperTechnicalSpecifications3/4.3.1.aand3/4.3.2.b.1.b.Thischangereducestheplant'svulnerabilitytoafullscrambyprohibitingthehalfscramsignaltobepresentduringthetimeperiodthatthedetectorisbeingreplaced.lntheeventoffueldamage,theremainingmainsteamlineradiationmonitorswillfunctiontodetectthereleaseoffissionproductsandinitiatetheappropriatemitigatingactionstolimitthereleaseandtoshutdowntheplant.Thischangedoesnotimpacttheremainingdetectorsfromperformingtheirsafetyfunctionsasoriginallydesigned.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage79of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:'TitleofChange:94-067DER2-94-00369.1-9,9.1-10N/AUpdateUFSARDescriptionofaRevisedBoraflexSurveillanceProgramandUseofNewSurveillanceAssembliesDescriptionofChange:USTool&Die(UST&D)originallysuppliedasurveillancesampleconsistingof2-inchsquarepiecesofBoraflexfortheUnit2spentfuelstorageracks.Thiswasshippedin1984andwasthestandardsurveillancesa'mplesuppliedbyUST&Datthattime.However,thesesampleswerelostandther'eforeneverinstalledintheUnit2spentfuelpool.ReplacementBoraflexsurveillancesampleswerepurchasedin1990.Thesecouponswereinstalledpriortotheracksbeingputintouseandthehottestbundlesfromeachreload.havebeenplacedaroundthem.ThissafetyevaluationupdatedthedescriptionintheSARoftheBoraflexcouponsurveillanceassembliestobeinagreementwiththeactualcouponswhichwereinstalledin1990,Inaddition,thelong-termBoraflexSurveillanceProgramhasbeenmodifiedtobeinagreementwiththemostrecentindustryguidanceforBoraflexsurveillance,issuedinareportbytheElectricPowerResearchInstitute(EPRI).SafetyEvaluationSummary:PerformingperiodictestingoftheBoraflexcouponsinstalledinUnit2'sspentfuelracksisnecessarytoprovideassurancethattheBoraflexmaterialinthespentfuelrackscontinuestoperformacceptablyovertheservicelifeoftheracks.ThereplacementcouponsandtheirassociatedsurveillanceprogramwillprovideadequateassurancethattheBoraflexmaterialisperformingasintendedandwillprecludetheoccurrenceofacriticalityaccidentduetodegradationoftheBoraflexmaterial.ThisrevisedsurveillanceprogramwillcontinuetoimplementtherequirementsofGDC61andisamoreconservativeprogramthantheoriginalonedescribedintheUSAR.NeithertheBoraflexcouponsortheirassociatedsurveillanceprogrampresentasafetyconcernforUnit2.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage80of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-068Rev.0L1SimpleDesignChangeSC2-0040-939.1-23,9.1-24,9.1-40,9C.3-4,9C.3-5,9C.8-1,9C.8-2,9C.8-3;Tables3.9AMSh6,3-1Sh1,3-3Sh1;Figure5-2System:TitleofChange:MHRUpgradeof125TonPolarCraneto132TonCapacityDescriptionofChange:Thischangetothepolarcrane'suseandfunctionupgradedthemainhoistfrom125-tonto132-toncapacitytoallowforthefullutilizationofthereactorpressurevessel(RPV)headcarouselstrongbackwhichwasinitiallyemployedduringRefuelingOutage3.Theupgradingofthepolarcranemainhoistinvolvedmodificationsandrecertificationloadtestingofthehoistat125loofthenewratedcapacityduringplantoperation.Theconstructibilityreview,theloaddropassessmentcalculation,andtheloadtestprocedureensuredthatplantequipmentwasnotaffectedbytheworkandtesting.TheupgradingofthepolarcranemainhoistreducespersonnelexposureandsavescriticalpathrefueloutagetimebypermittingtheremovalandreinstallationoftheRPVhead,thestudtensioners,the76studs,nuts,andwashersinoneliftingoperation.SafetyEvaluationSummary:Thedesignchangesandreanalysisofthepolarcranemainhoistfortheupgradeto132tonsmeetsthesamesingle-failureproofcriteriaofNUREG-0612,asdidtheexistingequipment.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage81of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:-94-069ProcedureN2-CSP-2V10.4-2,10.4-22through10.4-27CondensateDemineralizerSystemCondensateDemineralizerWaterPurityMaintenanceDescriptionofChange:IThischangereplacedcondensatedemineralizerresinatintervalswhicharekasedoninletconductivityanditsrelation'shiptothecompositionofthecirculatirjgwater,andcondensateflowratethroughthebedssinceregenerationofresinisnolongerperformedatUnit2.Thisapproachtotheoperationofthedeminer'alizerseliminatesthepotentialforcontaminationfromtheproductsformedduring:;acidandcausticregenerationoftheresin.SafetyEvaluationSummary:Thecondensatedemineralizerresinwillbereplacedsuchthatadequateremainingcapacitywillexistto.handlethepostulatedmaincondenserleakeventwithinthetimepermittedforar%r'derlyshutdown.TheeffluentqualityofthedemineralizersystemwillsatisfytheacceptablelimitfoundinTable2ofRegulatoryGuide1.56,.Rev.1,July1978.Thereplacementofcondensatedemineralizerresinsat:-thesefrequenciesisincompliancewithparagraphCoftheregulatoryguide.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation'ummaryReportPage82of131SafetyEvaluationNo.:implementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-070SimpleDesignChangeSC2-0028-94Figure10.1-6bFeedwater(FWS)ReplacementofDrainValves2FWS"V89ARBand2FWS"V90ASBDescriptionofChange:Thischangereplaceddrainvalves2FWS"V89ARBandV90A8aBforcontainmentisolationvalves2FWS"V12ASB.Thesevalvesare3/4"NPSandarenormallyclosed.Thevalvesarenotactivecomponentsandtheironlysafetyfunctionispressureretention./Thesevalvesarelocatedintheprimarycontainmentandwerereplacedtoenhanceleak-tightnessandpreventleakageinthedrywell.SafetyEvaluationSummary:InstallationofthereplacementdrainvalvesdoesnotimpactthedesignoftheFWSsystem.Thesystemcanstillprovideitsintendedflowandnewdrainvalves2FWS"V89ALBandV90ALBwillassuresystemintegrity.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage83of131SafetyEvaluationNo.:ImplementationDocumentNo.:VSARAffectedPages:94-071N/A2.2-1,2.2-3,2.2-8;Table2.2-3;Figure2.1-2System:TitleofChange:N/AGasPipeline¹63toSitheEnergiesUSAPlantand¹58toIndeckEnergyDescriptionofChange:SitheEnergiesUSAhasconstructeda1000-MWnaturalgas-firedelectricalgeneratingstationknownasIndependenceGenerationPlant.ItisacogenerationplantlocatedinOswegoCounty,NewYork./Twonaturalgaspipelinesliewithin8km(5miles)oftheNineMilePointStation.Onepipeline(¹63)suppliesgastotheSitheplantandtheotherpipeline(¹58)toIndeckEnergy./SafetyEvaluationSummary:Thenearestpointofthepipelinesisover2milesfromUnit2.DuetothedistancebetweenthepipelinesandNineMileStation,atmosphericdispersionwouldconservativelyreducethenaturalgasconcentrationbelowitslowerexplosivelimitmorethan1milefromNineMilePoint.Thedetonationofanunconfinednaturalgasdispersalinairisnotacredibleevent.DuetothedistancefromthepipelinestotheUnit2ControlRoomairintake()2miles),theresultantatmosphericdispersionwouldconservativelyreducethenaturalgasconcentrationattheintakestolessthan9g/m.Thisiswellwithinthenaturalgastoxicitylimitof287g/m'.Basedontheevaluationperformed,itisconcludedthatinstallationofthegaspipelinesdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage84of131SafetyEvaluationNo.:implementationDocumentNo.:USARAffectedPages:System:94-073SimpleDesignChangeSC2-0142-949.4-71;Figures9.4-22bthroughdHeatingandGlycol(HVG),WaterTreatment(WTS)TitleofChange:WaterTreatingMakeupWaterSupplytoHVGDescriptionofChange:Thischangeisolatedthehotwaterheatingandglycol(HVG)systemfrommakeupwatersuppliedbythemakeupwatertreatmentsystem(WTS)becauseWTShasbeenrepeatedlycontaminatedbyglycolintrusionthroughleaky/HVGvalves.TheneededmakeupwaterforHVGwassuppliedmanuallybyOperationsunderproceduralcontrols.Theisolationwasaccomplishedbyremovingthein-linecheckvalvesandblankingoffthelines.SafetyEvaluationSummary:NeithertheHVGnortheWTSsystemshaveanysafety-relatedfunctions.Failureormalfunctionofthesystemsorcomponentswillnotcompromiseanysafety-relatedsystemsorcomponentsorpreventasafereactorshutdown.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage85of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-076DER2-93-1935Table6.2-56Sh2,4,7,10,11,12,20,21'PrimaryContainmentAppendixJDiscrepancies,DER2-93-1935DER2-93-1935addresseddiscrepanciesinvolvingeditorialchangestotheUFSARclarifyingtheUnit2AppendixJProgram.ThissafetyevaluationaddresseschangestoUSARTable6.2-56asfollows:1.DeletedreferencetoTypeCtestingforthefollowingvalves:2RHS"IVlOY1A,2RHS"MOY1B,2RHS"MOV1C,2CSH"IVIOV118,2CSL"MOV112and2ICS"MOV1362.RevisedNotes23,24and25todeletereferencetoTypeAtestingofthefollowingrelief,safety,checkandvacuumbreakervalves:2RHS"SV34A/B,2RHS"SV62A/B,2RHS"RV56A/B,2RHS"V20,2RHS"V19,2RHS"V117,2RHS"V118,2RHS"RVV35A/B,2RHS"RVV36A/B,2RHS"RV108,2RHS"RV20A/B/C,2RHS"RV61A/B/C,2RHS"RV110,2CSL"RV123,2CSL"RV105,2RHS"RV139,2CSH"RV113and2CSH"RV1143.RevisedTable6.2-56toindicateaTypeCtestforvalves2CCP"RV170and2CCP"RV101.SafetyEvaluationSummary:ThevalvesinItem1areECCSsuctionvalvesthattakesuctionfromthesuppressionpoolatanelevationbelowminimumsuppressionpoolwaterlevelof'l99'-6"and,assuch,arewaterfilledpost-LOCA.ThevalvesinItem2arerelief,safety,checkandvacuumbreakervalvesthatterminateinthesuppressionpoolbelowtheminimumwaterlevelof199'-6".Thesuppressionpoolwatereffectivelysealsthesecontainmentisolationvalvesfromtheprimarycontainmentatmosphere,therebypreventinggaseousreleasesfromtheprimarycontainment.Sincethese SafetyEvaluationSummaryReportPage86of131SafetyEvaluationNo.:SafetyEvaluationSummary:{cont'd.)94-076(cont'd.)valvesdonotseecontainmentatmospherepost-LOCA,theydonotrepresentpotentialcontainmentatmosphericleakagepathsandarenotsubjecttoleaktestingasdefinedinAppendixJ.Reliefvalves2CCP"RV170and2CCP"RV171arelocatedinsideprimarycontainmentandtheiroutletsterminateopenendedinsidetheprimarycontainmentatanequipmentdrainand,assuch,provideanatmosphericleakpathfromtheprimarycontainment.Therefore,thesevalvesareconsideredcontainmentisolationvalvesasdefinedinAppendixJandareTypeCtestedtosatisfytherequirementsofAppendixJ.ThischangerevisesUSARTable6.2-56toaccuratelydenotetheproperleaktestingprovisionsforthevalvesinItems1,2and3.ThisisaneditorialchangeanddoesnotchangeleaktestingrequirementsorleaktestingmethodsoftheUnit2AppendixJtestprogram.TheapplicablecontainmentisolationvalvesinItems1,2and3willcontinuetobeproperlyleaktestedperexistingprocedurestoensureleak-tightintegrityasrequiredby10CFR50AppendixJandASMEXI.I.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage87of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-077ProcedureN2-OP-100B9.5%3,9.5-69System:TitleofChange:DescriptionofChange:EmergencyDieselGeneratorLubeOilDiv.3EDGLubeOilTemperatureThelubeoiltemperaturefortheDiv.3emergencydieselgenerator(2EGS"EG2)wasstatedintheUSARtobeabove120'Fduringstandbyconditions.However,actuallubeoiltemperaturewasobservedtobebetween90Fand110Fduringstandbyconditions.Withthevendor'sconcurrence,ithasbeenestablishedthattheminimumstandbylubeoiltemperaturerequirementfortheDiv.3dieselgeneratoris85F.SafetyEvaluationSummary:Establishingtherequirementof85FastheminimumlubeoiltemperatureduringstandbyconditionsisconsistentwiththeacceptancecriteriainNUREG-0800,thatthetemperatureofthelubricatingoilismaintainedaboveaminimumvaluetoenhancethe"first-try"startingreliabilityoftheengineinthestandbycondition.Thischangeisalsoconsistentwiththevendor'srecommendationforminimumlubeoiltemperatureandwillsupplyproperstandbylubricationtotheengine.Therefore,theactuallubeoiltemperatureofbetween90'Fand110'Fissufficienttoverifythatenginelubeoiltemperaturerequirementsaremetunderstandbyconditions.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage88of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:94-078ProcedureN2-OPS-RPS-W001N/AMSS,HRSTitleofChange:TurbineSteamValveSurveillanceTestIntervalExtensionDescriptionofChange:Thissafetyevaluationevaluateschangingthetestingrequirementforturbinecontrol,stop,andinterceptvalvesfromweeklytomonthly.(NOTE:SubsequentchangeshavebeenevaluatedunderSafetyEvaluation95-032).SafetyEvaluationSummary:Thepurposeofthistestingistodiscoveranyvalvemalfunctionsthatcouldcontributetoaturbineoverspeedeventcausingturbinecomponentstobecomehigh-energydebris(missiles)capableofstrikinganddamagingsafety-relatedequipment.TheNRCSafetyEvaluationReportforUnit2(NUREG-1047,Section3.5.1.3.10),withregardtotheturbinemissileissue,concludedthattheprobabilityofunacceptabledamagetosafety-relatedstructures,systemsandcomponentsduetoturbinemissilesisacceptablylow(i.e.,10peryear),providedthatthetotalturbinemissilegenerationprobabilityissuchthatconformancewiththeNRCcriteria(i.e.,P1<10forfavorablyorientedturbines,P1(10forunfavorablyorientedturbines)ismaintainedthroughoutthelifeoftheplantbyacceptableinspectionandtestprograms.Inreachingtheconclusion,theNRCstafffactoredintoconsiderationthefavorableorientationoftheUnit2turbinegenerator.AlsointheUnit2SafetyEvaluation,theNRCidentifiedthattherelevantGeneralElectric(GE)missileprobabilityanalysismaybeusedindeterminingtheinspectionintervalfortheturbinediscsatUnit2.Theexistingrequirementforsurveillancetestingofturbinestopvalves(TSVs),turbinecontrolvalves(TCVs)andturbinecontainedstopandinterceptvalves(CIVs)istoperformthesetestsonaweeklybasis.Inordertoassureplantavailabilityanddecreaseanypotentialofplantscrams,thesurveillancetesting SafetyEvaluationSummaryReportPage89of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)94-078(cont'd.)frequencyofthesevalvesisbeingtemporarilyextended(uptoRefuelOutage4(RF04))fromaweeklytoamonthlyinterval.Justificationforthischangeinfrequencyisprovidedbelow.DuringRF04,thelow-pressureturbinerotorsarebeingreplacedbymonoblockrotors.Missilegenerationisnotaconcernformono5lockrotors.Aspartofthemonoblockrotormodification,aseparatesafetyevaluationwillbepreparedwhichwillidentifysurveillancetestingrequirementsforTSVs,TCVsandCIVs.Itisanticipatedthatwiththereplacementoftheexisting"built-up"low-pressurerotorswithmonoblockrotors,surveillancetestingfrequencyofTSVs,TCVsandCIVscanfurtherbereduced(frommonthlytoquarterly).InresponsetoNiagaraMohawk'srequest,GErecalculatedwheelmissileprobabilitiesfortheUnit2low-pressureturbinerotors.Thesenewcalculationswerebasedonthe'revisedcalculationprocedurethat1)includedupdatedfailureratedataontheprimarysteamvalvesofGEnuclearunits,and2)includedthecapabilityofcalculatingwheelmissileprobabilitiesforextendedtimeintervalsbetweentheGEnormallyrecommendedfunctionaltestsofthesteamvalves.IGEevaluationindicatesthat,basedonNRCcriteria(P1<1x10forfavorablyorientedunits),0/0/0testing,andwithnopre-warming,theinspectionintervalisreducedto5.7yearsfortheArotor.Consideringpre-warming,IVI/0/Mtesting,andbasedonGErecommendation(P1(1x10'ortheunit),theArotorinspectionintervalisreducedto2.8years.Theexistinginspectionintervalis6years.Basedonexistingfrequency,oftesting(W/W/W)andtestscheduleoflVI/M/M(conservatively,Unit2shallutilizeM/M/IVIscheduleinsteadofM/0/ManalyzedbyGE),whichisanticipatedtobeutilizedforaveryshortdurationofthepresentoperatingcycle,thereducedinspectionintervalof2.8yearswouldrequireArotorinspectionbyR5.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage90of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-079ProceduresN2-FSP-FPM-A001-1through59.5-2,9A.3%3,9A.3~;Table9.5-3,Sh7&8System:TitleofChange:FireDetectionSystemPerformanceBasedFireDetectorSurveillanceTestingDescriptionofChange:ThischangeaddedaclarifyingparagraphthatindicatesthatsubsequenteditionsofNFPAcodesandstandardsmaybeusedforsubsequentplantmodificationsandprogramrevisions.Clarificationwasalsoaddedthatadeviation,fromNFPA-72specifiedfiredetectortestfrequenciesisutilizedforfirezonesthatdonotcontainanyequipmentconsideredimportanttosafety.Also,adeviationfromNFPA-72codespecifiedtestingrequirementsinfirezonescontainingsafety-relatedequipmenthasbeenadopted.Thisdeviationisbasedonobtainingequivalentreliabilitybetweentestintervalsasallowedby'NFPAcodeequivalencyprovisions.Therevisedtestingschemeusesa10%,20%expanded,totalzoneexpanded,rotatingtestsamplepopulationfortestingthatisconductedonanannualbasis.SafetyEvaluationSummary:Theclarificationsareinformationadditionsthatdonotaffectsafety-relatedequipmentandarenotchangesfrompresentoperatingpolicies.Thechangetothetestingschemeforfiredetectioninsafety-relatedequipmentareasisbasedontheplant-specificfailurerate(failuretoalarmundersimulatedfireconditions)offiredetectioninstruments.TheschemeadoptedprovidesanequivalentorreducedprobabilityofadetectorfailurebetweentestintervalsthanthatgenerallyassuredbyNFPA-72annualtestintervalsusinggenericfailureprobability.ThetestingschemechangedoesnotincreasetheprobabilityofapostulatedfireintheFireHazardsAnalysis,nordoesitincreaseordecreasetheseverityofthefire.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage91of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-080Mod.PN2Y94INX0063.7B-17,3.9A-3,3.9AM,3.9B&9;Table3.9B-2mSh1&2System:HydrogenRecombiner(HCS),ReactorWaterRecirculation(RCS),ResidualHeatRemoval(RHS),ServiceWater(SWP).TitleofChange:DescriptionofChange:NIVIP2SnubberReductionThismodificationreducedthenumberofmechanicalsnubbersonVnit2safety-relatedpipingsystemsbyreanalyzingthepipingsystemsforsnubberremovalorsnubberreplacementwithstruts.SafetyEvaluationSummary:Duetofailureratesassociatedwithsnubbers,snubberremovalresultsinpipingsystemsthataremorereliable.Otherbenefitsoftheprogramincludereducedlong-termmaintenance,inspectionandtestrequirements.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage92of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-082DER2-93-2060Figures10.1-9e,10.4-9Sh10CondensateDemineralizertCND)CNDUltrasonicResinCleaner(URC)LevelElement2CND-LE225NotInstalledDescriptionofChange:Thissafetyevaluationdocumentstheas-builtplantconditionfortheCNDsystemultrasonicresincleanertankasnothavingalevelelementinstalledandthecorrespondinglevelalarmsinoperative.Additionally,theassociatedsluicingwaterflowcontrolvalvehasbeenmaintainedinthefullopenpositionsinceplantstartupwithapprovedholdouttagpreventingmisoperation.SafetyEvaluationSummary:Theultrasonicresincleaningequipmentdoesnotinterfacewithoraffectanyequipmentimportanttosafety,andtheCNDsystemisnotrequiredtoeffectorsupportsafeshutdownofthereactorortoperformintheoperationofanyreactorsafetyfeatures.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage93of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-083ProcedureN2-FSP-FPM-R001Table9A.3-18Sh2FireDetection(FPM)EliminationofPeriodicTestRequirementsforThermalFireDetectorsinFireZone252SWDescriptionofChange:ThischangeremovedfourthermalfiredetectorsfromthescopeofUSAR-specifiedperiodictesting.ThethermaldetectorsarelocatedintheSFPPhaseSeparatorTankRoomonReactorBuildingelevation289'-0"andimmediatelyoutsidetheroom.Theareaoutsidetheroomisalsoprovideddetectioncoveragebyionizationdetectorsinanotherloopofthedetectionzone.Thecombustibleloadingwithintheroomisinsufficienttowarrantfiredetection.Thischangeleftthethermaldetectorsinstalledbutwillnotrequireperiodictestinginorderforthezonetobeconsideredoperable.Inaddition,shouldoneofthedetectorsgointoalarmduetosomefuturefailure,thischangeallowsthelooptobebypassedinthepanelwithoutdeclaringthezoneofdetectioninoperable.ThischangewasimplementedsinceveryhighradiationlevelsnormallypresentintheSFPPhaseSeparatorTankRoompreventtestinginaccordancewithpreviousrequirements.SafetyEvaluationSummary:ThereliabilityandmarginofsafetydiscussedinUSARSection9A.3.6.1.7willbemaintainedbythischangesinceredundantionizationdetectionintheareawillbemaintained.ThecombustibleloadingwithintheSFPPhaseSeparatorTankRoomisinsufficienttowarrantdetectionandhasbeendocumentedinafireprotectionengineeringevaluation.ThesafeshutdownanalysisisunaffectedbythischangeasistheFireHazardsAnalysis.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage94of131SafetyEvaluationNo.:implementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-087NUREG-0654,NUREG-0696,NUREG-073713.3-2N/AEliminateCorporateEmergencyOperationsCenterDescriptionofChange:NUREGS0654,0696,and0737containcriteriapertainingtoemergencyresponsefacilities.ThereisnorequirementspecifictomaintaininganoffsiteCorporate,EmergencyOperationsCenter(CEOC).Thereis,however,arequirementtomaintainabackupEmergencyOperationsFacility(EOF)shouldtheonsite;EOFbecomeuninhabitable.TheoffsitelocationpreviouslyusedtoobtainEngineeringsupportwasreferredtoastheCEOCintheSiteEmergencyPlan.TheCEOChashistoricallyprovidedaconvenientlocationforobtainingEngineeringsupportduringemergencyscenarios.TheCEOCcontainedresources(drawings,calculations,personalreferences)typicallyusedbyEngineeringpersonnel.Thelocationwasoutsidetheten-mileemergencyzoneanddedicatedphonelineswereusedtoensureicommunicationwiththeTechnicalSupportCenter(TSC)andEOF.TheEngineeringDepartmentrecentlyrelocatedtoabuildingonsiteandcouldbeaffectedbyevacuationrequirements.Foremergencyeventswhichdonotrequireevacuation,communicationviaphonelinesensuresaccesstothesameleveloftechnicalsupportpreviouslyavailable.However,ifsiteevacuationisrequired,accesstotheresourcescontainedintheEngineeringBuildingcouldbelost.Underthesescenarios,technicalsupportwouldcomesolelyfromtheTSCandEOFandwouldbedependentontheamountoftechnicalinformationavailableinthosefacilities.SafetyEvaluationSummary:Conformancewithapplicablecriteriaisassuredsince:1)thereisnotaregulatoryrequirementforaCEOC,and2)exceptunderscenariosrequiringevacuation,theproximityofEngineeringresourcestotheplantwillimprovesupport.Therefore,thereisnonetnegativeimpactfromrelocatingtheEngineeringDepartmenttothesiteandeliminatingtheCEOC.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolve'anunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage95of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-088SimpleDesignChangeSC2-0167-94Page7.7-20;Figure7.7-6Sh3ReactorCoolantSystem(RCS)RecirculationFlowControlValveMinimumPositionChangeDescriptionofChange:Thereactorrecirculationflowcontrolvalvescanbecomestuckatminimumpositionduetothedifferentialpressureacrossthevalveaftertherespectivepumpistransferredtohighspeed.Thischangenowpermitsincreasingthevalvepositiontoamaximumof22%open(hotindicated)withthevalvelimitswitchbypassedwhilethefirstpumpwasupshifted,andamaximumof20%open(hotindicated)whilethesecondpumpwasupshifted.'afetyEvaluationSummary:i~Thepeakneutronfluxthatwillresultfromtheincreasedflowwhentherecirculationpumpsareupshiftedisconservativelybelowthehighneutronfluxscram.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage96of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:94-089'SimpleDesignChangeSC2019-94Figures104-1,10.4-2aCondensateAirRemoval(ARC)DesignChangeto2ARC-AOV104Valve2ARC-AOV104failedtoopenwhenrequired.Therootcauseforthisdeviationwasdeterminedtobeimproperlysizedspringforthedesigncondition.Themostcost-effectiverepairwastoretrofitthisactuatortoopen(andclose)onair.Thisdesignchangedeletedthefailopenrequirementforthisvalve.SafetyEvaluationSummary:Sincethevalveisnonsafetyrelated,nosafetyconcernsexistinallowingthisvalvetoopenonair.Theairwillprovidethenecessaryforcetobreakthevalveawayfromitsseat.Additionally,shouldthevalvefailonceopen,itwillremainopenmaintainingcondenservacuum.Allowingthevalvetoopenandcloseon,airwillnotadverselyaffectnuclearsafety.Basedontheevaluationperformed,itisconcludedthattheretrofitofthisvalvedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage97of'l3'ISafetyEvaluationNo.:ImplementationDocumentNo.:95-005ProcedureNSAS-POL-01,ProcedureNEP-POL-0101USARAffectedPages:13.1-4,13.1-5,13.1;7;Figures13.1-3,13.1-5System:TitleofChange:N/AReorganizationoftheInformationManagementBranchtotheNuclearSafetyAssessmentandSupportDepartmentDesc'riptionofChange:ThefunctionsoftheInformationManagementBranchhavebeenrelocatedfromtheNuclearEngineeringorganizationtotheNuclearSafetyAssessmentandSupport(NSAS)organization.SafetyEvaluationSummary:/.RelocationoftheadministrativesupportfunctionsprovidedbytheInformationManagementBranchtotheNSASDepartmentisconsistentwiththecharterandresponsibilitiesofthatdepartmentandmaintainsclearmanagementcontrolandeffectivelinesofauthorityandcommunicationbetweentheorganizationalunitsinvolvedinthemanagement,operation,andtechnicalsupportfortheoperationofthefacility.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage98of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:95-030ProceduresS-RTP-165,S-RPIP-3.11Tables1.8-2Sh6,1.9-1Sh49&50,12.5-3System:TitleofChange:N/AUseofAudibleAlarmDosimetersandPersonnelAirSamplersDescriptionofChange:ThischangerevisedtheUSARtoagreewithcurrentRadiationProtectionProgramproceduresfortheuseofaudiblealarmdosimetersandpersonnelairsamplers.ISafetyEvaluationSummary:TheproposedchangestotheUnit2USARwillmeettheintentof10CFR20andcomplywithapplicableportionsofregulatoryguidelines.lgBasedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage99of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:95-032Rev.051Mod.PN2Y93MX0053.5-8,3.5-9,3.5-16,10.2-1,10.2-8,10.2-9,10.2-10,10.2-11;10.2-12,10.2-13;Tables3.5-3,3.5-6,3.5-9',3.5-12,3.5-15,3.5-16,10.2-1Sh1&2System:TitleofChange:TMSLow-PressureTurbineMonoblockRotorReplacementDescriptionofChange:Thismodificationreplacedthethreeexistinglow-pressureturbinerotors(2TIVIS-T2A,B,C)withGeneralElectric(GE)monoblockdesignrotors.Thepreviouslow-pressureturbinerotorswereofabuilt-updesign(shrunk-onwheels).Theshrunk-onwheeldesignhasapotentialofdevelopingcrackinginthekeyway,webandhubareaduetostresscorrosioncracking(SCC).ThemonoblockrotordesignhasbeenadoptedasacorrectivemeasureagainstSCC.Thebenefitofreplacementoftheexistinglow-pressureturbinerotorswithmonoblockrotorisasfollows:a.RecoveryoflostIVIWeduetowheelremoval.GEguaranteesa28.3IVIWerecovery.b.C.Reducedlow-pressureturbinerotorinspections.Therecommendedinspectionfrequencyreducesfrom6to10years.Reducedturbinevalvetesting.d.Replacementmonoblockrotorssupportreducedoutagedurations.e.Cobaltreduction.Thepreviouslow-pressureturbinelast-stagebucketsutilizedstelliteerosionshields.Thereplacementbucketsareflamehardened.Thereplacementlast-stagebucketsresultinareductioninradiationexposuretoplantpersonnel.

SafetyEvaluationSummaryReportPage100of131SafetyEvaluationNo.:SafetyEvaluationSummary:95-032Rev.05.1(cont'd.)Themonoblockrotorsweredesignedtomeettherequirementsofthepreviousdesign/operatingconditions,includingtransientoperatingconditions.Atthetimeofscheduledinstallation(1995),Unit2willbeundergoingapoweruprate.Themonoblockrotors,therefore,conformtothedesignrequirementsestablishedforpoweruprate.Therequirementsincludethefollowing:GuaranteedRating:InitialSteamConditions:ExhaustPressure:GuaranteedFlow:1,210,902kW1003psia2.0"HgAbsbackpressure13,583,244Ibs/hrTheturbinerotorsaredesignedwith5percentflowmarginabovetheflowrequiredtomeetthemaximumguaranteedoutputforpoweruprate.Theturbinegeneratorisnotrequiredtoeffectorsupportsafeshutdownofthereactorortoperformintheoperationofreactorsafetyfeatures.Theturbinegeneratoris,however,designedtominimizethepossibilityofturbinerotorfailurethatmightproduceahigh-energymissilethatcoulddamageasafety-relatedcomponent.ReplacementwithmonoblockrotorsreducestheprobabilityofmissilegenerationbyremovingthepotentialforSCCattheinterfacebetweenarotorandwheelviatheuseofamonoblockconstruction.Theoverallprobabilityofdamagebyturbinemissiles(formonoblockrotors)willbewithintheacceptancevalueof10/yr,asoutlinedinSRP2.2.3,andtheacceptancevalueof10/yr,asspecifiedinRegulatoryGuide1.115.Theexistingoverspeedprotectioncontrolswillpreventtherotorfromexceedingthemaximumtransientspeedof120percent(designoverspeed)ofratedturbinespeed.Thissafetyevaluationalsore-evaluatedtestingrequirementsforvariousturbinedevicesbasedonmonoblockrotorreplacement.Adequateproceduralcontrolsshallbemaintainedsuchthattherewillbenoadverseeffecttonuclearsafetybothduringthetransportationandinstallationofthemonoblockrotorsandduringstorageoftheremovedrotors.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage101of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:95-033Mod.PN2Y94MX003Figures9.2-8b,9.2-9bkDomesticWater(DWS),SanitaryPlumbing(PBS),AuxiliaryServiceBuildingHVAC(HVL),PagingSystem(COP)TitleofChange:DescriptionofChange:AuxiliaryBuildingRenovation,RFO4ScopeThischangerenovatedtheAuxiliaryServiceBuildingelevation261'-0"toallowuseascontrolledpersonnelingressandegressto/fromtheTurbineandReactorBuildingsviathelinkwayduringRefuelingOutage4(RFO4).Thischangeinvolvedmakinganopeninginthe13linewallatelevation261'eartheentrancetothesouthelectricaltunnelstairwell,installationofanadditional1.5-hr.fire-rateddoor(ET262-6)forstairwayisolation,removaloflockers,removalofthedrinkingfountainandwashbasins,thecappingoffloordrain(s)inthetemporaryaccesspassageway,andtheremovalofdoorAS261-7forimprovedaccess.Also,doorET262-4wasremovedwhiletheareawasbeingusedonlyforaccessandegressduringRFO4.Thetemporaryaccesspassagewaywascreatedbyinstallingpaintedgypsumwallboardpartitions.Theceilingtilegridandassociatedserviceswererevisedintheareaofthepassageway.Thesechangesarepartialscopeforthismodification.Afterthe'1995refueloutage(RFO4),themodificationwasresumedtoprovidearadiationprotectioncalibrationlaboratory,storageroom,separatemale/femalepersonneldecontaminationfacilities,removalofthe1,980-gallonhotwaterheaterandreplaceitwitha120-galloncapacity,installadifferentdesigndoorforET262%,andinstallanequipmentliftfromTurbineBuildingelevation250'-0"andelevation261'-0"oftheAuxiliaryServiceBuilding.ThechangestobemadeaftercompletionofRFO4willbeaddressedinasubsequentsafetyevaluation.SafetyEvaluationSummary:ThechangesbeingmadetothesouthelectricaltunnelstairwellwereaddressedforconformancewithGeneralDesignCriterion(GDC)2andnoadverseimpactwascreated.Potentialimpacttoadjacentsafety-relatedareasandconformancetoGDC3and10CFR50AppendixRwereevaluatedandconformancewasmaintained.Buildingserviceswererevisedanddidnotimpactanyoperationofequipmentimportanttosafety.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage102of131SafetyEvaluationNo.:ImplementationDocumentNo.:95-034CalculationES-216-OOBCalculationH21C38-01BUSARAffectedPages:System:Tables15.6-13Sh2through11,15.6-16bReactorContainmentPurge(CPS),Gas-Nitrogen(GSN)TitleofChange:RevisedBypassLeakageDesignBasis2GSNov205DescriptionofChange:ThischangerevisedthedesignbasisanalysesfordeterminationofthebypassleakagethroughtheCPSwetwellanddrywellsupplylinesandresultantdosesduetotheincreasedleakage.Theincreasedleakagewasduetoremovalofleakagemitigationcreditforcheckvalve2GSNV205.Sincethisvalveisnotpartofaleaktestprogram,andwillnotbeaddedtoone,creditcannotbetakenforleakagereductionfollowingadesignbasisLOCA,ashadbeenassumedintheoriginaldesignbasisanalyses.SafetyEvaluationSummary:Thissafetyevaluationconcludesthatanunreviewedsafetyquestiondoesnotexistasaresultofremovingleakagemitigationcreditforcheckvalve2GSN"V205.Thisconclusionisbasedonthecalculationoftheadditionalleakageattributabletodeletingcreditforthecheckvalve,anddeterminationthattheresultantdoseswillnotcausethelimitsof10CFR100or10CFR50GDC19tobeexceeded.Thecalculateddosesattheexclusionareaboundary,lowpopulationzone,andintheControlRoomincreaseasaresultofthischange;however,theyremainbelowthelimitsof10CFR100andGDC19.SinceUnit2islicensedtothelimitsof10CFR100andGDC19,theconsequencesofadesignbasisaccidentaredeterminednottohaveincreased.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage103of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:95-035SimpleDesignChangeSC2-0148-94Figures9.2-6a,9.2-17bCondensatelVlakeupandDrawoff(CNS),MakeupWater(MWS)TitleofChange:EliminationofHoseConnectionHeadersforMWSandCNSSystemsDescriptionofChange:ThischangeeliminatedhoseconnectionheadersandinstallednewpermanenthoseconnectionstoallowmovementoflargeequipmentintothedecontaminationroomoftheDirtyWorkshoponelevation261'.lSafetyEvaluationSummary:AnengineeringreviewfoundthateliminatinghoseconnectionheadersinthedecontaminationroomandinstallingnewpermanenthoseconnectionswillimprovemovementoflargeequipmentandstillsupplyCNSandlVIWStothedecontaminationroom.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage104of131SafetyEvaluationNo.:ImplementationDocumentNo.:VSARAffectedPages:95-036SimpleDesignChangeSC2-0157-94'.5-17,9.5-18,9.5-21;Table8.3-1Sh3&4;Figures8.3-2,8.3-3,8.3%,8.3-6Sh5&27~System:TitleofChange:DescriptionofChange:LAR,EJS,NJSChangePowerSupplyto2LAR-PNL200ThischangeseparatedthenondivisionalReactorBuildingnormallightingsystemfromitspresentDivisionalClass1Epowersource2EJS"US1andconnectedittoitsoriginallydesignednondivisionalsource2NJS-US2.Thischangealsodisconnectedaloss-of-coolantaccidentsignalcircuitryto2EJSUS1whichprovidedfortrippingthebreakerfeedingthelightingpanelandtheassociatedcomputerpointsandannunciationcircuitrytotheplantprocesscomputerandtopanel2CEC"PNL852,respectively.DuetoaNRCapprovedextensionintheamountoftimeallowedfortheReactorBuildingdrawdown,anewdrawdownanalysishasdeterminedthattheheatloadgeneratedfromtheReactorBuildingnormallightingsystemwouldnolongerpreventthedrawdownfrombeingachieved.SafetyEvaluationSummary:Theworkscopeisminimalandinvolvesthedisconnectionandconnectionofexistingcablesandfunctionaltesting.Nonewcablesorracewayswillbeinstalledandthosecablestobesparedwillbeabandonedinplace.Separationcriteria,AppendixRrequirements,andelectricalprotectionwillbemaintained:Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage105of131SafetyEvaluationNo.:ImplementationDocument'No.:USARAffectedPages:95-037SimpleDesignChangeSC2-0019-95Figure9.5%2System:EGSTitleofChange:DescriptionofChange:RerouteoftheGovernorOilCoolingLineThecoolingarrangementforthegovernoroilcoolerwasfoundtobeinadequatetokeepthegovernor'soiltemperaturetothevendor'srecommendedvalues.Thecauseofthisconditionwasattributedtoinadequatecoolingwaterflowratethroughthecooler.Thissimpledesignchangeimprovedthiscoolingarrangementbyreroutingthereturnlinefromthegove'rnoroilcoolertoalowpressurepointofthejacketwatersystemtoincreasethedifferentialpressureandtheflowrate.SafetyEvaluationSummary:Thischangewillmaintaindieselgeneratorreliabilitybyprovidingpropercoolingwaterflowtothegovernoroilcooler.Inaddition,athrottlevalvewillbe,addedtothereturnlinetoobtainoptimumgovernorcoolertemperature.OperationofthisvalvewillbecontrolledbyprocedureN2-OP-100Atomaintaingovernortemperaturebetween120Fand200F.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage106of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:95%38CalculationMS%3619.1-12,9.1-37,9.1-38FHSClarificationofDesignBasisforSpentFuelPoolRackExternalLoadingDescriptionofChange:Thischangecorrectedthediscrepancybetweenthedesignbasiscalculation,fuelhandlingprocedures,andSection9.1oftheUSAR.Thedesignbasiscalculationwasrevisedtoincludethecaseforthefuelbundledroppingontothespentfuelpoolrackswhilebeingmovedwiththepolarcrane1/2-tonhoist.Additionally,thecalculationrevisionaddressedthecaseofafuelbundleandgrapplebeingdroppedoverthespentfuelpoolracksfromamaximumheightof30inchesabovetheracks.Useofthe25-tonauxiliaryhoistfortransferofnewfuelbundlesandthepositionofthefuelbundlecratewhenopenednowbetterdescribetheactualnewfuelreceiptactivities.Therequiredchangesindicatetheuseofthe1/2-tonhoistforthetransferofnewfuelbundlestoeitherthenewfuelstoragevaultorthenewfuelinspectionstand.Also,thenewfuelbundlecratemaybeopenedinthehorizontalpositionprovidedthatthecratestillfunctionstosupportthefuelbundles.SafetyEvaluationSummary:Clarificationbetweentheprocedureandthedesignbasisdocumentsforthespentfuelstorageracks'xternalloadingwasdoneinaccordancewiththedesignbasisforthespentfuelpoolracksasreferencedinUSARSection9.1.ThecorrectionofUSARSection9.1regardingnewfuelreceiptactivitiesandassociatedprocedureswasdoneinaccordancewiththeheavyloadcommitmentsperNUREG-0612,asreferencedinUSARAppendix9C.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage107of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:95-043LDCR2-95-UFS%3815.7-8through15.7-14NIAUpdateSARDescriptionoftheBundleDropAccidentDescriptionofChange:ThefuelhandlingaccidentanalysisforthebundledropaccidentinSection15.7.4oftheUnit2USARhasbeenrevisedtoincorporateseveralchangesintheassumptionsoftheanalysis.Theaccidentoccurs'uringarefuelingoperationwhenafuelassemblyismovedoverthetopofthecore.Whilethefuelgrappleisintheoverhoistcondition(bottomoftheassembly32.95feetabovethetopofthecore),amainhoistcablefailsallowingtheassembly,thefuelgrapplemast,andheadtofallontopofthecoreimpactingagroupoffourassemblies.Thegrappleheadandmastarefixedverticallytothedroppedassemblysuchthatallthekineticenergyistransferredthroughthedroppedassemblytothegroupofimpactedassemblies.Thedroppedassemblyimpactsthecoreataslightangleandtherodsinthisassemblyaresubjectedtobending.Aftertheassemblyimpactsthecore,theassembly,grappleheadandmastfallontothecorehorizontallywithoutcontactingthesideofthepressurevessel.SafetyEvaluationSummary:Thenumberoffailedfuelrodsforthebundledropaccidentisdeterminedbybalancingtheenergyofthedroppedassemblageagainsttheenergyrequiredtofailarod.Thedroppedassemblyisconsideredtoimpactatasmallangle,subjectingallthefuelrodsinthedroppedassemblytobendingmoments.Thefuelrodsareexpectedtoabsorblittleenergypriortofailureasaresultofbending.Forthisreasonitisassumedthatalltherodsinthedroppedassemblyfail.Therefore,thetotalnumberoffailedrodsoninitialimpactis62+33=95.Theassemblyisassumedtotipoverandimpacthorizontallyonthetopofthecore.Theenergyfromthissecondimpactwillresultin9morefailedrods.Consequently,thetotalnumberoffailedrodsfrombothimpactsisdeterminedtobe104.Thiscompareswith124failedrodsfromtheanalysispresentedinthecurrentUSAR.Sincethenewanalysisshowsfewerfailedrods,theradiologicalconsequencesareboundedbythoseofthepreviousanalysis.Therevisedbundledropaccidentmethodologyincorporatesseveralconservativeassumptions(i.e.,includingtheweightofthefuel SafetyEvaluationSummaryReportPage108of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)95%43(cont'd.)assemblyandthemastandassumingagreaterdropheight)whilemaintainingtheradiologicalconsequencesofthisaccidentwithinthelimitsofthecurrentanalysis,intheUSAR.ThismethodologyisthestandardmethodologyusedbyGeneralElectric(GE)forthelicensingofallnewfueltypesandisincludedinGE'sStandardApplicationforReactorFuel(GESTAR-II).Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage109of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:95-049Rev.0&1ProcedureN2-OP-526.2-66,6.2-68,6.2-69;Figure6.2-77StandbyGasTreatment(GTS)1-HourDrawdownAnalysisThissafetyevaluationaddressestherevisiontothedrawdownanalysisandproceduralchangestoreflecttheanalysis.Thereviseddrawdownanalysisremovedexistingconservatism(reducethespentfuelpoolheatload,andreduceallowable2HVR"UC413A,Bdegradationfrom40%to20%)forthefollowingsiximprovements:11.2.3.4.5.6.ReducebTrequirementandeliminateperiodichTmonitoringEliminatethenormallightingtripuponLOCAsignaIUseonlyoneofthetwoECCSpumproomunitcoolersEliminateBTpenaltycurveforgeneralareaunitcoolersRestoreuseofelectricalheatersintheECCScubiclesandallowheatinginsecondarycontainmentbasedonspecificengineeringevaluationIncreasetheGTSandservicewater(SWP)systemsinitiationtimefollowingLOCAThesechangesweremadetoimproveplantflexibilityandeaseofmaintenancework.Thereviseddrawdownparametersareasfollows:~Thelongestcalculateddrawdowntimeis57minutes.~Emergencyunitcoolers2HVRUC413A,Bdegradationcanbeashighas20%.~TheGTSandSWP/unitcoolerssysteminitiationtimefollowingaloss-of-coolantaccident(LOCA)canbeashighas60and90seconds,respectively,fromdrawdownconsiderationsonly.SafetyEvaluationSummary:Theconsequencesofthesechangeshavebeenevaluatedagainstthecurrentrequirements.Itisconcludedthatthe1-hourdrawdowntimerequirementisnotimpacted.

SafetyEvaluation'ummaryReportPage110of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)95-049Rev.0&1(cont'd.)TheseimprovementsdonotimpactGTS/HVRsystemscapacitytorestoreand'aintainrequiredvacuuminthesecondarycontainmentfollowingaLOCA.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotincludeanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage111of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:95-050N/AN/AHigh-PressureCoreSpray(CSH)TemporaryEnclosureforCSHStrainerThehigh-pressurecorespray(HPCS)systemtakeswaterfromthesuppressionpoolthroughsuctionstrainer2CSH"STR1,penetrationZ-12,andsuctionvalve2CSH"MOV118.PenetrationZ-12andsuctionvalve2CSH"MOV118areatelevation194'-1115/16"andsuctionstrainer2CSH"STR1isatelevation189'-8".Withminimumsuppressionpoolwaterlevelatelevation199'-6",,maintenance/repairworkon2CSH"MOV118cannotbeperformedwithoutisolatingthesuppressionpool.Thissafetyevaluationwasissuedtoaddresstheinstallationofatemporaryenclosureonthesuctionstrainer,2CSH"STR1,inordertosupportsubsequentrepairandmaintenanceworktobeperformedon2CSH+MOV118.Theenclosureonthestrainerwillensuresufficientisolationofthesuppressionpoolfromsuctionvalve2CSH"MOV118.SafetyEvaluationSummary:Theenclosurewillbeutilizedonlyforrepairandmaintenanceactivitieson2CSH"MOV118.Administrativecontrolspertheworkordershallbeinplaceaspartofthemaintenanceworkpackage,whichwillnotallowforworktobedoneon2CSH"MOV118iftheenclosureleaks.TheplantwillbeinlVlode5withthereactorvesselheadremoved,thecavityflooded,thespentfuelpoolgatesremoved,andthewaterlevelmaintainedwithinthelimitsofTechnicalSpecifications3.9.8and3.9.9.Therefore,HPCSwillnotberequiredtobeoperationalperTechnicalSpecification3.5.2.ThesuppressionpoolisnotrequiredtobeoperableduringthisactivityperTechnicalSpecification3.5.3.However,suppressionpoollevelwillbemaintainedbetweenelevation199'-6"and201'-0"toensureadequatenetpositivesuctionheadforemergencycorecoolingsystempumpsneededforShutdownSafetyCriteriaN+1.

SafetyEvaluationSummaryReportPage112of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.}9550(cont'd.}Thevalvepitwallelevationisequaltomaximumsuppressionpoolwaterlevel.Therefore,shouldthetemporaryenclosurefail,thevalvepit.willcontainleakagefromthesuppressionpool.Basedonthesizeofthevalvepit,thetotalleakagefromthesuppressionpoolwouldamounttoapproximately5,723gallons.Thiswouldresultinloweringthesuppressionpoofwaterlevelbyapproximately1-1/2".Therefore,theavailabilityofthesuppressionpoolforwaterinventorycontrolwillnotbeaffected.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage1'13of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:95-051Rev.0&1Mod.PN2Y94MX0138.3-15;Tables3.9A-12Sh8,6.2-56Sh2,8.3-1Sh17&20,8.3-2Sh16,17,20,8.3-4Sh8,15,8.3-5Sh1,2,3,4,8.3-6Sh2,3,4System:TitleofChange:ResidualHeatRemoval(RHS)NewLimitorqueActuatorsfor2RHSMOV15A/BandMOV25A/BDescriptionofChange:BasedonrevisedsizingcalculationsduetochangesmadetotheUnit2motor-operatedvalve(MOV)sizingcalculationmethodology,themotoroutputtorque/thrustcapabilityforcontainmentspayisolationvalves2RHS"MOV15A/BandMOV25A/Bunderreducedvoltageconditionwasnotadequatetoclosethevalvesagainstthemaximumexpecteddifferentialpressure./~Containmentsprayinjectionvalves2RHS"MOV15A/BandIVIOV25A/BrequiredreplacementoftheirSMB-1-40Limitorquemotor/actuatorswithSMB-2-80motor/actuators.Thenewmotor/actuatorsareratedat5.2HPand80ft-lbs.Thenewmotor/actuatorsmeetvalveoperationtestandevaluationsystem(VOTES)testingrequirementsperGenericLetter89-10andverifyoperationunderdesignbasesconditions.SafetyEvaluationSummary:ReplacementoftheLimitorquemotor/actuatorsforvalves2RHS"IVIOV15A/BandMOV25A/Bwithlargersizemotor/actuatorswillprovideanacceptabletorqueswitchsettingthrustrangetoallowthevalvetooperateasintendedduringdesignbasisconditions.ThisnewrangewillalsoaccommodatetheuseoftheVOTESdiagnostictestequipmentandallowforactuatordegradation.QualificationforthenewLimitorquemotor/actuatorshasbeenperformedtoensurecontinuedstructuralintegrityandoperabilityofthemodifiedvalveassembly.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage114of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:95-053ProcedureN2-EMP-GEN-6608.3-74,8.3-81;Table1.8-1Sh63BYSChangeofIEEE-Std484YearofIssueUnit2replacedtheDiv.Isafety-relateddcbatteryduringRefuelOutage3.TheDiv.IIbatterywasreplacedduringRefuelOutage4.Unit2iscommittedtocomplywithIEEE-Std484-1975,"IEEERecommendedPracticeforInstallationDesignandInstallationofLargeLeadStorageBatteriesforGeneratingStationsandSubstations,"fornewbatteryinstallation.Sincethetimeoftheinstallation,thestandardhasbeenrevisedseveraltimes.The1987issueisnowineffect.AccordingtoIEEE,thelatestissueofthestandardreflectsthecurrentstateoftheartandisrecommendedforuse.Thecriteriaprovidedinthe1987issueofthestandardgenerallyencompassorexceedthecriteriaofthe1975issue.Thenewcriteriawillincreasesafetyduringinstallationandtestingandreducetheinstallationtime.The1987issueprovidesawiderrangeofacceptancecriterionfortheintercellconnectorsresistancethatmayfacilitateinstallationandtesting.Thischangehasnoimpactonbatterycharacteristicsorperformance.Unit2dcsystemdesigncriterionistomaintain105Vdcminimumatthebatteryterminalsregardlessoftheintercellconnectionresistance.Thiscriterionissatisfied.SafetyEvaluationSummary:Theanalysisperformedrevealedthatthenewresistancecriteriaforintercellconnectionsdoesnotcompromisetheabilityofthebatterytoperformthesafety-relatedfunctionasdesignedandasdescribedintheUSAR.Engineeringcalculationperformedforthemostloadedbatterydeterminedthattheimpactofthenewresistancecriteriononthetotalbatteryvoltageduringdischargecycleisnegligible.Thebattery'scapacity,shortcircuitcapability,andheatreleasearenotaffectedeither.TechnicalSpecificationoperabilitycriteriaandsurveillancerequirementsarealsosatisfied.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage115of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:95-055Rev.0&1SimpleDesignChangeSC2-0107-949.2-14;Figure9.2-3C;ReactorBuildingClosedLoopCoolingWater(CCP)TitleofChange:DescriptionofChange:AlternateDrywellCoolingInordertoprovideanalternatedrywellcoolingsystemtobeusedduringoutages,thissimpledesignchangeaddedtwopermanentchanges:~Twopipingpenetrationsthroughthesoutheastquadrant,oftheReactorBuildingwall~New4"hoseconnectionontheCCPsupplyandreturnheadersDuringoutages,achiller{locatedintheyard)willbeconnectedtotheReactorBuildingpenetrations.HoseswillberoutedfromtheReactorBuildingpenetrationsthroughemergencyairlocktotheCCPconnectionsinthedrywell.SafetyEvaluationSummary:ThepermanentchangesaredesignedinaccordancewithdesigncriteriaforCCP.TheReactorBuildingpenetrationsaredesignedtoASMEIIINC-3600requirementsandincluderedundantspring-loadedcheckvalves/blindflangestoassurethatsecondarycontainmentintegrityismaintainedwhenalternatedrywellcoolingisoperating/secured.Thehoseswillberoutedsoastopreventphysicalinteractionwithsafety-relateditemsintheeventofconnectorfailure.Allpotentiallyaffectedessentialequipmentorsystemsaredesignedforfloodorspray.Theimplementationofthischangewillensurethatdrywelltemperatureiscontrolledduringanoutagesuchthatpersonnelstaytimesaremaximized.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage116of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:95-056SimpleDesignChangeSC2-0114-94Table6.2-56,Sh4High-PressureCoreSpray(CSH)ReplaceValveStem,DiscandOperatorGearSetfor2CSH~MOV105DescriptionofChange:Thissimpledesignchangechangedtheoperatorgearsetandreplacedthevalvestemanddiscforsafety-relatedmotor-operatedvalve(MOV)2CSH~MOV105.ThenewgearsetwillincreasetheactuatoroutputcapacityunderreducedvoltageconditionsandthenewstemanddiscwillprovidehigherASME.allowablestresses.Thesechanges,inturn,willincreasethethrustwindowtoaccommodatediagnostictestequipmentfortorqueswitchsettingasrequiredbytheGenericLetter89-10program.Asaresultoftheactuatorgearsetchange,thevalveclosuretimewillbeincreased.SafetyEvaluationSummary:AnengineeringevaluationoftheproposedchangeconcludedthatthereplacementofthestemanddiscwithahigherASMEallowableandanincreaseinthestroketimeduetothereplacementgearsetforthesubjectvalvehasnoimpactonthecontainmentisolationrequirementsandthehigh-pressurecorespraysystemoperationasdescribedintheUSAR.Thehigherstroketimeisstillwithinthedesignbasisofthesystemrequirements.TheMOVaswellasthesystemwillperformitsintendedsafetyfunctionduringandafteranaccident.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage117of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:9557SimpleDesignChangeSC2-0095-943B-2,3B-3,3B-5,3B-6,5.4-24;Table6.2-56Sh5System:TitleofChange:ReactorCoreIsolationCooling(ICS)ActuatorGearSetChangesfor2ICS"MOV121and2ICS"MOV128DescriptionofChange:Thischangereplacedtheactuatorgearsetsforthesubjectvalvesinordertoprovideasufficientthrustwindowforthevalveoperationtestandevaluationsystem(VOTES)diagnosticequipment.Asaresultofthegearsetchange,thestroketimeforthesevalveswillincreasefrom15secondsto30seconds.SafetyEvaluationSummary:Anengineeringreviewoftherequestedchange,whichincludestheeffectsofthechangeonthesystem'soperability,reliability,maintainability,structuralintegrityandsysteminteractions,hasfoundthattheimplementationofthischangewillhavenochangeonthesafetyoroperabilityoftheICSsystem.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage118of131SafetyEvaluationNo.:ImplementationDocumentNo.:95%59Rev.0L1ProceduresN2-TSP-CNT4001,N2-TSP-CNT-9003,N2-TDP-IIT201,N2-TTP-CNT-001USARAffectedPages:6.2-104;Figures6.2-71a,6.2-71b,6.2-73aSystem:TrtleofChange:N/APrimaryContainmentIntegratedLeakRateTestDescriptionofChange:Theproceduresfortheintegratedleakratetestwererevisedfor:theTypeAtesttobeperformedinRefuelingOutage4(RFO4).Thechangesareasfollows:Item1(Rev.0)ToallowtheuseofANSI/ANS-56.8-1987,ContainmentSystemLeakageTestingRequirements,forthe"MassPoint"method.NUREG-1047,SafetyEvaluationReportrelatedtotheoperationofNineMilePointNuclearStation,UnitNo.2,Section6.2.6,statestheTypeAtestdatawillbeanalyzedusingthe"MassPoint"methodinANSI/ANS-56.8-1981.The"MassPoint"methodwillstillbeusedtoanalyzetheTypeAtestdata,butamorecurrentrevisiontoANSI/ANS-56.8wasused.Thereasonforthechangeisthat10CFR50AppendixJwasrevisedin1988toacceptthe"MassPoint"methoddescribedinANSI/ANS-56.8-1987butNineMilePointdidnotupdatethelicensingbasetoreflectthechangein10CFR50AppendixJ.Item2(Rev.0)ToallowtheinstallationanduseoftemporaryinstrumentationtomonitordrywellparametersduringtheTypeAtest.USARSection6.2.6statesthattwoindependentquartzdigital-typeabsolutepressuremanometersareconnectedtotheleakagemonitoringsystem(LMS)tomonitorprimarycontainmentpressureduringtheTypeAtest.USARSection6.2.6alsostatesthat18temperatureelementsand6humidityanalyzersareprovidedinthecontainmentatmospheremonitoringsystem(ClVIS)tomonitordry-bulbanddewpointtemperatures,respectively.Thetemporaryinstrumentationwillbeplacedinthesamelocationsasthepermanentplantequipment.

SafetyEvaluationSummaryReportPage119of131SafetyEvaluationNo.:DescriptionofChange:(cont'd.)95-059Rev.0L1(cont'd.)ThereasonforthechangeisthattheinstrumentationprovidesthetestdatafortheTypeAtest.Advancesinelectronictechnologyhaveresultedinmorereliableandreducedinstallationtimesoverconventionalinstrumentation.Theresultisreducedcostsinman-hoursandman-remduringtheinstallationandremovalphases.Item3(Rev.1)ProcedureN2-TSP-CNT-@001isbeingrevisedtoallowtheinstallationoftemporarydepressurizationflangeson2-CPS-014-9-4andpipingpenetration2PCB"Z74.TheseflangeswillbeusedduringtheTypeAtesttoreduceprimarycontainmentpressure.Thereasonforthechangeistoallowasafeandcontrolleddepressurizationoftheprimarycontainment.SafetyEvaluationSummary:Thissafetyevaluationhasconcludedthatanunreviewedsafetyquestiondoesnotexistasaresultofevaluatinga24-hourTypeAleakagerateinaccordancewiththe"MassPoint"methoddescribedinANSI/ANS-56.8-1987.ANSI/ANS-56.8-1987providesrecommendationsfortheTypeAtestinstrumentation.Theserecommendationsincludecalibrationrequirements,in-situchecks,andminimumquantitiesandlosscriteria.N2-TTP-CNT-001andN2-TSP-CNT4001werewrittentoensurethattherecommendationsofANSI/ANS-56.8-1987aremet.Also,thetemporaryinstrumentationwillbeplacedinthecorrespondinglocationsofthepermanentplantequipment.Therefore,anunreviewedsafetyquestiondoesnotexistasaresultofusingtemporaryinstrumentationtomonitorprimarycontainmentparametersduringtheTypeAtest.ThetemporaryflangeswillbeinstalledonlyinOperationalConditions4or5andareboundedbytheUSARloadcombinationsandstresslimitsforpipesandpipepenetrations.Therefore,thissafetyevaluationhasconcludedthatanunreviewedsafetyquestiondoesnotexistasaresultofconnectingtemporaryflangesto2-CPS-014-9-4and2PCBZ74.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage120of131SafetyEvaluationNo.:"ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:'95-060SimpleDesignChangeSC2-0028-9510.4-30;Figure8.3-1Feedwater(FWS)FeedwaterPumpMotorsHPUpgradeOnJanuary17,1995,feedwaterpumpmotor2FWS-M1Btrippedwhilerunningatapproximatelyfullpower.Thetripoccurredduetotheactionofthemotorrelayprotection.Theinvestigationoftheeventrevealedthattheinsulationofthestatorwindingofthemotorfailedcausingtheactionoftherelayprotectionandmotortrip.ThemotorwassenttoIVlonarchElectricServiceCo.forrepair.RootcauseevaluationperformedbyMonarchCo.identifiedthatthemotorinsulationfailureoccurredduetocoronaerosionofgroundwallinsulation.ThemotorwasrewoundandreturnedtoUnit2.Intheprocessofrepair,anewtypeofinsulationwasusedandtheHPratingofthemotorwasincreasedfrom12,000to14,100.ISincethemotors2FWS-IVl1Aand2FWS-M1Cmayalsobesusceptibleto,thesamemodeoffailure,thedecisionwasmadetorewindthesemotorsandupgradetheHPrating.SafetyEvaluationSummary:TheupgradingofHPofthefeedwaterpumpmotorssatisfiesfunctionalrequirementsofthesystem.Theperformanceofthepumpsisnotaffected.ThesystemandcomponentswillperformasdesignedandasdescribedintheUSAR.TheupgradedHPofthemotorsisadequateforthepoweruprateoftheplant.TheupgradedHPofthemotorsdoesnotadverselyaffectthemechanicalinterfacesystems.AccordingtoNMPCMechanicalEngineeringevaluation,themaximumHPrequirementforthepumpforpoweruprateconditionis13,190HP.Therefore,theupgraded14,100HPisadequate.Theelectricalequipmentsuchascables,circuitbreakers,currenttransformers,and.relaysratingswereevaluatedfortheupgradedHPofthemotorsandwerefoundtobeadequate.

SafetyEvaluationSummaryReportPage121of131SafetyEvaluationNo.:SafetyEvaluationSummary:(cont'd.)95-060(cont'd.)Thefeedwaterpumpsarenonsafety-relatedcomponentsandarenotrequiredforsafeshutdownoftheplant.TheupgradedHPofthemotorshasnoimpactonsafety-relatedsystemsandcomponents.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluation"SummaryReportPage122of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:95-062SimpleDesignChangeSC2-0029-95Appendix9CTable3-2MHRTitleofChange:AlternateMeansfortheSRVRemoval(Replacing2MHR-CRN200With2MHR-CRN200Aand2MHR-CRN200B)DescriptionofChange:Thepurposeofthissimpledesignchangeistoprovideaninterchangeablehandlingsystemfortheremovalandreplacementofthesafetyreliefvalves(SRVs).Hoists2IVIHR-CRN200Aand2MHR-CRN200Bwillreplacecrane2MHR-CRN200fortheSRVremovalactivity.TheSRVswereoriginallyshippedtothe'siteinthehorizontalpositionandcouldbehandledwithasingle4-tonhoist.TheSRVsnowarriveintheverticalposition,requiringasecondhoisttosafelyremovethevalvesfromtheirshippingcontainerandrepositionthevalveintothehorizontalposition.UponcompletionoftheremovalandreplacementoftheSRVs,hoists2MHR-CRN200Aand2MHR-CRN200Bcanberemovedfromthemonorailandcrane2MHR-'CRN200canbereinstalled.SafetyEvaluationSummary:Theimprovementbeingmadebythissimpledesignchangewiththeuseofalternatehoists2MHR-CRN200Aand2IVIHR-CRN200Bintheplaceofcrane2IVIHR-CRN200meetstherequirementsoftheseismicevaluationofnonsafety-relatedcomponentsinsafety-relatedareasanddoesnotaffectthesafetyandreliabilityofUnit2.Thereisnosafety-relatedequipmentthatwouldbeaffectedbyaloaddropinvolvinghoists2MHR-CRN200Aor2MHR-CRN200B.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage123of131SafetyEvaluationNo.:ImplementationDocumentNo.:95-064CalculationsECA44Rev.11,EC-045,Rev.7,EC-046Rev.5,EC-097Rev.2USARAffectedPages:System:'itleofChange:,8.3-76;Tables8.3-11through8.3-15BYS,BWSNonsafety-RelatedBatteriesLoadProfileUpdateDescriptionofChange:Thebatterysizingcalculationswereupdatedtoreflectas-builtdcloadsofthenonsafety-relatedsystem,andtoaccountfortheplantmodificationwhichwasimplementedwithoutrevisingthesecalculations.SafetyEvaluationSummary:Therevisedbatterysizingcalculationsconcludethatthechangeofthedcloadsiswithinthecapabilitiesofthebatteriesandthechargers.Thenonsafety-relateddcsystemwillcontinuetoperformasdesignedandasdescribedintheUSAR,withtheupdatedloadseachbatteryisstillcapableofperformingitsdutycyclefollowingthelossofchargerwhilefullychargedat65F,andwithcapacitydeterioratedto80percent.Eachbatterycanstartandoperateallrequiredloadsforthedurationofthedischargecycleaccordingtothebatteryloadprofilewithoutbatteryterminalvoltagefallingbelow105Vfor125Vdcsystem,and21Vfor24Vdcsyste~.Eachbatterychargercanstillsupplythecontinuousupdatedloadonthebatterywhilerechargingthebatteryfromthedesignedminimumchargestatetothefullychargedstateinlessthan24hours.Theimpactofthischangeontheplantresponsetostationblackoutevent(SBO)hasalsobeenevaluated.Basedonadditionalbatterycalculationsperformedforthenewrevisedloads,theconclusionismadethatnonsafety-relatedbatteriesstillmeetthe4-hourcapabilityrequirementasspecifiedinNUMARC87-00andRegulatoryGuide1.155,andasdemonstratedintheSBOstudyperformedbyGeneralElectric.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage124of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:DescriptionofChange:95-066TemporaryMod.95-011N/AReactorCoreIsolationCooling(ICS)ManualOperationof2ICS"AOV130TheICSsystemisdesignedtoassuresufficientreactorwaterinventoryismaintainedinthereactorvesseltopermitadequatereactorcorecooling.Thistemporarymodificationmanuallyopenedvalve2ICS"AOV130andmaintaineditintheopenpositionuntilthenextsystemoutagebecausethevalveactuatorisnotcapableofkeepingthevalveopenduetodiaphragmfailure.ThisvalveisoneofthetwonormallyopenvalvesinseriesonthedrainpotdrainlineofICSen-routetotheReactorBuildingequipmentdrainsystem(DER).SafetyEvaluationSummary:Basedonareviewofthesystemdesignbasesandconfiguration,thereislnospecificreasonintheUSARforthedoubleisolationarrangement.AsystemdesignreviewbyGeneralElectricdeterminedthatdoubleisolationarrangementwasintendedtoprovideredundancyofthedrainvalveclosureduringICSoperation.ThisredundancywastominimizethespreadofcontaminationandradiationreleaseintheReactorBuildingincaseofhighradiationlevelsinthesteamsupplylinetotheICSturbine.Basedonthereviewsperformed,ithasbeendeterminedthatthisisolationcapabilitycanstillbemaintainedviaasinglevalvewithnoimpactonnuclearsafety.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage125of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:95-068ProcedureN2-MPM-GEN-R9019.1-39,9.1-41FHPTitleofChange:RevisiontoFuelPoolGateRemovalProcessinUSARSection9.1DescriptionofChange:ThischangerevisedtheUSARtoindicatetheoptiontoremoveboththeinnerandtheouterspentfuelpoolgatesaftercompletionofflood-upactivitiespriortorefueling,asdescribedinprocedureN2-MPM-GEN-R901,Rev.1.SafetyEvaluationSummary:TherevisionoftheUSARtoindicatetheoptiontorem'oveboththeinnerandtheouterspentfuelpoolgatesafterthecompletionofflood-upactivitiesresultsinamoreconservativeplantconfigurationduringreactorvesseldisassemblyactivities.ThiswasperformedinaccordancewiththeGuidelinesfortheControlofHeavyLoads(NUREG-0612)asdescribedinUSARAppendix9C.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage126of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:9569N/AN/A345-kVTransmissionOutput,115-kV.OffsitePowerSourcesTitleofChange:ScribaStation,345-kV8BusConnectionDescriptionofChange:Asixth345-kVtransmissionlinewasaddedtoScribeStationandconnectedtothe345-kYAbusinJune1994.ScribeStationisa345-kVbreakerand1/2stationwithanAandaBbus.Thenewtransmissionlinewasconnectedtothe345-kVBbus./SafetyEvaluationSummary:Theplantwillbeshutdownforrefuelduringtheperiodwhentheworkwilltakeplace.AllapplicableTechnicalSpecificationrequirementswillbemet.Theworkandtheschedulehavebeenreviewedforsafeshutdowncriteria.iBasedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage127of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:95%71N/AA.0-1,A.4.3-1,A.4.4-3,A.5.2-1,A.5.2-2,A.5.2%,A.6-1,A.6-2,A.15.0-2,A.15.0-7,A.15.1%,A.15.1-9,A.15.2-5,A.15.2-.12,A.15.4-9,A.15B-1,A.15D-1;TablesA.5.2-1,A.5.2-2,A.6-2,A.15.0-4Sh1,2,3System:TitleofChange:DescriptionofChange:VariousOper'ationofNMP2Reload4/Cycle5ThischangeaddednewfuelbundlesandestablishedanewcoreloadingpatternforReload4/Cycle5operationofUnit2.Twohundredforty-eight(248)newfuelbundlesoftheGE11designwereloaded.Also,32twice-burnedGE6BbundlesthatweredischargedattheendofReload1/Cycle2werere-inserted.All124oftheGE6BbundlesfromReload3/Cycle4,and156of196GE9Bbundles(PSCWB299),weredischargedtothespentfuelpool.Variousevaluationsandanalyseswereperformedtoestablishappropriateoperatinglimitsforthereloadcore.Thesecycle-specificlimitsweredocumentedintheCoreOperatingLimitsReport.SafetyEvaluationSummary:ThereloadanalysesandevaluationsareperformedbasedontheGeneralElectricStandardApplicationforReactorFuel,NEDE-24011-P-A-10andNEDE24011-P-A-10-US(GESTARII).Thisdocumentdescribesthefuellicensingacceptancecriteria;thefuelthermal-mechanical,nuclear,andthermal-hydraulicanalysesbases;andthesafetyanalysismethodology.ForReload4,theevaluationsincludedtransientsandaccidentslikelytolimitoperationbecauseofminimumcriticalpowerratioconsiderations;overpressurizationevents;loss-ofwoolantaccident;andstabilityanalysis.Appropriateconsiderationofequipmentoutofservicewasincluded.Limitsonplantoperationwereestablishedtoassurethatapplicablefuelandreactorcoolantsystemsafetylimitsarenotexceeded.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage128of131SafetyEvaluationNo.:ImplementationDocumentNo.:95%77CalculationsH21C%38-01C,H21CA43-00B,A10.1-E-130USARAffectedPages:15.6-13;Tables15.6-13Sh10&11,15.6-16bSystem:TitleofChange:ResidualHeat(RHS)Revise/DeletetheLeakRateAcceptanceCriteriaandTestFrequencyforRHSValves2RHS"!VIOV142,MOV149,SOV35A/BandSOV36A/BDescriptionofChange:Thischangerevisedtheleakrateacceptancecriteriaandtestfrequencyforvalves2RHS"MOV142,MOV149,SOV35A/B,andSOV36A/B.Theleakageacceptancecriteriaoflessthanorequalto1gpmtimesthenumberofhydrostaticallytestedvalveswasincreasedto20gpmfor2RHS"SOV35A/BandSOV36A/B,andto10gpmfor2RHS"MOV142andMOV149atnormalsystemoperatingpressure.Thetestfrequencywasrevisedfromonceevery18monthstoonceevery2years.LeaktestingrequirementsforthevalvesremainintheISTtestingprogram;however,changestoNIP-DES-04(byrevisingthefootnote"m")andsupportingoperationsprocedureswererequiredtoimplementthenewleakagecriteria.ImplementationofsimpledesignchangeSC2-0046-95toinstallASMEClass2reducerstoreplacetheleakagecontrolfunctionofthesolenoid-operatedvalves(SOVs)wasdeterminedtobeanacceptablealternativetoleaktestingtheSOVs.SafetyEvaluationSummary:Thissafetyevaluationhasconcludedthatanunreviewedsafetyquestiondoesnotresultfromtheproposedchange.ThisconclusionisbasedontheabilitytodemonstrateRHSsystemleakageboundaryintegritybysatisfyingthefunctionalrequirementsofthelow-pressurecoolantinjectionsystemwiththeincreasedleakage,anddeterminingthattheconsequencesoftheincreasedleakageintosecondarycontainmentpost-LOCAareradiologicallyacceptable.

SafetyEvaluationSummaryReportPage129of131SafetyEvaluationNo.:ImplementationDocumentNo.:95-078ProcedureN2-FHP-021USARAffectedPages:System:TitleofChange:N/AFNR,FNS,GTSRevisiontoControlBladeMovementProcedureDescriptionofChange:ThissafetyevaluationwaswrittentoreviseprocedureN2-FHP-021,"ControlRodUncoupling,Removal,andInstallation."Thisrevisionallowscontrolroduncoupling,removal,andinstallationwithoutsecondarycontainmentintegrityandSGTSoperability,providedsevendayshaveelapsedsincereactorshutdownandallmovementsareofobjectstotallinglessthan617pounds(theestimatedweightofafuelbundle).SafetyEvaluationSummary:ITherevisedcontrolblademovementprocedureprovidesthesamelevelof'safetytotheControlRoomandpublicaswaspreviouslyavailable.ThechangedoesnotalterTechnicalSpecifications,orguidanceprovidedbythevendor.RadiologicalanalysishasshownthattheproposalallowsUnit2tomeet10CFRIOOlimitsandremainincompliancewiththeplantsafetyanalysisreport.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage130of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:95%79DER2-95-11838.3-11,8.3-12VBBReviseUPS2VBB-UPS1C/1DAcceptableVoltageOutputCriteriaDescriptionofChange:Uninterruptiblepowersupplies(UPSs)2VBB-UPS1Cand2VBB-UPS1Dfeedselectedlightingandcommunicationsloads.TheoriginalUPSunitsinstalledduringconstructionwerepurchasedfromExide.In1991,theseunitswerereplacedwithunitspurchasedfromHDRunderModificationPN2Y89MX042.Duringthereplacement,itwasdiscoveredthattheseunitsdidnotmeettheoutputvoltageacceptancecriteriaofSpecificationE-147,i.e.,+2%ofoutputvoltagevariation.Engineeringevaluationofthedeficiencywasperformedandunitswereacceptedassuppliedbythevendorwithvoltageoutputacceptableupto+3%basedonthetypeofloadstheseunitsarefeeding.TheengineeringspecificationE-147wasrevisedtoallowthenewacceptancecriteriaforUPSs2VBB-UPS1Cand1D.SafetyEvaluationSummary:Theproposedchangeofacceptingthe+3%ofoutputvoltagevariationdoesnotaffecttheperformanceoftheconnectedloads.ThepurposeofspecifyingpreciseoutputvoltageregulationfortheUPSsistomeettherequirementsoftheprecisioninstrumentationandcontrolequipmentwhichtheyfeed.Mostofthisequipmentwillrequirepowersupplyvoltagevariationnottoexceed2%.ThetwoUPSsinvolvedinthischange,2VBB-UPS1Cand2VBB-UPS1Dprovidepowersupplyonlytotheessentiallighting,egresslighting,andpageparty/publicaddress(PP/PA)communicationsystemloads.Theessentialandegresslightingsystemequipmentaredesignedfor+10%supplyvoltagevariation.ThePP/PAcommunicationsystemequipmentaredesignedfor90-140VasshowninGaitronicspecification.Therefore,anoutputvoltagevariationof+3%for2VBB-UPS1Cand2VBB-UPS1Dwillnotadverselyaffectoperationofanyoftheirconnectedequipmentandisacceptable.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage131of131SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:95-080Rev.0L1ProcedureN2-PM-S0123C-25,3C-28,3C-29System:N/ATitleofChange:ChangetheVisualLeak/FloodDetectionWalkdownstoaMinimumofOnceperCalendarDayDescriptionofChange:AsdepictedintheUSAR,areawalkdownsbyplantpersonnelforvisualleak/flooddetectionwereperformedonceevery8-hourshift.Inthepast,plantoperationspersonnelwerescheduledforthree8-hourshifts.Plantoperationshasrevisedtheirshiftworkschedulesfromthree8-hourshiftstotwo12-hourshifts.Calculationswererevisedtoreflecttheincreaseinwaterlevelsduetothechangeofthevisualleak/flooddetectionsfrom12hourstoaminimumofoncepercalendarday,nottoexceeda24-hourtimeperiod(36-hourtimeperiodfortheControlBuildingbasement)betweeninspections.SafetyEvaluationSummary:TherevisiontotheUSARtochangethetimeintervalsofthevisualflood/leakdetectionwalkdownsfromevery125hourstoaminimumofoncepercalendarday,nottoexceeda24-hourtimeperiod(36-hourtimeperiodfortheControlBuildingbasement)betweeninspections,doesnotaffectthesafetyandreliabilityofUnit2.Thelossofsafety-relatedequipmentduetofloodinghasalreadybeenevaluatedintheUSARAppendix3CSpray/FloodingEvaluationandwillnotbechanged.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

S-VI/

NINEMILEPOINTNUCLEARSTATION-UNIT2VNIAGARAUMOHAWKREVISION8

NineMilePointUnit2FSARINSERTIONINSTRUCTIONSThefollowinginstructionsarefortheinsertionofthecurrentrevisionintotheNineMilePointUnit2USAR.Removepages,tables,and/orfigureslistedintheREMOVEcolumnandreplacethemwiththepages,tables,and/orfigureslistedintheINSERTcolumn.Dashes(-)ineithercolumnindicatenoactionrequired.USARRevision8FII-1November1995 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NineMilePointUnit2FSAR,,INSERTIONINSTRUCTIONSVOLUME1INERTi/iiiii/ivv/-i/iiiii/ivv/-1-i/ii1-v/vi1.1-1/2F1.1-11.2-5/61.2-13/141.2-21/22F1.2-1F1.2-7(Sh2of2)F1.2-11(Sh3of4)F1.2-40T1.3-1(Sh1of3)T1.3-2(Sh1of2)T1.3-3(Sh1of2)T1.3-4T1.3-5(Sh1of2)'T1.3-6T1.3-7T1.3-8(Sh1of2)T1.3-9(Sh1of8)1-i/ii1-v/vi1.1-1/2F1.1-11.2-5/61.2-13/141.2-21/22F1.2-1F1.2-7(Sh2of2)F1.2-11(Sh3of4)F1.2-40T1.3-1(Sh1of3)T1.3-2(Sh1of2)T1.3-3(Sh1of2)T1.3-4T1.3-5(Sh1of2)T1.3-6T1.3-7T1.3-8(Sh1of2)T1.3-9(Sh1of8)USARRevision8FII-3November1995 NineMilePointUnit2FSARINSERTIONINSTRUCTIONSVOLUME2i/iiiii/ivv/-T1.8-1(Sh1/2)T1.8-1(Sh51/52)T1.8-1(Sh53/54)T1.8-1(Sh63/64)T1.8-1(Sh75/76)T1.8-1(Sh77/78)T1.8-2(Sh5/6)T1.9-1(Sh35/36)T1.9-1(Sh47/48)T1.9-1(Sh49/50)1.10-47/481.10-57/58TII.B.3-1(Sh1and2of2)1.10-121/1221.11-1/-T1.11-1(Sh1thru6of6)~$ERTi/iiiii/ivv/-T1.8-1(Sh1/la)T1.8-1(Sh1b/2)T1.8-1(Sh51/52)T1.8-1(Sh53/54)T1.8-1(Sh63/64)T1.8-1(Sh75/76)T1.8-1(Sh77/78)T1.8-2(Sh5/6)T1.9-1(Sh35/36)T1.9-1(Sh47/48)T1.9-1(Sh49/50)1.10-47/481.10-48a/48b1.10-57/581.10-58a/58bTII.B.3-1(Sh1and2of2)1.10-121/1221.11-1/-T1.11-1(Sh1thru6of6)USARRevision8November1995 NineMilePointUnit2FSAR,.INSERTIONINSTRUCTIONSVOLUME3INERTi/iiiii/ivv/-2-xiii/xivi/iiiii/ivv/-2-xDj/uvF2.1-2F2.1-22.2-1/22.2-3/42.2-7/8T2.2-1thruT2.2-3T2.2-5(Sh1and2of2)T2.2-6T2.3-4AT2.3-62.2-1/22.2-3/42.2-7/8T2.2-1thruT2.2-3T2.2-5(Sh1and2of2)T2.2-6T2.3-4AT2.3-62.4-1/2T2.4-6T2.4-7T2.4-9thruT2.4-11T2.4-13thruT2.4-15F2.4-12.4-1/la2.4-1b/2T2.4-6T2.4-7T2.4-9thruT2.4-11T2.4-13thruT2.4-15F2.4-1T2.5-3(Sh1thru3of3)T2.5-4T2.5-6thruT2.5-8T2.5-10thruT2.5-13T2.5-15thruT2.5-19T2.5-21thruT2.5-23T2.5-25thruT2.5-27T2.5-28AT2.5-30thruT2.5-32T2.5-45T2.5-48AthruT2.548CT2.5-3(Sh1thru3of3)T2.5-4T2.5-6thruT2.5-8T2.5-10thruT2.5-13T2.5-15thruT2.5-19T2.5-21thruT2.5-23T2.5-25thruT2.5-27T2.5-28AT2.5-30thruT2.5-32T2.5-45T2.5-48AthruT2.5-48CUSARRevision8FII-5November1995 NineMilePointUnit2FSARINSERTIONINSTRUCTIONSVOLUME4/EM(~VEi/iiiii/ivv/-~$ERTi/iiiii/ivv/-USARRevision8FII-6November1995 NineMilePointUnit2FSARINSERTIONINSTRUCTIONSVOLUME5R~EMVBi/iiiii/ivv/-~$ERTi/iiiii/ivv/-USARRevision8FII-7November1995 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NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER12PageT=TableF=FicFureRevisionNumberPageT=TableFFicFurePageRevisionT=TableNumberF=FicFureRevisionNumberFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFF12.3-2412.3-2512.3-2612'-2712.3-2812.3-2912.3-3012.3-30a12'-3112.3-3212'-3312.3-3412.3-3512'-3612~33712'-38123-3912.3-4012.3-4112.3-4212.3-4312.3-4412.3-4512.3-4612.3-4712'-4812'-4912'-5012.3-5112.3-5212.3-5312.3-5412.3-5512.3-5612.3-5712.3-5812.3-5912'-6012.3-6112.3-6212.3-6312.3-63a12.3-6412.3-6512.3-6612.3-67R02R02R02R02R02R02R03R02R02R02R02R05R02R07R02R02R02ROSR02R05R02R02R07R05R07R02R02R04R07R02R02R03R02R02R02R02R02R02R02R02R03R02R02R02R02ROOF12'-68F12.3-69Sh1F12.3-69Sh2F12.3-69S?I3F12.3-69S?1412.4-112.4-212.4-312'-412.4-512.4-6T12.4-1T12.4-2T12.4-3T12'-4T12.4-5T12'-6T12.4-7S?11T12'-7S?12T12.4-8T124-9T12.4-10T12.4-11T12.4-12T12.4-1312.5-112.5-212.5-312.5-412.5-512.5-612.5-712.5-812.5-912.5-1012'-1112.5-1212.5-1312.5-1412.5-1512.5-16125-1712.5-18T12'-1AOOROOR05ROOR05R08ROSR08ROSROSR08ROSROSROSROSROSROSA20A20A20A20ROOA20ROSR08R07R07R07R07R07R07R07R07R07R07R07R07R07R07R07R07R07R07R01T12'-2T12.5-3T12.5-4ROOR08R08USARRevision8EP12-2November1995

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NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER14PageT=TableF=FicFcreRevisionNumberPageT=TableFFicFFreRevisionNumberPageT=TableFFicFureRevisionNumberTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTT14~2-5714.2-5814'-5814.2-5914.2-5914.2-6014'-6114.2-6114.2-6214.2-6214.2-6314.2-6314.2-6414.2-6414.2-6514.2-6514'-6614.2-6714.2-6714.2-6814.2-6814.2-6914.2-6914.2-7014.2-7114.2-7114.2-7214.2-7214.2-7314.2-7314.2-7414.2-7514.2-7614'-7614.2-7714.2-7714.2-7814.2-7914'-7914.2-8014.2-8014.2-8114'-8114.2-8214.2-8214.2-83ShShShShShShShShshShShShShShShshShshShShShShShShShShShshShShShShShShShShshShSh212121212121212121212121212121212-.121212A22A24A22R08R08ROSA24A22A24A22A28A28R08R08R08R08ROSA24A22A24A22R08R08ROSA24A22A24A22R08ROSROSR08ROSR08A24A28ROSR08R08ROSR08R08R08A24A22ROSR08ROSR08R08R08ROSROSROSROSROSROSROSA24A22R08R08ROSR08A24A22Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2A24A24R08R08ROSR08R08Sh1R08Sh2ROSROSSh1A24Sh2A22Sh1A24Sh2A22Sh1A26Sh2A22A24Sh1Sh2A22R08Sh1Sh2A25A25R08Sh1Sh2A24A22R08A24T14.2-84T14.2-85T14.2-86T14.2-86T14.2-87T14.2-88T14.2-89T14.2-90T14.2-91T14.2-92T14.2-93T14.2-94T14.2-95T14.2-95T14.2-96T14.2-97T14.2-98T14.2-99T14.2-100T14.2-100T14.2-101T14.2-101T14.2-102T14.2-103T14.2-103T14.2-104T14.2-104T14.2-105T14.2-105T14.2-106T14.2-107T14.2-107T14.2-108T14.2-108T14.2-109T14.2-109T14.2-110T14.2-110T14.2-111T14.2-112T14.2-112T142-113T14.2-114T14.2-114T14.2-115T14.2-116"'TTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTT14.2-11714.2-11714.2-11814.2-11814.2-11914.2-11914.2-12014.2-12014.2-12114.2-12114.2-12214.2-12214'-12314.2-12314.2-124142-12414.2-12514.2-125142-12514'-126142-12614.2-12614.2-12714.2-12714.2-12814.2-12814-2-12914.2-12914.2-12914'-130142-13014.2-13114.2-13214.2-20114.2-20114.2-20214.2-20214'-20314.2-20314.2-20414.2-20414.2-20514.2-20614.2-20614.2-20614'-206Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh3Sh1Sh2Sh2aA24A22A24A22A24A22A24A22A24A22A24A22A24A22A22A22A24A22A22A24A22Sh1Sh2Sh1Sh2Sh1Sh2A22A22A22A22A22A24Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2Sh3Sh3aA22A22A24A26ROOA22ROOA28A08A28A22ROOA12A12ROOROOSh2aUSARRevisionEP14-2November1995

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NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER18PageT=TableF=FicFureRevisionNumberPageT=TableF=FicFurePageRevisionT=TableNumberFFicFureRevisionNumber18-i18-ii18-iii18-ivR08R08R08R08F18~2-6S?12R03F18.2-7R03F18.2-8R0318'-1'8.1-218'-3R08R08R0818.2-118.2-218.2-318.2-418.2-5182-618.2-718.2-818'-918.2-1018.2-1118.2-1218.2-1318.2-1418.2-1518.2-16T18.2-1T18.2-2T18'-2T18.'2-2T18.2-2T18.2-2T182-2T18.2-2T18.2-2T18.2-2T18.2-2T18.2-2T18.2-2T18'-2T18.2-2F18.2-1F18.2-2F18.2-3F18.2-4F18'-5F18.2-6S?11S?12Sh3S114Sh5S116S?17S?18S119S1110S?111S?112Sh13Sh14Sh1R08R08R08R08R08R08R08R08R08R08R08R08R08R08R08R08R03R03R03R03R03R03R03R03R05R05R04R03R05R05R05R03R03R03R03R03R03USARRevision8EP18-1November1995

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UPDTEDFETYNLYIENINEMILEPOINTNUCLEARSTATION-UNIT27NIAGARAUMOHAWK

NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANT1~11~21'1.41.51.61'1.81.91.101.111~121~13CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2.12.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2ZAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13.23'3.4DESIGNOFSTRUCTURES/COMPONENTS'QUIPMENTSANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3'1Appendixes3Athrough3EMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipment9,101010101012121212CHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER55.15'5.35.4Appendixes5A,REACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1212121212121212131313131313USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136.16.26.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77.17.27.37.47.57.67.7AppendixesCHAPTER88.18.28.3Appendix8A7A,INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystem15151515161616161616161616,1717CHAPTER99.19.29.39'9.5Appendixes9A,CHAPTER1010.110.210.3AUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem1717181920,2121,222323232324USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)~eectic10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411~111211.311.411.5Appendix11ACHAPTER1212.112.212~312.412'CHAPTER1313.113'13'13'13.513.6CHAPTER1414.114.2,14.3CHAPTER1515.0SourceTerms-Liquid.Waste.Management-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral2424-2525'52525252525262626262626262626262626,27272727USARRevision8ivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215.315.415.515.615.715.8Appendices15ACHAPTER16TitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSVolume27272727272727272828CHAPTER1717.017.117.2CHAPTER1818.118.2APPENDIXAAPPENDIXBQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE282828282828282828USARRevision8November1995

NineMilePointUnit2FSARCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTTABLEOFCONTENTS~SectioTitleINTRODUCTIONPacae1'-11.21.2.111.2.111.2.11.2.11.2.11.2.1~1~2~2~1~3~3~1~3~2.3.31.2.1.3.71.2.1.3.811'1.2.2.21.2.2.31.2.31.2'1.2.4.11.2.4.21.2.4.31.41.2.4.51.2.4.61.2.51.2.5'1.2.5.21.2.5.31.2.61.2.71.2'.3.41.2.1.3.51.2.1GENERALPLANTDESCRIPTIONPrincipalDesignCriteriaGeneralCriteriaPowerGenerationDesignCriteriaSafetyDesignCriteriaSystem-by-SystemApproachNuclearSystemCriteriaPowerConversionSystemsCriteriaElectricalPowerSystemsDesignCriteriaRadwasteSystemDesignCriteriaAuxiliarySystemsDesignCriteriaShieldingandAccessControlDesign,CriteriaNuclearSafetySystemsandEngineeredSafeguardsDesignCriteriaProcessControlSystemDesignCriteriaSiteDescriptionSiteCharacteristics:SiteLocationandSizeAccesstotheSiteDescriptionoftheSiteandEnvironsStructuresandEquipmentNuclearSteamSupplySystemReactorCoreandControlRodsReactorVesselandInternalsReactorRecirculationSystemResidualHeatRemovalSystemReactorWaterCleanupSystemNuclearLeakDetectionSystemElectrical,Instrumentation,andControlSystemsElectricalPowerSystemNuclearSystemProcessControlandInstrumentationPowerConversionSystemsProcessControlandInstrumentationRadioactiveWasteSystemFuelHandlingandStorageSystems1~211.2-11~211.2-21\231.2-61.2-61~271~271~271.2-81.2-81.2-81.2-91.2-101'-101.2-111.2-111.2-111~2131~2131'-131.2-141.2-141.2-151.2-151.2-151.2-151'-171.2-181.2-191.2-20USARRevision8November1995 NineMilePointUnit2FSARCHAPTER1TABLEOFCONTENTS(Cont'd.)Section1.2.7.11.2.7.21.2.7.31.2.7.41.2.81.2.8.11.2.8.21.2.8.31.2.8.41.2.8.51.2.8.61.2.8.71.2.8.81.2.8.91.2.91.2.9.11.2.9.21.2.9.31.2.9.41.2.9.51:2.9.61.2.9.71.2.9.81.2.9.91.2.9.101.2.9.111.2.9.121.2.9.131.2.9.141.2.9.151.2.9.161.2.9.171.2.9.181.2.9.191.2.9.20TitleNewFuelStorageSpentFuelStorageFuelHandlingSystemSpentFuelPoolCoolingandCleanupSystemPowerConversionSystemTurbineGeneratorMainSteamSystemMainCondenserMainCondenserAirRemovalSystemTurbineGlandSealingSystemSteamBypassSystemandPressureControlSystemCirculatingWaterSystemCondensateandFeedwaterSystemsCondensateDemineralizerSystemNuclearSafetySystemsandEngineeredSafetyFeaturesReactorProtectionSystemNeutronMonitoringSystemControlRodDriveSystemControlRodDriveHousingSupportsControlRodVelocityLimiterNuclearSystemPressureReliefSystemReactorCoreIsolationCoolingSystemEmergencyCoreCoolingSystemsContainmentSystemsContainmentandReactorVesselIsolationControlSystemMainSteamIsolationValves(MSIV)MainSteamFlowRestrictorsMainSteamRadiationMonitoringSystemResidualHeatRemovalSystemVentilationExhaustRadiationMonitoringSystemStandbyGasTreatmentSystemSafety-RelatedElectricalPowerSystemsStandbyLiquidControlSystemSafeShutdownfromOutsidetheControlRoomMainControlRoomHeating,VentilatingandAirConditioningSystemPacae1.2-201.2-201.2-201.2-201.2-211~2211.2-211~2211.2-211.2-221.2-221.2-221.2-221.2-231~2231~2231~2231~2231.2-241.2-24/1.2-241.2-241.2-241.2-251.2-261.2-261.2-261~2271.2-271.2-271.2-271.2-271.2-281.2-281.2-29'SARRevisionApril1994 NineMilePointUnit2FSARCHAPTER1LISTOFTABLESTableNumberTitle1~311~321~331'-41'-51.3-61~371.3-81.3-91.6-11~711~721.8-11.8-1a1'-21.9-11.10-11'1-1COMPARISONOFNUCLEARSTEAMSUPPLYSYSTEMDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFENGINEEREDSAFETYFEATURESDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFCONTAINMENTDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFELECTRICALPOWERSYSTEMDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFRADIOACTIVEWASTEMANAGEMENTDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFPOWERCONVERSIONSYSTEMDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFSTRUCTURALDESIGNCHARACTERISTICS(HISTORICAL)COMPARISONOFFINALANDPRELIMINARYDESIGNINFORMATIONFORTHENSSSSCOPEOFSUPPLY(HISTORICAL)COMPARISONOFFINALANDPRELIMINARYDESIGNINFORMATIONFORTHEBALANCEOFPLANT(HISTORICAL)REFERENCEDREPORTSFORTHENSSSSCOPEOFSUPPLYELECTRICAL,INSTRUMENTATION,ANDCONTROLDRAWINGSPIPINGANDINSTRUMENTATIONDIAGRAMSCONFORMANCEWITHDIVISION1NRCREGULATORYGUIDESCOMPLIANCEWITHREGULATORYGUIDE1.150CONFORMANCETODIVISION8NRCREGULATORYGUIDESTANDARDREVIEWPL'ANCONFORMANCETOACCEPTANCECRITERIANUREG-0737TMI-2ITEMSABBREVIATIONSANDACRONYMSUSEDINFSARUSARRevision81-vNovember1995 NineMilePointUnit2FSARCHAPTER1LISTOFFIGURESFigureNumberTitle1~111~211.2-2.1~231.2-41.2-5HEATBALANCEATRATEDPOWERPLOTPLANSTATION~UQTGEMENTDELETEDDELETEDDELETED1.2-6Sh.1GENERAL2QGVLNGEMENT~REACTORBUILDINGPLANOnAND188-6n1.2-6Sh.2GENERALARPANGEMENT~REACTORBUILDINGPLANEL196'-On1~27Sh.1GENERALAREV&GEMENT,REACTORBUILDINGPLANEL215I-On1e2-7Sh.2GENERAL2QUUQTGEMENTtREACTORBUILDZNGPLANjEL240I-On1.2-8Sh.11.2-8Sh.2GENERALAREUKGEMENT~REACTORBUILDINGPLANEL261'-OnANDMISCELLANEOUS.GENERALAE~NGEMENT~REACTORBUILDINGPLANEL215'-OnANDMISCELLANEOUS1.2-9Sh.11.2-9Sh.21.2-10Sh.1GENERAL2GGKNGEMENT~REACTORBUILDINGPLANEL289~-OnGENERALAEG&NGEMENT~REACTORBUILDINGPLANEL306'nGENERALARRANGEMENT,REACTORBUILDINGPLANEL328'-10n1.2-10Sh.2GENERALARRANGEMENT~REACTORBUILDINGPLANEL353'-10n1.2-111'12GENERALARRANGEMENTSREACTORBUILDINGSECTIONS(SHEETS1THROUGH4)GENERALAEGVQIGEMENT~REACTORBUILDINGSECTION2-2USARRevision61v3.April1994 NineMilePointUnit2FSARCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANT

1.1INTRODUCTION

ThisFinalSafetyAnalysisReport(FSAR)issubmittedbytheNiagaraMohawkPowerCorporation(Applicant)anditsco-owners(CentralHudsonGasandElectricCorporation,LongIslandLightingCompany,NewYorkStateElectricandGasCorporation,andRochesterGasandElectricCorporation)insupportoftheapplicationforaClass103operatinglicenseforthenuclearpowerstationdesignatedNineMilePointNuclearStation-Unit2'Unit2).Unit2islocatedona364-ha(900-acre)siteownedbyNiagaraMohawkPowerCorporation(NMPC),andissituatedonthesoutheastshoreofLakeOntario,OswegoCounty,NY,approximately10km(6.2mi)northeastofthecityofOswego.Unit2andsupportfacilitiesoccupyabout18.2ha(45acres),andsharethesitewiththeexistingNineMilePointNuclearStation-Unit1(Unit1)(DocketNo.50-220)whichhasbeenincommercialoperationsince1969.TheNineMilePointsiteisadjacenttotheJamesA.FitzPatrickNuclearPowerPlantownedbytheNewYorkPowerAuthority(NYPA)gUnit2islocated274m(900ft)eastofUnit1andabout716m(2,350ft)westoftheJamesA.FitzPatrickplant.Unit2employsanuclearsteamsupplysystem(NSSS)consistingofasingle-cycle,forcedcirculatingboilingwaterreactor(BWR).Theplant-ratedcorethermalpowerlevel(Figure1.1-1)is3,467MWtcorrespondingtoanetelectricaloutputof1,144MWe,anddesignthermalpowerof3,536MWtcorrespondingtoagrosselectricaloutputof1,207MWe.Thethermalpowerusedfortheplanttransientandloss-of-coolantaccident(LOCA)analysesis3,536MWt.Allsafetysystemshavebeendesignedforathermalpowerof3,536MWt.TheNSSSsupplierisGeneralElectricCompany-NuclearEnergyOperations(GE-NEO).ThebalanceoftheplantisdesignedandconstructedbyStone&WebsterEngineeringCorporation(SWEC).OtherplantsdesignedbySWECthataresimilarinconceptarecurrentlyunderreviewbytheNuclearRegulatoryCommission(NRC).ThesearetheShorehamNuclearPowerStation,Brookhaven,LongIsland,NY,andtheRiverBendStation,St.Francisville,LA.ThecontainmentdesignemploystheBWRMarkIIconceptofover-underpressuresuppressionwithmultipledowncomersconnectingthereactordrywelltothewater-filledpressuresuppressionchamber.Theprimarycontainmentisasteel-lined,reinforcedconcreteenclosurehousingthereactorandthesuppressionpool.USARRevision8November1995 NineMilePointUnit2FSARThereactorbuildingcompletelyenclosestheprimarycontainment.Thestructureprovidessecondarycontainmentwhentheprimarycontainmentisclosedandinservice,andprovidesprimarycontainmentwhentheprimarycontainmentisopen,asduringrefueling.Thereactorbuildinghousestherefuelingandreactorservicingequipment,newandspentfuelstoragefacilities,andotherreactorauxiliaryandserviceequipment.Theprimarypurposeofthereactorbuildingistominimizeground-levelreleaseofairborneradioactivematerial.Theouterwallofthereactorbuildingisreinforcedconcreteuptothecraneraillevelabovetherefuelingfloor.Abovethecraneraillevel,thesuperstructureisasteelframeusingmetalwallpanelswithsealedjoints.Accesstothebuildingisthroughairlocks.Thepowergenerationcomplexincludesseveralcontiguousbuildings:thereactorbuildingwithtwoauxiliarybays,thecontrolbuilding,theturbinebuilding,andtheradwastebuilding.Otherbuildings,suchasthesecurityfacility,arealsolocatedinthegeneralplantarea.Ascreenwellforthecirculatingandservicewatersystemsislocatedapproximately107m(350ft)northwestofthecenterlineofthereactorbuilding.CondensercoolingforUnit2isprovidedfromacounterflow,natural-draft,hyperbolic,concretecoolingtowerlocatedapproximately330m(1,000ft)southofthecenterlineofthereactorbuilding.TheultimateheatsinkforemergencycorecoolingisLakeOntario.Belowgradeandnorthofthescreenwellbuilding,therearetwoconcretetunnelsthatconveytheservicewaterintake,servicewaterdischarge,andcoolingtowerblowdown.Asafety-relatedintakepipeisenclosedineachtunnel.Theintakepipesextendfromtheintakeshaftapproximately396m(1,300ft)northwardunderLakeOntariotothesubmergedintakestructures.Onetunnelalsocontainsthedischargepipewhichextendsapproximately550m(1,800ft)tothedischargediffuser.RadionuclidesareemittedtotheatmospherefromtwolocationsatUnit2.Thesearethestackandthecombinedventfortheradwasteandreactorbuildings.Liquidradwasteisstoredfordecayorconcentratedtoasolidwasteforcontrolleddisposalatregulatedstoragesites.TheshieldingdesignandplantlayoutarebasedonextensiveexperienceofNMPCandSWECincontrollingradiologicalexposurestoaslowasreasonablyachievable(ALARA)levels.Estimatedradiologicaldosesfornormaloperationsandpostulatedaccidentsareallfractionalpartsofthedoseslistedinfederalradiologicalguidelinesforsitingandoperationofnuclearpowerplants.EnvironmentalimpactsaredescribedintheseparateEnvironmentalReport-OperatingLicenseStage(ER-OLS)beingsubmittedforUnit2.USARRevision6April1'994 NineMilePointUnit2FSAR1.11ABBREVIATIONSANDACRONYMSTable1.11-1isalistofabbreviationsusedinthisFSAR.ty~USARRevision8111-.1November1995

NineMilePointUnit2FSARTABLE1.11-1ABBREVIATIONSANDACRONYMSUSEDINFSARADSALARAAOVAPAPRMARIARMSATWSAutomaticdepressurizationsystemAslowasreasonablyachievableAir-operatedvalveAnnuluspressurizationAveragepowerrangemonitorAlternaterodinsertionArearadiationmonitoringsystemAnticipatedtransientwithoutscramBCPBOCBSWBTPBWRCADCAMCCWCGCSCHFCIVCIVMCMFACNDCOCPRCRDCRDACRPICRVICSCUFCWSDARDBDBADBEDBFLDCDTDERDGDRMSEABECAECCSECNBottomcenterpressureBeginningofcycleBiologicalshieldwallBranchtechnicalpositionBoilingwaterreactorContainmentatmospheredilution(device)ContinuousairmonitorClosedcoolingsystemCombustiblegascontrolsystemCriticalheatfluxCombinedintermediatevalveCollision-imported-velocitymethodCommonmodefailureanalysisCondensatedemineralizerCondensationoscillationCriticalpowerratioControlroddriveControlroddropaccidentControlrodpositionindicationContainmentandreactorvesselisolationcontrolsystemCumulativeusagefactorCirculatingwatersystemDesignAssessmentReportforHydrodynamicLoadsDesignbasisDesignbasisaccidentDesignbasisearthquakeDesignbasisfloodlevelDirectcurrentdifferentialtransducerDouble-endruptureDieselgeneratorDigitalradiationmonitoringsystemExclusionareaboundaryEngineeringchangeauthorizationEmergencycorecoolingsystemEngineeringchangenoticeUSARRevision81of6November1995 NineMilePointUnit2FSARTABLE1.11-1(Cont'd.)EFCVEHCEICEOCEOFEPAEPZEQDERFESFETSFAFASFATTFCDFDDRFLECHTFMEAFMHFPCCFPSFSARGDCGEGETABExcessflowcheckvalveElectrohydrauliccontrolEnergyInformationCenterEndofcycleEquivalentoccurrencefactorElectricprotectiveassemblyEmergencyplanningzoneEnvironmentalqualificationdocumentEmergencyresponsefacilityEngineeredsafetyfeatureEmergencytripsystemFullarc(modeofTCVoperation)FluidactuatorsystemFractureappearancetransitiontemperatureFunctionalcontroldiagramFielddeviationdispositionrequestFull-lengthemergencycoolingheattransferFailuremodesandeffectsanalysisFixturemountingheightFuelpoolcoolingandcleanupFireprotectionsystemFinalsafetyanalysisreportGeneraldesigncriterionGeneralElectricCompanyGEthermalanalysisbasisHAZHCUHDFMHELBHEMHEPAHEPCOHPCIHPCSHPUHXHVACHVRSIACIASIBAICCIDCIDSHeataffectedzoneHydrauliccontrolunitHeavydensityfillmaterialHighenergylinebreakHomogeneousequilibriummodelHigh-efficiencyparticulateair/absolute(filter)Hydro-ElectricPowerCommissionofOntarioHighpressurecoolantinjectionHighpressurecoresprayHydraulicpowerunitHeatexchangerHeating,ventilating,andairconditioningReactorbuildingventilationsystemInterimacceptancecriteria(NCR)InstrumentairserviceIntermediatebreakaccidentInadequatecorecoolingIncidentdetectioncircuitryInstrumentdatasheetUSARRevision82-of6November1995 NineMilePointUnit2FSARTABLE1.11-1(Cont'd.)IEDIGSCCILRTIPCEAIRMLCOLCSLDSLFMGLHGRLOCALOFWLOOP(LOP)LPAPLPCILPCSLPDSLPRMLPSPLPZLSALSDLSSSLTCLWSMAPLHGR'BAMCCM/CCMCPRMGMLDMLHGRMMIMOIMOVMPCMSIVMSIV-LCSmslMSLMSLBMTVInstrumentandelectricaldrawingIntergranularstresscorrosioncrackingIntegratedleakageratetestInsulatedPowerCablesEngineersAssociationIntermediaterangemonitorLimitingconditionofoperationLeakagecontrolsystemLeakdetectionsystemLowfrequencymotorgeneratorLinearheatgenerationrateLoss-of-coolantaccidentLossoffeedwaterLossofoffsitepowerLowpoweralarmpointLowpressurecoolantinjectionLowpressurecoresprayLoosepartsdetectionsystemLocalpowerrangemonitorLowpowersetpointLowpopulationzoneLowspecificactivityLakesurveydatum.,(of1935)LimitingsafetysystemsettingLoadtapchanging(mechanism)LiquidradwastesystemMaximumaverageplanarlinearheatgenerationrateMisplacedbundleaccidentMotorcontrolcenterMaintenanceandcalibrationcommunication(system)MinimumcriticalpowerratioMotorgeneratorsetMeanlowwaterdatumMaximumlinearheatgenerationrateModifiedMercalliintensityMethodofimagesMotoroperatedvalveMaximumpermissibleconcentrationMainsteamisolationvalveMainsteamisolationvalveleakagecontrolsystemMeansealevelMainsteamlineMainsteamlinebreakMechanicaltripvalveUSARRevision83of6November1995 NineMilePointUnit,2FSARTABLE1.11-1(Cont'd.)NBNBRNBSNDLNDTNDTTNEDNIOSHNMSNPRDSNPSHNRVNSSNSOANSSSNUMACRWMNuclearboilerNuclearboilerrated(power)NationalBureauofStandardsNucleardatalinkNilductilitytransitionNilductilitytransitiontemperatureNuclearenergydivision(GE)NationalInstituteforOccupationalSafetyandHealthNeutronmonitoringsystemNuclearplantreliabilitydatasystemNetpositivesuctionheadNonreturnvalveNonnuclearsafetyNuclearsafetyoperationalanalysisNuclearsteamsupplysystemNuclearmeasurementanalysisandcontrolrodworthminimizerOBEOFSOREOTPAPAMPASNYPCIPCIOMRPCRVICSPCSPCTp.f.PGCCPE(IDPLUPMFPMSPMWSPP/PAPQLPRMPSARPSDPTPDPVSPWROperatingbasisearthquakeOrificedfuelsupportOccupationalradiationexposuresOperationaltransientYorkcratingsselisolationPublicaddress(system)PostaccidentmonitoringPowerAuthorityoftheStateofNewPellet-claddinginteractionPreconditioningcladdinginterimopmanagementrecommendationPrimarycontainmentandreactorvecontrolsystemProcesscomputersystemPeakcladdingtemperaturePowerfactorPowergeneratingcontrolcenterPipingandinstrumentationdiagramPowerloadunbalanceProbablemaximumfloodProbablemaximumsurgeProbablemaximumwindstormPageparty/publicaddress(system)Product.qualitychecklistPowerrangemonitorPreliminarysaf'etyanalysisreportPowerspectrumdensityProjecttestprogramobjectivesPlantventstackPressurizedwaterreactorUSARRevision84of6November1995 NineMilePointUnit2FSARTABLE1.11-1(Cont'd.)QAQCRABRBCLCWRBMRBPCRCICRCPBRCSRCSCMRDCSRHRHRRMCSRMSRMSRPCRPISRPSRPTRPVRRCSRSCMRSCSRSORSPCMRSSRWCURWPQualityassuranceQualitycontrol1RestrictedareaboundaryReactorbuildingclosedloopcooling(system)RodblockmonitorReactorbuildingpolarcraneReactorcoreisolationcoolingReactorcoolantpressureboundaryReactorcoolantsystemRHRcontainmentspraycoolingmodeRoddrivecontrolsystemRelativehumidityResidualheatremovalReactormanualcontrolsystemRadiationmonitoringsystemRootmeansquareRodpatterncontrollerRodpositioninformationsystemReactorprotection(trip)systemRecirculationpumptripReactorpressurevesselRedundantreactivitycontrolsystemRHRreactorshutdowncoolingmodeRodsequencecontrolsystemReactorsystemoutlineRHRsuppressionpoolcoolingmodeRemoteshutdownsystemReactorwatercleanupRadiationworkpermitwaterSACFSARSBASCASCBASDIVSDVSEFSFCSGTSSLCSMSASOESOFSORCSPCSPDSSingleactivecomponentfailureSafetyanalysisreportSmallbreakaccidentSingle-channelanalyzerSelf-containedbreathingapparatus-ScramdischargeinstrumentvolumeScramdischargevolumeSingleequipmentfailureSpentfuelpoolcoolingandcleanupsystemStandbygastreatmentsystemStandbyliquidcontrolStandardmetropolitanstatisticalareaSingleoperatorerrorSingleoperatorfailureStationOperationsReviewCommitteeSound-poweredcommunication(system)SafetyparameterdisplaysystemUSARRevision85of6November1995 NineMilePointUnit2FSARTABLE1.11-1(Cont'd.)SPGSRABSRDISRMSRMSRPSRSSSRVSRVDLSSSSESWPTBCLCWTCVTGTIPTLDTSSTSVCUHSUPSSubstitutepositiongeneratorSafetyReviewandAuditBoardSafety-relateddisplayinstrumentationSourcerangemonitorSecurity-relatedmaterialsStandardReviewPlanSquarerootofthesumofthesquaresSafety/reliefvalveSafety/reliefvalvedischargelineSafeshutdownSafeshutdownearthquakeServicewatersystemTurbinebuildingclosedloopcoolingwaterTurbinecontrolvalveTurbinegeneratorTraversingin-coreprobeThermoluminescentdosimeterTemperaturesensor/switchTurbinestopvalveclosureUltimateheatsinkUninterruptible.powersupplyZPAZeroperiodasymptoteUSARRevision86of6November1995 LEGEND=FLOW,LB/HRF=TEMPERATURE.'FH=ENTHALPY,BTU/LBM=%MOISTUREPPRESSURE,PSIA1835PVESSELSTEAMFLOW15.881E6'191.8H>>~8.28M~1883P>>~32.5E60535.8F538.3HRECIRCULATIONDRIVELOOPS(TOTALFORBOTHLOOPS)3467MWtTOTALCOREFLOW188.5E6"MAINFEEDFLOW15.389E6"425.3F483.4H14.969E6"425.1F483,1HaH=1.31DtttD529.2H437.6F416.8HCONTROLRODDRIVEFEEDFLOW32.8E3"88.8F488HCLEANUPDEMINERALIZERSYSTEM34.8E4534.8F529.8HFROMCONDENSATESTORAGETANK~NOMINALPOWERUPRATEPLANTCONDITIONS~~THESEREPRESENTCONDITIONSBEFORETHETURBINESTOPVALVES.FIGUREI,I-IHEATBALANCEATRATEOPOWERSOURCE:NEDC-31994PTHISDRAWINGCREATEDELECTRONICALLYN'IAGARAMOHAWKPOWERCORPORATIONNINEMILEP0INT-UNIT2UPDATEDSAFETYANALYSISREPORTUSARREVISION8NOVEMBER1995 0

NineMilePointUnit2FSARaccidentsthatreleaseradioactivematerialintotheprimarycontainmentvolume.16.Itispossibletotestprimarycontainmentintegrityandleak-tightnessatperiodicintervals.17.Areactorbuildingisprovidedthatcompletelyenclosesboththeprimarycontainmentandthefuelstorageareas.Thesecondarycontainmentincludesamethodforcontrollingreleaseofradioactivematerialsfromthebarrierandincludesacapabilityforfilteringradioactivematerialswithinthebarrier.18.Thereactorbuildingisdesignedtoactasaradioactivematerialbarrier,ifrequired,whentheprimarycontainmentisopenforexpectedoperationalpurposes.19.Theprimarycontainmentandreactorbuilding,inconjunctionwithotherengineeredsafeguards,limitsradiologicaleffectsofaccidentsresultinginthereleaseofradioactivematerialtotheprimarycontainmentvolumetosignificantlylessthantherequirementsof10CFR100.20.21.Provisionsaremadeforremovingenergyfromwithintheprimarycontainmenttomaintaintheintegrityoftheprimarycontainmentsystemfollowingaccidentsthatreleaseenergytotheprimarycontainment.lPipingthatpenetratestheprimarycontainmentstructureandservesasapathfortheuncontrolledreleaseofradioactivematerialtotheenvironsisautomaticallyisolatedwheneversuchpotentialforradioactivematerialreleaseexists.Suchisolationiseffectedintimetolimitradiologicaleffectstosignificantlylessthantherequirementsof10CFR100.22.Theemergencycorecoolingsystem(ECCS)isprovidedtolimitfuelcladdingtemperatureto2,200'FasaresultofaLOCA.23.TheECCSprovidesforcontinuityofcorecoolingoverthecompleterangeofpostulatedbreaksizesintheRCPB.24.TheECCSisdiverse,reliable,andredundant.25.OperationoftheECCSisinitiatedautomaticallywhenrequired,regardlessoftheavailabilityofoffsitepower.26.Themaincontrolroomisshieldedagainstradiationtopermitcontinuedoccupancyunderaccidentconditions.USARRevision61.2-5April1994 NineMilePointUnit2FSAR27'ntheeventthatthemaincontrolroombecomesuninhabitable,itispossibletobringthereactorfrompowerrangeoperationtoacoldshutdownconditionbymanipulatinglocalcontrolsandequipmentavailableoutsidethemaincontrolroom.28.Backupreactorshutdowncapabilityisprovidedindependentofnormalreactivitycontrolprovisions.Thisbackupsystemshutsdownthereactorfromanynormaloperatingconditionandmaintainstheshutdowncondition.1.2.1.3System-by-SystemApproachTheprincipalarchitecturalandengineeringcriteriafordesignaresummarizedbelowonasystem-by-systemorsystemgroupbasis.Thesystem-by-systempresentationfacilitatesunderstandingoftheactualdesignofanyonesystem.Onlythemostrestrictiveofanyrelatedcriteriaarestatedforasystem.Wherethemostrestrictivecriterionisclassifiedasapowergenerationconsideration,lessrestrictivesafetycriteriamaynotbestatedinthesystem-by-systempresentation.However,theactualdesignofasystemmustreflectallcriteriathatpertaintoit.1.2.1.3.1NuclearSystemCriteriaPrincipaldesigncriteriaforthereactor,ECCS,RCPB,andreactivitycontrolsystemsareasfollows:1~ThenuclearsystemisdesignedtosupportaGEBWRratedat3,467MWt.2~3.Fuelcladdingisdesignedtoretainintegrityasaradioactivematerialbarrierthroughoutthedesignpowerrange.Fuelcladdingisdesignedtoaccommodate,withoutlossofintegrity,thepressuresgeneratedbythefissiongasesreleasedfromfuelmaterialthroughoutthedesignlifeofthefuel.Fuelcladding,inconjunctionwithotherunitsystems,isdesignedtoretainintegritythroughoutanyabnormaloperationaltransient.4~ThoseportionsofthenuclearsystemthatformpartoftheRCPBaredesignedtoretainintegrityasaradioactivematerialbarrierfollowingabnormaloperationaltransientsandaccidents.5.HeatremovalsystemsincludingtheECCSandmakeupwatersuppliesareprovidedinsufficientcapacity,redundancy,andoperationaladequacytoremoveheatgeneratedinthereactorcoreforthefullrangeofnormaloperationalconditionsfromunitshutdowntodesignpowerandforanyabnormaloperationaltransientUSARRevision81.2-6November1995 NineMilePointUnit2FSARTheauxiliaryboilerbuilding(Figure1.2-34),locatednorthofthescreenwellbuilding,housestheelectricboilersandaccessoriestosupplysteamtotheplantduringshutdown.Thestandbygastreatmentbuildingandrailroadaccessarea(Figures1.2-35and1..2-36)housethestandbygastreatmentfiltersandassociatedequipmentandallowaccessforspentfuelshipping.Thecondensatestoragetankbuilding(Figure1.2-37)housesthecondensatestoragetanksandassociatedequipment.Thenatural-draftcoolingtower(Figures1.2-38and1.2-39)providesthenormalheatsinkforheattransferredtothecirculatingwatersystemfromthemaincondensers.Theauxiliaryservicebuilding(Figures1.2-7and1.2-8),adjacenttothereactorbuilding,housestheheating,ventilatingandairconditioning(HVAC)roomanddecontaminationandshowerfacilitiesforpersonnel.Thedecontaminationarea(Figures1.2-19through1.2-21,1.2-23,and1.2-24),immediatelysouthoftheradwastebuilding,providesthefacilityfordecontaminationoflargetoolsandequipment,andasampleroom.-Italsohousescleansteamreboilersandrelatedequipment.Thehydrogenstoragearea(forhydrogencoolingoftheturbinegenerator,Figure1.2-40)islocatedwestoftheoffgasarea.Thehydrogenstoragebottlesaremountedonconcretepadsandareinafencedarea.1.2.4NuclearSteamSupplySystemThenuclearsystemincludesadirect-cycle,forcedcirculationfGEBWRthatproducessteamfordirectuseinthesteamturbine.AheatbalanceshowingthemajorparametersofthenuclearsystemforthewarrantedpowerconditionisshownonFigure1.1-1.TheNSSSisfurtherdiscussedinChapters4and5.1.2.4.1ReactorCoreandControlRodsThereactorfuelandcoredesignaredescribedinSection2ofReference5andSection1ofReference6.Experiencehasshownthatthecontrolrodsarenotsusceptibletodistortionandhaveanaveragelifeexpectancymanytimestheresidencetimeofafuelloading.1.2.4.2ReactorVesselandInternalsThereactorvesselcontainsthecoreandsupportingstructures;thesteamseparatorsanddryers;thejetpumps;thecontrolrodUSARRevision6April1994 NineMilePointUnit2FSARguidetubes;thedistributionlinesforthefeedwater,coresprays,andstandbyliquidcontrol;thein-coreinstrumentation;andothercomponents.Themainconnectionstothevesselincludethesteamlines,coolantrecirculationlines,feedwaterlines,CRDandin-corenuclearinstrumenthousings,corespraylines,residualheatremoval(RHR)lines,standbyliquidcontrolline,coredifferentialpressureline,jetpumppressure-sensinglines,andwaterlevelinstrumentation.Thereactorvesselisdesignedandfabricatedinaccordancewithapplicablecodesforapressureof1,250psig.Thenominaloperatingpressureinthesteamspaceabovetheseparatorsis1,035psia.Thevesselisfabricatedoflow-alloysteelandiscladinternallywithstainlesssteel(exceptforthetopheadnozzlesandnozzleweldzoneswhichareunclad).Thereactorcoreiscooledbydemineralizedwaterthatentersthelowerportionofthecoreandboilsasitflowsupwardaroundthefuelrods.ThesteamleavingthecoreisdriedbysteamseparatorsanddryerslocatedintheupperportionoftheRPV.Thesteamisthendirectedtotheturbinethroughthemainsteamlines.Eachsteamlinehastwoisolationvalvesinseries,oneoneithersideoftheprimarycontainmentbarrier.1.2.4.3ReactorRecirculationSystemThereactorrecirculationsystemconsistsoftworecirculationpumploopsexternaltotheRPV.TheseloopsprovidethepipingpathforthedrivingflowofwatertotheRPVjetpumps.Eachexternalloopcontainsonehigh-capacitymotor-drivenrecirculationpump,twomotor-operatedmaintenancevalves,and.onehydraulically-operatedflowcontrolvalve.Thevariablepositionhydraulicflowcontrolvalveoperatesinconjunctionwithalow-frequencymotorgenerator(MG)settocontrolreactorpowerlevelthroughtheeffectsofcoolantflowrateonmoderatorvoidcontent.ThejetpumpsareRPVinternals.Theyprovideacontinuousinternalcirculationpathforthemajorportionofthecorecoolantflow.Thejetpumpsarelocatedintheannularregionbetweenthecoreshroudandthevesselinnerwall.Anyrecirculationlinebreakstillallowscorefloodingtoapproximatelytwo-thirdsofthecoreheight,theleveloftheinletofthejetpumps.1.2.4.4ResidualHeatRemovalSystemTheRHRsystemisasystemofpumps,heatexchangers,andpipingthatfulfillsthefollowingfunctions:1.Removesdecayandsensibleheatduringandafterplantshutdown.hUSARRevision81.2-14November1995 NineMilePointUnit2FSARwatertemperature,purity,clarity,andlevel.Thisprocesspreventsthespentfuelfromoverheatingandthebuildupofexcessiveradioactivematerialsinthecoolingwater,therebyminimizingradiationlevels.Thesystemincludestwoheatexchangers,eachofwhichiscapableofremovingthefulldecayheatfromanormalrefuelingoffloadofspentfuel.Across-connectiontotheRHRsystemprovidesadditionalemergencybackupcoolingandcoolingduringafullcoreoffload.Chapter9givesfurtherdetailsofthefuelhandlingandstoragesystem.1.2.8PowerConversionSystemChapter10providesadetaileddiscussionofthefollowingequipmentsystems.1.2.8.1TurbineGeneratorTheturbineisa1,800-rpmtandem-compound,six-flow,single-stagereheatunitwithanelectrohydraulicgovernorcontrol.Theturbinegeneratorhasanemergencytripsystemforturbineoverspeed.Theoutputoftheturbinegeneratoris1,210.9MWeatturbineguaranteeconditionswith2.0inHgabsbackpressureand0percentmakeup.Thegeneratorisadirect-driven,,three-phase,60-Hz,25,000-V,1,800-rpmhydrogeninner-cooled,synchronousgeneratorratedat1,348,400kVAat0.90powerfactor,0.58short-circuitratioatmaximumhydrogenpressureof75psig.1.2.8.2MainSteamSystemThemainsteamsystemdeliverssteamfromthenuclearboilersystemthroughfour26-/28-inODsteamlinestotheturbinegenerator,turbinebypassvalves,SZAEs,offgaspreheaters,steamsealevaporator,andradwastesteamreboiler.1.2.8.3MainCondenserThemaincondensermaintains2.0inHgabswhenoperatingatreactorwarrantyconditionswith66.0~Fcirculatingwaterinlettemperature.Thecondenserincludesprovisionsforacceptingsteambypassedaroundtheturbinegenerator.Deaerationofcondensateisaccomplishedinthecondenser.1.2.8.4MainCondenserAirRemovalSystemThemaincondenserairremovalsystem,usingairejectorsfornormaloperationandvacuumhoggingpumpsforstartup,evacuatesgasesfromthemainturbineandcondenserduringplantstartupandmaintainsthecondenseressentiallyfreeofgasesduringUSARRevision8November1995 NineMilePointUnit2FSARoperation.Thissystemhandlesallin-leakageofnoncondensablegasesthroughtheturbineseals,condensate,feedwater,andsteamsystems,andnoncondensablesthataregeneratedinthereactorbydisassociationofwater.1.2.8.5TurbineGlandSealingSystemTheturbineglandsealingsystemprovidesmildlyradioactivesteamtothesealsoftheturbinethrottlevalvestemglandsandtheturbine'haftglands.Thesealingsteamissuppliedbyacleansteamreboilerusingcondensate.Theunitauxiliaryboilerprovidesanauxiliarysteamsupplyforstartupandwhenreactorheatingsteamisnotavailable.Thesteampackingexhaustercollectsandcondensestheairandsteammixtureanddischargestheairandothernoncondensablestotheplantexhaustducttotheatmosphere,usingamotor-drivenexhauster.1.2.8.6SteamBypassSystemandPressureControlSystemAturbinebypasssystemisprovidedwhichpassessteamdirectlytothemaincondenserundercontrolofthepressureregulator.Steamisbypassedtothecondenserwheneverthereactorsteamingrateexceedstheloadpassedtotheturbinegenerator.Thecapacityoftheturbinebypasssystemis25percentoftheturbineratedsteamflow.Thepressureregulationsystemprovidesmainturbinecontrolvalveandbypassvalveflowdemandstomaintainanearlyconstantreactorpressureduringnormalplantoperation.Italsoprovidesdemandstotherecirculationsystemtoadjustpowerlevelsbychangingreactorrecirculationflowrates./1.2.8.7CirculatingWaterSystemThecirculatingwatersystem(CWS)providesthecondenserwithacontinuoussupplyofcoolingwater.TheCWSisapumpedclosedloopsystemutilizinganair-coolednatural-draftcoolingtowerasaheatsink.Sixone-sixthcapacitycirculatingwaterpumpsareprovidedtopump,coolingwaterfromthecoolingtowerbasinthroughthemaincondenserandbacktothetopofthecoolingtower.MakeupwaterisprovidedfromLakeOntariobytheservicewatersystem.1.2.8.8CondensateandFeedwaterSystemsThecondensateandfeedwatersystemssupplycondensatefromthecondenserhotwelltotheRPV.Thecondensateispumpedbytwoofthethreecondensatepumpsthroughthefullflowcondensatedemineralizersystem,theintercoolerofthe.airejectors,andthesteampackingexhaustertothecondensateboosterpumps.Thecondensatebooster'umpspumptheflowthroughthreestringsconsistingoftwodraincoolersandfivestagesoflow-pressureheaterseach.Inaddition,threeheaterdrainpumpsprovideapproximatelyone-thirdofthefeedwaterflowrequirements.Thelastlow-pressureheatersdischargetothesuctionofthreeUSARRevision61.2-22April1994

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NineMilePointUnit2FSARTABLE1.3-1COMPARZSONOFNUCLEARSTEAMSUPPLYSYSTEMDESIGNCHARACTERISTICS(HISTORICAL)THERMALANDHYDRAULICDESIGN(Section4.4)Ratedpower,MWtDesignpower,MWt(ECCSdesignbasis)Steamflowrate,millionslb/hrCorecoolantflowrate,millionslb/hrFeedwaterflowrate,millionslb/hrSystempressure,nominalinsteamdome,psiaAveragepowerdensity,kW/1Minimumcriticalpowerfluxratio(MCPR)Coolantenthalpyatcozeinlet,Btu/lbCoremaxexitvoidswithinassembliesCoreaverageexitquality,0steamFeedwatertemperature,~FDesiPowerPeakinFactorMaximumrelativeassemblypowerAxialpeakingfactorNuclearDesiFirstCoreSee'"COREMECHANICALDESIGN(Sections4.2and7.6)NineMilePointUnit23.3233,46314.263108.514.5641,02049.151.24527.576.213.104201.401.40WPPSSUnit23.3233,46814.295108.514.2561,02049.151.24527.67913.54201.401.4ZimmerUnit12,4362,55010.47778.510.4771,02050.511.24527.47513.24201.401.4LaSalleUnits1,23,2933,43414.166106.514.1271,02050.01.28527.17613.24201.401.40See(t)FuelRodsSee"'uelPelletsSee"'SARRevision81of3November1995

NineMilePointUnit2FSARTABLE1.3-2COMPARISONOFENGINEEREDSAFETYFEATURESDESIGNCHARACTERISTICS(HISTORICAL)NineMilePointUnit2WPPSSUnit2ZimmerUnit1LaSalleUnits1,2EMERGENCYCORECOOLINGSYSTEMS(Systemssizedondesignpower)(Section6.3)Low-PressureCoreSraSstemNo.loopsFlowrate,gpmHih-PressureCoreSraSstemNo.loopsFlowrate,gpmAutomaticDeressurizationSstemNo.systemsNo.reliefvalvesLowPressureCoolantIn'ection"'o.LPCIsystemsNo.pumpsFlowrate,gpm/pumpAUXILIARYSYSTEMSResidualHeatRemovalSstem(Sectron5.4.7)No.loopsNo.pumpsFlowrate,gpm/pump"'uty,millionsBtu/hr/heatexchanger"'p.heatexchangersPrimarycontainmentcoolingmodeflowrate,gpm't"16,3508128psid11,55081,130psid6.3508200psid137,450826psid227,45041.627,45016,2508122psid11,65081,110psid6,2508200psid137,450820psid227,45041.627,45014,6258119psid11,33081,110psid4,7258200psid135.050820psid225,05030.825,05016,2508122psid11,65081,110psid6,2508200psid137,067820psid337,45046.628,400USARRevision81of2November1995

NineMilePointUnit2FSARTABLE1.3-3COMPARISONOFCONTAINMENTDESIGNCHARACTERISTICS(HISTORICAL)NineMilePointUnit2WPPSSUnit2ZimmerUnit1LaSalleUnits1,2PrimaContainment"'Section3.8)ConstructionOveraunderpressuresuppressionMarkZIReinforcedconcretesteellinerOveraunderpressuresuppressionMarkIZSteelfreestandingOveraunderpressuresuppressionMarkIIConcreteprestressedsteellinerOver&underpressuresuppressionMarkZ1ConcreteposttensionedsteellinerDrywellPressuresuppressionchamberFrustumofcone,upperportionCylindricallowerportionFrustumofcone,upperportionCylindricallowerportionwithellipticalbottomFrustumofcone,upperportionCylindricallowerportionFrustumofcone,upperportionCylindricallowerportionPressuresuppressionchamber-internaldesignpressure,psigPressuresuppressionchamber-externaldesignpressure,psigDrywell-internaldesignpressure,psigDrywell-externaldesignpressure,psigDrywellfreevolume,ft'ressuresuppressionchamberfreevolume(min),ft'ressuresuppressionpoolwatervolume,ft'03,418192,028154,794'~~200,540ui144,184"'12,197180,000oi93,000102,120221,518166,400109,096Submergenceofventpipebelowsuppressionpoolsurface,ftDesignenvironmentaltemperatureofdrywel1,~FDesignenvironmentaltemperatureofpressuresuppressionchamber,~F9.5min11.0max34027011.67min12.00max3402751034027512340275USARRevision81of2November'995

NineMilePointUnit2FSARTABLE1.3-4COMPARISONOFELECTRICALPOWERSYSTEMDESIGNCHARACTERISTICS(HISTORICAL)OffsitePowerSstem(Section8.2)Outgoinglines(No.-rating)Zncominglines(No.-rating)OnsiteacPowerSstem(Section8.3.1)NormalstationservicetransformersReservestationservicetransformersStandbydieselgenerators4,160-VESFbusesESFbusesdcPowerSu1(Sect@on8.3.2)Batteries(No.-volts)Buses(No.-volts)NineMilePointUnit2I-345-kv2-115-kv3(I)3(l)3(1)3-600-VI')6-125-V(')4+24-V6-125-V")2+24-VWPPSSUnit2I-500-kv1-230-kv1-115-kv3(l)3(l)3-480-V')4-24-V5-125-V()1-250-V2"24-V5-125-V()1-250-VZimmerUnit13-345-kv1-69-kv1-345-kv1(unitauxiliary)5-480-V3-125-V1-250-V3-125-V1-250-VLaSalleUnits1,22-345-kV(perunit)2-345-kV(perunit)1perunit1(systemaux)3I1)4-480-V3-125-V1-250-V3-125-V1-250-VIncludesoneaux).liaryboilertransformer.ZncludesaHPCSdieselgenerator.Fivetotalfor2units.Oneserveseitherunit.HPCSbatteryandbusincluded.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE1.3-5COMPARISONOFRADIOACTIVEWASTEMANAGEMENTDESIGNCHARACTERISTICS(HISTORICAL)NineMilePointUnit2WPPSSUnit2ZimmerUnit1LaSalleUnits1,2GaseousRadwaste(Section11.3)Designbasis,noblegases,uci/secProcesstreatmentNo.bedsDesigncondenserin-leakage,cfmReleasepoint,heightaboveground,ft100,000after30mindecayRecombinerambientcharcoal30430(stack)187(vent)100,000after30mindecayLowtemperaturecharcoal30230100,000after30mindecayChilledcharcoal12.5172100,000after30mindecayRecombinerambientcharcoal21370(Section11.2)Treatmentof:FloordrainsEquipmentdrainsChemicalwasteForE,F,Dreturnedtocondensatestorage,concentratestoradwastesolidificationF,DreturnedtocondensatestorageE,F,Dreturnedtocondensatestorage,concentratestoradwastesolidificationF,DreturnedtocondensatestorageF,DreturnedtocondensatestorageN,E,DreturnedtocondensatestorageF,EreturnedtocondensatestorageF,DreturnedtocondensatestorageE,Dconcentratestosolidradwaste,distillaterecycledE,DreturnedtocondensatestorageF,DreturnedtocondensatestorageE,Dconcentratestosolidradwaste,distillaterecycledUSARRevision81of2November1995

NineMilePointUnit2FSARTABLE1.3-6COMPARISONOFPOWERCONVERSIONSYSTEMDESIGNCHARACTERISTICS(HISTORICAL)Designpower,MWtDesignpower,MWe,grossGeneratorspeed,RPMDesignsteamflow,lb/hrTurbineinletpressure,psiaTurbineBassSstem(Section10.4.4)Capacity,percentofturbinedesignsteamflowMainCondenser(Section10.4.1)Heatremovalcapacity,Btu/hrCirculatinWaterSstem(Sectl.on10.4.5)No~PumpsFlowrate,gpm/pumpCondensateandFeedwaterSstems(Section10.4.7)Designflowrate,lb/hrNo.condensatepumpsNo.condensateboosterpumpsNo.feedwaterpumpsCondensatepumpdriveCondensateboosterpumpdriveFeedwaterpumpdriveNineMilePointUnit23,4631,2021,80014.3x10965257.830x106105,00014.917x103ruIlnl.ng3running2running1standbyacpoweracpoweracpowerWPPSSUnit23,4681,2051,80015.0x10'70257,702x10'82,00014260x10'rllnnl.ng3running2runnl.ngacpoweracpowerTurbineZimmer~Unit12,5508831,80011.0x10'65257,053x10c3150,00010971x10c332acpoweracpowerTurbineLaSalleUnits1,23,4341,1221,80014.2x10c965257,609x103210,00014.127x10c3plus1spare3plus1spare3acpoweracpowerTurbine2Motor1Indi.catesparametersatratedpower.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE1.3-7COMPARISONOFSTRUCTURALDESIGNCHARACTERISTICS(HISTORICAL)ElevatedReleasePoint(Sect@on11.3.3)ConstructionHeight(aboveground),ftSeismicDesi(Section3.7)OperatingbasisearthquakeHorizontal,gVertical,gNineMilePointUnit2Stack,ventStack-reinforcedconcreteVent-steel430(stack)187(vent)0.0750.075VentSteel2000.125WPPSSUnit2VentSteel1720.100.07ZimmerUnit1LaSalleUnits1,2VentSteel3700.100.07SafeshutdownearthquakeHorizontal,gVertical,gWindDesicin(section3.3)Maximumsustained,mphTornadoRotational,mphTranslational,mphTotal,mph0.150.1590290703600.250100300603600.200.1490300603600.200.149030060360USARRevision81of1November1995

NineMilePointUnit2FSARTABLE1.3-8COMPARISONOFFINALANDPRELIMINARYDESZGNINFORMATIONFORTHENSSSSCOPEOFSUPPLY(HISTORICAL)ItemChangeReasonforChangeFSARReferenceControlroddrivepositionRecirculationpumpandmotorRecirculationflowmeasurementRecirculationsystemFeedwaterandrecirculationnozzlesafeendsandthermalsleevesChangedto11wireprobeandsolidstate.Theflowrateandhorsepowerrequiredhavebeenreduced;voltagehaschangedfrom4,160Vto13,200V.Therecirculationflowmeasurementdesignwaschangedfromaflowelementtoanelbow-taptype.ThepressureinterlockforRHRinjectionwaschanged.Material/designchange.Pipingchangedtotype316Kfromtype304.Improvedreliabilityandincreasedfrequencyofcheckingactualrodposition.Detailedsystemdesign.Toimproveflowmeasurementaccuracy.ZEEE-279requirements.MitigateZGSCC.7.7.17.3.1,7.15.3NuclearfuelNuclearboilerMainsteamlineisolationMainsteamlinedrainsystemFeedwaterspargerRCICsteamsupplyControlroddrivesystemThenumberoffuelpinsineachfuelbundlehasbeenchangedfrom7x7to8x8.a.AturbinebuildinghightemperaturetripforMSZVswasadded.b.DeleteREVABsystem.Amaincondenserlowvacuuminitiationofthemainsteamlineisolationwasadded.Amainsteamlinedrainsystemwasimproved.Thethermalsleevewaschangedtoprovideweldeddesignofspargertonozzle.Awarmupbypasslineandvalvewereadded.Alternaterodinjectionandscramdischargevolumemodificationswereimplemented.Improvedfuelperformancebyincreasingsafetymargins.Improveleakdetectioncapability.GEMarkZZsuppressionpooldynamicstestprogramshowedREVABundesirable.NRCrequirement.PreventaccumulationofcondensateinanidlelineoutboardofMSZV.Toeliminatevibrationandcracking.Permitspressurizingandprewarmingofthesteamsupplylinedownstreamtotheturbineduringreactorvesselheatup.Toreducepotentialforfailuretoscram.7.35.2,5.4,8.3.17.3.15.15.34.6.1USARRevision81of2November1995

NineMilePointUnit2FSARTABLE1.3-9COMPARISONOFFINALANDPRELIMINARYDESIGNINFORMATIONFORTHEBALANCEOFPLANT(HISTORICAL)ItemReactorbuildingSummarydescriptionofstructuresPrimarycontainmentcoolingChangeAdditionofauxiliarybays.Additionalbuildingsincludedintheunit.a.Powerelectricmotorcomponentsthroughnormal4-kVswitchgear.ReasonforChangeProvideroomtoallowsegregationofECCS.Auxiliarybays,railroadaccesslock,condensatestoragetankbuilding,anddemineralizedwaterandwasteneutralizertankstoragebuildingadded.Containmentcoolingisnotanuclearsafety-relatedsystem.FSARReference6.2.3,3.2.1,3.8.41.2,3.2.18.3b.Revisedarrangementandnumberofunitcoolers.Improveairdistributionbasedonoperatingexperience.9.4.9Standbygastreatmentsystem(SGTS)AddASMEClass2isolationvalvebetweencontainmentpurgeandSGTS.Toisolatecontainmentpurge(Class4outsidecontainment)fromClass2SGTS.6.5.1ReactorbuildingventilationsystemPrimarycontainmentventilationHigh-densityspentfuelstoragePrimaryshieldwalla.LocatesupplyfansinSGTbuilding.b.Normalexhaustsystemtoconsistoftwosetsoftwofans.c.Changefromvalvestozero-leakagedampers.d.Eliminatemixingbox.AllcontainmentpurgeairispassedthroughtheSGTSandventedoutthestack.Changedspentfuelrackconfigurationtohigh-densitystoragedesign.AdditionalprovisionsaddedtosupplementthecommitmenttouseAISCSteelConstructionManualweldingrequirements.Providesamoreefficientisolationofthereactorbuilding.Improvesystemdesignforbetterairmovementandoptimumfanperformance.Reduceseismicloadandclosuretimeandcompactvalvedesign.Credittakenforturbulentmixingduringemergencyoperation.Toenhancesafetyofplantventilationdesign.Toincreaseonsitestoragecapacityofspentfuel.AISCstandardsdonotaccountforcertainweldconfigurationsnecessarytoachievepropererection,henceadditionalstandardsusedforthoseweldconfigurations.9.4.29.4.29.4.29.4.26.5.19.13.8.3USARRevision81of8November1995

PDTEDFETYNLYIREPNINEMILEPOINTNUCLEARSTATION-UNIT2TNIAGARAUMOHAWKVOL.2

NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANT1'1.21.31.41.51.61'1.81.91.101.111'21'3CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICSF12'2.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13.23.33.4DESIGNOFSTRUCTURES,COMPONENTS/EQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassification,ofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3'1Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER5TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated.WithPostulatedRuptureofPiping(GEScopeofsupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystems.andComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescription-FuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSVolume9,1010101010121212121212121212121212135.15.25.35.4Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136.16.26.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77'7.27.37.47.57.67'AppendixesCHAPTER87A,INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystems.RequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWER151515151616161616168.18.28.3Appendix8ACHAPTER9F19.29.39.49.5Appendixes9A,CHAPTER1010.110.210.3IntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem161616,17171717181920,2121,222323232324USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS{Cont'd.)Section10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411~111.211'11.411.5Appendix11ACHAPTER1212F112'12'12'12.5CHAPTER1313F113213~313413513.6CHAPTER1414.1I14.214.3CHAPTER1515'SourceTerms*LiquidWasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable{ALARA)RadiationSouxcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInfoxmationToBeIncludedinFSAR-InitialTestPxogramInitialTestProgramforOperationatPowerUprateConditions{3,467MWt)ACCIDENTANALYSISGeneral24242525252525252525262626262626262626262626'7272727USARRevision8ivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215'15'15.515.615'15.8AppendicesCHAPTER16CHAPTER1717~017-117.2CHAPTER1818.118'APPENDIXAAPPENDIXB15ATitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASEVolume27272727272727272828282828282828282828USARRevisionNovember1995

NineMilePointUnit2FSARTABLE1.8-1CONFORMANCEWITHDIVISION1NRCREGULATORYGUIDESReulatorGuide1.1Revision0November1970NetPositiveSuctionHeadforEmergencyCoolingandContainmentHeatRemovalSystemPumpsFSARSection6.3.2.2~PositioTheUnit2projectcompileswiththeRegulatoryPosition(ParagraphC)ofthisguide.ThephysicallocationoftheRHR,LPCS,andHPCSpumpsinrelationtotheminimumsuppressionpoolwaterlevelissuchthattherequiredNPSHismaintainedonthesepumpsundertheconditionsofzeropsigcontainmentpressureand212'Fsuppressionpoolwatertemperatureforalloperatingmodes.AdequateNPSHisverifiedbysystemcalculations.ReulatorGuide1.2Revision0November1970ThermalShocktoReactorPressureVesselsFSARSection5.3.3PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.ReulatorGuide1.3Revision2June1974AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaLoss-of-CoolantAccidentforBoilingWaterReactorsFSARSections3.11.5,15.6.5PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.RG1.3,togetherwithTID14844models,hasbeenusedtoarriveattheestimatedsiteboundary2-hrdose,andlowpopulationzone(LPZ)30-daydoseforaLOCA.RegulatoryPositionC.1.fofRG1.3isreplacedbyStandardReviewPlan(NUREG-0800)Section6.5.5forthefissionproductscrubbingandiodineretentioninthesuppressionpool,whichisincludedinthecontainmentleakageandTIPleakagereleasecalculationsduringthesecondarycontainmentdrawdownperiod.USARRevision81of78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.3Revision2June1974(cont'd.)(SeeSection15.6.5fordetails).AllotherreleasesareevaluatedusingtheRG1.3criteria.However,themeteorologicalassumptionswerebaseduponMurphyandCampeandRG1.145,asdiscussedinSection2.3.4.3.USARRevision81aof78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)THISPAGEINTENTIONALLYBLANKUSARRevision81bof78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.4Revision2June1974AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaLoss-of-CoolantAccidentforPressurizedWaterReactorsPositionRG1.4appliestoPWRplantsandthereforeisnotapplicabletoUnit2.ReulatorGuide1.5Revision0March1971AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaSteamLineBreakAccidentforBoilingWaterReactorsFSARSection15.6.3PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.TheassumptionsinRG1.5havebeenusedtoarriveatthesiteboundaryandLPZdosesforthesteamlinebreak.accident.ThecoolantactivitylevelgivenbytheNRCintheStandardTechnicalSpecificationforGEBWRs,NUREG-0123,isusedasareferencepointfortheaccidentanalysisandisgivena'sthefinalcoolantactivitylevelfortheUnit2TechnicalSpecifications.RelatorGuide1.6Revision0March1971IndependenceBetweenRedundantStandby(Onsite)PowerSourcesandBetweenTheirDistributionSystemsFSARSections8.3.1.2,8.3.2.2PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguideforDivisionI,II,andIIIdiesels.USARRevision62of78April1994 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.94Revision1Aril1976(cont'd.)2.(a)aftercutting,theedgesofthecutwillbegroundorreamedbackaminimumof1/32in,and(b)thefinalboltholedimensionswillnotexceedthosegivenintheSpecificationforStructuralJointsUsingASTMA325orA490bolts.ANSIN45.2.5-1974Section5.4FortheUnit'2project,thecriterionestablishedforcorrectboltlengthisonethreadextendingbeyondthefaceofthenut.3.4.ANSIN45.2.5-1974Section5.5Allreinforcingbarsplicesmadebyarcwelding,exceptthosesplicesweldedtometalembedments,willbeselectedonarandombasisforradiographyasspecifiedintheUnit2PSARSection12.6.3,andinspectedinaccordancewithAWSD12.1.SplicesweldedtometalembedmentswillbeinspectedinaccordancewithAWS12.1.Additionally,sistersplicetestingwillbedoneinaccordancewithSpecificationNo.NMP2-S203CwiththesamefrequencyasspecifiedforB-seriessisterspliceswhenrequiredbytheengineers.ANSIN45.2.5-1974Section6.2.2ExceptionsregardingmechanicalsplicingofQACategoryIreinforcin'gbarscanbefoundinUnit2ProjectPosition1.10.*ThiscommitmentismodifiedatthetimeoftheQATopicalReportimplementation.Atthattime,theQATR(seeAppendixB)supersedesthiscommitment.ReulatorGuide1.95Revision1Januar1977ProtectionofNuclearPowerPlantControlRoomOperatorsAgainstanAccidentalChlorineReleaseFSARSection6.4PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.USARRevision651of78April1994 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.96Revision1June1976DesignofMainSteamIsolationValveLeakageControlSystemsforBoilingWaterReactorNuclearPowerPlantsFSARSections1.2.9.11,5.4.5,6.2.3.2.3,15.6.5PositionMSIVleakage,atthemaximumrateallowedbytheTechnicalSpecifications,hasbeenincludedinthesecondarycontainmentbypassleakageanalysis(Section6.2.3.2.3)andintheLOCAradiologicalconsequenceanalysis(Section15.6.5).Thesedesign-basisanalysesdemonstratethatthecalculatedexposuresarewithintheguidelinesof10CFR100and10CFR50AppendixA,GeneralDesignCriteria19.Inaddition,aqualitativecomparisonhasbeenmadebetweenUnit2andtheplantusedasthebasisfor..analysespresentedinNUREG-1169,"TechnicalFindingsRelatedtoGenericIssueC-8;BoilingWaterReactorMainSteamIsolationValveLeakageandLeakageTreatmentMethods."ThiscomparisondemonstratedthatthedesignfeaturesofUnit2aresufficientlysimilartotheNUREG-1169baseplant,suchthattheconclusionsofNUREG-1169areconsidereddirectlyapplicabletoUnit2.NUREG-1169concludedthattheoverallrisksfromtheaccidentsequencesinwhichMSIVleakagecouldbeasignificantfactorarelowwithoutaleakagecontrolsystem,andalternatefissionproducthandlingtechniques;whichmakeuseoftheholdupvolumeofthemainsteamlinesandcondenser,producesignificantreductionsinoffsitedoseconsequences.ItisthereforeconcludedthataMSIVleakagecontrolsystemisnotrequiredforUnit2.ReulatorGuide1.97Revision3Ma1983InstrumentationforLight-Water-CooledNuclearPowerPlantstoAssessPlantandEnvironsConditionsDuringandFollowinganAccidentFSARSection1.10,7.1.2,7.5.2.1PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguidethroughthealternateapproachdescribedinSection7.5.2.1.USARRevision852of78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.98Revision0March1976AssumptionsUsedforEvaluatingthePotentialRadiologicalConsequencesofaRadioactiveOffgasSystemFailureinaBoilingWaterReactorFSARSection15.7.1PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.USARRevision853of78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.99Revision2Ma1988EffectsofResidualElementsonPredictedRadiationDamagetoReactorVesselMaterialsFSARSections5.3.1,5.3.2PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguidethroughthealternateapproachdescribedinSections5.3.1and5.3.2.RelatorGuide1.100Revision1Aust1977SeismicQualificationofElectricEquipmentforNuclearPowerPlantsFSARSections3.10A,3.10B,7.1,8.3PositionTheUnit2projectaddressestheRegulatoryPosition(ParagraphC)ofthisguidethroughthealternateapproachdescribedinSections3'0Aand3.10B.RelatorGuide1.101Revision2October1981EmergencyPlanningforNuclearPowerPlantsFSARSectionSiteEmergencyPlanPositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguidethroughthealternateapproachdescribedbelow.TheEmergencyPlanhasbeenwrittentocomplywithNUREG-0654.RelatorGuide1.102Revision1Setember1976FloodProtectionforNuclearPowerPlantsFSAR'Sections2.4.2,2.4.10,3.4PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.USARRevision654of78April1994 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.125Revision1October1978PhysicalModelsforDesignandOperationofHydraulicStructuresandSystemsforNuclearPowerPlantsFSARSection2.4PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.ReulatorGuide1.126Revision1March1978AnAcceptableModelandRelatedStatisticalMethodsfortheAnalysisofFuelDensificationFSARSectionChapter5PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.GeneralElectricStandardApplicationforReactorFuel,NEDE-24011-P-A(latestapprovedrevision),andGeneralElectricStandardApplicationforReactorFuel-UnitedStatesSupplement,NEDE-24011-P-A-US(latestapprovedrevision),areusedtocomplywiththerequirementofthisregulatoryguide.ReulatorGuide1.127Revision1March1978InspectionofWater-ControlStructuresAssociatedwithNuclearPowerPlantsPositionNotapplicabletoUnit2.ReulatorGuide1.128Revision1October1978InstallationDesignandInstallationofLargeLeadStorageBatteriesforNuclearPowerPlantsFSARSections8.1,8.3.2PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguidethroughthealternateapproach.InsteadofZEEE-484-1975,thelatestissueofIEEE-484-1987isused.AccordingtoIEEE,thelatestissueofastandardrepresentsthecurrentstateoftheartandisrecommendedforuse.USARRevision863of78November1995 NineMilePointUnit2FSARTABLE1.8-1(Contd.)ReulatorGuide1.129Revision1Februar1978Maintenance,Testing,andReplacementofLargeLeadStorageBatteriesforNuclearPowerPlantsFSARSections8.1,8.3.2PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.RelatorGuide1.130Revision1October1978DesignLimitsandLoadingCombinationsforClass1Plate-and-ShellTypeComponentSupportsFSARSection3.9.3.BRG1.130Revision0(July1977)wasissuedafterthedocketingdateforUnit2andworkwasinprogress.However,Unit2complieswiththeindicateditemsoftheRegulatoryPositionofthisguidethroughthealternativeapproach,describedasfollows.TheremainingdesignanalysiscriteriaofthisregulatoryguideareadequatelyaddressedbyconservatismsintheexistingASMEIIICode.PararahC.2Ultimatestrengthtemperaturecorrelationofthisguidewasusedinregionsadjacenttopipehavinghightemperatures.2.PararahC.3RegulatoryPositionC.4,withalternateconservativecollapsecriteriadevelopedbytheNSSSsupplierforplatesandshells,wasusedinlieuofRegulatoryPositionC.3.ReulatorGuide1.131Revision0Aust1977QualificationTestsofElectricalCables,FieldSplices,andConnectionsforLight-Water-CooledNuclearPowerPlantsFSARSection3.11PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguidethroughthealternateapproachdescribedbelow.USARRevision664of78April1994 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.148March1981(cont'd.)BOPOthersafety-relatedvalveassembliesclassifiedasQualityGroupA,B,orCinRG1.26complywiththeregulatoryguidesasdescribedbelow.a.SectionC.2.aValveAlicationCharacteristicsThefrequencyofuseforeachsafety-relatedvalveassemblyisnotspecified.Thenormal(open/closed)positionisnotspecified,exceptinthecaseofsafety-relatedbutterflyandsolenoidvalveassemblies.b.SectionC.2.bStructuralReirementsThedynamicloadingandthepipingfrequencyresponsespectraarenotspecified.Potentialwaterhammerisnotconsideredwhenestablishingthemaximumdifferentialpressureacrossavalve.c~SectionC.2.c0erationalReirementsThesafety-relatedfunction(open/close,remain-as-is)isnotspecified,exceptinthecasesofball,butterfly,andsolenoidvalveassemblies.Motorpowerrequirementsforvalveassembliesarenotspecified.NSSSFast-closingisolationvalveassembliesclassifiedasQualityGroupDinRG1.26meettherequirementsofANSIB31.1.0,1977.TheyalsocomplywithRG1.148,datedMarch1981)withthefollowingclarification:a.SectionC.2.aValveAlicationCharacteristicsThefrequencyofuseforeachsafety-relatedvalveassemblyisnotspecified.Thenormal(open/closed)positionisnotspecified,exceptinthecaseofsafety-relatedbutterflyandsolenoidvalveassemblies.USARRevision675of78April1994 NineMilePointUnit.2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.148March1981(cont'd.)b.SectionC.2.bStructuralReuirementsThedynamicloadingandthepipingfrequencyresponsespectraarenotspecified.Potentialwaterhammerisnotconsideredwhenestablishingthemaximumdifferentialpressureacrossavalve.MainsteamisolationvalveassembliescomplywithRG-1.148,datedMarch1981,withthefollowingclarification:a.SectionC.1.c.2AlicabilitandRelationshiwithotherStandardsThefunctionalspecificationdoesnotreferencethedesignspecification.ReulatorGuide1.149Aril1981NuclearPowerPlantSimulatorsforUseinOperatorTrainingFSARSectionChapter13.2PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguidefordesignandconstruction.ReulatorGuide1.149Revision1Aril1987NuclearPowerPlantSimulationFacilitiesforUseinOperatorLicenseExaminationsFSARSectionChapter13.2PositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguideforsimulatorcertification.USARRevision876of78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.150Revision1Februar1983UltrasonicTestingofReactorVesselWeldsDuringPreserviceandIn-serviceExaminationFSARSectionPSI/ISIPlanPositionThePreserviceInspectionPlanforUnit2consistsofthreeseparatedocuments.asfollows:1.PreserviceInspectionPlanforNuclearPipingSystemsandtheReactorPressureVessel.2.In-serviceTestingPlanforPumpsandValves.3.PreserviceInspectionPlanforNuclearPipingSystemandComponentSupports.Part1wassubmittedfortheStaff'sreviewbyletterdatedOctober15,1985,andincludedallNDEforitemsrequiredbyASMESectionXIfornuclearpipingsystems,andtheRPV,itsinternalsandsafeends.AlsoincludedinthatsubmittalisalistingofPSIultrasonicproceduresandthePSIisometricdrawings.Part2wastransmittedfortheStaff'sreviewbyletterdatedNovember27,1985,andPart3wassubmittedonDecember17,1985.AsdiscussedinSection1.7ofthePSIPlan(Part1),therequiredexaminationsforPSIshallbeperformedpriortoinitialstartupoftheplant.TheapplicablecodeforUnit2PSIisA(MESectionXI,1980EditionthroughtheWinter1980Addenda,asdiscussedinSection1.1.1ofthePSIPlan(Part1).Section1.2.1ofthePSIPlan(Part1)discussestheapplicationoftheexaminationselectioncriteria.Selectedforvolumetricexaminationwere7.5percentoftheweldsintheRHRsystem,HPCSsystem,andLPCSsystem,normallyexcludedfrompreservicevolumetricexamination.ThedegreeofcompliancewithRG1.150Revision1isprovidedinTable1.8-1a.Thisdocumentpresentsthealternatemethodofcompliancewiththeregulatoryguide,howthecomplianceisachieved(underthecolumn"Response"),andwhatdocumentsorproceduresreferencethecomplianceimplementation(underthecolumn"ProceduresandReferences").TheDegreeofCompliancepositionisincorporatedintheRPVexaminationprocedures.AtechniquequalificationshallbeperformedusingtheultrasonicexaminationsystemsthatwillbeemployedduringtheautomatedPSIexaminationsoftheRPV.ActualRPVandUSARRevision877of78November1995 NineMilePointUnit2FSARTABLE1.8-1(Cont'd.)ReulatorGuide1.150Revision1Februar1983-(cont'd.)nozzlesegmentscontainingknownsizereflectorslocatedintheIDsurfaceshallbeused.ThisqualificationshallbewitnessedbyNMPC,itsAgents,andtheNMPCANII,asaminimum.Thequalificationshalldemonstratethatflawsofthemaximumallowablelimitsaredetectable.ReulatorGuide1.155Auust1988StationBlackoutFSARSection8.3.1.5PositionTheUnit2projectcompileswiththeRegulatoryPosition(ParagraphC)ofthisguide.Unit2isevaluatedagainsttherequirementsoftheStationBlackoutRule,10CFR50.63,usingtheguidancecontainedinNUMARC87-00,"GuidelinesandTechnicalBasesforNUMARCInitiativesAddressingStationBlackoutatLightWaterReactors,"NUMARC87-00SupplementalQuestions/Answers,datedDecember27,1989,andNUMARC87-00MajorAssumptions,datedDecember27,1989,exceptwhereRG1.155takesprecedence.Table1ofRG1.155providesacross-referencebetweentheregulatoryguideandNUMARC87-00.AnyexceptionstotheNUMARCguidancetakenbyNMPCareidentifiedintheSBOdocumentationmaintainedbyNMPC(seeLetterNo.NMP2L1230,datedApril3,1990,toNRC,TACNo.68571).USARRevision878of78November1995 NineMilePointUnit2FSARTABLE1.8-2(Cont'd.)ReulatorGuide8.14Revision1Auust1977PersonnelNeutronDosimetryFSARSectionNonePositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.ReulatorGuide8.15Revision0October1976AcceptableProgramsforRespiratoryProtectionFSARSectionNonePositionTheUnit2projectcomplieswith.theRegulatoryPosition(ParagraphC)ofthisguide.PararahC.3.nExceptionistakentotherecommendationsofSection13.2ofNUREG-0041relativetoprohibitingtheuseofcontactlenseswithfullface-piecerespirators.ReulatorGuide8.19Revision1June1977ForCommentOccupationalRadiationDoseAssessmentinLight-WaterReactorNuclearPowerPlants-DesignStageMan-RemEstimatesFSARSectionNonePositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.ReulatorGuide8.20Revision1Setember1979ApplicationsofBioassayforI-125andI-131FSARSectionPositionTheUnit2projectcomplieswiththeRegulatoryPosition(ParagraphC)ofthisguide.USARRevision85of6November1995 NineMilePointUnit2FSARTABLE1.8-2(Cont'd.)ReulatorGuide8.26Revision0Setember1980ApplicationsofBioassayforFissionandActivationProductsPositionSeeSections12.5.3andExhibit12.1-2foranassessmentofthisRegulatoryGuide.ReulatorGuide8.27Revision0March1981RadiationProtectionTrainingforPersonnelatLight-WaterCooledNuclearPowerPlantsFSARSectionNonePositionSeeSection12.5.3foranassessmentofthisRegulatoryGuide.ReulatorGuide8.28Revision0Auust1981AudibleAlarmDosimetersFSARSectionPositionTheUnit2projectcomplieswiththisguidewiththefollowingclarification:Audiblealarmdosimetersmaybeusedinareasofhighnoiseprovidedthatthefrequencyofobservationofaccrueddoseisincreased.ReulatorGuide8.29Revision0Jul1981InstructionConcerningRisksFromOccupationalRadiationExposureFSARSectionNonePositionSeeSection12.5.3foranassessmentofthisRegulatoryGuide.USARRevision86of6November1995 NineMilePointUnit2FSARTABLE1.9-1(Cont'd.)37.STANDARDREVIEWPLAN5.4.6REVISION2-REACTORCOREISOLATIONCOOLINGSYSTEMBWRDifferenceTMIactionitemsarenotdiscussedinthissection.DiscussionSeeFSARSection1.10forNUREG-0737.38.STANDARDREVIEWPLAN5.4.8REVISION2-REACTORWATERCLEANUPSYSTEMDifference1AllRWCUsystemcomponentsarenotdrainedandventedthroughclosedsystems.DiscussionVentsanddrainsassociatedwiththepumpsandtheregenerativeandnonregenerativeheatexchangersareroutedtothereactorbuildingequipmentdrainsystemthroughopendrainswhichareventedtosecondarycontainmentatmosphere.Thepumpsandheatexchangerventsareusedtoventtheequipmentwhenfillingthesystem.Thedrainsareusedtoemptythecomponentspriortomaintenance.Thetemperatureofthewaterwillbelowenoughduringthesedrainingandventingoperationsthatthepossibilityofairbornecontaminationwillbeminimal.Therefore,theroutingoftheselinestoanopendrainconnectionisacceptable.Difference2EvaluationofcompliancewiththeTechnicalSpecificationsforwaterchemistrypar'ameterlimitsisnotprovided.DiscussionReactorwaterpuritywillbemaintainedbythesystemtoyieldeffluentwaterinaccordancewiththerequirementsofRG1.56(FSARSection5.4.8.1.2)andtheTechnicalSpecificationsforWaterChemistrywithinlimitsdescribedinTechnicalSpecifications.39.STANDARDREVIEWPLAN6.1.2REVISION2-PROTECTIVECOATINGSYSTEMSPAINTS-ORGAN1CMATERIALSDifferenceForasmallfractionoftheexposedsurfacesinthedrywell,therecommendationofRG1.54isnotmet.DiscussionSeeFSARSections6.1.2.1and6.1.2.2.Protectivecoatingsaregenerallynotusedinthesuppressionpool.Themajorityoftheexposedsurfaceswithinthedrywell(i.e.,primarycontainmentlines,USARRevision635of53April1994 NineMilePointUnit2FSARTABLE1.9-1(Cont'd.)drywellhead,biologicalshieldwall,structuralsteel,cranes,piperupturerestraints,pipesupports,piping,andconcrete)arecoatedwithmaterialsqualifiedinaccordancewithANSIN101.2andappliedinaccordancewithRG1.54.Thebalanceoftheexposedsurfaceswithinthedrywell(i.e.,valvebodies,handwheels,electricalandcontrolpanels,loudspeakers,andemergencylightcases),constitutingasmallfractionofthetotalexposedsurfaces,donotsatisfyRG1.54conditions.40.STANDARDREVIEWPLAN6.2.1.1.cREVISION4JULY1981APPENDIXITOSTANDARDREVIEWPLAN6.2.1.1.cREVISION1JULY1981-PRESSURE-SUPPRESSIONTYPEBWRCONTAINMENTSDifference1Peakcalculatedtemperatureforthewetwellairspaceexceedsthedesigntemperatureofthesuppressionpool.DiscussionPeakcalculatedcontainmentpressureanddeckdifferentialpressurearewithindesignlimits.Drywellcalculatedenvironmenttemperatureisbelowitsdesignvalue.However,followingthesteambypasstransient,theatmospherictemperatureinthesuppressionchamberisgreaterthan212'F(superheated).Forasmall-breakLOCAwithsteambypass,thetemperatureisdeterminedtobeapproximately2504F.AnyCategory1equipmentinthesuppressionchamberwillbequalifiedtothemaximumenvelopevalueof270F,whichhasbeenspecifiedinenvironmentalqualificationdocuments.However,thestructuretemperature,i.e.,steelliner,remainsbelowthesaturationtemperatureofthesuppressionchamberatmosphereforthedurationofthetransient.Sincethelinertemperatureisbelow212'F,thedesigntemperatureofthesuppressionchamberstructureisnotexceeded.Difference2SuppressionchambersprayisnotautoactuatedfollowingaLOCA.DiscussionOneoftheSRPrequirementsconcernstheautomaticsuppressionchamberspraylimitingcontainmentpressureto45psigconsideringsteambypass.AnalysisforUnit2showsthatcontainmentsprayisnotnecessaryforthefirst30minfollowingaLOCA;therefore,manualsprayisjustified.Thiswilleliminatethepotentialforinadvertentsprayduetothemalfunctionofanautomaticcontrol.USARRevision836of53November1995 NineMilePointUnit2FSARTABLE1.9-1(Cont'd.)63.STANDARDREVIEWPLAN11.3REVISION0BRANCHTECHNICALPOSITIONETSB11-5-POSTULATEDRADIOACTIVERELEASESDUETOAWASTEGASSYSTEMLEAKORFAILUREDifferenceAcomparisonofthemainparametersofthewastegassystemeventanalysis,aspresentedinthisSRPandthoseactuallyusedinFSARSection15.7.1,isprovidedbelow.ParameterAccident/eventSourcetermSourcetermdecaytimeIsotopesconsideredHolduptimeoncharcoalbedsReleasepointDurationofreleaseValueofX/QDurationofexposureDosecalculationsNUREG-0800BTPETSB11-5Bypassofcharcoaldelayunits,releaseofundelayedoffgasactivities7xnormaloperationsourceterm7x50,000uCi/s=350,000uCi/s30minXe,Kr,ArNotapplicableGroundlevel2hr5%overallsiteshortterm2hrSemi-infinitecloudFSARSection15.7.1Failureofcharcoaldelaybeds,releaseoftotalbedactivity100uCi/s/MWt(100x3,536.MWt)353,600uCi/s30minXe,KrXe-178daysKr-278hrGroundlevel2hr.54maximumsectorshortterm2hrSemi-infinitecloudExposurelimit<0.5Remtotalbody<5Remwholebody(calculated.24Rem)g<30RemBeta(calculated.22Rem)USARRevision847of53November1995 NineMilePointUnit2FSARTABLE1.9-1(Cont'd.)DiscussionTheanalysisofthefailureoftheoffgassystem,providedinSection15.7.1,ismoreconservativethantheanalysisproposedinthisSRP,intermsofduration,X/Q,andtransittime.Therefore,theexistinganalysisenvelopsthatproposedbyBTPETSB11-5.64.STANDARDREVIEWPLAN12.2REVISION2-RADIATIONSOURCESDifference1Shieldingandventilationdesignfissionproductsourcetermswerenotdevelopedusingthesebases:1.Anoffgasrateof100,000uCi/secafter30mindelayforBWRs.2.0.25percentfuelcladdingdefectsforPWRs.DiscussionThegeneralbasisfortheshieldingdesignisstatedinSection12.2.1.1.Sections12.2.1.2through12.2.1.5providesourcedatathatwereusedinshieldingdesigns.SourcesofairborneradiationtobeconsideredinventilationdesignarediscussedinSection12.2.2.Criterion(1)isdiscussedinSection11.1,andcriterion(2)doesnotapply."65.STANDARDREVIEWPLANS12.3AND12.4REVISION2RADIATIONPROTECTIONDESIGNFEATURESDifference1ThefollowingitemsrequiredbyNUREG-0800,SectionII.1,arenotpresentedintheFSAR.Accesscontroltospentfueltransfercanalshouldbemorestringentthanthatrequiredby10CFR20.203.2.3.Allaccessibleportionsofthespentfueltransfercanalthatarecapableofhavingradiationlevelsgreaterthan100rads/hrshallbeshieldedduringfueltransfer.Removableshieldingmaybeused(for1temb)butmustbeexplicitlymarked.Localaudibleandvisiblealarmingradiationmonitorsmustbeinstalledtoalertpersonnelifthetemporaryshieldingisremovedduringfueltransferoperations.AllaccessibleportionsofthespentfueltransfertubeshallbeclearlymarkedwithaUSARRevision648of53April1994 NineMilePointUnit2FSARTABLE1.9-1(Cont'd.)5.signstatingthatpotentiallylethalradiationfieldsarepossibleduringfueltransfer.SimilarprecautionstothosedescribedinItemsathroughdshallalsoapplytoanyotherradiationsourcehavingradiationlevelshigherthan100Rem/hr.Discussion1.Becauseoftheproceduresandshielddesigndescribedbelow,accesscontrolinaccordancewith10CFR20isconsideredtobeadequate.2.Aportableshieldoraccesscontrolwillbeusedtolimitdoseratesinareasofthedrywellaccessibleduringfueltransferto<20mRem/hr.3~Refuelingprocedureswilleithermandatetheplacementoftheradiationshieldorimplementaccesscontrolsbeforefueltransferoperations.Portablemonitorswillbeusedtoalarmaudiblyandvisiblyinthedrywelliftheportableshieldisnotinstalledorisremovedduringfueltransfer.4.NotapplicabletoUnit2design.5.Precautionssimilartothosedescribedabovemayalsobetakenforotherradiationsourceshavingradiationlevelsinexcessof100Rem/hr.Difference2ArearadiationmonitorsarerequiredbyNUREG-0800,paragraphII.4.A.3,toremainon-scalewhenmeasuring'doseratesduringaccidentsandanticipatedoperationaloccurrences.AdescriptionofvitalareamonitoringhasnotbeenprovidedinSection12.3.4.DiscussionPostaccidentvitalareamonitorsmeetthecriterionofNUREG-0800,paragraphII.4.A.3,andwillbeaddressedinanamendmenttoFSARSection12.3.66.STANDARDREVIEWPLAN12.5REVISION2-OPERATIONALRADIATIONPROTECTIONPROGRAMDifference1Nopersonnelcountratemetersareprovided.USARRevision849of53November1995 NineMilePointUnit2FSARTABLE1.9-1(Cont'd.)DiscussionTheuseofcountratemetersonprotectiveclothingwillprovidelittle,ifany,additionalradiationprotectioninviewoftheextensivepersonnelmonitoringthatwillbeimplemented.Difference2TLDsareprocessedquarterly.DiscussionAlthoughUnit2doesconformtoRegulatoryGuide8.3,in198710CFR20wasamendedtorequirealllicenseestohavepersonneldosimetrydevicesthatareutilizedtocomplywithNRCregulationsprocessedbyprocessorsthathavebeenaccreditedbytheNationalVoluntaryLaboratoryAccreditationProgram(NVLAP)oftheNationalBureauofStandards.Inthestatementofconsiderationforthisamendment,theNRCspecifiedthatdosimetryprocessorswoulddemonstratecompliancewithANSIN13.11-1983throughtesting.NineMilePointDosimetryFacilityisaccreditedbyNVLAPtoprocessTLDsbyvirtueofactualdemonstrationofcompliancewithANSIN13.11-1983throughtesting.Basedon"fade"studies,processingTLDsquarterlyinsteadofmonthlydoesnotaffectthedosimetryfacility'sNVLAPaccreditationandcomplieswith10CFR20.67.STANDARDREVIEWPLAN13.4REVISION2-OPERATIONALREVIEWDifferenceIndependentreviewisnotperformedbyanISEG.DiscussionIndependentreviewisperformedbytheSRABandtheOnsiteTechnicalServicesGroup,asdescribedinSection1.10andChapter13.Theapproachgivenmeetstheintentoftherequirementsstated.68.STANDARDREVIEWPLAN14.2REVISION2-INITIALPLANTTESTPROGRAMDifferenceThetestabstractscontainsignificantparametersbutdonotincludeplantperformancecharacteristics.USARRevision850of53November1995 NineMilePointUnit2FSARThefollowingtablesummarizestheseconsiderations:ContainmentLOCASourceTerm(NobleGas/Iodine/ParticulateNon-LOCAHighEnergyLineBreakSourceTerm(NobleGas/Iodine/ParticulateOutsideInside(100/50/1)inRCSLargerof(100/50/1)incontainment(10/10/0)inRCS(10/10/0)inRCSor(100/50/1)inRCSNineMilePointUnit2PositionAnalyseshavebeenperformedtoquantifythepostaccidentradiationlevelsthroughouttheUnit2plantbaseduponthesourcetermspresentedbelow.Theseradiationconditionsarebeingusedinconjunctionwithotherenvironmental'conditions(pressure,temperature,andhumidity)fortheequipmentqualificationprogram.Safety-relatedequipmentisbeingqualifiedinaccordancewithNUREG-0588.jAdescriptionoftheUnit2postaccidentshielddesignreviewisgiveninSection12.3.1.3.AreaswhereaccessisvitalafteranaccidentareanalyzedforpersonneloccupancytoensurethatdosestopersonnelperformingvitalpostaccidentfunctionsarelessthanGDC19limits.ThisinformationisprovidedinTable12.3-3.Adoseratemapfor*potentially-occupiedareasisprovidedonFigure12.3-69andcorrespondingTable12.3-4.SourceTermRadioactivesourcereleaseanddistributionassumptionsforUnit2areasfollows.RadioactiveSourceReleaseThepercentagesofcoreinventoryradioactivefissionproductsassumedtobe'releasedfromthefuelrodsare:Noblegases(Kr,Xe)100%Halogens50%Others1%Cesium50%USARRevision61.10-47April1994 NineMilePointUnit2FSAR2.Thisentirereleaseisassumedtooccurinstantaneouslyatthestartoftheaccident.RadioactiveSourceDistributioToenvelopthefullspectrumofbreaksizesanddepressurizationrates,twoboundingeventsandsourcedistributionswereconsidered.1~LOCAThefollowingfissionproductsareconsideredtobeuniformlymixedinthefollowingvolumes:a.SuressionPoolandReactorCoolantSstemNoblegasesHalogensOthersCesium09.50+o14504Thisdistributionassumesshort-termreactordepressurizationandisconsistentwithascenariowhichleadstogrossfissionproductreleasefromthefuel.b.CombinedDrellWetwellAirSaceNoblegasesHalogens100+o50+o*Usingthisdistribution,timehistoryradiationzonesareestablishedthroughouttheUnit2plantasfollows:a~Theabovesourceswillbedistributedinthefollowingsystempipingtoestablishtimehistoryradiationzonesfortheprimarycontainmentandreactorbuilding.Thesesystemswereconservativelyassumedtooperateconcurrently.(1)(2)(3)(4)(5)(6)(7)(8)Mainsteamsystem(primaryonly);RCIC.RHR.LPCSandHPCS.SGTS.RCS/RWCU(primaryonly).Containmentatmospheremonitoring.Hydrogenrecombinersystem.*Thefractionofairbornehalogensavailableforreleasetotheenvironmentis25percentofthecoreinventoryinaccordancewithRG1.3.ThispercentageisfurtherreducedduetosuppressionpoolscrubbingcreditinaccordancewithSRPSection6.5.5.USARRevision81.10-48November1995 NineMilePointUnit2FSARb.Znadditiontoradiationshinefromsystempipingandcomponents,theprimarycontainmentisassumedUSARRevision81.10-48aNovember1995 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKUSARRevision81.10-48bNovember1995 NineMilePointUnit2FSARCriterion5Thetimeforachlorideanalysistobeperformeddependsupontwofactors:(a)iftheplant'scoolantwaterisseawaterorbrackishwater,and(b)ifthereisonlyasinglebarrierbetweenprimarycontainmentsystemsandthecoolingwater.Underbothoftheaboveconditionsthelicenseeshallprovideforachlorideanalysiswithin24hrofthesamplebeingtaken.Forallothercases,thelicenseeshallprovidefortheanalysistobecompletedwithin4days.Thechlorideanalysisdoesnothavetobedoneonsite.Clarification5BWRsonseaorbrackishwatersites,andplantswhichuseseaorbrackishwaterinessentialheatexchangers(e.g.,shutdowncooling)thathaveonlysinglebarrierprotectionbetweenthereactorcoolantarerequiredtoanalyzechloridewithin24hr.Allotherplantshave96hrtoperformachlorideanalysis.Samplesdilutedbyuptoafactorof1,000areacceptableasinitialscopinganalysisforchloride,provided(1)theresultsarereportedas+2ppmCl(thelicenseeshouldestablishthisvalue;thenumberintheblankshouldbenogreaterthan10.0ppmCl)inthereactorcoolantsystem,and(2)thatdissolvedoxygencanbeverifiedat<0.1ppm,consistentwiththeguidelinesaboveinClarificationNo.4.Additionally,ifchlorideanalysisisperformedonadilutedsample,anundilutedsampleneedalsobetakenandretainedforanalysiswithin30days,consistentwithAL2~.Position5Chlorideinthereactorcoolantcanbedeterminedwithin96hrbyusingaspecificionelectrode.Unit2doesnotusebrackishwaterforplantcoolant.Anundilutedreactorcoolantsampleistreatedwithasodiumbromate-nitricacidsolutiontoeliminatehalogeninterferences.Thesampleishandledinafumehoodwithlongtongsandleadbrickshieldingtoreduceradiationexposure.Additionally,NMPCparticipatesinthePooledInventoryManagementProgramandshouldhaveapostaccidentsamplingcaskfromNuclearPackaging,Inc.,availableforsampletransporttoanoffsitefacilityforfurtheranalysis.Criterion6ThedesignbasisforplantequipmentforreactorcoolantandcontainmentatmospheresamplingandanalysismustassumethatitispossibletoobtainandanalyzeasamplewithoutradiationexposurestoanyindividualexceedingthecriteriaofGDC19(AppendixA,10CFR50),i.e.,5remwholebody,75remextremities.(Notethatthedesignandoperationalreviewcriterionwaschangedfromtheoperationallimitsof10CFR20USARRevision61.10-57April1994 NineMilePointUnit2FSAR(NUREG-0578)totheGDC19criterion(October30,1979,letterfromH.R.Dentontoalllicensees).Clarification6ConsistentwithRegulatoryGuide1.3or1.4sourceterms,provideinformationonthepredictedpersonnelexposuresbasedonperson-motionforsampling,transportandanalysisofallrequiredparameters.Position6AsshowninTableII.B.3-1,wholebodyexposureandextremityexposure*wouldbelessthan0.98Rand16R,respectively.Individualexposurewouldbeatevenlowerlevelsbecausemorethanonepersonwouldbeperformingtherequiredtasks.Criterion7TheanalysisofprimarycoolantsamplesforboronisrequiredforPWRs.(NotethatRegulatoryGuide1.97,Rev.2,specifiestheneedforprimarycoolantboronanalysiscapabilityatBWRplants).Clarification7PWRsneedtoperformboronanalysis.TheguidelinesforBWRsaretohavethecapabilitytoperformboronanalysis,buttheydohavetodosounlessboronwasinjected.Position7Boronconcentrationintheprimarycoolantcanbedeterminedbythecarminicacidmethodofanalysisonthedilutedreactorcoolantsamples.ReactorcoolantflowsintothePASSthroughaballvalveboredoutto0.10ml.Thevalveisrotated90degrees,andasyringeisusedtoflushthesampleplus10mlofdemineralizedwaterintoasamplebottle.Thebottleistransportedtothelaboratoryinalead-shieldedcask.Thesampleishandledinthelaboratorywithtongsandleadbrickshieldingtoreduceradiationexposure.Criterion8Ifin-linemonitoringisusedforanysamplingandanalyticalcapabilityspecifiedherein,thelicenseeshallprovidebackupsamplingthroughgrabsamples,andshalldemonstratethecapabilityofanalyzingthesamples.Establishedplanningforanalysisatoffsitefacilitiesisacceptable.Equipmentprovided*Thereferencedexposuresarebasedonapowerlevelof3,323MWt.Duetopoweruprateto3,467MWt,theexposurevaluesshownmustbemultipliedbyafactorof1.0136.USARRevision81.10-58November1995 NineMilePointUnit2FSARforbackupsamplingshallbecapableofprovidingatleastonesampleperdayfor7daysfollowingonsetoftheaccident,andatleastonesampleperweekuntiltheaccidentconditionnolongerexists.USARRevision81.10-58aNovember1995 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKUSARRevision81.10-58bNovember1995 NineMilePointUnit2FSARTABLEII.B.3-1TIMEANDDOSEPROJECTIONSPORPASSSAMPLING,TRANSPORT,ANDANALYSISTime(min)Exposureu~~n(mR)TaskStartStopPersons'"WholeBodyExtremitiesNotesDecisiontotakesampleReadcontainmentatmosphereH,levelsincontrolroomOperatecontrolpanelfordilutereactorcoolantTransportdilutereactorcoolanttolaboratoryPreparecoolantforisotopicPerformisotopicanalysisofcoolantAnalyzecoolantforboronPreparesamplepanelforcontainmentatmosphereOperatecontrolpanelforcontainmentatmosphereTransfercontainmentatmospheretosmallcaskTransportcontainmentatmospheretolaboratoryPreparecontainmentatmosphereforisotopicPerformisotopicanalysisofcontainmentatmosphereOperatecontrolpanelfordissolvedgas2049.520203539.858.563.939.8204244.549.554.2203539.858.563.968.9109.8N/AN/A9.53.6+15.0-12.2-42.54.8+01.8+15.8+23.32.7-32.5+1N/AN/A9.52.5+26.3+12.0-18.6+14.8+02.4+22.4+35.2+22.0-02.5+1AssumesTSCandOSCactivatedandsampleroomhabitated6leadshielding6leadshielding(Max)3leadshielding(Min)4leadglassforW.B.(Max)1/2leadshielding(Min)4leadglass+2leadforW.B.1/2leadshielding6leadshielding2"leadshielding2"leadshielding3leadshielding4leadglass&2"leadforW.B.(Max)1/2"leadshielding(Min)6"leadshieldingUSARRevision81of2November1995

NineMilePointUnit2FSARTABLEII.B.3-1(Cont'd.)Time(min)Exposure"mR)TaskStartStopPersons'"WholeBodyExtremitiesNotesOperatecontrolpanelfor10-mlreactorcoolant109.8119.83.6+03.6+06"leadshieldingTransport10-mlreactorcoolanttolaboratory119.8179.16.0+13.8+36"leadshielding(Max)2"leadshielding(Min)Analyze10-mlreactorcoolantforchloride179.1183.62.4+28.1+34"glasslead&2"leadforW.B.(Max)1/2"leadshielding(Min)nI0)Numberofpersonsperformingparticulartask.Dosesarebasedontheassumptionthatthedecisiontotakeasampleismade1hrafterreactorscram.TheexposurevaluesshowninTableII.B.3-1arebasedonapowerlevelof3,323MWt.Duetoapowerincreaseto3,467MWt,theexposurevaluesshownmustbemultipliedbyafactorof1.0136.USARRevision82of2November1995

NineMilePointUnit2FSARisthemanualequivalentoftheLLSrelieflogic.TheplantEOPsincorporatethisparticularinstructionoftheEPGs.ClosureoftheMSIVsisinitiatedwhenreactorwaterlevelreachesLevel1.TheSERspecifiesarecommendedsimmermarginof120psi.Theplantvesseloperatingpressureislessthan1,020psig,whereasthelowestspringsetpressureis1,165psig.Consequently,forthelimitingSRVunderlimitingoperatingpressure,asimmermarginofatleast120psiismaintained.II.K.3.17REPORTONOUTAGESOFEMERGENCYCORECOOLINGSYSTEMSLICENSEEREPORTANDPROPOSEDTECHNICALSPECIFICATIONCHANGESFSARCross-ReferenceSection6.3andtheTechnicalSpecificationsNUREG-0737PositionVSeveralcomponentsoftheECCSsarepermittedbyTechnicalSpecificationstohavesubstantialoutagetimes(e.g.,72hrforonedieselgenerator;14daysfortheHPCIsystem).Inaddition,therearenocumulativeoutagetimelimitationsforECCSs.LicenseesshouldsubmitareportdetailingoutagedatesandlengthsofoutagesforallECCSsforthelast5yrofoperation.Thereportshouldalsoincludethecausesoftheoutages(i.e.,controllerfailure,spuriousisolation).ThepresentTechnicalSpecificationscontainlimitsonallowableoutagetimesforECCSsandcomponents.However,therearenocumulativeoutagetimelimitationsonthesesamesystems.ItispossiblethatemergencycorecoolingequipmentcouldmeetpresentTechnicalSpecificationrequirementsbuthaveahighunavailabilitybecauseoffrequentoutageswithintheallowableTechnicalSpecifications.ThelicenseesshouldsubmitareportdetailingoutagedatesandlengthofoutagesforallECCSsforthelast5yrofoperation,includingcausesoftheoutages.Thisreportwillprovidethestaffwithaquantificationofhistoricalunreliabilityduetotestandmaintenanceoutages,whichwillbeusedtodetermineifaneedexistsforcumulativeoutagerequirementsintheTechnicalSpecifications.Basedontheaboveguidanceandclarification,adetailedreportshouldbesubmitted.Thereportshouldcontain(1)outagedatesanddurationofoutages;(2)causeoftheoutage;(3)ECCSsorcomponentsinvolvedintheoutage;and(4)correctiveactiontaken.Testandmaintenanceoutagesshouldbeincludedintheabovelistingswhicharetocoverthelast5yrofoperation.USARRevision81.10-121November1995 NineMilePointUnit2FSARThelicenseeshouldproposechangestoimprovetheavailabilityofemergencycorecoolingequipment,ifneeded.Applicantforanoperatinglicenseshallestablishaplantomeettheserequirements.NineMilePointUnit2PositionNMPCwillreportECCSoutagesviaLERsandAnnualSummaryReportsasrequiredbyTechnicalSpecifications.II.K.3.18ADSACTUATIONLOGICFSARCross-ReferenceSections6.3,7.3NUREG-0737PositionTheADSactuationlogicshouldbemodifiedtoeliminatetheneedformanualactuationtoassureadequatecorecooling.Afeasibilityandriskassessmentstudyisrequiredtodeterminetheoptimumapproach.OnepossibleschemethatshouldbeconsideredisADSactuationonlowreactorvesselwaterlevelprovidednoHPCIorHPCSsystemflowexistsandalow-pressure=ECCSisrunning.Thislogicwouldcomplement,notreplace,theexistingADSactuationlogic.NineMilePointUnit2PositionNMPChasparticipatedintheBWROGevaluationoflogicmodificationstosimplifyADSactuation.BasedontheBWROGdesignmodificationsfoundtobeacceptablebytheNRCstaff,NMPChasremovedthehighdrywellpressuretripinconjunctionwiththeadditionofamanualswitchtoinhibitADSactuation(Option2,NEDE-30045).II.K.3.21CORESPRAYANDLPCIAUTORESTARTFSARCross-ReferenceSections6.3,7.3NUREG-0737PositionThecoresprayandLPCIsystemflowmaybestoppedbytheOperator.Thesesystemswillnotrestartautomaticallyonlossofwaterlevelifaninitiationsignalisstillpresent.ThecoresprayandLPCIsystemlogicshouldbemodifiedsothatthesesystemswillrestart,ifrequired,toassureadequatecorecooling.Becausethisdesignmodificationaffectsseveralcorecoolingmodesunderaccident.conditions,apreliminarydesign-USARRevision61.10-122April1994 UPDTEDNLYIFETYEPNINEMILKPOINTNUCLEARSTATION-UNIT27NIAGARA4MOHAWKVOL.3

NineMilePointUnit2FSARTABLEOFCONTENTSSectionCHAPTER11~1121.31.41.51.61.71.81.91.101.111.121.13CHAPTER2TitleINTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTXntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalXnformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedXnformationConformancetoNRCRegulatoryGuidesStandardReviewPlan.ConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileXsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit,2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICSVolumeF12'2.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial-,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13.23'3.4DESXGNOFSTRUCTURES,COMPONENTS/EQUIPMENTIANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePoin'tUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3.7A3.7B3.83.9A3'B3.10A3.10B3.11Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER55.15.25.35.4.Appendixes5A,TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign{GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment{GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5BVolume9,1010101010121212121212121212121212131313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER66.16.26.36.46.56.6Appendixes6ACHAPTER77'727377.57.67.7Appendixes7A,CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5Appendixes9A,CHAPTER1010.110'10'TitleENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Componentsthrough6DINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingMaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOHERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystemVolume1313141515151515151515151616161616161616,17171717181920,2121,222323232324USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS{Cont'd.)SectionTitleVolume10.4CHAPTER11OtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT242411.111211.311.411.5Appendix11ACHAPTER1212.112.212'12.412'CHAPTER1313~113.213.313.413.513.6CHAPTER1414.1I14.214.3CHAPTER1515.0SourceTerms-LiquidWasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeatures.DoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral24242525252525252525262626262626262626262626,27272727USARRevisionivNovember,1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215.315.415.515.615.715.8Appendices15ACHAPTER16TitleDecxeaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSVolume27272727272727272828CHAPTER1717.017.117.2CHAPTER1818.118.2APPENDIXAAPPENDIXBQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOpexationQualityAssurancePxogramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE282828282828282828USARRevisionNovember1995 k

NineMilePointUnit2FSARCHAPTER2LISTOFTABLES(Cont'd.)TableNumberTitle2'-122.5-132'-142'-152'-162.5-172'-182.5-192.5-20MODULIFROMSONICTESTINGTRIAXIALTESTRESULTS(T-3-3SERIES)TRIAXIALTESTRESULTS(30DEGREESTOBEDDING)TRIAXIALTESTRESULTS(RTSERIES)UNIAXIALMODULUSDETERMINATIONSYOUNG'SMODULUSDETERMINEDBYBIAXIALTESTSWELLTESTRESULTSTRIAXIALSWELLANDCREEPTESTRESULTSDIRECTSHEARSTRENGTHOFINTACTBEDDINGPLANESASAFUNCTIONOFNORMALSTRESSANDMULTIPLEDISPLACEMENT2.5-212.5-222.5-232.5-242.5-252.5-262.5-272.5-282.5-28A2'-292.5-30EXPLORATIONATTHEUNIT2SITEAFTERGENERALSITEEXPLORATION(POST-PSAR)PARTICIPANTSOFPOST-PSARINVESTIGATIONSSUMMARYOFBORINGSCOMPLETEDONTHENINEMILEPOINTSITESOURCESOFCATEGORYISTRUCTURALFILLTRIAXIALSHEARTESTRESULTSTRIAXIALSHEARTESTRESULTSTRIAXIALSHEARTESTRESULTSINDEXANDMECHANICALPROPERTIESOFCATEGORYISTRUCTURALFILLQUALITYCONTROLPROGRAMFORCATEGORYISTRUCTURALFILLANDGRANULARFILLPIEZOMETERREADINGS,P-SERIESPIEZOMETERREADINGS,PI-SERIESUSARRevision82-xiiiNovember1995 NineMilePointUnit2FSARCHAPTER2LISTOFTABLES(Cont'd.)TableNumber2.5-312.5-322.5-332.5-342.5-352.5-362.5-372.5-382.5-392.5-402.5-412.5-422.5-432.5-442.5-452.5-45A2.5-462.5-46A2'-46B2.5-46CTitleSUMMARYOFCYCLICTRIAXIALTESTS-CHAUVINPITSUMMARYOFCYCLICTRIAXIALTESTS-MEANYENGLESROADPITINSTRUMENTATIONGRADATIONLIMITSANDWEIGHTREQUIREMENTSFORBACKSLOPEARMORANDUNDERLAYERSGRADATIONLIMITSFORGRANULt&FILTERSSTANDARDVERMICULITEGRADESCONCRETESANDGRADATIONREQUIREMENTSQUALITYCONTROLPROGRAMFORVERMICULITEQUALITYCONTROLPROGRAMFORVERMICULITE-CONCRETEQUALITYCONTROLPROGRAMFORVERMICULITE-SANDQUALITYCONTROLPROGRAMFORNUFOAM/RODAFOAMDESIGNSOILANDROCKPARAMETERSUSEDINTHEDESIGNOFCATEGORYISTRUCTURESFOUNDATIONDESIGNPARAMETERSFORMAJORSTRUCTURESRESULTSOFLIQUEFACTIONANALYSISMAXIMUMRESPONSESOFINPUTEARTHQUAKESTO.DUCTLINES907AND922ANDMANHOLENO.1,CL-1ESUMMARYOFFIELDPERCOLATIONTESTRESULTSSUMMARYOFFIELDPERCOLATIONTESTRESULTSTRIAXIALCOMPRESSIONTESTDATASUMMARYFORWHELSKYPITSPECIMENSTRIAXIALCOMPRESSIONTESTDATASUMMARYFORKELLERPITSPECIMENSTRIAXIALCOMPRESSIONTESTDATASUMMARYFORMEANYPITSPECIMENSUSARRevision8November1995 NineMilePointUnit2FSARTABLE2.2-1DAILYTRAFFICVOLUMEOFCOUNTYHIGHWAYSZNTHEVICINITYOFUNIT2HighwayDailyTrafficVolumeDateofSurveyDistanceandDirectionfromUnit2DirectionCountyRte29BetweenLakeRdandRte1BetweenRte1and104BetweenRte51Aand4CountyRte63atMinerRdCountyRte1BetweenLakeRdandCremeryRdBetweenCremeryRdandLakeviewRdBetweenLakeviewRdandRte29BetweenRte29and44BetweenRte44andHickoryGroveDrBetweenHickoryGroveDrandRte104BMiddleRdbetweenRte1andCremeryRdCremeryRdBetweenRte1andMiddleRdBetweenMiddleRdandRte104KocherRdbetweenRte1and104CountyRte53betweenRte104and4KlocksCornerRdbetweenRte104and4CountyRte51ABetweenRte104and29BetweenRte29and51CountyRte51BetweenRte104and51ABetweenRte51AandMudLakeRdCountyRte6BetweenRte1and104BBetweenRte104and641,7292,8561,2296711,3411,3059721,3121,3129648851,0111,5583,063702826792595205402602702April1978May1978April1979June1978April1978April1978April1978July1978July1978September1978April1979April1979October1979April1978May1980April1979October1979October1979October1979October1979April1979April1979ESESESSESESWSSWSSESSESSESSWSSWSSSESWSSEESESE1.21.94.32.53.12.52.53.14.35.03.72.53.73.74.33.75.65.05.0SOURCE:Reference1USARRevision8lof1November1995

NineMilePointUnit2FSARTABLE2.2-21978FREIGHTTRAFFICFORLAKEONTARIOAROUNDOSWEGOHARBOR(shorttons)CommodityTotalOverseasImportsForeignCanadianImportsLakewiseReceiptsDomesticLocalBarleyandryeRiceWheatCocoabeansFreshandfrozenvegetablesAnimalsandanimalproductsFreshfish,exceptshellfishCrudepetroleumNonmetallicmineralsAlcoholicbeveragesMiscellaneousfoodproductsBasictextileproductsPrintedmatterRadioactivematerials.wastesBasicchemicalsandproductsPaintsPhosphaticchemicalfertilizersResidualfueloilBuildingcementNonmetallicmineralproductsZronandsteelpipeandtubeUnworkedaluminumandalloysFabricatedmetalproductsMachinery,exceptelectricalElectricalmachineryandequipmentMotorvehicles,parts,andequipmentIronandsteelscrapNonferrousmetalscrap5,880522,51555961186155,74540,189131931,7001460371819,953857,67772,33526237,94940188205811201,215,979559611155,745131931,700260371891226215,9584018120120175,6625240,1891219,953857,67771,42321,9915811,011,8885,88022,51528,395SOURCE:Reference2USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.2-5HAZARDOUSMATERIALSSTORED/USEDBYINDUSTRIESWITHIN8KM(5MI)MaterialCarbondioxideIndustrialUserAlcanFitzPatrickStorageonPremises(Max.atOneTime)65tons26,000lbModeTruckTruckAverageSize6tons6,900galShipmentMaximumQuantityShipped10tons6,900galFrecgxencyWeeklyInfrequently,asneededsystemAverageQuantityShipped/yr250tonsSmallguantitiesusedtorechargeChlorineHeliumNMPUnit1AlcanAlcan20,000lb30tons1,917ft'ruckTruckTruck5,000lb1(1ton)cylinder213ft6,300gal12tons9cylinders(213ft'ach)MonthlyBiweeklyAsneeded56,000gal350cylinders94cylinders(20,022fti)HydrochloricacidAlcanOswegoWire500gal4galTruckTruck55gal4gal385gal4galWeeklyBiannually16,000gal8galHydrogenNitrogenPropaneFitzPatrickNMPUnit1OswegoWireAlcanFitzPatrickNMPUnit1OswegoWireFitzPatrickAlcanOswegoWire308,000fthm12,000ft',450ft'0,000lb10,000gal15,300gal160,000fthm1,000gal80,000lb500galTruckTruckTruckTruckTruckTruckTruckTruckTruckTruck128,000fti24,000fthm215ft~6,000lb6,900gal6,300gal145,000fthm22,500lb7,000lb275gal128,000fti24,000ft~5,375ft~6,000lb6,900gal6,300gal160,000fthm22,500lb7,000lb450galBiweeklyBimonthly10WeeksTriannuallyMonthlyMonthlyWeeklyMonthlyBiweeklyBiweekly5,881,928ft72,000fthm27,305fthm18,000lb129,000gal56,000gal8,000,000fthm3,000gal200,000gal7,000galUSARRevision81of2November1995

NineMilePointUnit2FSARTABLE2.2-5(Cont'd.)MaterialSodiumhydroxideSulfuricAcid1'sopropylalcoholIndustrialUserFitzPatrickAlcanNMPUnit1OswegoWireAlcanFitzPatrickNMPUnit1OswegoWireOswegoWireStorageonPremises(Max.atOneTime)5,000gal3,000gal165gal385gal375gal5,000gal165gal110gal110galModeTruckTruckTruckTruckTruckTruckTruckTruckTruckAverageSize3.000lb55gal55gal55gal375gal3,000lb55gal55gal55galShipmentMaximumQuan'ti'tyShipped3,000lb1,000gal55gal55gal375gal3,000lb55gal55gal55galFrequencyMonthlyMonthlyAsneededMonthlyAsneededMonthlyAsneededBimonthlyBiweeklyAverageQuantityShippedlyr246,000lb10,000gal100gal660gal4,875gal396,000lb100gal1,320gal1,430galUSARRevision82of2November1995

NineMilePointUnit2FSARTABLE2.2-61978LAKEONTARIOCARGOTRANSPORTFOROSWEGOHARBOR(shorttons)HazardousCommodityDesignation13112810281128122813281728182819284128612871287228732879289129112912291329142915291629172918292029212991CommodityDescriptionCrudepetroleumSodiumhydroxideCrudeproductsfromcoaltar,petroleum,andnaturalgasDyes,organicpigment,tanningmaterialsAlcoholsBenzeneandtolueneSulfuricacidBasicchemicalsandproductsSoap,detergents,andcleaningpreparationsGumandwoodchemicalsNitrogenouschemicalfertilizersPotassicchemicalfertilizersPhosphaticchemicalfertilizersFertilizersnotelsewhereclassifiedMiscellaneouschemicalproductsGasolineJetfuelKeroseneDistillatefueloilResidualfueloilLubricatingoilsandgreasesNaphtha,solventsAsphalt,tar,pitchesCokeLiquifiedpetroleumgases,naturalgasesPetroleumandcoalproductsnotelsewhereclassifiedTotal155,7453719,953857,677ForeignImports155,7453719,953857,677DomesticReceiptsHazardouscommoditiesAllcommoditiesAllcommoditiesforentireLakeOntario1,033,4121,215,97949,887,1551,033,4121,187,55049,501,19728,429385,958USARRevision81of1November1995 I

NineMilePointUnit2FSARTABLE2.3-6FASTESTMILEWINDSPEEDSATOSWEGO,SYRACUSE,ANDROCHESTERTrueSpeed(FastestMile)AnemometerHeightFastestMile10m(33ft)or30m(98ft)StationYearm/secm/secm/secOswegoWeatherBureauOffice"'swegoNWSStation"'ochesterWeatherBureauOffice'"RochesterNWSRochesterAirport"'yracuseWeatherBureauOffice<~'yracuseNWSHancockAirport<'>189319261964192219501979192119541967282838273327282862628560736075636226262031216226848565102692011372213429302530776566566738374184837692<n<n<5<PeriodofrecordPeriodofrecordPeriodofrecordPeriodofrecordPeriodofrecordPeriodofrecord1887through19521953through1967,generallyApril10throughDecember151887through19401941through19791903through19401941through1979Source:Reference57USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.4-6PREDICTEDHOURLYVALUESOFPRESSURE,WINDSPEED,ANDWINDDIRECTIONFORPMWSONLAKEONTARIOSequentialTimeDuringStorm(hr)Time(EST)Pl(mb)Slkm/hrmphDl(deg)P2(mb)S2km/hrmphD2(deg)P3(mb)S3km/hrmphD3(deg)P4(mb)012356789101112131415161718192021222324252627080009001000110012001300140015001600170018001900200021002200230024000100020003000400050006000700080009001000110098998329809779789709669649629619619649689719729769829869909939979991000100210041006100910112132557764535364697911312414314815816116114814314313211911311174606348132034484033334043497077899298100100928989827470694637393017017017017016016017020021022023026027027027028028029029030030029030031033032034032099699298798297997597296896696496396496196496897297297998398899199399910001001100310061008ll19223771724253616474108117130148151161161148148137135130122100726056712142344452633384046677381929410010092928584817662453735170170170170170170170170190210210220260280280280290280280290290290290310310330320330100510009959869869819789749729689649639619619629689709739759829869899939979991000100210051111101831648758556363747910812714014616116115614814514213211693696477611194054363439394649677987911001009792908882725843401701701701701601701701601701702002102502602702802902702902902902802903003003303203201011100610039929939909849839789749709669619599589579589629659689729799849889909959991000KEY:PS=D=PressureWindspeedWinddirectionNOTE:Numbersshowninpressure,speed,anddistancecolumnsindicateregionofLakeOntarioshownonFigure2.4-6.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.4-7BRETSCHNEIDER'SJOINTDISTRIBUTIONOFHANDTFORZEROCORRELATIONNumberofWavesper1,000ConsecutiveWavesforVariousRangesinHeightandPeriodRangeinRelativeHeight(H/H)0-0.20.2-0.40.4-0.60.6-0.8RangeinRelativePeriodT/T0.8-1.01.0-1.21.2-1.41.4-1.61.6-1.81.8-2.00-2.0Accumulative0-0.20.2-0.40.4-0.60.6-0.80.8-1.01.0-1.21.2-1.41.4-1.61.6-1.81.8-2.02.0-2.22.2-2.42.4-2.62.6-2.82.8-3.00-3.00.030.100.140.160.160.150.120.090.060.030.030.010.011.090.501.412.062.402.402.141.741.300.900.480.420.180.090.0416.062.055.818.549.919.928.877.215.373.721.991.720.760.390.1866.444.8613.7820.2323.4823.5121.0217.0712.728.824.724.091.800.930.43157.46'.6821.7631.9537.0837.1333.1926.9620.0913.937.456.452.841.470.678.0923.9233.6539.0639.1134.9728.4021.1614.677.856.802.991.550.715.3115.0522.1025.6525.6922.9618.6513.909.645.154.471.971.020.47248.65262.93172.031.925.447.999.279.288.306.745.023.481.861.610.710.370.1762.160.340.981.441.671.671.491.210.900.630.330.290.130.070.0311.180.030.070.110.120.120.110.090.070.050.030.020.010.8330.8188.32128.21148.80148.99133.20108.1980.6255.9029.8925.9011.405.902.7030.8119.13247.34396.14545.13678.33786.52867.14923.04952.93978.83990.23996.13998.83Accumulative1.0917.1583.59241.05489.70752.63924.66986.82998.00998.83T=waveperiodT=MeanwaveperiodH=WaveheightH=MeanwaveperiodSOURCE:Reference8USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.4"9PUBLZCWATERSUPPLYDATADistanceFromSite(mi)0to1010to2020to30Number"'0121315<<>16TOWI1OnondagaCountyWaterAuthorityOswegoVillageofMexicoVillageofPulaskiCityofFultonVillageofSandyCreekVillageofCentralSquareTownofOrwellVillageofPhoenixBaldwinsvilleFairhavenCatoWolcottAdamsRedCreek"'onstantiaEstimatedPopulationServed(1980)40,00030,2701,7252,70015,0001.4351,4272502,60010,0007655001,6401,7353,060AverageOutput(mgd)22-24'14<>>0.24<>>0.025<'>00>0.33<'>0.96<>>0.015'>'.0<'>1.00.150.0330.2200.30.030.20SourceofWaterSupplyLakeOntario(intakeatOswego)LakeOntario(intakeatOswego)3wells:240-ftdeep,138-ftdeep;averageyield275gpm;probablyinalluviumSprings12wells:30-to70-ftdeep;inalluvium2wells:21-ftdeep,averageyield275gpm;probablyinalluvium2wells:124-ftdeep,110-ftdeep;inalluviumSpring2wells:125-ftdeep,145-ftdeep;averageyield400gpm;probablyinalluvium4wells:193-ftdeep,yield1,500gpm;3shallowwells,inalluviumSpring;1well46-ftdeep,yield300gpm3wells:255-ftdeep,170-ftdeep;averageyield350gpmLakeOntarioSpring,infiltrationgalleryWellsandspringsSpring-fedreservoirRefertoFigure2.4-9.Averageoutputfor1982;currentdesigncapacityis36mgdforbothOnondagaCountyWaterAuthorityandCityofOswego.Averageoutputbaseduponcurrentlyavailabledata,OswegoCountyPublicHealthDepartment.RedCreekisanindustrial,notpublic,supplysource.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.4-10DOMESTICWELLSWITHIN2-MIRADIUSOFPLANT*WellNo.WellDepth(ft)Approx.LandSurfaceEl(ft)DepthtoWaterLevel(ft)Approx.ElofWaterLevel(ft)TypeofWellEstimatedPumpageRate(gpd)NameofOwner1234567891011121314151617181920212223242526272829303132333435363738394041184343252830454030354060602580203860122570703012801520406018224227527527528028027527527027027027028527527528028527528528027526025531031029029028528528528528529033033033034035031032033033010NeartoSurface1125581050000301812265268272278267262262262262264260255247300285280285265285290300343302318diam.Dug,3'rilledDrilledDrilledDrilledDrilledDrilled,Drilled,Drilled,Drilled,Drilled,DrilledDrilledDrilledDrilledDugDrilledDrilled6"6>>6>>6>>6>>DugDrilled,6"DrilledDrilledDugDugDrilledDugDugDugDrilledDugDugDugDugDugDugDugDrilledDrilledNotinuse150300300100225150(forlawnonly)(forlawnonly)975975Notinuse375Notinuse1502251,000375500Notinuse400Upto1,500NotinuseNotinuseNotinuse100NotinuseNotinuseNotinuse100NotinuseNotinuse375NotinuseNotinuseNotinuseNotinuse225100150150JackTimonJackTimonE.Roy'~RoyMasonBarnsMaloneMaloneMaloneMaloneMaloneHudsonUpcraftR.FauataR.Dickenson-BrownR.Dickenson-BrownJ.E.ReardonJ.MurrayDonahueKetchemR.PalmateerMalone(campground)D.StevensD.StevensSimineauSimineauSimineauSimineauSimineauWhitingWhiting-J.McLeanAdkinsC.UpcraftC.UpcraftPryorR.W.RasmussenJ.O'ConnerE.LaBouefF.PeckRandallUSARRevision81of3November1995 0

NineMilePointUnit2FSARTable2.4-10(Cont'd.)WellNo.WellDepth(ft)Approx.LandSurfaceEl(ft)DepthtoWaterLevel(ft)Approx.ElofWaterLevel(ft)TypeofWellEstimatedPumpageRate(gpd)NameofOwner424344454647484950515253545556575859606162636465666768697071727374757677787980818283841004515122563828226027303030303039301525655825301565324422309425445183303303253253253253253253403303303353403353403403403403403453403353253403253253253303353253303353403303353152902902907527527028017105123211192512151515271524151410251288312315320313322319319327315328325325325318325311320322335322327325316325290286263262272DrilledDrilledDrilledDugDrilledDugDrilledDugDrilledDrilledDugDrilledDugDrilledDrilled,Drilled,DugDrilledDrilledDrilled,DrilledDrilledDugDrilledDrilled,DugDrilled,DugDugDugDrilledDugDrilledDugDrilled,Drilled,DugDrilledDrilledDrilledDug6s6~4~6~6~6>>30300700Notinuse10050300375300375375Notinuse45037510015015030015060050500300NotinuseNotinuse500500375200300NotinuseNotinuse40040050800300150Notinuse225Notinuse375100100PitcherHopkinsandKerseyUnknownE.WhaleyL.WhaleyL.WhaleyDickensonR.LaBouefCarpenterNelsonUnknownM.CoeUpcraftF.A.NewsteadL.F.DillenbeckLawtonWoodsUnknownGoodnessVandishRichardsonAlbrightUnknownProsser(temp.vacant)ReadandOcheebeinLaBouefWillsG.DrakeC.DrakeBrandon(temp.vacant)Klesinger(temp.vacant)ConroyS.McLeanE.PatrickFranceWhaleyF.O'ConnerF.O'ConnerL.WhaleyUnknownJ.O'ConnerJ.T.O'ConnerE.HenryUSARRevision82ofNovember1995

NineMilePointUnit2FSARTable2.4-10(Cont'd.)WellNo.858687888990919293949596979899100101102WellDepth(ft)26610909031128243010Approx.LandSurfaceElevation(ft)275280300315320325325290295300280280270275280265300285DepthtoWaterLevel(ft)1520032520315Approx.ElofWaterLevel(ft)271285295320322275278270270265297TypeofWellDugDugDugDugDugDugDrilledDugDrilledDrilledDugDugDugDugEstimatedPumpageRate(gpd)Notinuse10,500+8,500+100850+4,200+150300+375400225Notinuse225150375NotinuseNotinuseNotinuseNameofOwnerE.HutchinsC.ParkhurstK.ParkhurstM.GoeweyJ.ParkhurstWoolsonW.WoolsonKingKingBartonParkhurstUnknownBellemoR.FoxFox8ansenUnknown(summerhome)Unknown(summerhome)Forlocationofwells,seeFigure2.4-10.USARRevision83of3November1995

NineMilePointUnit2FSARTABLE2.4-11PUBLICANDPRIVATEWATERSUPPLYSYSTEMSINTHEUNITEDSTATESDRAWINGFROMLAKEONTARIOWITHIN80KM(50MI)OFUNIT2MapNo.*NameofSystem(IntakeCounty)Distance(km/mi)andDirectionfromUnit2Distance(km/mi)byWaterfromUnit2AverageWithdrawalRate1980-81cum/dayTypeofUsePopulationServedProductionCapacitycum/dayCommentsRochesterGas&Electric-RobertE.GinnaNuclearPowerPlant(WayneCounty)78/49WSW78/492,180,160576.00Industrialcooling2,180,160576.00OntarioTownWaterDistrict(WayneCounty)WilliamsonWaterDistrict(WayneCounty)SodusVillage(WayneCounty)SodusPoint(WayneCounty)74/46WSW66/41WSW58/36WSW53/33SWS74/4666/4158/3653/3311,3556,8139847573.001.800.260.20Domestic,industrialDomestic,industrialDomestic,industrialDomestic5,0004,7001,8004,50011,35514,7623,7852,8393.003.901.000.75Expandedsystemstartupsummer1981Apr-Jun(avg)4;921cum/day(1.3mgd);Sep-Deccanreach9,463cum/day(2.5mgd)Jan-Junlowsof265to492cum/day(0.07to0.13mgd);Aug-Nov1highsof3,747cum/day(0.99mgd)Wintermin.454cum/day(0.12mgd);peakindrysummerweather1,703cum/day(0.45mgd)USARRevision81of4November1995

NineMilePointUnit2FSARTABLE2.4-11(Cont'd.)MapNo.*NameofSystem(IntakeCounty)Distance(km/mi)andDirectionfromUnit2Distance(km/mi)byWaterfromUnit2AverageWithdrawalRate1980-81cum/dayTypeofUsePopulationServedProductionCapacitycum/dayComments10WolcottVillage(WayneCounty)NMPCOswegoSteamStation-Unit5(OswegoCounty)NMPCOswegoSteamStation-Units1-4(OswegoCounty)NMPCOswegoSteamStation-Unit6(OswegoCounty)CityofOswego(OswegoCounty)MetropolitanWaterBoardofOnondagaCounty,Syracuse,NY(OswegoCounty)41/25WSW15/10WSW15/10WSW15/10WSW13/8WSW13/8WSW41/2515/1015/1015/1013/813/89081,558,814452,3831,771,38037,85090,8400.24411.84119.52468.0010.0024.00Domestic,IndustrialIndustrialcoolingIndustrialcoolingIndustrialcoolingDomestic,industrialDomestic,Industrial2,50032,000120,0003,7851,558,814452,3831,771,38060,560136,2601.00411.84119.52468.0016.0036.00Avg.winterusage(Jan-Mar)approx.681cum/day(0.18mgd);avg.peakusageJun-Nov1,363cum/day(0.36mgd)Winter,30,280cum/day(8mgd);summer,37,850cum/day(10mgd)Winter75,700cum/day(20.0mgd);summer,98,410-105,980cum/day(26.0-28.0mgd);toOnondagaCountyWaterAuthority;remaindertocityofSyracuseUSARRevision82of4November1995

NineMilePointUnit2FSARTABLE2.4-11(Cont'd.)MapNo.*NameofSystem(IntakeCounty)Distance(km/mi)andDirectionfromUnit2Distance(km/mi)byWaterfromUnit2AverageWithdrawalRate1980-81cum/dayTypeofUsePopulationServedProductionCapacitycum/dayComments1213NMPCScriba,NY,Unit1(OswegoCounty)PowerAuthorityoftheStateofNewYork,Scriba,NY(OswegoCounty)750(Unit2dischargetoUnit1intake)3,500(Unit2dischargetoFitzPatrickintake)1,444,356381.602,158,358570.24IndustrialcoolingIndustrialcooling1,444,3562,158,358381.60570.241516SackettsHarborVillage(JeffersonCounty)ChaumontVillage(JeffersonCounty)CapeVincentVillage(JeffersonCounty)49/31NNE60/37NNE65/41N51/3261/3865/415682657570.150.070.20DomesticDomesticDomestic1,2005507501,8939089080.500.240.24Withdrawalsfluctuateinsummerfrom492cum/day(0.13mgd)inJunto681cum/day(0.18mgd)inAugandSepWinter(Dec-Mar)usageisapprox.189cum/day(0.05mgd);summerusage(Jun-Sep)avg.341cum/day(0.09mgd)WithdrawalsfluctuatebetweenJunandSepfrom473to1,136cum/day(0.125to0.3mgd)*LocatronscorrespondingtomapnumbersareshownonFigure2.3-17USARRevision83of4November1995

NineMilePointUnit2FSARTABLE2.4-11(Cont'd.)SOURCES:NewYorkStateDepartmentofHealth.SelectedPublicWaterSupplyInventory.Albany,NY,July22,1981.PersonalcommunicationbetweenC.Gaye,MetropolitanWaterBoardofOnondagaCounty,Syracuse,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,August11,1981;February2,1982;andJune1,1982.PersonalcommunicationbetweenMrs.Frantic,OntarioTownWaterDistrict,Ontario,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,August11,1981.PersonalcommunicationR.Walvoord,WilliamsonWaterDistrict,Williamson,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,August11,1981.PersonalcommunicationbetweenMr.Wilkinson,CityofOswegoWaterSupply,Oswego,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,August11,1981.USARRevision84of4November1995

NineMilePointUnit2FSARTABLE2.4-13UNITEDSTATESZRRIGATZONZNTAKESONLAKEONTARIOWZTHZN80KM(50MI)OFUNZT2FarmerLocationofIntake(County)Distanceinkm(mi)byWaterfromDischargeAreainha(acres)cm/ha(in/acre)1/ha(gal/acre)AverageWaterUseTotalWaterUse/Applicationcum(mgd)FrequencyofApplicationJ.SimplaarMexico,NYOnLakeOntario,betweenDemsterBeachRoadandHickoryGroveRoad(OswegoCounty)8.2(5.1)24.3(60)7.6(3)762,000(81,463)18,510(4.89)Onceperyear,1yearin4L.HurlbuttMexico,NYSouthsideofButterflySwamp(OswegoCounty)9.9(6.2)8.1(20)7.6(3)762,000(81,463)6,170(1.63)Onceperyear,dryweatheronlyD.OuelletteSterling,NYEastBranchofSterlingCreek(CayugaCounty)38.6(24.1)28.3(70)5.1(2)508,000(54,308)14,380(3.80)Onceperyear,1yearin5NOTE:Irrigatedcropateachlocation,apples.SOURCES:PersonalcommunicationbetweenJ.Simplaar,Mexico,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,June10,1981.PersonalcommunicationbetweenL.Hurlbutt,Mexico,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,June9,1981.PersonalcommunicationbetweenD.Ouellette,Sterling,NY,andC.S.Ellis,Stone&WebsterEngineeringCorporation,Boston,MA,June15,1981.USARRevision8lof1November1995

NineMilePointUnit2FSARTABLE2.4-14CANADIANIRRIGATIONZNTAKESONLAKEONTARIOWITHIN80KM(50MI)OPUNIT2NamePictonGolfandCountryClubG.VaderK.PerryLocationHallowellTownshipAtholTownshipAtholTownshipRateNottoBeExceededlpm4542,0441,249120540330AmountNottoBeExceededcum/day1891,1361,1730.050.300.31R.K.HrcksWindyAcresFarmsB.McArthur(WestLakeFarmsLtd.)C.FosterG.BosmaPointPleasantFarms,Ltd.WaupoosCanningCo.,Ltd.J.CarterR.aK.CarsonE.VowinckelR.R.DodokinW.HicksC.A.McCormackCataraquiGolfandCountryClubNorthMarysburghTownshipHallowellTownshipHallowellTownshipHallowellTownshipSouthMarysburghTownshipNorthMarysburghTownshipNorthMarysburghTownshipNorthMarysburghTownshipNorthMarysburghTownshipSouthMarysburghTownshipSouthMarysburghTownshipSouthMarysburghTownshipSouthMarysburghTownshipKingston1,4231,6359081,7035681,7031,7032,5021,7032,2759088401,5903764322404501504504506614506011202402224202,0441,3639841,4385302,4602,0442.2331,4383,2556812277572.2710.540.360.260.380.140.650.540.590.380.860.180.060.200.60SOURCE:OntarioMxnistryoftheEnvironment.DataonPublicandPrivateWaterSupplySystemsDrawingPromLakeOntario.Kingston,Ontario,July24andAugust20,1981.USARRevision81of1November'995

NineMilePointUnit2FSARTABLE2.4-15SUMMARYOFRESULTSANALYSISOFBUIIDINGFLOODINGDUETOPMPBASEDONHYDROMET51AND52BuildingDoorLength(ft)TotalFlow(ft')Bldg.Depth(in)DistributionofFlow/FluxDieselgeneratorControlbuildingAuxiliarybaysouthElectricaltunnel-southareaElectricaltunnel-northareaAuxiliarybaynorthRBrailroadtrackbayStandbygastreatmentServicewaterpumproom(north)fromauxiliaryboilerroomStoplogsC261-29C261-24C261-31SA262-3ET262-4ET262-3ET261-1ET261-2NA262-1RR-261-1SG261-2SG261-1SG261-6AB261-31517404.2551.1257.2110.2110.263.663.663.6102.6102.663.6581.5273.6273.6102.6408.1Evenlyoverfloor;providedcaulkingmaterialtomakestoplogswatertight.C261-29andC261-31flowswillcombineandspreadthroughEl261corridorsandintosomerooms.C261-24willflowdownstairwellandspreadthroughcorridorsonlowerfloors.Nofixisrequired.Flowwillbeconfinedtoauxiliarybaystairwellarea.Nofixisrequired.Flowwillbespreadevenlythrougheachtunnel.Plowwillbespreadevenlythrougheachtunnel.Plowwillbespreadevenlythrougheachtunnel.Flowwillbespreadevenlythrougheachtunnel.Plowwillbeconfinedtoauxiliarybaystairwellarea.Nofixisrequired.Doorsareequippedwithweatherstripand1/16neopreneloop.Thedoorsareairtight;waterleakagewillbenegligible.Nosafety-relatedequipmentisinthisarea.Plowisspreadevenlythroughoutthebuilding(seeNote5).PlowintoauxiliaryboilerbuildingisdistributedintothepumphouseifAB261-3isopen.NOTES:1.UsehydrographsfromCalculationNo.12177-WH(B)-062forwatersurfaceelevations.2.Doorsillelevationisinthedooridentificationnumber,e.g.,SG261-1,where261isthedoorsillelevation.USARRevision81of2November1995 0

NineMilePointUnit2PSARTABLE2.4-15(Cont'd.)Calculationmethodforin-flowthroughdoorwaysfromPMPsubmergedorificedischargeequation:Q=CAf2ghQ"-Plow(cfs)C=Dischargecoefficient=0.6A=Cross-sectionalareaofflow=lengthofdoor(L)xcrackwidthofdooropening(1/16induetoflow"necking)g=Gravityh=HeadwatersurfaceelevationonexteriorofdoorNocredithasbeentakenintheanalysisforsumpwaterretainageorsumppumpoperation.Sinceequipmentstructuralpadheightis6in,resultantbuildingwaterdepthslessthanthisareacceptable.USARRevision82of2November1995

NineMilePointUnit2FSARTABLE2.5-3INSITUSTRESSMEASUREMENTSBYOVERCORINGNo.ReferenceLocationHorizontalStressMaximumMinimum(psi)(psi)AverageOrientationMaximumHorizontalStressDepthofMeasurement(ft)212213214215216217218217HookerandJohnsonKaprowskiFranklinandHungrDames&MoorePalmerandLoLoMortonetalLoProctor,VTBoreholeNo.1BoreholeNo.2Sterling,NYBoreholeNo.1(Average)Scarborough,OntSomerset,NYBoreholeNo.1(Average)BoreholeNo.2(Average)Thorold,Ont.BoreholeNo.l(Average)Mississauga,Ont.DuffinCreek,Ont.1,4271,1321,2001,5001,4501,3001,3602456404502953404304502655004001,8801,3101,1801,3002,1302,1302,0001,5201,6804705178509507506508002304604060170180240-401401101,7507569569661,6001,6209619901,2001,1001,000NSEN24WN20WN50WN70WNSOWN50WN90EN15WN45WN60WN15WN34WN15WN10WN15EN3WN27WN88WN62EN76EN60EN58EN56EN60EN60EN-NEn~N-NE"'.5-1.80.5-1.833.242.846.759.323027.731.232.671.341.751.053.156.660.061.065.081.0<85ft'n<85ft~>>USARRevision81of3November1995

NineMilePointUnit2FSARTABLE2.5-3(Cont'd.)No.ReferenceLocationHorizontalStressMaximumMinimum(psi)(psi)AverageOrientationMaximumHorizontalStressDepthofMeasurement(ft)21821721812021921422081MortonetalMortonetalSbarandSykesAmericanFallsInternationalBoardFranklinandHungrGoldbergetalNYSE&GWesleyville.ONT.Niagara,NYBoreholeNo.1"'oreholeNo.2"'iagara,ONT.BoreholeNo.1Rochester,NYBoreholeNo.1(Average)BoreholeNo.2"'Average)BoreholeNo.3(Average)NewHaven,NYBoreholeG-84(Average)1,6001,0008701,4958001,6002,0004,0004,3002,5409001,0001,9002,4001,7001,5803,0003,000-7001,4001,6752507542757081,5007677091,400-10-3305001,0006001,4001,5001,000-700-208-900-400300-3812,0001,400-1,400900725157440-71(T)510516438332N13WN34-55EN34-55EN76EN80WN80WN78WN86EN88WN10EN62EN18EN39EN11EN28EN76EN32WN38WN22WN49WN78ENSSWN21EN84WN40WN13WN16W<85ft'"6-706-7011524.535.940.845.146.432.237.346.150.655.419.240.548.251.221.724.530.338.042.350.6USARRevision82of3November1995

NineMilePointUnit2PSARTABLE2.5-3(Cont'd.)No.ReferenceLocationHorizontalStressMaximumMinimum(psi)(psi)AverageOrientationMaximumHorizontalStressDepthofMeasurement(ft)BoreholeG-85(Average)BoreholeG-86(Average)3561562232636935463731,301443481900731771941338-84(T)25924895666263460772452523N30EN04WN14EN29WN49WN48WN14WN38WN42WHydrostaticN04WN20WN26W21.222.825.529.135.637.521.831.235.438.741.9OrxentatxonanddepthreportedbyMortonetal.SitesclosetotheNiagaraGorge;orientationandmagnitudeofstressmaybeinfluencedbythisfact.NoteBoreholeNo.2isclosertogorge.DatafromBoreholeNo.2maybeinfluencedbyeffectsassociatedwithanearbyopenverticalfracture.NOTE:Positivenumbersindicatecompressivestresses;negativenumbersindicatetensilestresses.USARRevision83of3November1995

NineMilePointUnit2FSARTABLE2.5-4OC-100OVERCORERESULTSTestDepth"'ockTypeP(psi)0(psi)x10~psiEzEsRemarks11'"43'45'>>49'MassivesandstoneShale/siltysandstone/siltysandstonewithshalylaminaeGraywackeSiltysandstone,interbeddedshale,andshaleclasts-162+419+395+129-318+210+38-331N43EN20EN37EN35E9u)2.93.14.74.45.12.92.92.83.23.22.8ModulusassumedfromTestNo.6;corefracturedat43'whenrecovered.Biaxialcorefractured1,000psi.Buttonsatsiltysandstone/siltysandstonewithshaleclastscontact.100)10(>>52'63'SiltysandstoneSiltysandstonewithshalylaminaeat63'3/4+35(V)-263(7)N82W+157(2)+87(?)N43E1.83.53.51.73.51.23.6Used1/2"aszero;biaxialcorefractured1,600psioffirstloadcycle.Biaxialtestdepthat62'0".Inol(>>Belowcasingcollar.Assumed;negativevaluesdenotetensilestresses.Datatermeduncertainduetodriftofallaxesattheendoftest.Datatermeduncertainduetodriftofallaxesatthebeginningandendoftest.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-6INSITUELASTICPROPERTIESFROMCROSSHOLESURVEYSBORINGGP-1TOBORINGGP-2(TimeCorrectionApplied)Distance(ft)CompressionalVelocity(ft/sec)ShearVelocity(ft/sec)ShearModulus(psix10~)Depth(ft)MinAvgCompressionalTime(msec)ShearTime(msec)MinMinAvgSpecificGravity(g/cc)MinPoisson'sRatio0212535405566708510011512513013714516017519020522023223525026528029530031031632134035330.9531.0031.0531.1031.1531.2031.2531.3031.2531.4531.6031.7031.7031.8031.8531.8531.9532.1032.2532.4032.5032.5532.7032.9033.0533.2533.3033.5033.5533.6533.9034.1030.9531.1031.1031.1531.2531.3531.5031.5031.7031.8532.1032.2032.2532.3532.4532.5532.6532.8033.0033.1033.2533.2533.4533.5533.7033.9033.9534.0534.1034.2034.3534.6530.9531.0531.0731.1231.2031.2731.3731.4031.4831.6531.8531.9531.9832.0732.1532.2032.3032.4532.6232.7532.8732.9033.0833.2233.3733.5833.6233.7733.8233.9234.1234.382.242.242.242.122.202.202.201.962.162.122.002.002.042.202.042.202.082.162.122.201.982.142.002.082.122.162.082.182.162.080.006.285.925.785.785.085.044.904.865.184.964.484.844.764.924.884.844.844.844.924.884.884.804.884.684.724.844.924.724.965.205.24134781350013522142891380513827138501547014167144951538815388151431409315167141371500014527148621438115956149551604415537152751509015678150221527015935142661426614289151701465014720147201668415167155831659816624163381516416439152571623815714160681553717318161301737116782164811621416881161321635717153138621387313895147171421614261.1427316059146531502415975159871572314614157841468215601151041544814943166161552616687161421586115637162621556215799165265805623564266436753676227904797274177861895581288325800380848192823182698141824982618472835088378796853884178876837179587930605165066713673579578077837885227884840396418716893685858703882488658919875788908890913989719520946991769008952589538461845159266368656665827741784481358240764581259288841486228286838585008539858684418561856887978652916991248849870591928654820381852.6252.6712.6552.6982.6842.6682.6862.7112.6682.6522.6922.6812.6672.7212.7082.6512.6612.6702.6832.7362.7422.7142.7212.7352.7122.7362.7112.7172.7272.7102.7211.1931.4001.4781.5062.0552.0892.2622.322l.9792.2092.9102.3882.4912.3492.3852.3982.4302.4612.3972.5092.5232.6262.5582.8792.8292.6892.5892.8852.5762.3132.3071.2951.524l.6131.6502.2912.3462.5412.6542.2352.5243.3732.7462.8712.7032.7652.7832.8192.8632.7732.9152.9213.0562.9523.3413.2783.1052.9653.3232.9462.6152.6201.2421.4601.5431.5762.1682.2132.3962.4812.1022.3603.1302.5592.6732.5182.5672.5822.6162.6532.5772.7032.7132.8312.7463.0993.0432.8882.7693.0942.7532.4582.4570.3880.3670.3560.3750.2890.2830.2590.3210.3130.2930.2450.3080.2850.2630.3030.2480.2860.2610.2870.2560.3190.2750.2840.2650.2740.2750.2650.2760.3150.337USARRevision81of1Novemher1995

NineMilePointUnit2PSARTABLE2.5-7INSITUELASTICPROPERTIESPROMCROSSHOLESURVEYSBORINGGP-1TOBORINGRT-1(TimeCorrectionApplied)Depth(ft)MinDistance(ft)AvgCompressionalTime(msec)ShearTime(msec)MinCompressionalVelocity(ft/sec)AvgShearVelocity(ft/sec)MinSpecificGravity(g/cc)MinShearModulus(psix10')Poisson'sRatio0212535405566708510011512513013714516017519020522023223525026528028530031031632115.5015.3015.2515.0514.9514.7014.5014.4514.3014.2014.2014.2014.2514.3014.4014.6515.0515.5015.9016.5016.9517.1017.7016.2019.0519.7520.0020.5020.6521.1015.5015.3515.3515.1015.0514.8014.6014.6014.4514.3514.3514.4014.4514.5514.6014.8015.1015.6516.2516.8017.3517.5018.2519.0019.7520.5020.7521.3021.6021.8515.5015.3215.3015.0715.0014.7514.5514.5214.3814.2714.2714.3014.3514.4314.5014.7215.0715.5716.0716.6517.1517.3017.9818.6019.4020.1220.3720.9021.2321.481.141.161.141.021.121.141.100.961.041.041.000.920.961.040.921.101.061.121.181.161.121.121.241.141.301.241.321.341.363.503.564.063.162.922.922.783.022.682.762.762.682.802.943.042.962.923.123.283.163.123.383.383.423.443.483.543.761275012500125421384312458120831245714020129091290913396145411402013091149491297413839134751330613893144921500014000156751452215365148551489314659142131395513981156771396213619140381605614643146431531916802161671489817209145191565015330150001577316509172171610218267165321758516905168751680813443131901322414706131701276313205149741372613726143001559815026139421600513705146931435314110147841544616049150001701815481164311583315840157905977582148246734742473237772682773207802783082187742732571677673803075697244770381197459807279646000807178987482650463435171745083158202881176338247888969209448879582227947659991298485810766639217648291446991902291038852634062306071499270757846773982617210775883148343879682397750753781128551800576566160864279498584sass84906566836678952.6252'.6712.6552.6982.6842.6682.6862.7112.6682.6522.6922.6812.6672.7212.7082.6512.6612.6702.6832.7362.7422.7142.7212.7352.7122.7362.7112.7172.7271.2641.220.8331.6491.9941.9292.2071.6761.9152.2092.2162.4282.1981.9591.8352.1122.3212.0721.9352.1932.4122.0412.4022.3192.3602.3802.2842.058l.4971.449.9572.0192.5012.4202.8372.0952.4312.8672.8753.2092.8372.4662.2572.6523.0002.6042.4242.7743.1082.6393.0822.9553.0023.0282.8702.5571.3731.327.8921.8212.2272.1542.4941.8692.1522.5082.5162.7812.4902.1932.0302.3602.6312.3172.1622.4612.732'.3172.7172.6142.6582.6812.5572.2910.3630.3660.4170.3490.2250.2090.2810.3100.2650.2450.3000.2390.2320.3470.2830.2810.2250.2630.3170.3060.2960.3050.3290.2870.3180.2930.3070.333USARRevision8lof1November1995

NineMilePointUnit2FSARTABLE2.5-8INSITUELASTICPROPERTIESPROMCROSSHOLESURVEYSBORINGRT-1TOBORINGGP-2(TimeCorrectionApplied)Depth(ft)MinDistance(ft)AvgCompressionalTime(msec)shearTime(msec)CompressionalVelocity(ft/sec)MinAvgShearVelocity(ft/sec)MinSpecificGravity(g/cc)ShearModulus(psix10')MinAvgPoisson'sRatio0212535405566708510011512513013714516017519020522023223525026528029530031031632127.2726.8526.6526.3025.1025.4524.9524.7523.9523.3522.7022.2522.0021.7021.2020.4019.6518.8018.0017.2016.6516.4515.7015.0014.3013.7013.5013.1012.8012.7027.2726.9026.7026.4026.2025.6525.2025.0024.4023.7523.1522.7022.4522.1521.7521.1020.4019.7018.8518.2017.6517.4516.8016.0515.4014.7014.5014.0013.7513.5527.2726.9826.5726.3526.1525.5525.0824.8724.1723.5522.9222.4822.2321.9221.4820.7520.0219.2518.4217.7017.1516.9516.2515.5214.4514.2014.0013.5513.2713.132.001.881.921.841.721.901.761.501.541.561.441.401.401.561.221.401.321.281.181.161.081.001.040.960.880.920.880.840.820.004.324.164.324.284.224.003.983.683.803.683.723.943.783.723.363.303.123.043.082.822.862.802.642.562.642.522.50130341373713283137371429813414135991442813735140121483315068148631308615938134591362313433138711364814430148111363614020145741377613936142221443213866146701419414719154521448314706158441503215433164491675416580149001819015224156351545116250160451710817872163781711117927168601707317628178291343714189137241421214855139311413415109143601469615608158751566113766170081430414583143951500014784156941625014928154691613615217153981580416006778181067530747075467827768182857780802978067067718370687769762778907929768783517812768880598333770681018141830286758066802581178531836391148534883985857768799279078874872791929289899510000933192779800102119333996499638034838177907789782281678010868481438419818174057573747282978153851085758309912985308437887592118469897089902.6252.6712.6552.6982.6842.6682.6862.7112.6682.6522.6922.6812.6672.7212.7082.6512.6612.6702.6832.7362.7422.7142.7212.7352.7122.7362.7112.7172.7272.1672.3892.0512.0072.0622.2392.1222.4542.1962.3302.1901.8321.8831.7852.1652.0942.2512.3182.1842.5512.2392.1792.3742.5612.1702.4042.4362.4672.7372.3542.3162.3852.6602.5152.9702.6432.8232.6502.2132.3322.2342.8252.7413.0563.1832.9913.6583.1943.1733.5113.8463.1833.6363.6492.3102.5552.1952.1542.2152.4382.8082.6962.4062.5612.4062.0112.0941.9952.4702.3922.6192.7122.5523.0492.6692.6252.8793.1292.6212.9472.9710.2390.2340.3100.2770.2790.2940.2740.2320.3130.3040.3120.2960.3760.3120.2610.2610.2630.2460.3050.2690.2580.2880.2830.2110.2830.2620.269USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-10MINERALOGICALCOMPOSITIONESTIMATEDMODALANALYSISBYPETROGRAPHICEXAMINATIONOFTHINSECTIONSComponent(0)SarpleDepthRockType(byThinSection)GeologicUnitQuartsChertFeldsparRockFragmentsMatrixandAccessoryMineralsSR-1SR-2SR-3SR-4SR-5SR-621'll'6.68m)23'0(7.01m)26'10(8.18m)27'l(8.51m)91'0(27.74m)92'3(28.12m)SubmaturelithicareniteSubmaturelithicareniteLithicgraywackeLithicgraywackeShaleShaleOswegoSandstoneOswegoSandstoneTransitionZoneTransitionZonePulaskiUnitBPulaskiUnitB605325251020252530171774AsampesareromBoringTD-1.USARRevision8lof1November1995

NineMilePointUnit2FSARTABLE2.5-11MINERALOGICALCOMPOSITIONMODALANALYSISBYX-RAYDIFFRACTIONSampleSR-1SR-2SR-3SR-4SR-5SR-6RockType(bythinsection)SubmaturelithicareniteSubmaturelithicareniteLithicgraywackeLithicgraywackeShaleShaleSilica,Quartz,andChert5958525032SodicFeldspar101012ChloriteGroup1013Mineral(%)IlliteGroup19Kaolinite151517182723OtherUndifferentiatedorasNoted10*8*Includesamajorpercentageofhalloysite,andprobablyorganicmaterialandrockfragments.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-12MODULIFROMSONICTESTINGSampleNo.DepthRockTypeCompressionWaveVelocity(V~)(ft/sec)ShearWaveVelocity(V.)(ft/sec)UniaxialStress(psi)Poisson'sRatio(u)ShearModulusG(x10'si)Young'sModulusE(x10'si)GP-1-1GP-1-2GP-1"4GP-1-5GP-1-12GP-1-14GP-1-21GP-1-30GP-1-44GP-1-49GP-1-712'10-13'1525'25'6'5'll'29'830'6-30'll60'2-61'282'1-82'9101'109'6158'2-158'll280'4-281'22'6-323'0'7'4l'5SandstoneSandstoneSandstoneSiltstoneSandstoneGraywackeSandstoneSandstoneSandstoneSiliciousGraywacke13,56015,17114,42911,48815,21518,39717,37218,72816,89116,35413,9568,7829.4359.8295.0289,81911,23810,99311,52910,94110,4578,76710.010.020.020.040.060.075.0110.0800.0225.030.00.1390.1850.2010.3820.1430.2020.1660.1950.1390.1540.1742.6763.1502.7870.9123.4004,3855.0024.3874.0042.7656.0967.4646.6922.5207.77311.40910.226ll.9529.9919.2426.491GP-1-9GP-113GP-1-2253'5-53'll70'll-71'10GraywackeGraywacke110'll-111'10Sandysiltstone12,57413,67112,4447,7188,2715,92340.025.070.00.1980.2110.3542.1232.4651.2635.0875.9713.419GP-1-53GP-1-42GP-1-29GP-1-6GP-1-47GP-1-24339'7-340'2251'2-252'0155'155'439'8'40'0303'5-304'0121'9-122'4SandysiltstoneShaleShaleShaleSiltyshaleShale14,38911,58511,58510.48510,04211,49511,49511.35111.35110,8549,4866.9366,9366,3476,1826,7457,0566,9466,9466,702240.0151.3175.0151.6110.0151.530.0152.8210.0151.70.1160.2210.2210.2110.1950.2370.1980.2010.2010.1923.2651.7461.7461.4480.3741.6361.7901.7621.7621.6247.2864.2634.2633.5063.2834.0494.2894.2324.2323.871USARRevision8lof2November1995

NineMilePointUnit2PSARTABLE2.5-12(Cont'd.)SampleNo.DepthRockTypeCompressionWaveVelocity(V,)(ft/sec)ShearWaveVelocity(V,)(ft/sec)UniaxialStress(psi)Poisson'sRatio(9)ShearModulusG(x10~psi)Young'sModulusE(x10'si)GP-1-55GP-1-36GP-1-27GP-1-15GP-1-28GP-1-35GP-1-39350'1-350'688'll-89'5152'6-153'8195'0-195'8'39'3-239'8SiltyshaleSiltstoneShaleInterbeddedsandstoneandshaleSandysiltstoneShaleSiltysandyshale11,84710,88111,3889,62212,00313,39411,48112,1406,9776,3675,9585.8647,2667,9527.0107,461245.0150.9302.1100.0151.0151.0150.8301.80.2350.2400.3120.2050.2110.2280.2030.1961.7681.4751.2791.2391.9022.2851.7752.0234.3653.6583.3552.9854.6055.6124.2704.841USARRevision82of2November1995

NineMilePointUnit2FSARTABLE2.5-13TRIAXIALTESTRESULTS(T-3-3SERIES)ResultsfromTriaxialCompressionTestingofRockSamplesfromBoringT-3-3ConfiningPressureSamplePorePressureYoung'sModulusMaximumStressRockTypeSiltstone/shaleSiltstone/shaleSandstoneSandstoneSiltyshaleSiltyshaleSiltyshaleSiltyshaleSiltyshaleFormationPulaskiUnitAPulaskiUnitAPulaskiUnitAPulaskiUnitAPulaskiUnitBPulaskiUnitBPulaskiUnitBPulaskiUnitBPulaskiUnitBpsi200200200200200200400400400kg/cm'414282828psl200200kg/cm~psix10'.564.626.706.713.644.103.603.983.90x10~kg/cm'.213.254.714.722.562.882.532.802.74psi11,65915,69737,43540,90610,41010,53213,5367,4598,128kg/cm'201,1032,6322,8772,876740952524571NOTE:Longaxlesofcylindricalsamplesisperpendiculartobedding.USARRevision81of1November1995

NineMilePointUnit2TABLE2.5-15TRZAXIALTESTRESULTS(RTSERIES)TestNo.SampleNo.RockTypeRelationofTestSpecificationAxistoBedding(deg)*ConfiningPressure(psi)MaximumPointDifferentialStress(psi)MaximumPointStrain(4)Young'sModulus(psix10~)MaximumStrainUnderConfiningPressure(41123456789101112131415161718192021222324252627282930RTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRTRT1-11-11-12-72-72-72-72-72-72-72-72-71-221-221-221-221-221-221-221-221-221-511-511-511-511-511-511-511-511-51SandstoneSiltstoneGraywacke909090909090454545000909090454545000909090454545000507501,500507501,500507501,500507501,500507501,500507501,500507501,500507501,500507501,500507501,50031,74537,01239,0559,58811,58612,4087,0737,8647,5719,86112,01612,4998,5839,4859,8484,1143,9905,9134,8578,2869,40612,05410,39312,2505,6687,11611,2089,48810,62811,1550.810.971.060.780.921.050.520.670.690.470.620.741.031.151.160.530.590.940.380.580.710.901.021.220.500.690.860.400.570.675.635.625.061.611.701.751.601.581.622.422.522.421.281.441.480.810.871.001.601.982.091.961.701.581.321.461.772.962.372.375.445.756.413.032.793.122.533.012.682.853.063.113.273.253.222.062.293.432.263.873.963.433.433.493.262.713.392.972.963.16BeddingistakentobeperpendiculartothebulksamplecoreaxisUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5<<16UNZAXZALMODULUSDETERMINATIONSSpecimenNo.RT1-3ART1-4ART1-6ARTl-12ART2-2ART2-6ART1-56ART1-56BRT1-17ART1-20ART1-26ART1-36ADepth(ft)18.9-19.120.5-20.6523.9-24.2531.3-31.525.55-25.9526.9-27.396.7-97.196.7-97.141.6-42.046.0-46.451.2-51.351.55-61.95RockandFormationSandstoneOswegoSandstoneSandstoneOswegoSandstoneSandstoneOswegoSandstoneSiltstone(sandy)TransitionZoneSiltstone(shaly)TransitionZoneSiltstone(sandy)TransitionZoneSiltstone(shaly)PulaskiBSiltstone(shaly)PulaskiBGraywackePulaskiAGraywacke(silty)PulaskiAGraywacke(shaly)PulaskiSiltysandstoneandgraywacke(silty)PulaskiUnit1909045909010'siE,4.084.124.421.121.121.146.274.826.287.266.767.94uIx0.1680.1680.1670.3300.3330.3210.3310.350.0.3300.1750.2420.21110'siE5.203.155.224.974.415.451.934.704.653.915.934.487.150.2920.4450.3200.2700.2970.2700.1770.3310.4160.3600.3790.6540.2840.0960.1250.1140.4030.4460.3930.4280.4370.4890.4850.6320.7260.61910'siEi2.371.792.603.293.563.423.203.183.57StressRange(psi)2ndloading218-18652ndunloading4662-3113rdloading311-31082ndloading377-18402ndunloading1950-2203rdloading220-31452ndloading109-18762ndunloading1076-1253rdloading125-31272ndloading156-19072ndunloading1907-1563rdloading156-31272ndloading125-18702ndunloading1870-1253rdloading125-18702ndloading140-23412ndunloading2341-943rdloading94-18731stloading188-1407(specimenfailed)2ndloading63-14082ndunloading1408-1253rdloading125-19402ndloading94-19072ndunloading1970-943rdloading94-31272ndloading188-18782ndunloading1878-1563rdloading156-15652ndloading1876-312ndunloading1876-313rdloading31-31272ndloading157-19422ndunloading1911-1253rdloading125-1927USARRevision81of2November1995

NineMilePointUnit2FSARTABLE2.5-16(Cont'd.)Speci~enNo.RTl-61ARTl-61BRT1-62DDepth(Xt)105.7-106.1105.7-106.1106.4-106.9RockandFormationShale(silty)PulaskiCShale(silty)PulaskiCShale(silty)PulaskiCioa904510'siE,2.682.852.81uax0.6820.6560.65510'siE4.614.074.710.4370.4230.4010.5170.5370.52410cpsiEi1.391.461.43StressRange(psi)2ndloading111-22222ndunloading2222-1673rdloading167-22222ndloading56-16692ndunloading1669-1673rdloading167-16692ndloading56-16802ndunloading1680-1123rdloading112-1680i"eincanat>onocoretobedding.USARRevision82of2November1995

NineMilePointUnit2FSARTABLE2.5-17YOUNG'SMODULUSDETERMINEDBYBIAXIALTEST(modulusx10'si)LithologicUnitOswegoSandstoneTransitionZoneofOswegoSandstonePulaskiFormationUnitAPulaskiFormationUnitBPulaskiFormationUnitCWhetstoneGulfFormationUnitAWhetstoneGulfFormationUnitBTotalRockTypeTestedSandstoneSandstone,shale,andgraywackeGraywackeandsandstoneSandstoneShale,siltstone,andsandstoneSandstoneSandstoneNo.Tests37175231148Minimum1.62.71.83.21.91.6Mean5.1Maximum8.57.98.37.15.88.5StandardDeviation(x10'si)1.531.251.280.700.990.10.81.34USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-18SWELLTESTRESULTSSampleNo.RT2-1TD-1TestNo.RockTypeSandstoneSandstoneOswegoOswegoRockUnitTestTypeSwellStrainFreeSwellVerticalStressO(psi)25HorizontalStressOR(psi)75-140FirstStressInvarianta,+2a,(psi)175-305VerticalSwellStrainRate(10-'ellog>>day)HorizontalSwellStrainRate(10i%/logday)TD-2RT1-14RT114RT1-15RT1-15RT1-9RT1-9RT1-10RT1-10RT2-4RT2-4TD-1TD-1TD-1RT1-23RT1-23RTl-24RT1-29RT1-37RT1-171818252521211014SandstoneShaleShaleShalewithsiltstonelensesShalewithsiltstonelensesSiltstoneSiltstoneSiltstoneSiltstoneSandysiltstoneSandysiltstoneGraywackeShalesiltstoneSandstoneGraywackeGraywackeGraywackeGraywackeGraywackeGraywackeOswegoTransitionZoneTransitionZoneTransitionZoneTransi.tionZoneTransitionZoneTransitionZoneTransitionZoneTransitionZoneTransitionZoneTransitionZoneTransitionZoneTransitionZoneTransitionZonePulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAFreeSwellSwellStrainSwellStrainSwellStrainSwellStrainSwellStrainSwellStressSwellStressSwellStressSwellStressSwellStressFreeSwellFreeSwellFreeSwellSwellStrainSwellStrainSwellStrainSwellStzainSwellStrainSwellStrain3719371972857012011511547232323-47636344-7588-10760-112110-14056-727575-11110490-150155-178110-130130-148133-1615293-148150-170125-187195-233157-261254-299180-220238220-292328295-415425-471267-307283-319289-345127-151249-359360-403121212.410.44.03.00.255.05.01.70.91.20.550.70.751.650.44.23.20.350.90.80.52.10.9USARRevision8lof3November1995

NineMilePointUnit2FSARTABLE2.5-18(Cont'd.)SampleNo.TestNo.RockTypeRockUnitTestTypeVerticalStressG(psi)HorizontalStressaR(psi)FirstStressInvariantc+26(psi)VerticalSwellStrainRate(10i%/log>>day)HorizontalSwellStrainRate(10'0/logday)RT1-44RT1-44RT1-30RT1-30RT1-33RT1-33RT1-48RT1-40TD-1TD-1TD-1TD-1RT1-52RT1-52RT1-55RT1-60TD-1TD-1TD-1TD-1TD-1TD-12020722217171919211012131416GraywackeGraywackeGraywackeGraywackeGraywackeGraywackeGraywackeGraywackeGraywackeSandstoneGraywackeGraywackeShaleShaleShaleSiltyshaleGraywackeSandstoneShaleShalewithsandstonelensesShalewithsandstoneinterbedsInterbeddedshale,sandstoneandsiltstonePulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiAPulaskiBPulaskiBPulaskiBPulaskiCPulaski.BPulaskiBPulaskiBPulaskiBPulaskiCPulaskiCSwellStrainSwellStrainSwellStressSwellStressSwellStressSwellStressSwellStressSwellStressFreeSwellFreeSwellFreeSwellFreeSwellSwellStressSwellStressSwellStressSwellStressFreeSwellFreeSwellFreeSwellFreeSwellFreeSwellFreeSwell666655-220220-60020-4545-706060-750200-460460-55075-22501130-165165-1900-6060-70120-160160-17075-110110-12050-100100130-140127-150324-396396-44655-340340-740260-365365-410210-280280-315300-660600-750335-505335-38105.54.05.60.1812.00.3513.10.226.017.016.41.70.770.251.40.25'.550.52.20.45.05.30.30.40.457.37.06.46.7USARRevision82of3November1995

NineMilePointUnit2FSARTABLE2.5-18(Cont'd.)SampleNo.RT1-63RT166RT1-77RT1-77TestNo.17RockTypeSiltstoneSiltyshaleSiltyshaleSiltyshaleSiltyshaleRockUnitPulaskiCWhetstoneGulfAWhetstoneGulfAWhetstoneGulfAWhetstoneGulfATestTypeFreeSwellSwellStrainSwellStrainSwellStrainSwellStrainVerticalStressc(psi)8213113065HorizontalStresscR(psi)120-105111-18075-110125-145FirstStressInvarianta+2c(psi)322-452353-491280-350315-355VerticalSwellStrainRate(10i%/lo9>>day)15.212.58.00.11.25HorizontalSwellStrainRate(10~%/logioday)1.51.350.950.75USARRevision83of3November1995

NineMilePointUnit2FSARTABLE2.5-19TRZAXZALSWELLANDCREEP'TESTRESULTSStrainRates(10~/min)'"RockTypeSiltyshaleBlackshaleGraywackewithsiltlensesGraywackewithsiltlensesGraywackewithsiltlensesSiltyshaleSiltyshaleo'ampleNo.RT1-35CRT2-12BRT1-47ART1-28ART1-28BRT1-35ART1-35BCellPressure(psi)90040629900406299004062990040629406203291,39340620344Cycle11,300-891,8007,200-2,800-2,800-280-1,100-1,800560280560-1,000-89012,0006,900-740-370AxialCycle274028-1601,000-5628-860110-320-610-56-28-190470-1,100-260-56-110Cycle313-6432120-32250210110-100160-12825011-12-200-60-32-24Cycle1190897401,5000-278-5,000560-3,500-1,700-370-1,000-5,000190-190-3,200-1,1000280CircumferentialCycle2100-37-64-42056-250140-630-2809200-33028-9-240-2500-19Cycle310-7454075411083-39021791207-5-50-26-5-8Swellstrainsarepositive;shrinkagestrainsarenegative.Denotestestedspecimenwassealedtopreventwaterlossorgain.Othertestswereexecutedwithwatersuppliedtospecimen.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-21EXPLORATIONATTHEUNIT2SITEAFTERGENERALSITEEXPLORATION(POST-PSAR)ZnvestigationDateScopeofWorkFSARSectionReferenceGeneralexcavationmapping5/75through8/76Mappingand/orphotographingallCategoryIexcavationsandanomalousfeatures.2.5.4.3Appendix2H2.5.1.2.3ThruststructureswithinpowerblockcomplexCoolingTowerfault(geologicinvestigation)CoolingTowerfault(geologicinvestigation)8/76through9/769/76through4/789/76through4/78DetailedmappingandphotographsNorthandsouthradwastetrenchesNorthwallheaterbayCirculatingwaterintakeSoutherncirculatingwaterpipingencasementNormalswitchgearbuildingNorthwestreactornotchRadiometricdating(K/Ar)ofclayPalynologicanalysisofunconsolidatedclayFractureandfoldgeometricanalysisDetailedmappingExploratoryexcavationsPit1Trench3Trench4Trench5ExistingexcavationsCirculatingwaterpipingtrenchCoolingtowerexcavationDrainageditchIntakeshaftGeometricanalysisofdeformationalfeaturesAllexposureslistedaboveBoringprogramSubsurfacestratigraphyandstructureattwolocationsalongCoolingTowerfault(totalof24borings)T-3andT-4seriesStandardboringandgeophysicallogsDownholeimpressionpackersurveyMineralizationstudiesFluidinclusionanalysisofmineralizationfromsurficialexposuresandrockcores2.5.1.2.32.5.1.2.32.5.1.2.3Appendix2H2.5.1.2.32.5.1.2.32.5.1.2.6Reference94Vol.I,Section3.4DamesEMoore,1976Reference94,Vol.I,Section3.4Reference94,Vol.I,Sections3.2and3.4Reference94,Reference94,Reference94,Reference94,Reference94,Vol.I,Section4.0Vol.I,Section4.0Vol.I,Section4.0Vol.I,Section4.0Vol.I,Section4.0Reference94,Vol.I,Section4.0Reference94,Vol.I,Section3.3Reference94,Vol.I,Section3.3Reference94,Vol.I,Section3.4Reference94,Vol.I,Section5.0Reference94,Vol.I,AppendixI-AReference94,Vol.I,AppendixI-BReference94,Vol.I,Section6.0Reference94,Vol.I,Section6.3andAppendixI-EUSARRevision81of5November1995

NineMilePointUnit2FSARTABLE2.5-21(Cont'd.)InvestigationDateScopeofWorkFSARSectionReferenceCoolingTowerfault(geomorphologyinvestigation)CoolingTowerfault(rockmechanicsinvestigation)9/76through4/761/77through4/78X-raydiffractionanalysisofbedrocksamplesUraniumseriesagedatingofcalciteStratigraphyandageofunconsolidatedsedimentsC-14agedatingPalynologicAnalysesGrainsizeanalysesMineralogicandX-raydiffractionanalysesAerialphotographinterpretationStressmeasurementsbyovercoringNumerousmeasurementsinboringsOC-1throughOC-9LogsofboringsOC-1throughOC-9StressmetersinstalledinboringsOC-1,OC-2,OC-S,andOC-7AnalysisofresidualstrainreliefbyundercoringMeasurementsfromfivecores2.5.1.2.22.5.1.22.5.4.1.42.5.4.1.4Reference94,Vol.I,Section6.4andAppendixI-FReference94,Vol.I,AppendixI-GReference94,Vol.Z1,Section1.4Reference94,Vol.ZZ,Section1.4andAppendixZZ-AReference94,Vol.I,AppendixI-AandVol.ZZ,Section1.4andAppendixII-BReference94,Vol.ZZ,Section1.4andAppendixZZ-CReference94,Vol.ZZ,Section1.4andAppendixIZ-DReference94,Vol.ZZ,Section1.4.3Reference94,Vol.IIZ,Section3.0andAppendixZZZ-CReference94,Vol.ZZZ,AppendixZII-DReference94,Vol.IZI,Section4.0andAppendixIIZ-GAdditionalrockmechanicsinvestigationandinitialrockmonitoringprogram3/77through6/82MeasurementsofunconfinedswellingstrainMeasurementsofseventeencoresundervarietyofrelativehumidityconditionsSamplesfromboringTD-1MeasurementofgroundwaterlevelsinvicinityofCoolingTowerfaultStandpipesinstalledinboringsT-4-7,T-4-9,T-4-10,andT-4-11Waterlevelsmonitored9/30/77to1/19/78InclinometerinstallationandmonitoringI-1throughI-4aroundcirculatingwaterpipingtrenchandintakeshaftBoringlogsI-1throughI-42.5.4.1.42.4.132.5.4.13Appendix2KReference94,Vol.ZZZ,Section6.0andAppendixIIZ-KReference94,Vol.IIZ,AppendixZZZ-DReference94,Vol.-IZZ,Section5.0andAppendixIIZ-JUSARRevision82of5November1995

NineMilePointUnit2FSARTABLE2.5-21(Cont'd.)InvestigationDateScopeofWorkFSARSectionReference4/77through11/7819856/77through6/8211/7711/77through2/78Testexcavationandmonitoringoftrench5alongCoolingTowerfaultInclinometersIt-1throughIT-5TapeextensometermeasurementarrayPreciselevelingsurveyDisplacementmonitoringof12-linewallExtensometerinstallationandmonitoringMPX-1andMPX-2(multipointwireextensometers)adjacenttointakeshaftandreactorcontainmentexcavationsBoringlogsMPX-1andMPX-2GeophysicalsurveysBoringsGP-1,GP-2,andRT-1StandardlogsofboringsGeophysicallogs(caliper,gamma,density,and3-Dvelocity)UpholecompressionalwavesurveyCrossholecompressionalwavesurveyCrossholeshearwavevelocitysurveyTestingofrocksamplesfromboringsRT-1andRT-2BoringlogsRT-1andRT-2DirectsheartestsonbeddingRingtests;swellingstrain,swellingstress,creepstrainTriaxialswellandcreeptestsUniaxialcompressiontestsTriaxialstrengthtestsDeterminationofelasticparameters:Young'smodulusandPoisson'sratioparallelandperpendiculartobedding,andshearmodulus2.5.4.13Appendix2K2.5.4.132.5.4.13Appendix2K2.5.4.4Appendix2K2.5.4.42.5.4.2Appendix2K11/77through2/78StressmeasurementsbyovercoringStressdeterminationsinBoringOC-100LogofBoringOC-1002.5.4.1.4Appendix2KUSARRevision83of5November1995

NineMilePointUnit2FSARTABLE2.5-21(Cont'd.)InvestigationDateScopeofWorkFSARSectionReferenceRadwastethruststructure(geologicinvestigation)4/79through10/80DetailedmappingofvariousfoundationexcavationsCirculatingwaterpipingexcavationRelocatedcoolingtowerexcavationNorthradwastetrenchEastlakewaterintaketunnel2.5.1.2.3Appendix2HReference154,Section2.14/79through10/80AnalysisofstructuralelementsfrommappedareasBoringprogramSubsurfacestratigraphyandstructurewestofsurficialexposureofradwastefault(totalof9borings)Standardboringandgeophysicallogs,Borings801through810Downholetelevisionsurvey2.5.1.2.32.5.1.2.3Reference154,Section2.1Reference154,Section2.2andAppendixAReference154,AppendixARockmechanics(intakeshaft)11/79through1985MineralizationstudiesFluidinclusionanalysisofmineralizationfromexposuresofthruststructuresandrockcoresC-13and0-18analysisofcalciteAgedatingC-14analysisofcalciteunconsolidatedsedimentfromwithinthruststructuresUraniumseriesdatingofcalcitePalynologicanalysisofsedimentsMineralogicanalysisofunconsolidatedsedimentswithinthruststructuresInstallationofinstrumentationinvicinityofintakeshaftZnclinometersSZ-1throughSZ-7ExtensometersEX-1throughEX-4(multipointrodtype)PiezometersPZ-1throughPZ-4(2transducerseach)BoringlogsofSZ,EX,andPZboringsTapeextensometermeasurementarraysatfourlevelsinshaft2.5.1.2.62.5.1.2.32.5.1.2.62.5.1.2.32.5.4.132.4.13Appendix2K2.5.4.2Reference154,AppendixB.2Reference154,Section2.3Reference154,AppendixB.2Reference154,Reference154,C.2Reference154,AppendixC.3AppendixB.3AppendixC.landSection2.3,Reference154,Section2.3andAppendixB.lUSARRevision84of5November1995

NineMilePointUnit2FSARTABLE2.5-21(Cont'd.)InvestigationRadwastethruststructure(rockmechanicsinvestigationGeophysicalsurveyRockmassdisplacementmonitoringprogramDate2/80through10/807/808/81through1985ScopeofWorkStressmeasurementsbyovercoringnumerousmeasurementsinboringsRS-1throughRS-4LogsofBoringsRS-1throughRS-4InstallationofinclinometersinthrustblockZnclinometersinstalledinBorings803,805,806,810,andRS-2Groundmagnetometersurvey(acrosstraceofhigh-anglefaults)InstallationandmonitoringofinstrumentsinandaroundsiteexcavationsZnclinometersIntakeshaft,SI-8,SZ-9,SZ-10ReactorcontainmentSI-20throughSZ-23Radwastethrustblock820,821Extensometers(multipointrodtype)ZntakeshaftEX-5andEX-6ReactorcontainmentEX-20andZIEX-1PiezometersIntakeshaftPI-5ReactorcontainmentPZ-20andPZ-21BoringlogsofaboveboreholesVariousdisplacementmonitoringgaugeswithinsiteengineeringstructuresFSARSection2.5.4.1.42.5.4.22.5.1.2.32.5.4.13Appendix2KReferenceReference154,Section3.0andAppendicesE.1andE.3Reference154,AppendixE.2Reference154,ResponsetoNRCQuestionQ361.26USARRevision85of5November1995

NineMilePointUnit2FSARTABLE2.5-22PARTICIPANTSOFPOST-PSARINVESTIGATIONSInvestigationDateParticipantContributionGeneralexcavationmappingThruststructureswithinthepowerblockcomplexCoolingtowerfaultAdditionalrockmechanicsinvestigationandinitialmonitoringprogram5/75to19838/76through9/769/76through4/7811/77through2/78Stone&WebsterEngineeringCorporationDames&MooreDr.F.A.Donath,CGS,Znc.KruegerEnterprises,Znc.,Cambridge,MADr.I.A.Sirkin-AdelphiUniversity,NYDames&MooreDr.F.A.DonathDr.D.Coates,SUNY,Binghamton,NYDr.S.Alexander,PennsylvaniaStateUniversityDr.H.L.Barnes,PennsylvaniaStateUniversityDr.A.H.Vassiliou,Rutgers,theStateUniversityDr.Teh-LungKu-UniversityofSouthernCaliforniaDr.L.A.SirkinBrockUniversity,Toronto,CanadaTeledyneIsotopes,Westwood,NJKruegerEnterprises,Inc.Dr.N.J.Price,ImperialCollege,London,EnglandDames&MooreBirdwellGeophysicalCompanyFranklinTrowAssociates,Ltd.,Toronto,CanadaCGS,Inc.,Urbana,ZLWoodwardClydeAssociatesArchitect-engineer,allfoundationexcavationmappingPrincipalinvestigatorAssessmentofgeologicstructuresK/AragedatingPalynologicanalysisPrincipalinvestigatorNMPCreviewpanelmemberNMPCreviewpanelmemberNMPCreviewpanelmemberFluidinclusionanalysis,oremicroscopy,X-raydiffractionMineralogicanalysis,X-raydiffraction,X-ray,fluorescenceUraniumseriesagedatingPalynologicanalysisC-14agedatingC-14agedatingC-14agedatingAssessmentofevolutionofbedrockstressesPrincipalinvestigatorDownholegeophysicalsurveyRocktestingRocktestingRocktestingRadwastethruststructure4/79through10/80Dames&MooreDr.F.A.DonathDr.D.CoatesDr.S.AlexanderDr.S.S.PhilbrickDr.R.H.Johns,Mr.W.W.MooreDr.T.Z.Pewe,Tempe,AZDr.C.Fairhurst,UniversityofMinnesota,Minneapolis,MNprincipalinvestigatorNMPCreviewpanelmemberNMPCreviewpanelmemberNMPCreviewpanelmemberDames&MoorereviewpanelmemberDames&MoorereviewpanelmemberDames&MoorereviewpanelmemberAssessmentoforiginofclaydeformationAssessmentofpotentialfordifferentialmovementonradwastestructureUSARRevision81of2November1995

NineMilePointUnit2FSARTABLE2.5-22(Cont'd.)InvestigationDateParticipantContributionRockmechanicsinvestigationofintakeshaft11/79through1985Dr.N.J.PriceDr.I.A.SirkinDr.J.Dr.H.Dr.T.Dr.H.Dr.A.Dames&MooreDr.C.FairhurstTerasmae,BrockUniversityKruegerL.KuL.BarnesH.VassiliouRockmechanicsassessmentofradwastestructureAssessmentoforiginofclaydeformationandpalynologicanalysesPalynologicanalysesIsotopicandradiometricanalysesUraniumseriesagedatingParageneticandfluidinclusionanalysesMineralogicalanalysesPrincipalinvestigatorReviewerRockmassdisplacementmonitoringprogram8/81through1985Dames&MooreDr.C.FairhurstDr.E.D.McKay,CGS,Inc.Dr.B.SellersMr.J.Dunnicliff,P.E.Dr.F.A.DonathDr.S.AlexanderDr.D.CoatesOverallresponsibilityforinstallationandmonitoringprogramPrincipalinvestigatorStaffinvestigatorprovidingcoordinationbe-tweenDames&MooreandprincipalinvestigatorInstrumentationconsultantInstrumentationconsultantNMPCreviewpanelmemberNMPCreviewpanelmemberNMPCreviewpanelmemberUSARRevision82of2November1995

NineMilePointUnit2FSARTABLE2.5-23SUMMARYOFBORINGSCOMPLETEDONTHENINEMILEPOINTSITEBoringSeriesYear(s)CompletedTotalNo.BoringsRangeofDepth(ft)PurposeCoreSample(Yes/No)100200300400T-3TDGPRT800MPXHEXSIPI1963196819681971-721977197719771977-78197719781977-781977198019801977-791979,198119811979,19811979,198119771977197921153110131010-10012-15075-19852-205176-22290-342160-16122-)16106360-36140-350115-13294-12590-300115-165151-162155151-20588-12750-1502043-95FoundationinvestigationUnit1FoundationinvestigationproposedfacilityFoundationinvestigationJAFplantFoundationinvestigationUnit2CoolingTowerfaultsubsurfaceinvestigationCoolingTowerfaultsubsurfaceinvestigationCoolingTowerfaultsubsurfaceinvestigationStressmeasurementsFreeswelltestingGeophysicaltestingRocktestingFoundationinvestigationlakewatertunnelsStressmeasurementsRadwastefaultinvestigationandrockmonitoringRockmonitoringUnit2RockmonitoringUnit2RockmonitoringUnit2RockmonitoringUnit2RockmonitoringUnit2RockmonitoringUnit2RockmonitoringUnit2PiezometerinstallationUnit2YesYesYesYesYesYesYesYesYesYesYesYesYesYesYesYesYesYesYesNoNoNoUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5"25TRIAXIALSHEARTESTRESULTSSource:MeanyAirportRoadPitConfiningPressure:U,=69kn/m'10psi)AxialDeviatorInducedPrincipalPoreNormalizedDataStressPathStrain(4)psiStresskn/mlPorePressure(kn/m')StressRatioPressureParameterDeviatorStressPorePressurekn/m'sl.psiZ457kn/ml0.00.040.100.180.290.440.781.171.622.353.174.205.568.4411.7714.650.04.510.118.628.738.145.343.839.738.136.135.136.234.735.035.50.031.270.1128.9198.0263.2313.2302.6274.6263.2249.4242.4250.0239.4241.5245.20.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.01.0001.4522.0162.8693.8704.8155.5395.3854.9794.8144.6144.5134.6244.4704.5014.5530.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.4521.0161.8692.8703.8154.5394.3853.9793.8143.6143.5133.6243.4703.5013.5530.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.015.635.064.599.0131.6156.6151.3137.2131.6124.7121.2125.0119.7120.8122.60.02.25.09.314.319.022.721.919.819.018.017.518.117.3(17.5)(17.7)10.012.215.019.324.329.032.731.929.829.028.027.528.127.3(27.5)(27.7)69.084.6104.0133.5168.0200.6225.6220.2206.2200.6193.7190.2194.0188.7189.8191.6USARRevision81of1November1995

NineMilePointUnit2PSARTABLE2.5-26TRZAXIALSHEARTESTRESULTSSource:MeanyAirportRoadPitConfiningPressure:a,=138kn/m'20psi)AxialDeviatorInducedPrincipalPoreNormalizedDataStressPathStrain(4)psiStresskn/m~PorePressure(kn/m~)StressRatioPressureParameterDeviatorStressPorePressurekn/m~psipsiE45kn/m'.00.050.100.160.310.560.560.801.101.592.133.194.345.226.989.4011.8214.240.06.612.618.833.949.349.358.061.861.661.362.061.761.762.363.665.065.70.045.787.2129.8233.9340.4340.4400.7426.6425.0423.1428.1425.7425.7430.5439.4448.5453.80.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.01.0001.3311.6321.9402.6953.4663.4663.9044.0914.0804.0654.1024.0854.0874.1194.1844.2504.2890.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.3311.6320.9401.6952.4662.4662.9043.0913.0803.0653.1023.0853.0873.1193.1843.2503.2890.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.022.843.664.9117.0170.2170.2200.4213.3212.5211.5214.1212.9212.9215.2219.7224.3226.90.03.36.39.416.924.624.629.030.930.830.631.030.830.831.131.832.532.820.023.326.329.536.944.644.649.050.950.850.651.050.850.851.151.852.552.8138.0160.8181.6202.9255.0308.2308.2338.4351.3350.5349.5352.1350.9350.9353.2357.7362.3364.9USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-27TRZAXIALSHEARTESTRESULTSSource:MeanyAirportRoadPitConfiningpressure:U,=276.0kn/m'40psi)AxialDeviatorInducedPrincipalPoreNormalizedDataStressPathStrain(4)pslStresskn/m1PorePressure(kn/m')StressRatioPressureParameterDeviatorStressPorePressurekn/m1pslPS1E45kn/m'.00.040.100.210.360.631.031.542.363.304.496.017.7810.8113.3915.060.08.6,19.031.447.264.979.989.397.8104.3110.5116.8121.5128.8133.2134.3059.8131.1216.9325.9448.4551.8616.3675.1719.9762.8806.1838.9889.3919.6926.90.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.01.0001.2161.4751.7862.1812.6242.9993.2333.4463.6083.7643.9214.0404.2224.3324.3580.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.2160.4750.7861.1811.6241.9992.2332.4462.6082.7642.9213.0403.2223.3323.3580.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.029.965.6108.5162.9224.2275.9308.2337.6359.9381.4403.1419.5444.7459.8463.40.04.39.515.723.632.439.944.648.952.155.258.460.764.466.667.14o.o44.349.555.763.672.479.984.688.992.195.298.4100.7104.4106.6107.1276.0305.9341.6384.5438.9500.2551.9584.2613.6635.9657.4679.1695.5720.7735.8739.4USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-30PZEZOMETERREADINGS,PZ-SERIESWaterLevelElevation(ft)DateShaftWaterLevelElev.(ft)ASensorPI-1BSensorASensorPI-2BSensorASensorPI-3BSensorASensorPI-4BSensor11/12/7912/09/7912/12/7912/17/7912/19/7912/21/7912/28/7901/03/8001/17/8001/29/8002/11/8003/17/8004/14/8005/21/8006/18/8007/21/8009/04/8010/17/8012/01/80186.0177.0143.5142.0140.0140.0140.0136.0135.0130.0130.0130.0130.0130.0130.0130.0123.0123.0184.1184.5178.3151.3150.4149.0149.5148.5138.8190.2189.7185.6184.2184.2184.2183.8183.3188.6184.9182.1164.6162.2164.2164.2163.7196.9197.3197.8196.9196.4196.9195.5195.0195.5206.1209.6198.7198.3198.3201.0202.3202.0202.9202.0184.9180.8155.8155.4154.5156.5156.3141.5136.9139.6137.8136.0135.5136.0136.0135.5134.2132.3184.2185.6184.2184.7184.7184.7184.2184.7204.3197.9207.8189.1189.1187.7188.2185.4185.4188.2184.5184.0182.6183.1183.1182.6181.3202.8198.6195.8KEY:=WaterlevelbelowsensorlevelNR=NoreadingNOTE:Sensorelevationsare:PZ-1A131.0PZ-2A160.0PI-3A130.0PZ-4A160.5PZ-1B'PI-2BPI-3BPZ-4B181.0189.5181.0194.0USARRevision81of1'fNovember1995

NineMilePointUnit2PSARTABLE2.5-31SUMMARYOPCYCLICTRIAXIALTESTSBORROWSOURCE:CHAUVINPITInitialAfterConsolidationkN/aPpcfDryUnitWeightRelativeDensity(4)kN/m~pcfDryUnitWeightRelativeDensity(4)EffectiveConsolidationPressurepsiBatEndofConsolidationkN/m'siCyclicDeviatorStress2.5$10%PailureinExtensionNumberofCyclesto:DoubleAmplitudeStrain17.918.018.018.018.018.018.017.918.018.218.118.318.218.218.118.218.218.418.518.318.318.418.418.418.418.418.4(113.7)(113.8)(114.3)(114.3)(113.9)(114.4)(113.9)(113.7)(114.1)(116.1)(115.1)(116.5)(115.9)(116.2)(115.7)(115.8)(115.9)(117.1)(118.0)(117.0)(117.0)(117.1)(117.5)(117.2)(117.3)(117.1)(117.3)68697373707370697184778682848182829095898990929091909118.018.018.018.018.018.118.118.118.118.218.118.318.318.318.318.318.318.418.518.418.418.418.518.518.518.518.5(113.8)(113.9)(114.4)(114.5)(114.4)(114.9)(114.8)(114.6)(115.0)(116.2)(115.4)(116.61(116.41(116.7)(116.6)(116.6)(116.7)(117.2)(118.1)(117.1)(117.1)(117.5)(118.0)(117.7)(118.11(117.8)(118.1)69707374737676747784798785878787879095909092959395949549.049.049.049.0147.1147.1294.2294.2294.249.049.049.0147.1147.1294.2294.2294.249.049.049.049.0147.1147.1147.1294.2294.2294.2(7.11)(7.11)(7.11)(7.11)(21.33)(21.33)(42.66)(42.66)(42.66)(7.11)(7.11)(7.11)(21.33)(21.33)(42.66)(42.66)(42.66)(7.11)(7.11)(7.11)(7.11)(21.33)(21.33)(21.33)(42.66)(42.66)(42.66)0.840.970.970.970.960.920.931.000.970.970.950.930.950.930.990.940.940.980.900.960.950.920.880.960.940.930.9634.336.347.143.285.3114.7161.8135.3119.752.045.142.285.3114.7116.7143.2173.639.242.252.068.7100.085.3120.6146.1173.6201.0(4.98)(5.26)(6.83)(6.26)(12.38)(16.64)(23.47)(19.63)(17.26)(7.54)(6.54)(6.12)(12.38)(28.03)(16.93)(20.77)(25.18)(5.69)(6.12)(7.54)(9.96)(14.51)(12.38)(17.50)(21.20)(25.18)(29.16)46271010186728531329532275728111466626933172114327748281111196729531632562385829169733011361751344295029122030542036662585930304823513391801530121421783155279SOURCE:StoneawesterGeotechnicalLaboratory.Reference208.USARRevision81ofNovember1995

NineMilePointUnit2FSARTABLE2.5-32SUMMARYOFCYCLICTRIAXIALTESTSBORROWSOURCE:MEANYENGLESROADPITInitialAfterConsolidationkN/m'cfDryUnitWeightRelativeDensity('4)kN/sPpcfDryUnitWeightRelativeDensity(4)EffectiveConsolidationPressurepsiBatEndofConsolidationkN/aPpsiCyclicDeviatorStressNumberofCyclesto:2.5%10%FailureinExtensionDoubleAmplitudeStrain18.118.118.118.118.218.118.118.218.218.618.718.618.618.618.618.618.718.619.219.219.319.219.219.219.219.219.219.219.219.219.219.219.2(115.2)(115.3)(115.3)(115.2)(115.5)(115.4)(115.2)(115.5)(115.5)(118.51(118.7)(118.4)(118.5)(118.5)(118.5)(118.5)(118.8)(118.6)(122.1)(122.0)(122.6)(122.1)(122.1)(122.1)(122.2)(122.0)(121.9)(122.1)(122.2)(122.2)(122.3)(122.0)(122.0)50505050515150515160616060606060616070707270707071707070717171707018.118.118.118.118.218.118.218.218.218.618.718.618.618.618.618.618.718.719.219.219.319.219.219.219.219.219.219.219.219.219.219.219.2(115.2)(115.3)(115.3)(115.2)(115.5)(115.4)(116.0)(115.5)(115.5)(118.5)(118.7)(118.4)(118.5)(118.5)(118.5)(118.5)(118.8)(119.4)(122.1)(122.0)(122.6)(122.1)(122.1)(122.1)(122.2)(122.0)(121.9)(122.1)(122.2)(122.2)(122.3)(122.0)(122.0)505050505151525151606160606060606162707072707070717070707171717070147.1147.1147.1294.2294.2294.2440.3440.3440.3147.1147.1147.1294.2294.2294.2440.3440.3440.3147.1147.1147.1147.1147.1294.2294.2294.2294.2294.2294.2440.3440.3440.3440.3(21.33)(21.33)(21.33)(42.66)(42.66)(42.66)(63.99)(63.99)(63.99)(21.33)(21.33)(21.331(42.661(42.66)(42.66)(63.99)(63.99)(63.99)(21.33)(21.33)(21.33)(21.33)(21.33)(42.66)(42.66)(42.66)(42.66)(42.66)(42.66)(63.99)(63.99)(63.99)(63.99)0.960.980.960.950.950.950.950.950.950.950.950.950.930.950.940.900.940.950.950.950.980.950.950.960.950.930.960.950.960.910.910.910.9582.460.847.1163.8138.3111.8242.2182.4124.661.888.351.0166.7127.598.1257.9197.1163.878.562.8108.9175.6369.7128.5112.8136.3272.6303.0363.8317.8386.4257.9447.2(11.95)(8.82)(6.82)(23.75)(20.05)(16.21)(35.13)'26.46)(18.06)(8.96)(12.80)(7.40)(24.18)(18.49)(14.22)(37.40)(28.59)(23.75)(11.37)(9.10)(15.79)(25.46)(63.62)(18.63)(16.36)(19.77)(39.54)(43.95)(52.76)(46.08)(56.03)(37.48)(64.85)5199061015510711685582282618392684982278626859716562092611155117318105892385720413293131243192291277131121862193712166117320116211258992442451511617536109351699181529107239791418711732412821226969254248175182083714136179919153011SOURCE:Gorg-Zoxno-Dunnicliff&Associates,Inc.,Reference209.USARRevision81ofNovember1995

NineMilePointUnit2FSARTABLE2.5-45MAXIMUMRESPONSESOFINPUTEARTHQUAKESTODUCTLINES907AND922ANDMANHOLENO.1,CL-1EMaximumAccelerationHeleneRangeAvg.SantaAnitaRangeAvg.LakeHughesRangeAvg.Avg.Max.AccelerationofThreeEarthquakesDuctlines907and922,depthat10'-14'.17-0.184(g)0.18g0.247-0.292(g)0.27g0.247-0.3(g)0.27g0.24gManholeNo.1,CL-1E,depthat0'-17'.16-0.205(g)0.18g0.208-0.3280.27g0.208-0.3380.27g0.24gI'lNOTES:1.2.BasedonFigure2.5-151.Thecorrespondingfrequencyfortheburiedductlinesandmanholeisatleast20Hzforthemaximumaccelerationof0.24g.USARRevision8lof1November1995

vf///IlIIIIAg.ELjRI0"s.2o+UNITSVISITORINPORMATIONCENTERov~Is~<PLA4vII\~JIrIIIIrr~rhroCONTROLLEO07THECOASTOUAROOURINOEIIEROENCIESINACCOROANCEWITHLE'TEEROfAOREEIIENT~op>vrvIroro~Iv&LOLOviOP//V'NDEPENDENCEPLANT~NINENILEPOINTSITEJAIIESA.PIT?PATRICKSITEwYORKPOwER'.AUTHORITYPROPERTYLINENIAGARAMOHAWK~POWERCORPPROPERTYLINEIEXCLUSIONAREASOUNOARTIIIINESLTcohIih0ROADIIoNollhSelibo0oooo70voarIvsvolvore>>SCALEMILESISCALEAILOIIETEPSFIGURE2.1-2SITEBOUNDARIESANDTRANSPORTATIONROUTESNIAGARANOHAMKPOMERCORPORATIONNINEMILEPOINT-UNIT2UPDATEDSAFETYANALYSISREPORTUSARREVISION8NOVEMBER199

NineMilePointUnit2FSAR2~2NEARBYINDUSTRIALSTRANSPORTATIONgANDMILITARYFACILITIES2.2.1LocationsandRoutesOnlyonemanufacturingorindustrialplant,AlcanAluminumCorporation'sAlcanSheetandPlateDivision,islocatedwithin8km(5mi)ofUnit2.TherearealsothreeelectricalpowerIgenerationfacilities,theJ.A.FitzPatrickNuclearPowerPlantoperatedbyNYPA,Unit1operatedbyNMPC,andIndependenceGenerationPlantoperatedbySitheEnergiesUSA,locatedwithin8km(5mi)ofUnit2.Figure2.1-2showsthelocationofthesethreefacilitiesrelativetoUnit2.ITheprincipalproductsoftheAlcanAluminumCorporationplantarealuminumsheetandplate.Therearenochemicalplants,refineries,militarybases,orundergroundgasstoragefacilitieswithin8kmoftheplant.Inaddition,nofuelstorageIfacilitiesliewithinthe8-kmradiusexceptthosestoragefacilitiesassociatedwiththeAlcanplant,theFitzPatrickplant,Sitheplant,andUnits1and2.Twonaturalgaspipelinesliewithin8kmoftheplant;onepipelinesuppliestheSitheplantandtheothersuppliesINDECKEnergy.Botharelocatedonthenorth-southandeast-westtransmissionlinecorridors.Finally,therearenohazardouswastestorageordisposalsitespermittedbythestateinthe8-kmradiusfromtheplant.MajortransportationfacilitiesareshownonFigure2.2-1.Theprincipalroadwaywithin8kmofUnit2isU.S.Route104whichpasses6.2km(3.9mi)southoftheplantandconnectsthecityofOswegoandMexicoVillage.DailytrafficvolumeforU.S.Route104was5,841vehiclesin1979.Highwayaccesstothesiteisviatwocountyroutes,Route1AtothesouthwestandRoute29totheeast.Aprivateeast-westroadcrossesthesiteandconnectsthesetwocountyroutes.Otherlocalroadsinthevicinitygenerallyhadaveragedailytrafficcountsoffewerthan2,000vehiclesin1978-1979,themostcurrentsurveydates+.Table2.2-1presentsdailytrafficvolumecountsforcountyhighwayswithin8kmoftheplant.Onerailroadcompany,Conrail,transportsfreightinthevicinityoftheplant.TheraillinesandspursservingUnit2,aswellastheJ.A.FitzPatrickplantandUnit1,areshownonFigure2.1-2.TheclosestraillinetoUnit2istheOswego-MexicobranchofConraillocatedapproximately2.5km(1.5mi)fromtheNineMilePointsite.Thisbranchlinehasdailyserviceondemandandaveragesonetraindaily,5daysaweek.ArailspurwasconstructedtoserveUnit2duringconstructionandoperationoftheplant.Possiblesourcesoftrafficorhazardousmaterialsutilizinggroundtransportationrouteswithin8kmoftheplantareidentifiedanddetailedinSection2.2.3.TheOswegoRiverpasseswithin11to12km(6.6to7.2mi)ofUnit2atitsnearestpointandservesasamajorrouteforwaterbornecommerceonLakeOntario.FreighttrafficstatisticsUSARRevision82'-1November1995 NineMilePointUnit2FSARaremaintainedbytheU.S.ArmyCorpsofEngineers.TotalsfortheriversectionfromNewYorkStateBargeCanalLockNo.8totheportoftheCityofOswegoaretheonlystatisticsapplicableforthenearestreachofrivertotheStation.Table2.2-2detailsthe1978freighttrafficforthisreachofriver.ThePortofOswego,theeasternmostportonLakeOntario,islocatedapproximately11km(6.6mi)southwestofUnit2andprovidesalinkwithallportsontheGreatLakesandSt.LawrenceRiver.ShipsinnormalcommerciallanesboundtoandfromthePortofOswegopassnocloserthan11.3km(7mi)totheintakestructuresofUnit2.RegularcommercialairserviceisprovidedattheClarenceE.HancockAirport,located49.8km(31mi)southeastofUnit2nearSyracuse,NY.Thenearestflightcorridorassociatedwiththisairportis22.2km(13.8mi)fromtheNineMilePointStation.LightplanetrafficishandledattheOswegoCountyAirportinthetownofVolney,approximately19.3km(12mi)southoftheNineMilePointsite.LakesideAirstrip,aprivatefacilitywhichoperatesprimarilyasamaintenancefacilitywithverylittleairtraffic,islocatedalongRoute176approximately10km(6.2mi)southoftheNineMilePointsite.HelicopterserviceisprovidedforlocaltransportationbetweenHancockAirportandthesite.Theserviceinvolvesapproximately45to60flightsperyeartothreelandinglocationsonthesiteapproximately1000to2000feetwestandsouthofthereactorbuilding.Itisnotanticipatedthattherewillbeanysignificantincreaseinthenumberofindustrial,transportation,andmilitaryfacilitieslocatedwithinan8-kmradiusofUnit2overtheplantlifetime.TherearealsonosignificantchangesexpectedinthenatureofexistingfacilitiesortheextentoftheiractivitieswithinthedesignatedareaovertheprojectedlifetimeofUnit2.2.2.2Description2.2.2.1DescriptionofFacilitiesMajorindustrialfacilitieswithin8kmofUnit2arelistedinTable2.2-3.AlcanRolledProducts,locatedapproximately4.5km(2.7mi)southwestofNineMilePointStation,isthelargestemployerwithapproximately1,000workersmanufacturingaluminumsheetandplating.Nohazardousmaterialsaremanufacturedwithinthe8-kmradius.HazardousmaterialsstoredorusedarediscussedinSection2.2.2.2.TheNewYorkStateDepartmentofEnvironmentalConservationrecordsthetype,amount,androuteofhazardousmaterialscarriedinthestate.Oneraillinepassesthroughthe8-kmradius.ConrailhasabranchlineservingAlcanAluminum,Units1and2,andtheJamesA.FitzPatrickNuclearPowerPlant.Themainlineislocatedapproximately3.5km(2.1mi)atitsnearestpointfromUnit2.USARRevision82~22November1995 NineMilePointUnit2FSARWaterbornecommercestatisticspreparedbytheU.S.ArmyCorpsofEngineersonlypartiallyidentifyspecifichazardousmaterialsonLakeOntario.Commerceisrecordedbygeneralcommodity+.AlistingofhazardousmaterialsidentifiedandtheircommoditydesignationsisprovidedinTable2.2-4.HazardousmaterialstransportedbyairhavenotbeenidentifiedbecauseofthedistanceofairwaysandfacilitiesfromUnit2.2.2.2.2DescriptionofProductsandMaterialsToidentifyhazardousmaterialsregularlystoredorusedwithin8kmofUnit2,surveyswereconductedofindustrialfirms,pipelinecompanies,anddistributorsthatmightbeexpectedtohandletoxicchemicalsorexplosives.Appendix2Adescribesthemethodusedtocollectdataregardinghazardousmaterialsusedbyvariousindustriesnearthesite.HazardousmaterialsconsideredareincludedinTable2.2-4.ToxicchemicalsandexplosivesstoredorusedbyindustriesordistributorsinthevicinityoftheStationaresummarizedinTable2.2-5.Twonaturalgaspipelinesandasmallpropanedistributioncompanyarelocatedwithin8kmofUnit2.Waterbornecommercefor1978LakeOntariotrafficisdescribedinTables2.2-2and2.2-6.Approximately1.2milliontonsofcargoweretransportedonLakeOntario.Sincemorespecificcommoditycategoriesarenotusedindatacollection,therearenomeansofidentifyingtypes,frequency,andamountsofhazardousmaterialshipmentspastthesite.ThenearestpassageofcommercialvesselstoUnit2occurswhennavigatingtoandfromtheCityofOswegoharbor,locatedapproximately10km(6.2mi)fromNineMilePointStation.ThePortofOswegoAuthorityindicatesthatnoneofthehazardousmaterialslistedinTable2.2-5havebeentransportedonLakeOntario,eitheroriginatingatordestinedtothePortofOswego.AllindustriesreportedreceivinghazardousmaterialshipmentsviaU.S.Highway104andCountyRoute1bytruck.2.2.2.3ProjectionsofIndustrialGrowthTherearenoplansformajorexpansionintransportation,storage,orindustrialfacilitiesinthevicinityofUnit2.2.2.3EvaluationofPotentialAccidentsTheconsiderationofavarietyofpotentialaccidents,andtheireffectsontheplantorplantoperation,isincludedinthissection.Typesofaccidentsconsideredincludeexplosions,flammablevaporclouds,toxicchemicals,fires,collisionswithintakestructures,andliquidspills.USARRevision82~23November1995 NineMilePointUnit2FSAR2.2.3.1Dete'rminationofDesignBasisEvents2.2.3.1.1ExplosionsBasedonacomprehensivesurveyofindustrieswithina10-km(6.2-mi)radiusofUnit2,thenearesthighwayonwhichexplosivematerialscanbetransportedisRoute104,whichisadistanceofabout6.2km(3.9mi)fromsafety-relatedstructures.Thisseparationdistancefarexceedsthesafedistancefortrucktraffic(approximately548.6m,1,800ft)givenonFigure1ofRG1.91.IndiscussionswithConrail,itwasdeterminedthatnoexplosiveorflammablematerialsaretransportedtotheOswegoterminaloftheraillinebetweenOswegoandMexico,NY.Inanyevent,thedistancefromthisraillinetoUnit,2ismuchgreaterthanthesafedistanceforrailtrafficgiveninRG1.91.SincethenearestcommercialshippinglanesonLakeOntarioaremorethan10km(6.2mi)fromUnit2(accordingtotheU.S.CoastGuard),potentialexplosionsonashiporbargearenotconsideredadesignbasisevent.Thisdis'tanceiswellbeyondtheradiusofthepeakincidentpressureof1psiasgiveninRG1.91.Therefore,accordingtoguidancecontainedinRG1.91,explosionsonnearbytransportationroutesarenotconsidereddesignbasiseventsduetotheseparationdistancesofpotentialsourcesofexplosionsfromUnit2.2.2.3.1.2FlammableVaporClouds(DelayedIgnition)/PropanestoredattheJamesA.FitzPatrickplantistheonlypotentialsourceofaflammablevaporcloudthatmightaffecttheUnit2site'.Approximately3,7851(1,000gal)ofpropaneattheJamesA,.FitzPatrickplantisstoredabout700m(2,297ft)fromtheUnit2containmentbuilding.Ananalysishasbeenperformedtoassessthepotentialofa1-psioverpressureoccurringattheUnit2containmentbuildingasaresultofthedelayedignitionofaflammablevaporcloudofpropane.A.1-psioverpressureisthatpressurebelowwhichnosignificantdamagetocriticalplantstructuresisexpected,asdeterminedbytheU.S.NRCinRG1.91,"EvaluationsofExplosionsPostulatedtoOccuronTransportationRoutesNearNuclearPowerPlants."Thedelayedignitionanalysiswasperformedutilizingacomputerprogram(GASBLAST)thatcalculatestheextentandvolumeofthemixtureofairandgaseousexplosiveforagivensetofmeteorologicalconditionsandrichandleanconcentrationdetonabilitylimits.TheTNTequivalentandincidentblastpressureisobars,representedbyconcentriccirclesemanatingfromthecenteroftheplume,arethendetermined.Theprogramassumesthatthegasisreleasedatgroundlevelataconstantreleaserate.TheanalyticalmethodthatformsthebasisoftheprogramfollowsthecomputationalmodelestablishedbyBurgessandZabetakes'.TheblasteffectisdeterminedbyusingtheUSARRevision62.2-4April1994 NineMilePointUnit2FSAROnlythosechemicalsthathavethepotentialtoformatoxicvaporcloudorplumeafterreleasetotheenvironmentneedtobeevaluated.ThiscriterionismetbyallchemicalslistedinTable2.2-7.ControlRoomHabitabilitDeterminationTheeffectofanaccidentalreleaseofeachofthechemicalsdescribedintheprevioussectiononcontrolroomhabitabilityisevaluatedbycalculatingvaporconcentrationsinsidethecontrolroomasafunctionoftimefollowingtheaccident.ThiscalculationisperformedusingtheconservativemethodologyoutlinedinNUREG-0570andutilizingtheassumptionsdescribedinRG1.78.Inapostulatedaccident,the'ntirecontentofthelargestsinglestoragecontainerisreleased,resultinginatoxicvaporcloudand/orplumethatisconservativelyassumedtobetransportedbythewinddirectlytowardthecontrolroomintake.Theformationofthetoxiccloudand/orplumeisdependentonthecharacteristicsofthechemicalandtheenvironment.Theentireamountofachemicalstoredasagasistreatedasapufforcloudthathasafinitevolumedeterminedfromthequantityanddensityofthestoredchemical.Asubstancestoredasaliquidwithaboilingpointbelowtheambienttemperatureformsaninstantaneouspuffduetoflashing(rapidgasformation)ofsomefractionofthestoredquantity.Theremainingliquidformsapuddlethatquicklyspreadsintoathinlayerontheground,subsequentlyvaporizingandformingaground-levelvaporplume.Ahighboilingpointliquid(aboveambienttemperature)formsapuddlethatevaporatesbyforcedconvectionwithnoflashinginvolved.Thecalculationsaredonebyacomputerprogram(VAPOR)basedonNUREG-0570methodologythatrequiresthefollowinginputinformation:chemicalphysicalproperties,controlroomparameters,meteorology,distancefromthespilltothecontrolroomintake,quantityofchemicalreleased,andtoxicitylimits.ThefollowingUnit2controlroomparametersareused:ventilationrateof0.708m/sec(1,500ft/min),andnetfreevolumeof5,935m(209,600ft).Themostconservativemeteorologicalconditionisassumedforthecalculation,consistingofPasquillClassGstability,awindspeedof0.5m/sec(1.6ft/sec),andanambienttemperatureof33'C(91'F).Thecriteriafordeterminingchemicaltoxicityandsettinglimitsforhabitabilitydeterminationsaretakenfromregulatoryguidancedocuments.AccordingtoRG1.78,thetoxicitylimitofachemicalisthemaximumconcentrationthatcanbetoleratedbyanaveragehumanfor2minwithoutphysicalincapacitation(severecoughing,eyeburn,severeskinirritation).StandardReviewPlan(SRP)Section6.4statesthatacuteeffectsshouldbereversiblewithinashortperiodoftime(severalminutes)withoutthebenefitofmedicationotherthantheuseofUSARRevision62~27April1994 NineMilePointUnit2FSARself-containedbreathingapparatus(SCBA).TheacutetoxicitylimitslistedinRG1.78areusedinthisstudyexceptthat,wheremoreappropriate,documentedsourcesareavailable~.Nonguidelinetoxicitylimitsarebasedonconcentrationsthatproducenoeffectsorminorirritationaffectingmentalalertnessandphysicalcoordination,assuminga15-minexposuretime.Incaseswhereappropriatehumandataarenotavailable,dataareusedbyapplyingaconservativefactorof10tolowertheacuteexposurelimit.ResultsandConclusionsTheresultsoftheanalysisaresummarizedinTable2.2-8,whichindicatesthatnoneofthetoxicchemicalsevaluatedhavethepotentialtoincapacitatetheControlRoomOperators.2.2.3.1.4FiresTheproductionofhighheatfluxesandsmokefromfiresatindustrialorstoragefacilities,oilandgaspipelines,transportationroutes,orhomesinthesitevicinitydoesnotpresentahazardtothesafeoperationoftheplantduetothelargeseparationdistancesofthesepotentialfiresfromthesite.Theneareststoragefacilitiesofflammablematerialsinlargequantitiesandthenearestoilpipelineareover10km(6.2mi)fromtheNineMilePointsite.Thenearestgaspipelineisover3.2km(2mi)fromNineMilePointsite.Thenearesttruckroute(Route104)passesthesiteatadistanceofabout6.2km(3.9mi)fromtheplant.Therearenoknownregularshipmentsofflammablematerials.onRoute104withtheexceptionofpossiblelocalgasolinedeliveries.Thenearestresidenceisapproximately1.6km(1mi)fromthesite.Thesiteissufficientlyclearedinareasadjacenttotheplantthatforestorbrushfiresposenosafetyhazards.Onsitefuelstoragefiresdonotjeopardizeplantsafetysincethesefacilitiesaredesignedinaccordancewithapplicablefirecodes.AdetaileddescriptionoftheplantfireprotectionsystemispresentedinSection9.5.1.2.2.3.1.5CollisionswithIntakeandDischargeStructuresOswegoHarborislocatedapproximately12km(7.5mi)southwestoftheintakestructures.Theintakestructuresarelocatedapproximately305m(1,000ft)offshoreinawaterdepthof6m(20ft)attheminimumcontrolledlakelevel.InaccordancewithCoastGuardrecommendations,theintakestructuresareconstructedwiththetops3m(10ft)belowtheminimumcontrolledlakelevelduringthenavigationalseason.Evengreaterprotectionisaffordedthedischargestructuresinceitislocated1,500ftoffshoreandcoveredbyapproximatelyanadditional12ftofwater.USARRevision82.2-8November1995 NineMilePointUnit2FSARTABLE2.2-3INDUSTRIALFIRMSWITHIN8KM(5MI)OFUNIT2FirmAlcanAluminumCorporationDistance/DirectionfromSitekm4.5/SWProductsAluminumsheetandplateEmloent1,000JamesA.FitzPatrick<1/ENuclearPowerPlantElectricalgeneration515NineMilePointUnit1SitheEnergiesUSAIndependenceGenerationPlantAdjacenttoUnit23.5/SWElectricalgenerationElectricalgeneration45075SOURCE:References4,10,11,17,18USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.3-4AMETEOROLOGZCALZNSTRUMENTATZONSPECZFZCATZONSOperationalMeasurementsProgramParameterZnstrumentSpecificationValueWinddirectionWindspeedTemperatureDewpointPrecipitationBarometricPressureTeledyneGeotechSensor-50.2C/50.2DVane-53.2Processor-21.21TeledyneGeotechSensor-50.1BCups-52.1Processor-40.12c&21.11TeledyneGeotechSensor-PlatinumRTDProcessor-21.32AspiratedThermalRadiationShield327GeneralEastern1200EPSorE1BelfortZnstrumentCompanyTippingBucketYellowSpringsZnstrumentCompanySensor-2014-28/32-HA-3WHTeledyneGeotechProcessor-40.61&21.61AccuracyDampingratioDistanceconstantRangeThresholdAccuracyDistanceconstantStartingthresholdRangeAmbienttemperaturerangeTemperaturedifferenceRangeLinearityErrorRangeCalibrationincrementRange+2deg0.41.1m(3.7ft)0-360/540deg0.30m/sec(0.7mph)+0.67m/sec(+0.15mph)or1%1.5m(5.0ft)0.27m/sec(0.6mph)0-45m/sec(0-100mph)-40to43C(-40to110F)-4to11C(-8to20F)+02oC(+04oF)0.1C(0.2F)underradiationof1.6cal/cm'/min(353.8Btu/ft'/hr)-40to43C(-40to110F)0.25mm(0.01in)948to1084mb(28.00to32.00inHg)USARRevision81of1November1995

NineMilePointUnit2FSAR2.4HYDROLOGICENGINEERING2.4.1HydrologicDescription2.4.1.1SiteandFacilitiesUnit2islocatedonthewesternportionoftheNineMilePointpromontoryonthesoutheasternshoreofLakeOntarioinOswegoCounty,NY.AllelevationsinthisreportrefertotheUSLS1935Data.1.ToconvertelevationsfromUSLS1935to1955InternationalGreatLakesData,subtract0.375m(1.23ft).2.ToconvertelevationsfromUSLS1935to1985InternationalGreatLakesData,subtract0.217m(0.71ft).ThenaturalgradeelevationoftheNineMilePointsitevariesbetweenel78.03m(256ft)andel80.77m(265ft).Therearenoperennialstreamslocatedonthesite.PrecipitationatthesiteiscarriedtoLakeOntarioviadrainageditches,.stormsewers,andgroundwaterflow.ArevetmentditchsystemisconstructedalongthelakeshoreinfrontofUnit2.Thetopoftherevetmentisatel80.16m(263ft)andpreventspossibleplantfloodingduetolakewaveaction(Section2.4.5).Aditchlocatedimmediatelysouthoftherevetmentcollectsrainfallrunoffflowingnorthtowardthelakeandconveystheflowtobothendsoftherevetment.AllpersonnelentrancestoCategoryIstructuresareatel79.55m(261ft)orhigher.Adetaileddescriptionofthewaterlevel(flood)designisfoundinSection3.4.2.4.1.2HydrosphereLakeOntario,theeasternmostoftheGreatLakes,isaninternationalbodyofwaterformingpartoftheborderbetweentheUnitedStatesandCanada.Thelakeis310.6km(193mi)longand85.3km(53mi)wideatitslargestpoints,andhasasurfaceareaof19,010.6sqkm(7,340sqmi)or1.901millionha(4.7millionacres).Ithasamaximumdepthof244.4m(802ft),anaveragedepthofapproximately86.3m(283ft),andavolumeof1,638cukm(393cumi)or0.164billionha-m(1.34billionacre-ft).InflowintothewesternendofLakeOntarioaveragesapproximately5,806cum/sec(205,000cuft/sec[cfs)).directlyintoLakeOntariofrom70,707sqkm(27,300sqwatershedinNewYorkStateandtheprovinceofOntariotoanadditional1,020cum/sec(36,000cfs).ThemaintheNiagaraRiver;otherlargeriversdrainingintotheRunoffmi)ofamountsfeederislakeareUSARRevision82.4-1November1995 NineMilePointUnit2FSARtheGeneseeandtheOswegofromthesouthshore,theBlackRiverfromtheeastshore,andtheTrentRiverfromthenorthshore.TheoutflowfromthelakeintotheSt.LawrenceRiveraveragesabout6,824cum/sec(241,000cfs).Duringthewinter,icecoverformsintheslackwaterbays,butthelakeitselfisseldommorethan25percentice-covered.LakeUSARRevision82.4-1aNovember1995 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKUSARRevision82.4-1bNovember1995 NineMilePointUnit2FSAROntario'soutflowriver,theSt.Lawrence,isice-coveredfromlateDecemberuntiltheendofMarch,allthewayfromthelaketotheinternationalboundaryatMassena,NY.Priortothebeginningofflowregulation,theelevationofthelakesurfacewascontrolledbyanaturalrockweirlocatedabout6.4km(4mi)downstreamfromOgdensburg,NY,intheGalopRapidsreachoftheSt.LawrenceRiver.The111-yrrecordoftheUSLS(1860to1970)indicatesameanlakesurfaceelevationof75m(246ft).Overthisperiod,themaximummonthlylakesurfaceelevationwas75.98m(249.29ft)andtheminimumwas73.97m(242.68ft),arangeof2.01m(6.61ft).Theannualrangeofelevationsvariesbetween1.09and0.21m(3.58and0.69ft).DamsontheSt.LawrenceRiver,undertheauthorityoftheInternationalSt.LawrenceRiverBoardofControl,arenowusedtoregulatethelakelevel.Thelowlimitissetforel74.37m(244ft)onApril1andismaintainedatorabovethatelevationduringtheentirenavigationseason(April1toNovember30).Theupperlimitofthelakelevelisel75.59m(248ft).Watersurfacesetupandseicheareproducedbywindsandatmosphericpressuregradients.Theseshort-termlakefluctuationsaregenerallylessthan0.6m(2ft)inamplitude.Windsaredirectlyrelatedtotheformationofsurfacewaves,themagnitudeofwhichvariesbetween0and4.6m(15ft)inheightduringagivenyear.,Tidemagnitudesamounttolessthan2.5cm(1in).Theaverageannualprecipitationinthesiteareaisabout92cm(36in).Itisestimatedthat,approximately46cm(18in)arelostasrunoffintostreamflow.Oftheremaining46cm(18in),approximately41cm(16in)arelostviaevaporationfromlandandwatersurfacesandtranspirationbyplants,referredtotogetherasevapotranspiration.Theremaining5cm(2in)areavailableforgroundwaterrecharge.Therelativelyhighrunoffcanbeattributedtothelowpermeabilityoftheglacialsoilsandrockformations.Thehistoricalmaximumprecipitationinthevicinityofthe'iteislistedinTable2.4-1.Unit2islocatedbetweentwosurfacewaterusersemployingonce-throughcoolingwatersystems.Unit1islocatedimmediatelywestofUnit2andrecirculatesanaverageof1,011cum/min(268,000gpm)ofLakeOntario.JamesA.FitzPatrickNuclearPowerPlant,locatedimmediatelyeastofUnit2,recirculatesanaverageof1,401cum/min(370,200gpm).Theonlymajorpublicwatersupplieswithina50-km(30-mi)radiusofthesitethatdrawwaterfromthelakethroughacommonintakearethecityofOswegoandtheOCWD.AllwatersupplysystemsandindustrialusersdrawingfromU.S.watersonLakeOntarioarelistedinTable2.4-11.DataonCanadianwatersuppliersandindustrialusersareprovidedinTable2.4-12.The16U.S.and10CanadianmunicipalwatersuppliesandindustrialUSARRevision62.4-2April1994 z5"~1ON1284000N1283000ELSHOREUNE+gOOP%g+~Og5I0yBL3900CFS411ISEWAGE7REATMEPlANTUNIT2REVETMENT03OGORSPStstt~rMAINr<+STACKENLESEBZICEHAZARGGiOi~.SEORA$raBVIL01%ACCESSCDIIRBLTOPOFBERMEL2652WSE2647ATERIALBLDG.BOT.GASSTOA.BLDG.TELEPHONEBLDG.IDENTIFICATIONLEGENDREACTORBIÃLDIMGTURBHEBULOIHQRAOWAStEBULOIIIQHEAZERBAYSSCREENWELLBULDINGCONOESAZESTORAGEtANKBLDGCONTROLBIRLOIHGNORMALSWIZCHGEARBULDNGAOMINSZRATONBOLDHGWAREHOUSELIMNOMAJORAREASCON'IAIIINQCOHSZRUCZIOIIBUILDlIGSCONSOEREOINTHEAHALZSISt03000CFSCENTERUNEOF,TOPOFERM2605t,B\WSE2600FLOODCONTROLBERMSWSE2590PAVEDiANGER)~u1it'5(<IeBUILD1%QsPILNGEGOPFA~HGuEDPP&~COOUNGITOWERCENTERUNEOFFLOODCONTROLBERMSEASTBERMN1282000N128100001100CFS"02100CFTOPOFBERM2755CONCRETERAILROADCROSSING04MCFSVISE75301900CFSIWESTWSE2754OfSDGIISIBZBLIECZIDIA%ANALZSISFACILIttTRANSMISSIONLINESOCATEDuKOLD!ttESPORAIRAGERtLAKEROADBERMEASTENTRANCERDWSE27540400CFSWSE272001200CFSTOPOFBERM-RAILROAD02500CFSSOUTHEASTBERMTOPOFBERMEL277302100CFSNOTESGRIDCOOROBIATESREFERTONEWYORKSTATECOORDINATESYSTEM2WSEWATERSURFACEELEVATION3~---PMFDRAINAGEPATHDURINGPMP4~PIIPORAIRAGEPAtHDURNGPMPFIGURE2.4-1PNFDRAINAGENIAGARAMOHAWKPOWERCORPORATIONNINEMILEPOINT-UNIT2UPDATEDSAFETYANALYSISREPORTUctARREV[S[QN8NOVEMBER['O'[5

NineMilePointUnit2FSARTABLE2.5-28AQUALITYCONTROLPROGRAMFORCATEGORYISTRUCTURALFILLANDGRANULARFILLTestorInsectionGradationtestTestDesinationASTMC136-81MinimumFreuenc1/1,000cuydforstructuralfill1/4,000cuydforgranularfillMoisturedensitytestASTMD1557-78BackfillconditionsBackfillandcompactionprocedureLiftthicknessCompactionequipmentPassesofcompactionequipment1/1,000cuydforstructuralfill1/2,000cuydforgranularfillEachliftEachliftEachliftPriortoeachplacementEachliftIn-placedensitytestRelativedensitytestASTMD1556-74ASTMD2922-81ASTMD2049-69Foropenareas,1/500cuyd<'>Forconfinedareas,1/100cuyd+Priortoplacement,CategoryIstructuralfillonlyPerformatleastonetesteveryliftiftheliftislessthan500cuyd.Performatleastonetesteveryotherliftiftheliftislessthan100cuyd.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE2.5-48ATRIAXIALCOMPRESSIONTESTDATASUMMARYFORLACUSTRINESILTYCLAYSPECIMENSTypeofTest:ConsolidatedUndrainedTypeofSpecimens:UndisturbedBlockSamplesSizeofSpecimens:SoilDescription:1.4inDiameterby3.5inHeightSiltyClay,ModeratelyPlastic,Yellow-BrownSamleNumberDepth(ft)SecimenProertiesInitialw(4)r,(pcf)eAfterConsolidation82A21.9102.00.65282B23.7100.10.68382C22.4100.30.681w(4)ra(p<<)e25.1101.80.65525.1101.30.66426.2102.40.647USARRevision81of1November1995 NineMilePointUnit2FSARTABLE2.5-48BTRIAXIALCOMPRESSIONTESTDATASUMMARYFORLACUSTRINESILTYCLAYSPECIMENSTypeofTest:ConsolidatedUndrainedTypeofSpecimens:UndisturbedBlockSamplesSizeofSpecimens:SoilDescription:1.4inDiameterby3.5inHeightSiltyClay,ModeratelyPlastic,GraywithYellowSamleNumberDepth(ft)SecimeProertiesInitial81G81H81Iw(>)rd(pcf)eAfterConsolidation18.2108.10.56019.5106.10.57821.3102.30.646w(4)r.(pcf)e20.0108.10.56020.3108.00.56122'104.60.611USARRevision81'of.1November=1995 NineMilePointUnit2FSARTABLE2.5-48CTRIAXIALCOMPRESSIONTESTDATASUMMARYFORORGANICSILTSPECIMENSTypeofTest:TypeofSpecimens:ConsolidatedUndrainedUndisturbedBlockSamplesSizeofSpecimens:1.4inDiameterby3.5inHeightSoilDescription:OrganicSilt,HighlyPlastic,DarkGraytoBlackSamleNumberDepth(ft)SecimenProertiesInitial81A81B81Cw(4)r~(pcf)efterConsolidatiow(4)r,(pcf)e46.767.01.42351.367.11.41747.165.71.46951.667.31.41345.169.01.35248.671.41.275USARRevision81of1November1995

UPDTEDFETYXLYIEPNINEMILEPOINTNUCLEARSTATION-UNIT27NIAGARAUMOHAWKVOL.4

NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER11.11'1'1.41.51.61'1.81.91.101'11'2'~13CHAPTER2INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTIntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2~12.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33~13.2333.4DESIGNOFSTRUCTURESgCOMPONENTSgEQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3'B3.7A3.7B3'3.9A3'B3.10A3.10B3'1Appendixes3ACHAPTER44.14.24'4'4.54.6Appendix4ACHAPTER5TitleMissileProtectionProtectionAgainst,EffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSVolume9,1010101010121212121212121212135~15'5.35'Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevisionNovember.1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136'6.26'6.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77'7'7'7'7'7'77Appendixes7A,CHAPTER88.18'8.3Appendix8ACHAPTER9F19.29'9.49.5Appendixes9A,CHAPTER1010.110.210.3INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystems.SystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystem-AUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem151515161616161616161616,17171717181920,2121,222323232324USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume10.4CHAPTER11OtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT242411'11.211.311.411'Appendix11ACHAPTER1212'12212'12412'CHAPTER1313'13'13'13.413.513.6CHAPTER1414114214.3CHAPTER1515~0SourceTermsLiquidWasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral2424.2525252525252525262626262626262626262626,27272727USARRevisionivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215.315.415.515.615.715.8Appendices15ACHAPTER16CHAPTER1717.017.117.2CHAPTER1818.118.2APPENDIXAAPPENDIXBTitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssurance,ProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCE,PROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASEVolume27272727272727272828282828282828282828USARRevisionNovember1995

UPDTEDFETYNLYIEPNINEMILEPOINTNUCLEARSTATION-UNIT2VNIAGARA4MOHAWKVOL.5

NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER11.11.21.31.41.51.61.71.81.91.101.111.121.13CHAPTER2INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTIntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2'2.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2ZAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33~13.23033.4DESIGNOFSTRUCTURES,COMPONENTS/EQUIPMENTgANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3.11Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER55.15.25.35.4Appendixes5A,~it16MissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5BVolume9,1010101010121212121212121212121212131313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136.16'6.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2'ndClass3Components13141515151515CHAPTER77'7'7.37'7.57'7~7Appendixes7A,CHAPTER88.18.28'Appendix8ACHAPTER99.19.29.39.49.5Appendixes9A,CHAPTER1010110'10'INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem151515151616161616161616,17171717181920,2121/222323232324USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section10'CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411~111.211.311.411.5Appendix11ACHAPTER1212'12~212'12'125CHAPTER1313~113~213'13.413'13.6CHAPTER1414.1l14~2143CHAPTER1515'SourceTermsLiquidWasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral24242525252525252525262626262626262626262626,272727.27USARRevisionivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume15.115.215.315.415.515.615.715.8'AppendicesCHAPTER16CHAPTER1717.017~117.2CHAPTER1818.118.2APPENDIXAAPPENDIXB15ADecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE27272727272727272828282828282828282828USARRevisionNovember1995

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NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER11.11'1'1.41.51.61~71.81.91.10F111.121~13CHAPTER2INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTIntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2'2'2.3242.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33~13'3'3.4DESIGNOFSTRUCTURES,COMPONENTS'QUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3.7A3.7B3.83.9A3'B3.10A3.10B3'1Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER55.15'5.35.4Appendixes5A,TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign,(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipment,through3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolant,PressureBoundaryReactorVesselComponentandSubsystemDesign5BVolume9,10101010101212121212121212121212121313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolumeCHAPTER66.16.26.36.46.56.6Appendixes6ACHAPTER77'7'7'7.47'7~67'Appendixes7A,CHAPTER88.18'8.3Appendix8ACHAPTER99~19'9.39.49.5Appendixes9A,CHAPTER1010.110.210.3ENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Componentsthrough6DINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatuxeSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliaxySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem1314151515151515151616161616161616,17171717181920,2121/222323232324USARRevision,November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section'0.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411'112ll~311.411.5Appendix11ACHAPTER1212'12.212312.412.5CHAPTER1313'13~213.313.413.513.6CHAPTER1414.1I14.214.3CHAPTER1515.0SourceTermsLiquidWasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicant~TrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral24242525252525252525262626262626262626262626,27272727USARRevisionivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215e315e415.515.615.715.8Appendices15ACHAPTER16CHAPTER1717.017.117.2CHAPTER1818.118.2APPENDIXAAPPENDIXBTitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASEVolume27272727272727272828282828282828282828USAR-RevisionNovember1995

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NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANT1~11'1.31.41.51.61.71.81.91.10CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeNileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2,PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2'2.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,'M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13.23'3.4DESIGNOFSTRUCTURES,COMPONENTS'QUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel{Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)~Sectio3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10BF11Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER55.15.25.35.4AppendixesSA,TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofsupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5BVolume9,101010101012121212121212121212121313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136.16.2636.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProduct-RemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77-17.27.37'7.57.67.7Appendixes7A,CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5Appendixes9A,CHAPTER1010.110.210'INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAixConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTuxbineGeneratoxMainSteamSupplySystem15151515161616'61616161616,171717181920/2121/222323232324USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)~Sectile10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411.111.211.311.411.5Appendix11ACHAPTER1212.112.212312'12.5CHAPTER1313.113.213.313.413.513.6CHAPTER1414~1l14.214.3CHAPTER1515.0SourceTermsLiquidWasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral2424'525252525252525262626262626262626262626,27272727USARRevisionivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215e315e415.515.615.715.8AppendicesCHAPTER16CHAPTER1717.017.117.2CHAPTER1818.118.2APPENDIXAAPPENDIXB15ATitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNXCALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOXNTNUCLEARSTATIONUNXTS1AND2OPERATIONSPHASEVolume27272727272727272828282828282828282828USARRevisionNovember1995e

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NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER11.1121.31.41.51.61.7181.91.101.111.121.13CHAPTER2INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTIntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2~12.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2Z,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13~23.33.4DESIGNOFSTRUCTURES,COMPONENTSIEQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3'3.6A3'B3.7A3.7B3.83.9A3.9B3.10A3.10B3~11Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER5TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-.WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSVolume9,1010101010121212121212121212121212135.15.25.354Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevisionNovember'1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolumeCHAPTER6ENGINEEREDSAFETYFEATURES136~16'6.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Components131415151515CHAPTER77.17.27.37.47.57.67.7Appendixes7A,CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5Appendixes9A,CHAPTER1010~110'103INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Rela'tedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGenerator=MainSteamSupplySystem15151515161616161616161616,17171717181920,2121,222323232324USARRevision8November1995 NineMilePoint,Unit-2FSARTABLEOFCONTENTS(Cont'd.)Section10-4CHAPTER1111-111'11-311411.5Appendix11ACHAPTER1212112'12'12-412'CHAPTER1313~113.213'13.413.5CHAPTER1414'I14.214'CHAPTER1515'TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTSourceTermsLiquid:Waste=Management-"SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneralVolume24242424'525252525252525262626262626262626262626~27272727USARRevisionSivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215.315.415.515.615.715'AppendicesCHAPTER16CHAPTER1717.017.117~2CHAPTER1815ATitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistribution-Anomalies.IncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMVQllllllB27272727272727272828282828282818.118.2APPENDIXAAPPENDIX'DetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE28282828USARRevision.vNovember1995

NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.5.1.1.33.5.1.1.43.5.1.33.5.1.3.13.5.1.3.23.5.13.5.13.5.13.5.13.5.1.3.3.3.4.3.5.3.6~43.5.1.53.5.1.63.5.23.5.33.5.43.63.5.1.1.53.5.1.2Ti.tiePipingandInstrumentationDrawingsIdentificationofMissiles,TheirSources,andBasisofSelectionMissileProtectionProvidedInternally-GeneratedMissiles(InsideContainment)TurbineMissilesTurbinePlacementandOrientationMissile'Identification,Characteristics,andTargetDescriptionProbabilityAnalysisTurbineOverspeedProtectionTurbineValveTestingTurbineCharacteristicsMissilesGeneratedbyNaturalPhenomenaMissilesGeneratedbyEventsNeartheSiteAircraftHazardsStructures,Systems,andComponentstobeProtectedfromExternally-GeneratedMissilesBarrierDesignProceduresReferencesPROTECTIONAGAINSTDYNAMICEFFECTSASSOCIATEDWITHTHEPOSTULATEDRUPTUREOFPIPINGPacae3.5-33.5-33.5-53.5-83.5-83.5-83.5-83.5-93.5-163.5-163.5-163.5-173.5-173.5-173.5-173.5-183.5-213.6A-13.6A3.6A.13.6A.1.13.6A.1.23.6A.1.33.6A.1.3.13.6A.1.3.23.6A.1.3.33.6A.2PROTECTIONAGAINSTEFFECTSASSOCIATED,WITHTHEPOSTULATEDRUPTUREOFPIPING(SWECSCOPEOFSUPPLY)PostulatedPipingFailuresinFluidSystemsInsideandOutsidetheContainmentDesignBasesDescriptionofPipingFailuresSafetyEvaluationApproachProtectionMethodsSpecificProtectionMeasuresDeterminationofBreakLocationsandDynamicEffectsAssociatedwiththePostulatedRuptureofPiping3.6A-23.6A-23.6A-23.6A-53.6A-53.6A-53.6A-63.6A-73.6A-8USARRevisionh73-vOctober1994 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.6A.2.13.6A.2.1.13.6A.2.1.23.6A.2.1.33.6A.2.1.43.6A.2.1.53.6A.2.1.63.6A.2.23.6A.2.2.13.6A.2.2.23'A.23.6A.2.2.43.6A.2.2.53.6A.2.2.63.6A.2.2.73.6A.2.33.6A.2.3.13.6A.2.3.23.6A.2.43.6A.2.53.6A.33.6B3'B.13.6B.23.6B.2.13.6B.2.1.13.6B.2.1.1.13.6B.2.1.1.2TitleCriteriaUsedtoDefineBreakandCrackLocationandConfigurationDefinitionofHigh-EnergyFluidSystemDefinitionofModerate-EnergyFluidSystemPostulatedPipeBreaksandCracksExemptionsFromPipeWhipProtectionRequirementsPostulatedPipeBreakLocationsDesignBasisBreak/CrackTypesandOrientationAnalyticalMethodstoDefineForcingFunctionsandResponseModelsIntroductionTime-DependentBlowdownForceSimplifiedBlowdownAnalysisLumped-ParameterDynamicAnalysisEnergyBalanceAnalysisLocalPipeIndentationConcreteBarrierImpactDynamicAnalysisMethodstoVerifyIntegrityandOperabilityJetImpingementAnalysisPipeRuptureRestraintsGuardPipeAssemblyDesignCriteriaMaterialfortheOperatingLicenseReviewReferencesPROTECTIONAGAINSTDYNAMICEFFECTSASSOCIATEDWITHPOSTULATEDRUPTUREOFPIPING(GESCOPEOFSUPPLY)PostulatedPipingFailuresinFluidSystemsOutsideContainmentDeterminationofBreakLocationsandDynamicEffectsAssociatedwiththePostulatedRuptureofPipingCriteriaUsedtoDefineBreakandCrackLocationandConfigurationCriteriaforRecirculationPipingSystemInsideContainmentDefinitionofHigh-EnergyFluidSystemDefinitionofModerate-EnergyFluidSystemPacae3.6A-83.6A-83.6A-83'A-93.6A-103.6A-103.6A-173.6A-193.6A-193.6A-203.6A-253.6A-263.6A-273.6A-293.6A-303.6A-313.6A-313.6A-323.6A-343.6A-343.6A-353.6B-13.6B-13.6B-13.6B-13.6B-13.6B-13.6B-lUSARRevision3viNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.6B.2.1.l.33.6B.2.1.1'3.6B.2.53.6B.2.13.6B.2.1.1.73.6B.2.13.6B.23.6B.2.23.6B.2.2.13.6B.2.2.1.13.6B.2.2.23.6B.2.2.2'3.6B.2.33.6B.23.6B.2.3.23.6B.2.3.2.13.6B.2.3.33.6B.2.3.3.13.6B.2.43.6B.23.6B.2'.23.6B.2.4.33.6B.33'Title"','ostulatedPipeBreaksandCracksExemptionsfromPipeWhipProtectionRequirementsLocationforPostulatedPipeBreaks(ASMESafetyClass1Piping)OtherHigh-EnergyPipingandModerate-EnergyPipingRegulatoryGuide1.46TypesofBreakstoBePostulatedinFluidSystemPipingCriteriaforPipingSysteminAreaofContainmentIsolationValvesAnalyticalMethodstoDefineBlowdownForcingFunctionsandResponseModelsAnalyticalMethodstoDefineBlowdownForcingFunctionsRecirculationPipingSystemPipeWhipDynamicResponseAnalysesRecirculationPipingSystemDynamicAnalysisMethodstoVerifyIntegrityandOperabilityJetImpingementAnalysesandEffectsonSafety-RelatedComponentsPipeWhipEffectsonSafety-RelatedComponentsPipeWhipEffectsFollowingaPostulatedRuptureoftheRecirculationPipingSystemLoadCombinationsandDesignCriteriaforPipeWhipRestraintsRecirculationPipingSyst:emPipeWhipRestraintsMaterialtoBeSubmittedfortheOperatingLicenseReviewImplementationofCriteriaforPipeBreakandCrackLocationandOrientationImplementationofSpecialProtectionCriteriaSummaryofJetEffectsAnalysesResultsReferencesSEISMICDESIGNpacae3.6B-23.6B-33.6B-33.6B-43.6B-43.6B-43.6B-63.6B-63.6B-63.6B-63.6B-93.6B-93.6B-113.6B-113.6B-113.6B-113.6B-123.6B-123.6B-173.6B-173.6B-183.6B-183.6B-193.7A-1USARRevision83-viiNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.7A3.7A.3.7A.3.7A.3.7A.3.7A.3.7A.3.7A.3.7A.11~11.2131.3.11.3.21.3.31.43.7A.23.7A.2.13.7A.2.23.7A.2.33.7A.2.43.7A.2.4.13.7A.2.53.7A.2.63.7A.2.73.7A.2.83.7A.2.93.7A.2.103.7A.2.113.7A.2.123.7A.2.133.7A.2.143.7A.3.1.33.7A.3.23.7A.3.33.7A.3.3.13.7A.2.153.7A.33.7A.3.13.7A.3.1.13.7A.3.1.2TitleSEISMICDESIGN(SWECSCOPEOFSUPPLY)SeismicInputDesignResponseSpectraDesignResponseSpectrumDerivationCriticalDampingValuesStructuresEquipmentPiping'upportMediaforCategoryIStructuresSeismicSystemAnalysisSeismicAnalysisMethodsNaturalFrequenciesandResponseLoadsProceduresUsedforModelingSoil/StructureInteractionRock/StructureInteractionDevelopmentofFloorResponseSpectraThreeComponentsofEarthquakeMotionCombinationofModalResponsesInteractionofNon-CategoryIStructuresWithCategoryIStructuresEffectsofParameterVariationsonFloorResponseSpectraUseofConstantVerticalStaticFactorsMethodUsedtoAccountforTorsionalEffectsComparisonofResponsesMethodsforSeismicAnalysisofDamsDeterminationofCategoryIStructureOverturningMomentsAnalysisProcedureforDampingSeismicSubsystemAnalysisSeismicAnalysisMethodsSeismicQualificationofComponentsSeismicQualificationofPipingSystemsOtherDynamicLoadsDeterminationofNumberofEquivalentStressCyclesProcedureUsedforModelingSummaryPacae3.7A-13.7A-13.7A-13'A-13.7A-23.7A-23.7A-23'A-23.7A-33.7A-33'A-33.7A-53.7A-53.7A-63.7A-73.7A-73'A-93.7A-93.7A-93.7A-103.7A-103.7A-103.7A-113.7A-113.7A-113.7A-113.7A-123.7A-133.7A-133.7A-173.7A-173.7A-173.7A-183.7A-18USARRevision8November1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.7A.33.7A.3.3.33.7A.3.3.43.7A.3.3.53.7A.3.43.7A.3.4.13.7A.3.4'3.7A.3.53.7A.3.63.7A.3'A.3'A.3.7A.3.7A.3.7A.3.73.83.8'3.8.23.8.33.93.7A.3.103.7A.3.113.7A.3.123.7A.3.133.7A.3.143.7A.3.153.7A.43.7A.4.13.7A.4.23'A.4'3.7A.4.53.7A.53.7A.4'.13.7A.4.2.23.7A.4.2.33.7A.4.2.43.7A.4.3Title'eometricBoundariesof-AnalyticalModelsModelSelectionofMassPointsNumberofModesandCutoffFrequencyBasisforSelectionofFrequenciesComponentsPipingUseofEquivalentStaticLoadMethodofAnalysisThreeComponentsofEarthquakeMotionCombinationofModalResponsesAnalyticalProceduresforPipingIntroductionAnalyticalTechniquesDynamicAnalysisMultiplySupportedEquipmentComponentswithDistinct,InputsUseofConstant.VerticalStaticFactorsTorsionalEffectsofEccentricMassesBuriedCategoryIPipingSystemsandTunnelsInteractionofOtherPipingwithCategoryIPipingSeismicAnalysesforReactorInternalsAnalysisProcedureforDampingCriteriaforSeismicInstrumentationProgramComparisonwithRegulatoryGuide1.12LocationandDescriptionofInstrumentationTriaxialTimeHistoryAccelerographTriaxialPeakAccelerographTriaxialResponseSpectrumRecorderTriaxialSeismicSwitchMainControlRoomOperatorNotificationComparisonofMeasuredandPredictedResponsesIn-serviceSurveillanceRequirementsReferencesPacae3~7A-183.7A-183.7A-193'A-193.7A-203.7A-203.7A-203.7A-203.7A-213.7A-213.7A-213.7A-213.7A-233.7A-243.7A-273.7A-283.7A-283.7A-283.7A-283.7A-293.7A-293.7A-293.7A-293.7A-303.7A-303.7A-303.7A-313.7A-323.7A-323.7A-333.7A-333.7A-34USARRevision8"November1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.7B3.7B.3.7B.3.7B.3.7B.3.7B.11.11.21.31.43.7B.2.1.23.7B.2.1.33.7B.2.1.43.7B.2.1.53.7B.2.1.63.7B.2.23.7B.2.33.7B.2.3.13.7B.2.3.23.7B.2.43.7B.2.53.7B.2.63.7B.2.73.7B.2.83.7B.2.93.7B.2.103.7B.2.113.7B.2.123.7B.2.133.7B.23.7B.2.13.7B.2.1.1TitleSEISMICDESIGN(GESCOPEOFSUPPLY)SeismicInputDesignResponseSpectraDesignTimeHistoryCriticalDampingValuesSupportingMediaforCategoryIStructuresSeismicSystemAnalysisSeismicAnalysisMethodsTheEquationsofDynamicEquilibriumSolutionoftheEquationsofMotionbyModeSuperpositionAnalysisbyResponseSpectrumMethodMultisupportExcitationAnalysisofSystems,Components,andEquipmentDynamicAnalysisofCategoryISystems,Components,andEquipmentSeismicQualificationbyTestingNaturalFrequenciesandResponseLoadsProcedureUsedforModelingModelingTechniquesforCategoryISystems,Components,andEquipmentModelingofReactorPressureVesselandInternalsSoil-StructureInteractionDevelopmentofFloorResponseSpectraThreeComponentsofEarthquakeMotion(NSSS)CombinationofModalResponses(NSSS)InteractionofNon-CategoiyIStructureswithCategoryIStructuresEffectsofParameterVariationsonFloorResponseSpectraUseofConstantVerticalStaticFactors(NSSS)MethodUsedtoAccountforTorsionalEffects(NSSS)ComparisonofResponses(NSSS)MethodsforSeismicAnalysisofDamsPacae3.7B-13.7B-13.7B-13.7B-13.7B-23.7B-23.7B-23.7B-23.7B-23.7B-33.7B-43.7B-53.7B-83.7B-103.7B-103.7B-103.7B-103.7B-103.7B-113.7B-113.7B-113.7B-113.7B-123.7B-123.7B-123.7B-123.7B-123.7B-12USARRevision83-xNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)~Sectic3.7B.2.143.7B.2.153.7B.33.7B.3.13.7B.3.23.7B.3.2.13.7B.3.2.23.7B.3.33.7B.3.3.13.7B.3.3.23'B.3.3.33.7B.3.43.7B.3.53.7B.3.63.7B.3.6.13.7B.3.6.23'B~3'3.7B.3.7.13.7B.3.7.23.7B.3.83.7B.3.93.7B.3.103.7B.3.113.7B.3.123.7B.3.133.7B.3.143.7B.3.153.7B.43.7B.5Title'eterminationofCategoryIStructureOverturningMomentsAnalysisProcedureforDampingSeismicSubsystemAnalysisSeismicAnalysisMethodsDeterminationofNumberofEarthquakeCyclesPipingSystemsOtherEquipmentandComponentsProcedureUsedforModelingModelingofPipingSystemsModelingEquipmentFieldLocationofSupportsandRestraintsBasisofSelectionofFrequenciesUseofEquivalentStaticLoadMethodofAnalysisThreeComponentsofEarthquakeMotionResponseSpectrumMethodTime-HistoryMethodCombinationofModalResponsesSquareRootoftheSumoftheSquaresMethodDoubleSumMethodAnalyticalProcedureforPipingMultiplySupportedEquipmentComponentsWithDistinctInputsUseofConstantVerticalStaticFactorsTorsionalEffectsofEccentricMassesBuriedCategoryIPipingSystemsandTunnelsInteractionofOtherPipingWithCategoryIPipingSeismicAnalysisforReactorInternalsAnalysisProceduresforDampingSeismicInstrumentationReferencePacae3.7B-123.7B-123.7B-143.7B-143.7B-153.7B-153'B-153.7B-163.7B-163.7B-183.7B-183.7B-193.7B-193.7B-203.7B-203.7B-203.7B-213.7B-213.7B-213.7B-223.7B-223;7B-223.7B-223.7B-233.7B-233.7B-233.7B-233.7B-233.7B-233.83.8.13'.1.13.8.1.1.1DESIGNOFSEISMICCATEGORYISTRUCTURESeConcreteContainmentDescriptionofthe.ContainmentReinforcingSteelArrangement3'-13.8-13.8-13.8-2USARRevision83-xiNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)3.83.8.1.F13.8.1.3.23.8.1.43.8.1.4.13'.13.8.133~8~13.8.1.4.2.5.5.1.5.2.63'.1~6'3.8.1.6.23.8.1.6.33.8.13.8.13.8.13.8.23.8.3~7~7~1~7~23.8.3.13.8.3.1.13.8.3.1.23.8.3.1.33.8.3.1.43.8.3.1.53.8.3.23.8.33.8.33.8.33.8'.F1.2'~3~3~13.8.33.8.33.8.33.8.33.8.33.8.3~3~2.3.3.4.4.1.4.2.4.3~Sectic3~8.1.1.23.8.1.2TitleSteelLinerandPenetrationsApplicableCodes,Standards,andSpecificationsLoadsandLoadCombinationsPrimaryContainmentStructureSteelLinerandPenetrationsDesignandAnalysisProcedureConcretePrimaryContainmentStructureSteelLinerandPenetrationsStructuralAcceptanceCriteriaPrimaryContainmentStructureSteelLinerandPenetrationsMaterials,QualityControl,andConstructionTechniquesConcretePrimaryContainmentStructureSteelLinerandPenetrationsExceptionsand/orClarificationstoASMECodeTestingandIn-serviceInspectionConcreteContainmentSteelLinerandPenetrationsNotApplicableConcreteandSteelInternalStructuresofthePrimaryContainmentDescriptionoftheInternalStructuresDrywellFloorReactorVesselPedestalBiologicalShieldWallStarTrussFloorsApplicableCodes,Standards,andSpecificationsBiologicalShieldWallStarTrussLoadsandLoadingCombinationsDrywellFloorandReactorVesselPedestalBiologicalShieldWallStarTrussDesignandAnalysisProceduresDrywellFloorReactorPedestalBiologicalShieldWallPacae3.8-33.8-83.8-83.8-83.8-83.8-93.8-93.8-113.8-133.8-133.8-143.8-143.8-143.8-153.8-213.8-253.8-253.8-263.8-273.8-273.8-273.8-283.8-293.8-293.8-303.8-303.8-303.8-303.8-313.8-313.8-313.8-323.8-323.8-323.8-323.8-333.8-34USARRevision83-xllNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Contd.)Section3.8.33.8.33.8.33.8.3~4'.4.5.5.63.8.3.6.13.8.3.6.23.8.3.6.33.8.3.73.8.43.8.43.8.43.8.43.8.43.8.43.8.43.8.43.8.4.1~1~1~1~2.1.3.1.4.1.5.1.6~1.73.8.4.1.83.8.4.1.93.8.4.1.103.8.4.1.113.8.4.1.123.8.4.23.8.43.8.43.8.43.8.43.8.43.8.43.8.43.8.43.8.4.3~4~4.1.4.2.4.3.4.4.4.5.4.6.4.73.8.4.4.83.8.4.4.93.8.4.4.103.8'.'4.113.8.4.4.123.8.4.5TitleStarTrussFloorsStructuralAcceptanceCriteriaMaterials,QualityControl,andSpecialConstructionTechniquesReactorVesselPedestalandDrywellFloorBiologicalShieldWallStarTrussTestingandIn-serviceSurveillanceRequirementsOtherSeismicCategoryIStructuresDescriptionoftheStructuresReactorBuildingControlRoomBuildingDieselGeneratorBuildingScreenwellBuildingIntakeStructuresIntake(andDischarge)TunnelsElectricalTunnelsandPipingTunnelsMainStackStandbyGasTreatment,BuildingandRailroadAccessLockAreaAuxiliaryServiceBuildingRadwasteBuildingTurbine'uildingApplicableCodes,Standards,andSpecificationsLoadsandLoadCombinationsDesignandAnalysisProceduresReactorBuildingControlRoomBuildingDieselGeneratorBuildingScreenwellBuildingIntakeStructuresIntake(andDischarge)TunnelsElectricalTunnelsandPipingTunnelsMainStackStandbyGasTreatmentBuildingandRailroadAccessLockAreaAuxiliaryServiceBuildingRadwasteBuildingTurbineBuildingStructuralAcceptanceCriteriaPacae3.8-353.8-353.8-353.8-363.8-363.8-373.8-373.8-373.8-383.8-383.8-393.8-413.8-413.8-413.8-423.8-423.8-433.8-433.8-433.8-443.8-443.8-453.8-463.8-493.8-493.8-503.8-533.8-533.8-533.8-543.8-5438-543.8-553.8-553.8-553'-553.8-553.8-56USARRevision83-xiiiNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.8.4.63.8.43.8.43.8.43.8.4.6.1.6.2.6.3~73.8.53.8.5'3.8.53.8.53.8.53.8.5~3~4.5.63.8.5.73.8.63.93.8.5.1'3.8.5.1.23.8.5.2TitleMaterials,QualityControl,andSpecialConstructionTechniquesConcreteReinforcingSteelStructuralSteelTestingandIn-serviceSurveillanceRequirementsFoundationsandConcreteSupportsDescriptionoftheFoundationandSupportsReactorBuildingFoundationsforOtherStructuresApplicableCodes,Standards,andSpecificationsLoadsandLoadCombinationsDesignandAnalysisProceduresStructuralDesignCriteriaMaterials,QualityControl,andSpecialConstructionTechniquesTestingandIn-serviceSurveillanceRequirementsReferenceMECHANICALSYSTEMSANDCOMPONENTSPacae3.8-563.8-573.8-633.8-683.8-703.8-703.8-703.8-703.8-713.8-713.8-723.8-723.8-733.8-743.8-743.8-743.9A-13.9A3.9A.13.9A.1.13.9A.1.23.9A.1.33.9A.1.43.9A.3.9A.3.9A.3.9A.3.9A.3.9A.1.4.11.4.1.11.4.21.51.5.11.5.23.9A.1.63.9A.1.5.33.9A.1~5'MECHANICALSYSTEMSANDCOMPONENTS(SWECSCOPEOFSUPPLY)SpecialTopicsforMechanicalComponentsDesignTransientsComputerProgramsUsedinAnalysesExperimentalStressAnalysisConsiderationfortheEvaluationoftheFaultedConditionEquipmentandComponentsASMEIIICompliancePipingSystemsAnalysisofPipingSystemsStaticAnalysisOccasionalDynamicLoadsExcludingSeismicandHydrodynamicInertiaLoadsField-RunPipingLoadCombinationsandStressCriteriaSafety-Related:HVACDuctworkandSupports3.9A-13.9A-13.9A-13.9A-13.9A-13.9A-13.9A-13.9A-13.9A-13.9A-43.9A-53.9A-73.9A-83.9A-83.9A-9USARRevision83-xivNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.9A.23'A.2'3.9A.2.1.13.9A.2.1.23.9A.23.9A.2.1.43.9A.2.1.53.9A.2.1.63.9A.2.23.9A.2.2.13.9A.2.2.23.9A.2.2.33'A.33.9A.3.13.9A.3.1.13.9A.3.1.23.9A.3.1.33.9A.3.23.9A.3.2.13.9A.3.2.23.9A.3.33.9A.3.43.9A.3.4.13.9A.3.4.23.9A.33.9A.43.9A.53.9A.63.9A.F13.9A.6'3.9A.6.33.9A.6'TitleDynamicTestingandAnalysisPipingVibration,ThermalExpansion,andDynamicEffectsFlowModesPreoperationalVibrationTestingPreoperationalThermalExpansionTestingMeasurementLocationsAcceptanceCriteriaCorrectiveActionsSeismicQualificationofSafety-RelatedMechanicalEquipmentSeismicQualificationCriteriaAcceptanceCriteriaSeismicQualificationof.SpecificNon-NSSSMechanicalEquipmentASMECodeClass1,2,and3Components,ComponentSupports,andCoreSupportStructuresLoadingCombinations,DesignTransients,andStressLimitsASMESectionIII,Class1ComponentsASMEClass2and3ComponentsCompliancewithRegulatoryGuide1.48PumpandValveOperabilityAssurancePumpOperabilityProgramValveOperabilityProgramDesignandInstallationDetailsforMountingofPressure-ReliefDevicesComponentSupportsPipeSupportsPumpSupportsOtherComponentsSupportsControlRodDriveSystemsReactorPressureVesselInternalsIn-serviceTestingofPumpsandValvesIn-serviceTestingofPumpsIn-serviceTestingofValvesReliefRequestsPipeWeldsWithinBreakExclusionAreaPacae3.9A-93.9A-93.9A-93.9A-93.9A-113.9A-113.9A-113.9A-123.9A-133.9A-133.9A-153.9A-163.9A-183.9A-183.9A-193.9A-213.9A-223.9A-223.9A-223.9A-243.9A-293.9A-293.9A-303.9A-343.9A-353.9A-373.9A-373.9A-373.9A-373.9A-383.9A-39I3.9A-39USARRevision8November'1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)SectionTitlePacae3.9B3.9B.13.9B.1.13.9B.1.1.13.9B.1.1.23.9B.1.1.33.9B.1.1.43.9B.1.1'3.9B.1.1'3.9B.1.1.73.9B.1~1'3.9B.1.1.93.9B.1.1.103.9B.1.1.113.9B.1.1.123.9B.1.23.9B.1.2.13.9B.1.2.23.9B.1.2.33.9B.1.2.43.9B.1.2.53.9B.1.2.63.9B.1.33.9B.1.3.13.9B.1.3.23.9B.1.43.9B.1.4.13.9B.1.4.23.9B.1.4.33.9B.13.9B.1.4.5MECHANICALSYSTEMSANDCOMPONENTS(GESCOPEOFSUPPLY)SpecialTopicsforMechanicalComponentsDesignTransientsControlRodDriveTransientsControlRodDriveHousingandIn-coreHousingTransientsHydraulicControlUnitTransientsCoreSupportandReactorInternalsTransientsMainSteamSystemTransientsRecirculationSystemTransientsReactorAssemblyTransientsMainSteamIsolationValveTransientsSafety/ReliefValveTransientsRecirculationFlowControlValveTransientsRecirculationPumpTransientsRecirculationGateValveTransientsComputerProgramsUsedinAnalysisReactorPressureVesselandInternalsPipingRecirculationPumpEmergencyCoreCoolingSystemPumpsandMotorsRHRHeatExchangersDynamicLoadAnalysisExperimentalStressAnalysisExperimentalStressAnalysisofPipingComponentsOrificedFuelSupport,VerticalandHorizontalLoadTestsConsiderationsfortheEvaluationofFaultedConditionsControlRodDriveSystemComponentsStandardReactorInternalComponentsReactorPressureVesselAssemblyCoreSupportStructureRecirculationGate,Safety/ReliefValves,andMainSteamIsolationValves3.9B-13.9B-13.9B-13.9B-13.9B-23.9B-33.9B-33.9B-33.9B-33'B-43.9B-43.9B-53.9B-73'B-73.9B-83.9B-93.9B-103.9B-153.9B-163.9B-163'B-173.9B-173.9B-173.9B-183.9B-183.9B-183.9B-183.9B-193.9B-203.9B-203.9B-21USARRevision83-xviNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.9B.1.4.63.9B.1.4.73.9B.1.4.83.9B.3.9B.3.9B.3.9B.3.9B.3.9B.1.4.91.4.101.4.111.4.1222.13.9B.2.1.13.9B.2.1.23.9B.2.1.33.9B.2.1.43.9B.2.1.63.9B.2.23.9B.2.2.13.9B.2.2.23.9B.2.33.9B.2.43.9B.2.53.9B.2.63.9B.2'.4.13.9B.2.1.4.23.9B.2.1.4.33.9B.2.1.5TitleRecirculationSystemFlowControlValveRecirculationPipingNuclearSteamSupplySystemPumps,HeatExchanger,andTurbine.ControlRodDriveHousingSupportsFuelStorageRacksFuelAssembly(IncludingChannels)RefuelingEquipmentDynamicTestingandAnalysisPipingVibration,ThermalExpansion,andDynamicEffectsPipingVibrationThermalExpansionTestingofRecirculationPipingDynamicEffectsTestingofRecirculationPipingTestEvaluationandAcceptanceCriteriaforRecirculationPipingLevel1CriterionLevel2CriteriaAcceptanceLimitsCorrectiveActionsforRecirculationPipingMeasurementLocationsforRecirculationPipingSeismicandHydrodynamicQualificationofSafety-RelatedMechanicalEquipmentTestsandAnalysisCriteriaandMethodsSeismicandHydrodynamicLoadQualificationofSpecificNSSSMechanicalComponentsDynamicResponseofReactorInternalsUnderOperationalFlowTransientsandSteady-StateConditionsPreoperationalFlow-InducedVibrationTestingofReactorInternalsDynamicSystemAnalysisofReactorInternalsUnderFaultedConditionsCorrelationsofReactorInternalsVibrationTestsWithAnalyticalResultsPacae3.9B-213.9B-213.9B-213.9B-213.9B-213.9B-223.9B-223.9B-223.9B-223.9B-223.9B-233.9B-243.9B-253.9B-253.9B-253.9B-263.9B-263.9B-273.9B-273.9B-283.9B-293.9B-333.9B-343.9B-353.9B-35USARRevision83xviiNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.9B.33.9B.3'3.9B.3.9B.3.9B.3.9B.3.9B.3.9B.3.9B.3.9B.3.1.13~1~23.1~33.1.43.1.53.1.63.1.7'.1.83.9B.3.9B.3.9B.3.9B.3.9B.3.1.93.1.103.1.1131123.1.133.9B.3.2.13.9B.3.2.23.9B.3.9B.3.9B.3.9B.3.2.33.2.3'3.2.3.23'3.9B.3.9B.3.9B.3.9B.3.9B.3.3.13.43.4.13.4.23.4.33.9B.3.4.43.9B.3.4.53.9B.43.9B.4.13.9B.4.23.9B.3.1.143.9B.3.2TitleASMESectionIII,SafetyClass1,2,and3Components,ComponentSupports,andCoreSupportStructuresLoadCombinations,DesignTransients,andStressLimitsPlantConditionsReactorPressureVesselAssemblyMainSteamPipingRecirculationLoopPipingRecirculationSystemValves.RecirculationPumpStandbyLiquidControlTankResidualHeat.RemovalHeatExchangersRCICTurbineRCICPumpECCSPumpsStandbyLiquidControlPumpMainSteamIsolationandSafety/ReliefValvesReactorWaterCleanupSystemPumpandHeatExchangersPumpandValveOperabilityAssuranceECCSPumpsandMotorsSLCPumpandMotorAssemblyandRCICPumpAssemblyNSSSValvesSafetyClass1ActiveValvesSafetyClass2and3ActiveValvesDesignandInstallationofPressureReliefDevicesMainSteamSafety/ReliefValvesComponentSupportsPipingReactorPressureVesselStabilizerNSSSFloor-MountedEquipment(Pumps,HeatExchanger,andRCICTurbine)SupportsforASMESafetyClass1,2,and3ActiveComponentsBoltingSupportControlRodDriveSystemDescriptiveInformationonCRDSystemApplicableCRDSystemDesignSpecificationsPacae3.9B-363.9B-363.9B-363.9B-383.9B-393.9B-393.9B-393.9B-393.9B-403.9B-403.9B-403.9B-403.9B-413.9B-413.9B-423.9B-423.9B-423.9B-433.9B-453.9B-463.9B-463.9B-483.9B-483.9B-483.9B-493.9B-493.9B-533.9B-533.9B-543.9B-553.9B-553.9B-553.9B-56USARRevision83-xviiiNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.9B.4.33.9B.4.43.9B.53.9B.5.13.9B.5.1.13.9B.5.1.23.9B.5.23.9B.5.2.13.9B.5.2.23.9B.5.2.33.9B.5.33.9B.5.3'3.9B.5.3'3.9B.5.3.33.9B.5.3'3.9B.5.3.53.9B.5.3.63.9B.63.103.10A3.10A.13.10A.23.10A.2.13.10A.2.23.10A.2.33.10A2.43.10A.33.10A.4Title'esignLoads,StressLimits,andAllowableDeformationCRDPerformanceAssuranceProgramReactorCoreSupportStructuresandPressureVesselInternalsDesignArrangementsCoreSupportStructuresReactorVesselInternalsDesignLoadingConditionsEventstoBeEvaluatedPressureDifferentialDuringRapidDepressurizationRecirculationLineandSteamLineBreakDesignBasesSafetyDesignBasesPowerGenerationDesignBasesDesignLoadingCategoriesResponseofInternalsDuetoInsideSteamBreakAccidentStress,Deformation,andFatigueLimitsforEngineeredSafetyFeatureReactorInternals(ExceptCoreSupportStructure)Stress,Deformation,andFatigueLimitsforCoreSupportStructuresReferencesSEISMICQUALIFICATIONOFCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENTSEISMICQUALIFICATIONOFCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENT(SWECSCOPEOFSUPPLY)SeismicQualificationCriteriaMethodsandProceduresforQualifyingElectricalEquipmentandInstrumentationTestingPrototypeTestingAnalysisCombinedAnalysisandTestingMethodsandProcedures'ofAnalysisorTestingofSupportsofElectricalEquipmentandInstrumentationOperatingLicenseReviewPacae3.9B-563.9B-563.9B-573.9B-573.9B-593.9B-613.9B-643.9B-643.9B-643.9B-653.9B-663.9B-663.9B-673.9B-673.9B-683.9B-68.3.9B-693.9B-703.10A-13.10A-13.10A-13.10A-23.10A-23.10A-33.10A-43.10A-43.10A-43.10A-5USARRevision83-xixNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)Section3.10B3.10B.13.10B.1.13.10B.1.23.10B.1.2.13.10B.23.10B.2.13;10B.2.23.10B.2.33.10B.2.43.10B.33.10B.3.13.10B.3.1.13.10B.43.113.11.13.11'3.11.2.13.11.2.23.11.33.11.43.11.53.11.F13.11.5.23.11.63.11.7TitleSEISMICANDHYDRODYNAMICQUALIFICATIONSOFSEISMICCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENT(GESCOPEOFSUPPLY)DynamicQualificationCriteriaSeismicCategoryIEquipmentIdentificationDynamicDesignCriteriaNSSSEquipmentMethodsandProceduresforQualifyingElectricalEquipmentandInstrumentationMethodsofShowingNSSSEquipmentCompliancewithIEEE-344-1975andRegulatoryGuide1.100TestingProceduresforQualifyingElectricalEquipmentandInstrumentationQualificationofValveOperatorsQualificationofNSSSMotorsMethodsandProcedureofAnalysisorTestingofSupportsofElectricalEquipmentandInstrumentationDynamicAnalysisandTestingProceduresPanel-MountedEquipmentOperatingLicenseReviewENVIRONMENTALQUALIFICATIONOFMECHANICALANDELECTRICALEQUIPMENTEquipmentIdentificationandEnvironmentalConditionsQualificationTestsandAnalysesQualificationMethodofQualificationofClass1EEquipmentandComponentsQualificationTestResultsLossofHeating,Ventilating,andAirConditioningEstimatedChemicalandRadiationEnvironmentChemicalEnvironmentRadiationEnvironmentSubmergenceReferencesPacae3.10B-13.10B-13-10B-13.10B-13.10B-13.10B-23.10B-2310B-33.10B-43.10B-43.10B-43.10B-43.10B-43.10B-63.11-13.11-13.11-23'1-23~1133.11-43.11-43.11-43.11-43.11-43.11-53.11-6USARRevision8"'-xxNovember1995 NineMilePointUnit2FSARCHAPTER3TABLEOFCONTENTS(Cont'd.)SectionAPPENDIX3A,APPENDIX3BAPPENDIX3CAPPENDIX3DTitleCOMPUTERPROGRAMSFORDYNAMICANDSTATICANALYSISOFCATEGORYISTRUCTURES~EQUIPMENTSANDCOMPONENTSPRESSUREANALYSISFORSUBCOMPARTMENTSOUTSIDECONTAINMENTFAILUREMODEANALYSISFORPIPEBREAKSANDCRACKSUNIT2ASSESSMENTOFGENERALDESIGNCRITERIA51TO10CFR50APPENDZX3ECLASSIFICATIONOFSTRESSESINCOMPONENT/PIPINGSUPPORTSDUETOLOADSFROMSEISMICANCHORMOTIONANDTHERMALGROWTHOFPIPINGUSARRevision63.xxi NineMilePointUnit2FSARCHAPTER3LISTOFTABLESTableNumberTitle3~213~223~233.2-43~313.4-13.4-2EQUIPMENTANDSTRUCTURECLASSIFICATIONCODEGROUPDESIGNATIONSIINDUSTRYCODESgANDSTANDARDSFORMECHANICALCOMPONENTSSUMMARYOFSAFETYCLASSDESIGNREQUIREMENTSREACTORCOOLANTPRESSUREBOUNDARYCLASSIEQUIPMENTCODEAPPLICATIONDYNAMICWINDPRESSUREFORCATEGORYISTRUCTURESFLOODPROTECTIONFORSAFETY-RELATEDSTRUCTURESANDSYSTEMSPENETRATIONSTHROUGHEXTERIORWALLSOFREACTORBUILDINGBELOWDBFL3.4-3PENETRATIONSTHROUGHEXTERIORWALLSOFCONTROLANDTURBINEBUILDINGSBELOWDBFL3.4-43.4-53.4-6PENETRATIONSTHROUGHEXTERIORWALLSOFRADWASTEBUILDINGANDSCREENWELLBUILDINGBELOWDBFLPENETRATIONSTHROUGHEXTERIORWALLSOFPIPETUNNELSBELOWDBFLPENETRATIONSTHROUGHEXTERIORWALLSOFDIESELGENERATORBUILDINGANDMAINSTACKBELOWDBFL3.4-73.5-13.5-2PERFORMANCEOFWATERSTOPMATERIALINEXPECTEDENVIRONMENTSAFETYRELATEDSTRUCTURES~SYSTEMSIANDCOMPONENTSSUMMARYOFFORCESANDSTRESSESACTINGONTHERMOWELLWELDSINTHEVARIOUSHIGH-ENERGYSYSTEMS3.5-33.5-4DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2(Manufacturer'sProbability)DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMUNIT1STRIKINGPLANTREGIONSATUNIT2(Manufacturer'sProbability)USARRevision8'3-xxiiNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumber3.5-53.5-63.5-73.5-83.5-93.5-103.5-113.5-123.5-133.5-14TitleDAMAGEPROBABILITY,DUETOLOW-TRAJECTORYTURBINEMISSILESFROMJAMESA.'ITZPATRICKPOWERSTATIONSTRIKINGPLANTREGIONSATVNZT2(Manufacturer'sProbability)DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2(NRCProbability)DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMVNZT1STRIKINGPLANTREGIONSATUNIT2(NRCProbability)DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMJ'AMESA.FITZPATRICKPOWERSTATION'TRIKINGPLANTREGIONSATUNIT2(NRCProbability)DAMAGEPROBABILITYDUETOHIGH-TRAJECTORYTURBINEMZSS1LESFROMVNZT2STRIKINGPLANTREGIONSATUNIT2(Manufacturer'sProbability)DAMAGEPROBABILITYDUETOHIGH-TRAJECTORYTURBINEMISSILESFROMUNIT1STRIKINGPLANTREGIONSATUNZT2(Manufacturer'sProbability)DAMAGEPROBABILITYDUETOHIGH-TRAJECTORYTURBINEMISSILESFROMJAMESA.FITZPATRICKPOWERSTATIONSTRIKZNGPLANTREGIONSATUNIT2(Manufacturer'sProbability)DAMAGEPROBABILITYDUETOHIGH-TRAJECTORYTURBINEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2(NRCProbability)DAMAGEPROBABILZTYDUETOHIGH-TRAJECTORYTURBINEMISSILESFROMVNIT1STRIKINGPLANTREGIONSATUNIT2(NRCProbability)DAMAGEPROBABILITYDUETOHIGH-TRAJECTORYTURBINEMXSSZLESFROMJ'AMESA.FITZPATRXCKPOWERSTATIONSTRIKINGPLANTREGIONSATUNIT2(NRCProbability)USARRevision63..XXiiiApril,1994 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumberTitle3.5-153.5-163.5-173.5-183'-193.5-203.5-213.5-223.6A-13.6A-2thru3.6A-713.6A-723.6A-733.6B-13.6B-23.7A-l.3.7A-2SUMOFDAMAGEPROBABILITYDUETOLOW-ANDHIGH-TRAJECTORYTURBINEMISSILESGENERATEDFROMTURBINESATUNITS1AND2ANDJAMESA.FITZPATRICKTOPLANTREGIONSOFUNIT2(Manufacturer'sProbability)SUMOFDAMAGEPROBABILITYDUETOLOW-ANDHIGH-TRAJECTORYTURBINEMISSILESGENERATEDFROMTURBINESATUNITS1AND2ANDJAMESA.FITZPATRICKTOPLANTREGIONSOFUNIT2(NRCProbability)TURBINEMISSILEINFORMATION(43-INCHLASTSTAGEBUCKETUNIT)TURBINEMISSILEINFORMATION(38-INCHLASTSTAGEBUCKETUNITS)BASICASSUMPTIONSFORPROBABILITYANALYSISOFTURBINEMISSILESTRIKEDELETEDSELECTEDEXTERNALMISSILESMISSILEBARRIERSFORNATURALPHENOMENAANDTURBINE-GENERATEDMISSILESCOMPARISONOFPIPERUPTURECRITERIADELETEDESSENTIALSYSTEMS/COMPONENTS/EQUIPMENTEVALUATEDFORPIPEFAILURESHIGHENERGYPIPINGPARTI(INSIDECONTAINMENT)PDAVERIFICATIONRESTRAINTDATACOMPARISONOFPDAANDNSCCODEDAMPINGFACTORSFOUNDATION/SUPPORTMEDIAFORCATEGORY1STRUCTURESUSARRevision8'3-xxivNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumber3.7A-33.7A-43.7A-53.7A-63.7A-73.7A-83.7A-93.7A-10.TitlePRIMARYCONTAINMENTMODESHAPES(CRACKED)PRIMARYCONTAINMENTMODESHAPES(UNCRACKED)SECONDARYCONTAINMENTMODESHAPESCONTROLANDDIESELGENERATORBUILDINGMODESHAPESPRIMARYCONTAINMENT-MODALRESPONSES(CRACKED)PRIMARYCONTAINMENT-MODALRESPONSES(CRACKED)SSEACCELERATIONCOMPARISONTABULATIONOFSTRUCTURALGAPANDWORST-CONDITIONGAPFORSSECOMPARISON3.7A-11DESIGNATTRIBUTESTOBEREVIEWEDFORVERIFICATIONOFLARGEBORESAFETY-RELATEDPIPINGASREQUIREDBYIEBULLETIN79-143.7A-12DESIGNATTRIBUTESTOBEREVIEWEDFORVERIFICATIONOFSMALLBORESAFETY-RELATEDPIPINGASREQUIREDBYIEBULLETIN79-143.7A-133.7B-13.7B-23.8-1COMPARISONOFRESULTS:STATICVERSUSDYNAMICANALYSISFORINSTRUMENTPANEL2DFM-PNL102CRITICALDAMPINGRATIOSFORDIFFERENTMATERIALSNUMBEROFDYNAMICRESPONSECYCLESEXPECTEDDURINGASEISMICEVENTLOADCOMBINATIONSFORCONCRETEPRIMARYCONTAINMENT3.8-2LOADCOMBINATIONSFORCONTAINMENTWALLLINER,FLOORLINERSCORNERTRANSITIONREGIONS'NDEMBEDMENTLINERINSERTPLATES3.8-33.8-43.8-5LOADCOMBINATIONSFORACCESSLOCKSANDHATCHESLOADCOMBINATIONSFORTHEDRYWELLHEADLOADCOMBINATIONSANDSTRESSLIMITSFORSAFETYCLASS1PIPEPENETRATIONSUSARRevision83-.xxvNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumber3.8-63.8-73.8-83.8-93.8-103.8-113.8-123.8-133.8-143.8-15TitleLOADCOMBINATIONSANDSTRESSLIMITSFORSAFETYCLASS2PIPEPENETRATIONSLOADCOMBINATIONSANDSTRESSLIMITSFORPENETRATIONS-CLASSMCPORTIONSSTRESSLOADCOMBINATIONSFORTHEBIOLOGICALSHIELDWALLDESIGNSTRENGTHFORLOADCOMBINATIONSONCATEGORYISTEELSTRUCTURESREQUIREDSTRENGTHFORLOADCOMBINATIONSONCATEGORYICONCRETESTRUCTURESLOADCOMBINATIONSFORINTAKETUNNELSMAJORSTRUCTURESFOUNDATIONSYSTEMSFACTORSOFSAFETYFOROVERTURNING,SLIDINGANDFLOATATIONOFMAJORCATEGORYISTRUCTURESPREDICTEDSTRUCTURALRESPONSE-CONTAINMENTPRESSURETEST3.9A-1TRANSIENTSANDTHENUMBEROFASSOCIATEDCYCLESCONSIDEREDINTHEDESIGNANDFATIGUEANALYSISOFCLASS1PIPING3.9A-2LOADCOMBINATIONSANDSTRESSLIMITSFORPIPESTRESSANALYSIS3.9A-33.9A-43.9A-53'A-6PIPESTRESSANALYSISCLASSIFICATIONSFORASMECODECLASSES1,2,3BOPSEISMIC/DYNAMICQUALIFICATIONRESULTSMECHANICALEQUIPMENTLOADCOMBINATIONSFORASMESECTIONIIICLASS1VALVESLOADCOMBINATIONSFORASMESECTIONIIICLASS2AND3ANDNON-ASMECOMPONENTSUSARRevision83-xxviNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumberTitle3.9A-73.9A-S3.9A-93.9A-103.9A-113.9A-123.9A-133.9A-143.9A-153.9A-163.9B-13.9B-23.9B-2a3.9B-2b3.9B-2c3.9B-2d3.9B-2e3.9B-2f3.9B-2gSTRESSLIMITSFORASMESECTIONIIICLASS1(NB)SEISMICCATEGORYICOMPONENTS(ELASTICANALYSIS)STRESSLIMITSFORASMESECTIONIIICLASS2AND3COMPONENTS(ELASTICANALYSIS)SUMMARYOFACTIVEPUMPS(SWECSCOPEOFSUPPLY)SUMMARYOFSEISMICSTRESSANALYSISRESULTSDELETEDACTIVEVALVES(BOP)LOADCOMBINATIONSFORCOMPONENTSUPPORTSANDSTRESSLIMITSFORPLATEANDSHELL-TYPESUPPORTSLOADCONDITIONSFORPIPESUPPORTSREQUIREMENTSFORSAFETYCLASSES2AND3INSTRUMENTANDPNEUMATICTUBINGANDSUPPORTSBASISFORDESIGNANDCONSTRUCTIONOFASMEANDNON-ASMEPIPINGSUPPORTSPLANTEVENTSLOADCOMBINATIONSgSTRESSLIMITSgANDALLOWABLESTRESSESCONTROLRODDRIVECONTROLRODGUIDETUBEINCOREHOUSINGJETPUMPSHIGHESTSTRESSEDREGIONONTHELPCICOUPLING(ATTACHMENTRING)REACTORPRESSUREVESSELSUPPORTEQUIPMENTCONTROLRODDRIVEHOUSINGUSARRevision8,3-xxv3.3.'November1995 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumber3.9B-2h3.9B-2i3.9B-2j3.9B-2k3.9B-2L3.9B-2m3.9B-2n3.9B-2o3.9B-2p3.9B-2q3.9B-2r3.9B-2s3.9B-2t3.9B-2u3.9B-2v3.9B-2w3.9B-2x3.9B-2y3.9B-2z3.9B-3TitleREACTORPRESSUREVESSELANDSHROUDSUPPORTASSEMBLYREACTORVESSELINTERNALSANDASSOCIATEDEQUIPMENTSAFETY/RELIEFVALVESSPRING-LOADEDDIRECT-ACTINGTYPEREACTORRECIRCULATIONSYSTEMGATEVALVESRECIRCULATIONFLOWCONTROLVALVE24-INSIZE(FISHER)ASMESAFETYCLASS1RECIRCULATIONPIPINGANDPIPEMOUNTEDEQUIPMENTHIGHESTSTRESSSUMMARYREACTORREFUELINGANDSERVICINGEQUIPMENTFUELASSEMBLY(INCLUDINGCHANNEL)RECIRCULATIONPUMP(SUMMARYOFLOADCLASSIFICATIONHIGHSTRESSLOCATIONSANDLIMITCRITERIAPUMPCASE)STANDBYLIQUIDCONTROLTANKRESIDUALHEATREMOVALHEATEXCHANGERRCICTURBINERCICPUMPECCSPUMPSSTANDBYLIQUIDCONTROLPUMPREACTORWATERCLEANUPSYSTEMPUMPREACTORWATERCLEANUPCRDHOUSINGSUPPORTSMAINSTEAMISOLATIONVALVESNSSSCOMPLIANCEWITHREGULATORYGUIDE1.48USARRevision83-xxviiiNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFTABLES(Cont'd.)TableNumberTitle3.9B-43.9B-53.9B-63.9B-73.9B-S3.9B-93.9B-103.9B-113.10A-1GE-SUPPLIEDSEISMICACTIVEPUMPSANDVALVESDEFORMATIONLIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)PRIMARYSTRESSLIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)BUCKLINGSTABILITYLIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)FATIGUELIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)CORESUPPORTSTRUCTURESSTRESSCATEGORIESANDLIMITSOFSTRESSINTENSITYFORSERVICELEVELSAANDB(NORMALANDUPSET)CONDITIONSCORESUPPORTSTRUCTURESSTRESSCATEGORIESANDLIMITSOFSTRESSINTENSITYFORSERVICELEVELC(EMERGENCY)CONDITIONSCORESUPPORTSTRUCTURESSTRESSCATEGORIESANDLIMITSOFSTRESSINTENSITYFORSERVICELEVELD(FAULT)CONDITIONCLASS1EELECTRICALEQUIPMENTQUALIFICATIONRESULTS3.10B-1ESSENTIALELECTRICALCOMPONENTSANDINSTRUMENTSSEISMICQUALIFICATIONTESTSUMMARYUSARRevision83-XX1XNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURESFigureNumberTitle3~213~313.5-13.5-23.5-33.5-4,3.5-53.6A-13.6A-23.6A-33.6A-43.6A-53.6A-63.6A-73.6A-83.6A-93.6A-103.6A-113.6A-12thru3.6A-51GROUPCLASSIFICATIONDIAGRAMANNUALEXTREMEWINDVELOCITY30FTABOVEGROUNDi100-YRMEANRECURRENCEINTERVALTURBINEPLACEMENTANDORIENTATIONTURBINEMISSILEREFERENCEDCOORDINATESYSTEMSOLIDANGLEONAUNITSPHERETOPVIEWOFIDEALIZEDTARGETSIDEVIEWOFIDEALIZEDTARGETAREASOFANALYSISSTEADYSTATEBLOWDOWNFORCESVSFRICTIONPARAMETERDYNAMICANALYSISMODELRHS(LPCI)RESTRAINT2RHS*PRR004FLUIDBLOWDOWNFORCESUSEDFOR2RHS*PRR004RESTRAINTANALYSISRESTRAINT(2RHS*PRR004)REACTIONLOAD'NERGYBALANCESAMPLEPROBLEMPIPECRUSHBUMPERTWO-PINLAMINATEDPIPERUPTURERESTRAINT(SMALLLINES)TWO-PINLAMINATEDPIPERUPTURERESTRAINT(LARGELINES)OMNI-DIRECTIONALPIPERUPTURERESTRAINTLIMITSTOPRESTRAINTDELETEDUSARRevision8,3-.xxxNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumberTitle3.6A-52HIGHENERGYPIPINGCOMPOSITEPLANEL175'-0"AND215/-03.6A-533.6A-543.6A-553.6A-563.6A-573.6A-583.6A-593.6A-603.6B-13.6B-23.6B-33.7A-13.7A-2HIGHENERGYPIPINGCOMPOSITEPLANEL240-0"HIGHENERGYPIPINGCOMPOSITEPLANEL261-0"HIGHENERGYPIPINGCOMPOSITEPLANEL289'-0"HIGHENERGYPIPINGCOMPOSITEPLANEL306'-6"HIGHENERGYPIPINGCOMPOSITEPLANEL328-10"HIGHENERGYPIPINGCOMPOSITESECTION1-1HIGHENERGYPIPINGCOMPOSITESECTION2-2HIGHENERGYPIPINGCOMPOSITESECTIONS3-3AND4-4TYPICALRESTRAINTFORCEDEFLECTIONCURVETYPICALPIPEWHIPRESTRAINTCONFIGURATIONBREAKLOCATIONSANDRESTRAINTSANALYZED,PDAVERIFICATIONPROGRAMHORIZONTALSSEDESIGNRESPONSESPECTRANORMALIZEDTO0.15GVERTICALSSEDESIGNRESPONSESPECTRANORMALIZEDTO0.15G3.7A-3HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTHQUAKE)BASEDON2.0PERCENTDAMPINGRATIO3.7A-4HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTHQUAKE)BASEDON1PERCENTDAMPINGRATIO3.7A-5HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTHQUAKE)BASEDON5.0PERCENTDAMPINGRATIOUSARRevision83-.xxxi..November.1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumberTitle3.7A-63.7A-7HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTHQUAKE)BASEDON7.0PERCENTDAMPINGRATIOHORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(EAST-WESTEARTHQUAKE)BASEDON10.0PERCENTDAMPINGRATIO3.7A-8HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(NORTH-SOUTHEARTHQUAKE)BASEDON1.0PERCENTDAMPINGRATIO3.7A-93.7A-10HORIZONTALSSEDESIGNRESPONSESPECTRUMAND"RESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(NORTH-SOUTHEARTHQUAKE)BASEDON2.0PERCENTDAMPINGRATIOHORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(NORTH-SOUTHEARTHQUAKE)BASEDON5.0PERCENTDAMPINGRATIO3.7A-11HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(NORTH-SOUTHEARTHQUAKE)BASEDON7.0PERCENTDAMPINGRATIO3.7A-12HORIZONTALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTALSSESYNTHETICTIMEHISTORY(NORTH-SOUTHEARTHQUAKE)BASEDON10.0PERCENTDAMPINGRATIO3.7A-13VERTICALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMVERTICALSSESYNTHETICTIMEHISTORYBASEDON1.0PERCENTDAMPINGRATIO3.7A-14VERTICALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMVERTICALSSESYNTHETICTIMEHISTORYBASEDON2.0PERCENTDAMPINGRATIO3.7A-15VERTICALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMVERTICALSSESYNTHETICTIMEHISTORYBASEDON5.0PERCENTDAMPINGRATIOUSARRevision83-xxxiiNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumberTitle3.7A-16VERTICALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMVERTICALSSESYNTHETICTIMEHISTORYBASEDON7.0PERCENTDAMPINGRATIO3.7A-17VERTICALSSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMVERTICALSSESYNTHETICTIMEHISTORYBASEDON10.0PERCENTDAMPINGRATIO3.7A-183.7A-193.7A-203.7A-213.7A-223.7A-233.7A-243.7A-253.7A-263.7A-273.7A-283.7A-293.7A-30DYNAMICMODELFORSEISMICANALYSISOFPRIMARYCONTAINMENTDYNAMICMODELFORSEISMICANALYSISOFREACTORBUILDINGWALLDYNAMICMODELFORSEISMICANALYSISOFTHECONTROLANDDIESELGENERATORBUILDINGSSSEPRIMARYCONTAINMENTCRACKEDCONDITIONACCELERATIONPROFILE(G)EAST-WESTDIRECTIONSSEPRIMARYCONTAINMENTCRACKEDCONDITIONACCELERATIONPROFILE(GS)VERTICALDIRECTIONSSEPRIMARYCONTAINMENTCRACKEDCONDITIONACCELERATIONPROFILE(GS)NORTH-SOUTHDIRECTIONSSEPRIMARYCONTAINMENTUNCRACKEDCONDITIONACCELERATIONPROFILE(GS)EAST-WESTDIRECTIONSSEPRIMARYCONTAINMENTUNCRACKEDCONDITIONACCELERATIONPROFILE(GS)VERTICALDIRECTIONSSEPRIMARYCONTAINMENTUNCRACKEDCONDITIONACCELERATIONPROFILE(GS)NORTH-SOUTHDIRECTIONSSEREACTORBUILDINGWALLACCELERATIONPROFILE(GS)EAST-WESTDIRECTIONSSEREACTORBUILDINGWALLACCELERATIONPROFILE(GS)VERTICALDIRECTIONSSEREACTORBUILDINGWALLACCELERATIONPROFILE(GS)NORTH-SOUTHDIRECTIONSSECONTROLANDDIESELGENERATORBUILDINGSACCELERATIONPROFILE(GS)EAST-WESTDIRECTIONUSARRevision83-xxxi'iiNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumber3.7A-313.7A-323.7A-333.7A-343.7A-353.7A-363.7B-13.7B-23.7B-33.8-13.8-23.8-33.8-3a3.8-43.8-53.8-6TitleSSECONTROLANDDIESELGENERATORBUILDINGSACCELERATIONPROFILE(GS)VERTICALDIRECTIONSSECONTROLANDDIESELGENERATORBUILDINGSACCELERATIONPROFILE(GS)NORTH-SOUTHDIRECTIONPLANANDSECTIONSFORDUCTLINES907,922/ELECTRICALMANHOLENO.1,ANDDIESELGENERATORBUILDINGFLOORSLABSALTERNATIVEDAMPINGVALUESPERASMECODECASEN-411RELATIVEDISPLACEMENTBETWEENREACTORBUILDINGANDPRIMARYCONTAINMENTJUSTIFICATIONOFSTATICCOEFFICIENTOF13(SHEETS1AND2)SEISMICANALYTICALMODELFORNSSSCOMPONENTSREACTORPRESSUREVESSELANDINTERNALSSEISMICMODELDENSITYOFSTRESSREVERSALSPRIMARYCONTAINMENT,LINERELEVATION,ANDDETAILSPRIMARYCONTAINMENT,LINERFLOORPRIMARYCONTAINMENTWALL,SECTIONVIEWPRIMARYCONTAINMENTWALLREINFORCINGDETAILSEL175'>~TO241'n~AZIMUTH180~TO360~PRIMARYCONTAINMENTWALL,STRUCTURALDETAILSAROUNDDRYWELLACCESSHATCHESPRIMARYCONTAINMENT,TYPICALBEAMSEATDETAILSCOMBINATIONEQUIPMENTHATCHANDPERSONALAIRLOCKANDESCAPEAIRLOCK-PRIMARYCONTAINMENT3.8-7CONTROLRODDRIVEREMOVALHATCHANDSUPPRESSIONPOOLACCESSHATCHUSARRevision83-xxxivNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumber3.8-83.8-93.8-103.8-113.8-123.8-133.8-143.8-153.8-163.8-173.8-183.8-193.8-203.8-213.8-223.8-233.9A-1TitleDRYWELLHEADANDFINGERPINCLOSUREDETAILSOTHERPIPINGANDINSTRUMENTPENETRATZONSTHROUGHPRIMARYCONTAINMENTTHERMALLYHOTANDTHERMALLYCOLDPIPINGPENETRATIONSTHROUGHPRIMARYCONTAINMENTPRIMARYCONTAINMENTANDINTERNALSTRUCTURESARRANGEMENTOFPENETRATIONSTHROUGHDRYWELLFLOORTYPICALREINFORCINGBARDETAILSFORDRYWELL,FLOORTYPICALREINFORCINGBARDETAILSFORRPVPEDESTALBIOLOGICALSHIELDWALLDETAILSRINGGIRDERSSTARTRUSSgANDSTABILIZER2Q~NGEMENTTYPICALDETAILSATCONSTRUCTIONJOINTSANDSPACESBETWEENBUILDINGANDROCKSURFACEEXTERIORREACTORBUILDINGWALLTYPICALREINFORCINGARPANGEMENT(SHEETS1AND2)SPENTFUELPOOLGIRDERSPLANTANDELEVATION(SHEETS1AND2)REINFORCEMENTREACTORBUILDINGMATTYPICALDETAILWALL/COLUMNTOFOUNDATIONMATJUNCTIONCONTAINMENTMAT-TOPREINFORCINGDETAILSCONTAINMENTMAT-BOTTOMREINFORCINGDETAILSTYPICALSAFETYCLASSES2AND3TUBESUPPORTSANDMARKING3.9A-2TYPICALPLATEANDSHELLTYPESUPPORTJURISDICTIONALBOUNDARIESrUSARRevision8November1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumberTitle3.9A-33.9A-43.9A-53.9A-63.9A-73.9A-83.9A-93.9A-103.9A-113.9A-123.9A-133.9A-143.9A-153.9A-163.9A-173.9A-183.9A-193.9A-203.9A-213.9A-223.9A-233.9A-24TYPICALPLATEANDSHELLTYPESUPPORTJURISDICTIONALBOUNDARIESTYPICALLINEARTYPESUPPORTJURISDICTIONALBOUNDARIESPIPESUPPORTJURISDICTIONALBOUNDARIESARSOFACC.PRIMARYCONT.(ELEV196.67FT)ARSOFACC.PRIMARYCONT.(ELEV196.67FT)ARSOFACC.SHIELDWALL(ELEV315.08FT)ARSOFACC.SHIELDWALL(ELEV315.08FT)ARSOFACC.RPVSHELL(ELEV332.70FT)ARSOFACC.RPVSHELL(ELEV332.70FT)ARSOFACC.PRIMARYCONT.(ELEV196.67FT)ARSOFACC.PRIMARYCONT.(ELEV196.67FT)ARSOFACC.SHIELDWALL(ELEV315.08FT)ARSOFACC.SHIELDWALL(ELEV315.08FT)ARSOFACC.RPVSHELL(ELEV332.70FT)ARSOFACC.RPVSHELL(ELEV332.70FT)ARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.SECONDARYCONT.(ELEV175)ATMATUSARRevision83-xxxviNovember1995 NineMilePoint,Unit,2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumber3.9A-253.9A-263.9A-273.9A-283.9A-293.9A-303.9A-313.9A-323.9A-333.9A-343.9A-353.9A-363.9A-373.9A-383.9A-393.9A-403.9A-413.9A-423.9A-433.9A-443.9A-453.9A-463.9A-47TitleARSOFACC.SECONDARYCONT.(ELEV175)ATMATARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.SECONDARYCONT.(ELEV175)ATMATARSOF'ACC.SECONDARYCONT.(ELEV175)ATMATARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.SECONDARYCONT.(ELEV175)ATMATARSOFACC.SECONDARYCONT.(ELEV175)ATMATARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.PRIMARYCONT.(ELEV206.11FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.SHIELDWALLOUT(ELEV315.23FT)ARSOFACC.RPVSHELL(ELEV315.08FT)ARSOFACC.RPVSHELL(ELEV315.08FT)USARRevision83-xxxviiNovember1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumberTitle3.9A-483.9A-493.9A-503.9A-513.9A-523.9A-533.9A-543.9A-553.9A-563.9A-573.9A-583.9A-593.9A-603.9A-613.9A-623.9A-633.9A-643.9A-653.9A-663.9A-673.9B-13.9B-23.9B-3ARSOFACC.PRIMARYCONT.(ELEV176.0FT)ATMATARSOFACC,.PRIMARYCONT.(ELEV176.0FT)ATMATARSOFACCELERATIONPRIMARYCONT.EL.19667FTARSOFACCELERATIONPRIMARYCONT.EL.196.67FTARSOFACCELERATIONPRIMARYCONT.EL.196.67FTARSOFACCELERATIONPRIMARYCONTEL.19667FTARSOFACCELERATIONPRIMARYCONT.EL.196-67FTARSOFACCELERATIONPRIMARYCONT.EL.196.67FTARSOFACCELERATIONSHIELDWALLEL.315.09FTARSOFACCELERATIONSHIELDWALLEL.315.09FTARSOFACCELERATIONSHIELDWALLEL.315.09FTARSOFACCELERATIONSHIELDWALLEL.315.09FTARSOFACCELERATIONSHIELDWALLEL.315.09FTARSOFACCELERATIONSHIELDWALLEL.315.09FTARSOFACCELERATIONRPVSHELLEL.332.70FTARSOFACCELERATIONRPVSHELLEL.332.70FTARSOFACCELERATIONRPVSHELLEL.332.70FTARSOFACCELERATIONRPVSHELLEL.332.70FTARSOFACCELERATIONRPVSHELLEL.332.70FTARSOFACCELERATIONRPVSHELLEL.332.70FTDELETEDREACTORINTERNALSFLOWPATHSFLUESUPPORTPIECESUSARRevision83-xxxv3.3.3.November,1995 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont'd.)FigureNumberTitle3.9B-43.9B-5JETPUMPPRESSURENODESUSEDFORDEPRESSURIZATIONANALYSISUSARRevision83-xxxixNovember1995

NineMilePointUnit2FSARsensorsona.commonprocesstapareruninseparate.conduits.Thesystemsensorsareelectricallyandphysicallyseparated.Onlyonetripchannelactuatorlogiccircuitfromeachtripsystemisruninthe,sameconduit.TheRPSisdesignedtopermitmaintenanceanddiagnosticworkwhilethereactorisoperatingwithoutrestrictingplantoperationorhinderingtheoutputofthatsafetyfunction.Flexibilityindesignaffordedtheprotectionsystemallowsoperationalsystemtestingbytheuseofanindependenttripchannelforeachtriplogicinput.Whenanessentialmonitoredvariableexceedsitsscramtrippoint,itissensedbyatleasttwoindependentsensorsineachtripsystem.Maintenanceoperation,calibrationoperation,ortest,unlessmanuallybypassed,canresultinasinglechanneltripandonetripsystemtrip(halfscram).Thisleavesatleasttwotripchannelspermonitoredvariableoftheothertripsystemcapableofinitiatingascram.Thus,thearrangementoftwotripchannelspertripsystemensuresthatascramoccursasamonitoredvariableexceedsitsscramsetting.Onlyonetripchannelineachtripsystemmusttriptoinitiateascram.Theprotectionsystemmeetsthedesignrequirementsforfunctionalandphysicalindependence,asspecifiedinCriterion22.Forfurtherdiscussion,seethefollowingsections:PrincipalDesignCriteria1.2.1FunctionalDesignofReactivityControlSystem4.6MainSteamLineIsolationSystemResidualHeatRemovalSystemEmergencyCoreCoolingSystemReactorProtection(Trip)SystemEngineeredSafetyFeatureSystems5.4.55.4.76.37.27.3AllOtherInstrumentationSystemsRequiredforSafety7.6AccidentAnalysis153.1.2.23ProtectionSystemFailureModes(Criterion23)Criterion"Theprotectionsystemshallbedesignedtofailintoasafestakeorinto,astatedemonstratedtobeacceptableonsomeother.USARRevision63~123April1994 NineMilePointUnit2FSARdefinedbasisifconditionssuchasdisconnectionofthesystem,lossofenergy(e.g.,electricpower,instrumentair),orpostulatedadverseenvironments(e.g.,extremeheatorcold,fire,pressure,steam,water,andradiation)areexperienced."DesinConformanceTheRPSisdesignedtofailintoasafestate.Useofanindependenttripchannelforeachtriplogicallowsthesystemtosustainanytripchannelfailurewithoutpreventingothersensorsmonitoringthesamevariablefrominitiatingascram.Asinglesensorortripchannelfailurecausesachanneltrip.Onlyonetripchannelineachtripsystemmustbeactuatedtoinitiateascram.Maintenanceoperation,calibrationoperation,ortest,unlessmanuallybypassed,canresultinasinglechanneltripandonetripsystemtrip(halfscram).AfailureofanyoneRPSinput,orsubsystemcomponentproducesatripinoneoftwochannelsandthereforeinonetripsystem.Thisconditionisinsufficienttoproduceareactorscram,butthesystemisreadytoperformitsprotectivefunctionuponanotherchanneltripintheothertripsystem.EnvironmentalconditionsinwhichtheinstrumentationandequipmentoftheRPSmustoperatewereconsideredinestablishingcomponentspecifications.Instrumentationisdesignedtofunctionintheworstexpectedambientconditionsinwhichtheinstrumentsmustoperate.Failuremodesoftheprotectionsystemaresuchthatitwillfailintoasafestate,asrequiredbyCriterion23.Forfurtherdiscussion,seethefollowingsections:PrincipalDesignCriteriaEquipmentQualificationEmergencyCoreCoolingSystemReactorProtection(Trip)SystemEngineeredSafetyFeatureSystems3.1.2.24SeparationofProtectionand(Criterion24)Criterion1.2.13'16.37.27'ControlSystems"Theprotectionsystemshallbeseparatedfromcontrolsystemstotheextentthatfailureofanysinglecontrolsystemcomponentorchannel,orfailureorremovalfromserviceofanysingleprotectionsystemcomponentorchannelwhichiscommontotheUSARRevision83.1-24November1995 NineMilePointUnit2FSARTABLE3.2-1(Cont'd.)Auxiliaryservicebuilding,superstructureDemineralizedwaterstorageandwasteneutralizingtankbuildingShorefrontrevetmentditchPMPexteriorfloodprotectionbermsRoofandstormdrainagesystemsSpentfuelpoolandlinerMiscellaneousRadiationProtectionxmentandProramsScopeofSupplyNANANAPNALocationM00RB,S,T,W,RBElectricalClassifi-cationNANANANANASeismicCategoryNANA(23)NANAQualityGroupClassifi-cationNANANANANAQARequirementNANAIINATornadoProtectionNotes(34)(29)PortableradioactivitymonitoringequipmentRadioactivitysamplingequipmentRadioactivitycontaminationmeasurementandanalysisequipmentPersonnelmonitoringequipmentInstrumentstorage,calibration,andmaintenanceprogramDecontaminationfacilitiesRespiratoryprotectionequipmentContaminationcontrolequipmentZn-plantI,monitoringequipment(NUREG-0737,ItemZZZ.D.3.3)CrackArrestVerificationSstemPiping,OtherValves,OtherPressureVesselControls/Instruments0enFeedwaterZn'ectionSstemPiping,OtherValves,OtherControls/InstrumentsGE,PGE,PGEGE,PGE,PGE,PGE,PMMMMMTB,W,MMMMMMMMMMNon-1ENon-1ENon-1ENon-1ENANANANon-lENon-1ENANANANon-1ENANANon-1ENANANANANANANANANANANANANANANANANANANANADDDNADDNANANANANANANANANANANAP,NRP,NRP(34a)(34a)(34a)(34a)(34a)(34a)(34a)(34a)(34a)USARRevision818of34November1995

NineMilePointUnit2FSARTABLE3.2-2CODEGROUPDESIGNATIONS,INDUSTRYCODES,ANDSTANDARDSFORMECHANICALCOMPONENTS(((ASMESectionIZZCodeApplicableSectionsQualityGroupClassificationASMESectionZZZCodeClass8PressureVesselsandHeatExchangersPumps,ValvesandPzpxngMetalContainmentComponentsStorageTanks0-15(psig)StorageTanksAtmosphericA(nBNAorNCA&NBTEMACNAorNCA&NCTEMACNAorNCA&NB(2ii)NAorNCA&NC((r>INAorNCA&NC"'AorNCA&NC"'MCNAorNCA&NDTEMAR,CASMEVZZZDiv.1TEHAC,RNAorNCA&ND""Piping&valvesB31.1.0pumpsNAorNCA&NENAorNCA&ND"'SMEVIZZorequivalent"'AorNCA&ND'"ASMEVZIZ,NBS-PS15-69API-650orequivalent"'~(ComponentsrequiredtobestampedtoASMEBoilerandPressureVesselCodearestampedwiththeapplicableASHECodesymbolandthird-partyinspectedbyaqualifiedinspector.ComponentsoftheRCPBcomplywiththerequirementsof10CFR50.55acodesandstandards.Allothercomponentssatisfycodesandaddendaineffectatthetimeofthecomponentorder.ForpumpsclassifiedinA,B,orC,theapplicablesubsectionNB,NC,orND,respectively,ofASMESectionZZZisusedasaguideincalculatingthethicknessofpressure-retainingportionsofthepumpandinsizingcoverbolting.100%volumetricexaminationofthesidewallandroofweldjointsforplatesover3/16-inthickand100'%urfaceexaminationofweldjointsforplates3/16-inthickorlessofthesidewall-to-bottomandsidewallroofjoints.TheseexaminationrequirementsareperformedinaccordancewiththerulesofASMESectionIIZ,CodeClass2and3.100%volumetricexaminationofthesidewallweldjointsforplatesover3/16-inthickand100%surfaceexaminationofthesidewall-to-bottomjoints.TheseexaminationrequirementsareperformedinaccordancewiththerulesofASMESectionIIZ,SafetyClass2and3.ForGE-suppliedpumpsclassifiedD,theASMESectionVIII,DivisionIpumpdesignfortheintendedserviceisutilized.ForotherpumpsclassifiedD,themanufacturers'tandardpumpdesignfortheintendedserviceisutilized.StoragetanksaredesignedtomeettheintentofAPI,NBS-PS,and/orASMESectionVIIZstandardsasapplicable.ZnthecasethatmaterialcannotbepurchasedtomeetthespecifiedASMEZZICode,thenmaterialthatmeetssubsequentASMEZIICodeEditions/Addendauptoandincluding1980Edition/Summer1982AddendamaybesubstitutedafterareviewandreconciliationofrelatedrequirementsoftheASMEZZZCodeareperformedanddocumented.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.2-3SUMMARYOFSAFETYCLASSDESIGNREQUIREMENTSDesinReuirementsQualitygroupclassification('Qualityassurancerequirement(')Seismiccategory"'BCIIIIIIDNANASafetClass23Other(4)EquipmentisconstructedinaccordancewiththeindicatedcodegrouplistedinTable3.2-1anddefinedinTable3'2~AsindicatedinTable3.2-1,forQACategoryIcomponents,thequalitygroupclassificationand/orseismiccategoryisnotapplicable(NA)incertaincases,e.g.,reactorinternalstructuresandtheshorefrontrevetmentditch.I=EquipmentmeetstheQArequirementsof10CFR50AppendixB.NA=Conformancewith10CFR50AppendixBisnotrequired.I=EquipmentisconstructedinaccordancewiththerequirementsforCategoryIcomponents(Section3.7).NA=TherequirementtowithstandtheSSEisnotapplicabletothisequipment.USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.2-4REACTORCOOLANTPRESSUREBOUNDARYCLASSIEQUIPMENTCODEAPPLICATIONEuimentReactorpressurevesselMainsteamsstemPipingContainmentisolationvalves~MPLMarkB13-D003B22-F022AB22-F022BB22-F022CB22-F022DB22-F016B22-F019B22-F028AB22-F028BB22-F028CB22-F028D2MSS*MOV208Code*Edition1971197419771977197719771974197419771977197719771974AddendaWinter1972NoAddendaSummer1977Summer1977Summer1977Summer1977Winter1975Winter1975Summer1977Summer1977Summer1977Summer1977Winter1975ManualblockvalveSafety/reliefvalves2MSS*MOV2071974B22-F0131974Winter1975Summer1976USARRevision81of2November1995 NineMilePointUnit2FSARTABLE3.2-4(Cont'd.)RecirculationssteMPLMarkCode<'>EditionAddendaPiping<'>PumpsGatevalvesB35-G001B35-C001B35-F023B35-F067197719711974Summer1977Summer1973Winter1974FlowcontrolvalvesB35-F060A1974B35-F060BSummer1976Hih-ressurecoresrasstemIsolationvalveE22-F004PipingStandbliuidcontrolsstem19711974Winter1973NoAddendaExplosivevalveC41-F0041977Summer1977Codeinvokedinpurchaseorder.ThereferenceconstructionpermitdocketdatewasJune15,1972.Deleted.SeeSection5.4.1.3.USARRevision82of2November1995

NineMilePointUnit2FSARTABLE3.3-1DYNAMICWINDPRESSUREFORCATEGORYISTRUCTURESHeightAboveGradeft0to5050to150150to400400to600BasicWindVelocityCorrespondingtoHeightmh90115145175DynamicWindPressuressf26426695USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.4-1FLOODPROTECTZONFORSAFETY-RELATEDSTRUCTURESANDSYSTEMSSafety-RelatedStructuresSafety-RelatedSystemsNormalDBFLGroundWaterLevelAveragePlantGradeElevationofLowestExteriorAccessOpeningsBelowDBFL~ElevationofPenetrationsThroughExteriorWallsBelowDBFLElevationofElectricalDuctBankPenetrationsThroughExteriorWallsBelowDBFLReactorbuildingincludingauxiliarybaysControlbuildingDieselgeneratorbuildingScreenwellbuildingMainstackStandbygastreatmentbuildingTurbinebuilding(mainsteamtunnelarea)PipingandelectricaltunnelsPrimarycontainment,RHRRCICiLPCSiHPCSADS,servicewaterreactorprotectionandstandbyliquidcontrolControlroomwithPGCC,emergencyswitchgearrooms,batteryroomsStandbydieselgeneratorsandrelatedsupportsys'te1tlsServicewaterpumpsandrelatedpipingStandbygastreatmentsystemStandbygastreatmentsystemMainsteamandfeedwaterisolationvalvesandsafety-relatedinstrumentsServicewatersystemandelectricalsystemsnecessaryforreactorcontrol255255255255255255255255260.6260.6260.6260.6260.6260.6260.6260.6260260260260260260260260NoneNoneNoneNoneNoneNoneNoneNoneSeeTable3.4-2SeeTable3.4-3SeeTable3.4-6SeeTable3.4-4SeeTable3.4-6NoneSeeTable3.4-3SeeTable3.4-5Topofductel253'opofductel234'-2Topofductel257'woductlinesatsameelevationUSARRevision81of2November1995

NineMilePointUnit2PSARTABLE3.4-1(Cont'd.)NOTES:1.Alldimensionsarelakesurveydatum(LSD)elevationsinfeetandinches.ThetunnelshousingCategoryIsystemsandcomponentsareaccessibleonlyfromtheadjoiningbuildings.PipepenetrationsthroughexteriorwallsofCategoryIstructureshavewatertightsealsdesignedtowithstandthefloodloads.WhereelectricalductspenetrateCategory1structures,waterstopsareprovidedtopreventanyadverseeffectfromflooding.TheDBFLof260.6isbasedonthePMPasdeterminedfromNOAAHydrometeorologicalReportNo.33andistheoriginalbasisfortheplantdesign.SeeSections2.4.10and3.4forfurtherdiscussionconcerningDBFL.USARRevision82of2November1995

NineMilePointUnit2FSARTABLE3.4-2PENETRATIONSTHROUGHEXTERIORWALLSOFREACTORBUILDINGBELOWDBFL*SleeveNo.W3888W31670W3227RW3226RW3225RW3455CW4288CW4025CW3224RW4241CW3596CW3177CW4374CW3190CW3820CW3546CW4364CW3943CW3944CW3945CW3946CW3947CW3545CW3102CW3890CW3625CW3082CW3083CW3084CW3045CW3046CW3042CW3821CW3041CW3079CW3108CW3550CW3815CW3544CW4242CW4243CW3598CW34820W3582CElevation210~-8"227'35'-1"225~-11"235'-7235'-3224'-61/2"HWP236-2"2301-3n256'47'-3251I-4251I-4247'48'-3"256'-33/8"254'WP254'54'54I254'54'46'-3"208~-8"HWP210'-8"203I-4208'08~210-4"208'08I206I208-11"HWP206'03'08-99/16"HWP253-111/2"254r6it256I256~-6"2561-6n255I256'-9"249'-11~setemRHRCRD,ElectricalHVRHVRHVRSWPSpareInstrumentHVRCMSFPLSWPSWPRCICFPWFPW6"DrainDFRDFRDFRDFRDFRFPWRHRRHRInstrumentHPCSHPCSRHRSWPSWPSWPDFRSWPSWPRHRDFRFPWFPWCMSCMSFPLSWPSWPUSARRevision81of3November1995 NineMilePointUnit2FSARTABLE3.4-2(Cont'd.)SleeveNo.W3583CW3584CW3585CW3570SW3185CW4240CW3008RW3065CW3066CW4121SW4122SW4123SW4120SW4118SW4119SW4115SW4114SW4112SW4113SW4110SW4111SW3062CW3074SW3075SW3018CW3019CW3615CW4150SW4152SW4153SW4151SW4154SW4155SW4156SW4157SW4158SW4159SW3616CW3622CW4160SW4161SW4162SW3023RW4163SW3040CW3068CW3067CElevation248r5252'-11251-5"248I-81/4246I-6256'94i-3n183I-6177'-17/16"178'1/16179m75/16178r51/16n179-75/16"182'-4"179r75/16178'-51/16"179-75/16"177r17/16182I4182r4n192i-3n193-2"193i-2n189'-9"186'n193'-2"181s49/16178'1/16177'-21/16"179'-79/16"178s71/16n179'-79/16177'1/16179I-79/16"179-79/16"17721/16190'89I178~-71/16"179I-79/16"178'-71/16"194I181I-49/16"182-6"176i-6176r3~setemSWPSWPSWPMWSCNSCMSRHRRBCLCWRBCLCW02Mappargon0,Mappargon0,MappargonElectricalCompressedairConstructionwaterElectricalElectricalElectricalElectricalSpareSpareRCICSWPSWPRHRRHRInstrumentSpare0,MappargonCompressedairConstructionwaterOzMappargon2MappargonSumpdischargeElectricalElectricalElectricalInstrumentSpareElectricalElectricalElectricalAASgIASgSASgRHRSpareSWPRBCLCWRBCLCWUSARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.4-2(Cont'd.)SleeveNo.W3022RW3617CW3787CW3037CW3038CW3568CW3051CW30480W3606CW3605CW3623CW3052CW3565SElevation194i190'85'90I-3"185'-9"184'-10"192r6192I-9187'-9"189'88r186'83I~sstsmRHRInstrumentDFRSWPSWPMWSRBCLCWSWPSpareMWSSpareRBCLCWInstrumentKEY:AASCMSCNSCRDDFRFPLFPWHPCSIASHWPMWSRBCLCWRCICRHRSASSWPBreathingairContainmentatmospheremonitoringCondensatemakeupanddrawoffControlroddrivehydraulicReactorbuildingfloordrainsFireprotection-low-pressureC02Fireprotection-waterHigh-pressurecoresprayInstrumentairReactorbuildingventilationHighworkpointMakeupwaterReactorbuildingclosedloopcoolingwaterReactorcoreisolationcoolingResidualheatremovalServiceairServicewater*ThetableisbasedonaDBFLof260.6ft,theoriginalbasisforplantdesign.SeeSections2.4.10and3.4forfurtherdiscussionconcerningDBFL.USARRevision83of3November1995

NineMilePointUnit2FSARTABLE3.4-3PENETRATIONSTHROUGHEXTERIORWALLSOFCONTROLANDTURBINEBUILDINGSBELOWDBFL'leeveNo.TurbineBuildin+Elevation~SstemW5335CW0504CW0505CW5045CW0508CW0509CW0024CW5275CW0023CW5274CW0507CW0506CControlBuildin253'-9"255ll1/16n252i-9it254'54'-6"256'57I257I257'57'54i254'WS15"RoofdrainFPW4"DrainFPWFPWFWSFWSFWSFWSFPWFPWW6185RW6186R230I7II230'-7"VentductVentductKEY:DWS=DomesticwaterFPW=Fireprotection-waterFWS=FeedwaterThetableisbasedonaDBFLof260.6ft,theoriginalbasisforplantdesign.SeeSections2.4.10and3.4forfurtherdiscussionconcerningDBFL.TheturbinebuildingisCategoryIinthefollowingareasonly:a.ElectricalbayareabetweencolumnlinesAMandAK,uptoel261'.b.Mainsteamtunnelareaandareaunderneathmainsteamtunnelbetweencolumnlines10and12,whenprovidingsupporttomainsteamtunnel.c.Pipetunnelsbetweencolumnlines10and12uptoel248'.USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.4-4PENETRATIONSTHROUGHEXTERIORWALLSOFRADWASTEBUILDINGANDSCREENWELLBUILDINGBELOWDBFL'leeveNo.RadwasteBuildin+Eevation~sstemW8001CW8002CSceenwellBuildin248'-9"250'-9TBCLCWTBCLCWW2250CW2247C253'-73/8"252~-11/4"DFM10"RoofdrainThetableisbasedonaDBFLof260.6ft,theoriginalbasisforplantdesign.SeeSections2.4.10and3.4forfurtherdiscussionconcerningDBFL.TheradwastebuildingisdesignedasaCategoryIstructure.However,CategoryIclassificationisnotusedinconstructionoftheradwastebuilding.KEY:TBCLCW=TurbinebuildingclosedloopcoolingwaterDFM=MiscellaneousfloorandequipmentdrainsUSARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.4-5PENETRATIONSTHROUGHEXTERIORWALLSOFPIPETUNNELSBELOWDBFL*SleeveNo.Elevation~sstemW1251SW1252SW1253SW1254SW1255SW1256SW1257SW1258SW1132RW1134RW1133CW1215CW1020CW1285CW1208CW1077CW1143CW1145CW1147CW1207CW1006CW1141CW1078CW1137CW1139CW1286CW1140CW1144CW1148CW1138CW1142CW1146CW1081CW1259CW1276CW1243CW1244CW1109SW1219SW1220SW1069CW1283CW1070CW1057C256'-13/4"256'-13/4"255'-13/4"256'-13/4"255'-13/4"256'-21/4"255I-13/4it249i-5n251I101/4250I-6256'-21/4"255'-107/8"257'-03/4"247I-4"254'54'46'13/8245'-117/16"244117/16254'52'-73/16"247'-103/4"253'-85/8250'-05/8248'-115/16"251'-01/8248I119/16246'17/16244-111/4"249-1115/16"247111/16245'-113/8"255r31/2251'49'56-6"251-81/4"252'-5"251'-3n248I-9251I-4251'-4"247'54i-6itschargechargeineLWSMWSLWSLWSLWSLWSLWSDrainSpareSpareOFG4"Drain4"DrainCCSDFM4"SumpdiSWPSWPSWPDFMAASSWP4"SumpdisSWPSWPLWSSWPSWPSWPSWPSWPSWPSpareLWSDFTAbandonedAbandoned8"DrainlCCSCCSSWPSWPRCICSWPUSARRevision81of3November1995 NineMilePointUnit2FSARTABLE3.4-5(Cont'd.)SleeveW1058CW1056CW1097CW1099CW1100CW1101CW1102CW1103CW1104CW1105CW1106CW1107CW1108CW1186CW1187CW1188CW1238CW1239CW1240CW1241CW1242CW1189CW1190CW1249CW1152CW1153CW1154CW1155CW1195CW1196CW1216CNo.Elevation254'-6247-7"249~-5"249i-5249'-5"249~-5"249'-5"249r5249I5II249'-5"249'-5249'-5249-5"245'-315/16"245'-315/16"245~-315/16245'-315/16"245-315/16"245r315/16n245r315/16245'1/16245'-315/16"245r61/16n247'52r7249i-10247-93/8"246'-03/8252r7n252r-7252'-4"~Ss~teCWSSWPSpareFPWFPWFPWFPWFPWFPWFPWFPWFPWFPWMSSMSSMSSMSSMSSMSSMSSMSSMSSMSSIASSWPSWPSWPSWPWTSWTSFPWKEY:AASCWSDFTDMFPWIASLWSMSSMWSOFGRCICSWPCCSWTSBreathingairCirculatingwaterTurbinebuildingfloordrainsMiscellaneousfloorandequipmentFireprotection-waterInstrumentairRadioactiveliquidwasteMainsteamMakeupwaterOffgasReactorcoreisolationcoolingServicewaterdrainsTurbinebuildingclosedloopcoolingwaterWatertreatingUSARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.4-5(Cont'd.)*ThetableisbasedonaDBFLof260.6ft,theoriginalbasisforplantdesign.SeeSections2.4.10and3.4forfurtherdiscussionconcerningDBFL.USARRevision83of3November1995 NineMilePointUnit2FSARTABLE3.4-6PENETRATIONSTHROUGHEXTERIORWALLSOFDIESELGENERATORBUILDINGANDMAINSTACKBELOWDBFL*SleeveNo.DieseGeeratorBuildinW1294CW1295CW1328CW1329CMainStackW2275CW2276CElevation258'-3"256'-6n255'-102551-101'56'-6"254I-01/8~setem6"drainage12"drainage6"drainage6"drainageDFMARCKEYARC=CondenserairremovalDFM=Miscellaneousfloorandequipmentdrain*ThetableisbasedonaDBFLof260.6ft,theoriginalbasisforplantdesign.SeeSections2.4.10and3.4forfurtherdiscussionconcerningDBFL.USARRevision81of1November1995 NineMilePointUnit2PSARTABLE3.4-7PERFORMANCEOPWATERSTOPMATERIALINEXPECTEDENVIRONMENTExpectedEnvironmentExpectedPerformanceofMaterial"'"'aterialStyrene-ButadienesyntheticrubberwaterstopsTemperatureRange"'20oFto+325oFChemicalsUnit2sitehasaveragepH-8.0-8.4.Noacidicenvironmentexpectedwithinthewallsbelowgradearea.RadiationLevelBelow1.4x10~radsAging40yratnormaloperatingtemperature(109oF)TemperatureRange-35oPto+176oFChemicalsUnaffectedbyacidicoralkalinesoilsorsoilbacteria.RadiationLevel2x10'adsbeforethresholddamage.lx10'adsbefore25%damage.6.0x107radsbefore50%damageAging40yrat109oPTemperaturerangevariesfrom-26oFminimumoutsideatSite,109oFnormaloperatinginsidesecondarycontainment,to325Fmaximumaccidentinsidesecondarycontainment.Theworst-casedesignconditionsduringwhichthewaterstopmustfunctiondonotexceedtheexpectedperformancetemperatureofthematerial.Safety-relatedwaterstopsareinsulatedandsealedfromambientenvironmentalconditionstoestablish40-yrqualifiedlife.Waterstopsystemsarerequiredtocontainlong-termfloodingfromcracksinlowtemperature((175oF)systemswhichhavealargeinventoryofwater,e.g.,systemsconnectedtothesuppressionpool.Cracksinthesesystemscouldremainundetectedforlongperiodsoftimeassumingfailureofnonredundantleakdetectionsystems.Undertheseconditions,watertightcubicles,whichemployseveralwaterstops,preventthespreadoffloodingtoredundantsafeshutdownequipment.ThisisdiscussedinAppendix3C.5.Waterstopsarenotrequiredtocontainfloodingfromhightemperature(>175op)systems,e.g.,RCIC,RWCU,orRHR(shutdowncooling)systems.LossofwaterfromaHELBormoderate-energylinecrackinthesesystemsisquicklydetectedandisolatedeitherbytherespectivesysteminstrumentationorbyredundantleakdetectionsystem.Undertheseconditions,onlyalimitedquantityofwaterisreleased,andfloodingofredundantsafeshutdownequipmentisnotaconcern.Thus,thewaterstopfunctionisnotrequired.Requiredserviceconditionshavebeenevaluatedinestablishingthe40-yrqualifiedlifeofthewaterstops.Inaddition,thewaterstopsareprotectedwithlayersofinsulationandcaulkingmaterialforaddedassurancethatthesystemremainsfunctionalunderallconditions.Expectedenvironmentalradiationlevelof1.4x10'adsisconsistentwiththemanufacturer'sdesigndata.USARRevision81of1November1995

PDTEDFETYNLYIEPNINEMILEPOINTNUCLEARSTATION-UNIT2TNIAGARAUMOHAWKVOL.9

NineMilePointUnit2FSARTABLEOFCONTENTSSectionCHAPTER1TitleINTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTVolume1~11'1.31'1'1.61.71.81.91'01'11.12113CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2'2'2.32'2.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,"45678CHAPTER33'3.23'3.4DESIGNOFSTRUCTURES,COMPONENTS,EQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3'1Appendixes3ACHAPTER44.14.24.34.44.54.6Appendix4ACHAPTER55.15.25.35.4Appendixes5A,TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5BVolume9,1010101010121212121212121212121212131313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolumeCHAPTER66.16.26.36.46.56.6Appendixes6AENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Componentsthrough6D131415151515CHAPTER7'NSTRUMENTATIONANDCONTROLSYSTEMS157'F27.37.47.57.67.7Appendixes7A,CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.4~9.5Appendixes9A,CHAPTER1010~110.210.3IntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem151515161616161616161616,171717181920,2121,222323232324USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS{Cont'd.)Section10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411~111~211.311.411.5Appendix11ACHAPTER1212'12'12'12.4'12.5CHAPTER1313'13.213.313.4'3.513.6CHAPTER1414.1l14.214.3CHAPTER1515~0SourceTermsLiquidWasteManagement:-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral24242525252525252525262626262626262626262626,27272727USARRevision8ivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215e315e415.515.615.715.8Appendices15ACHAPTER16CHAPTER1717.017e117.2CHAPTER1818.118.2"APPENDIXAAPPENDIXBTitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithout.Scramthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-l),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASEVolume27272727272727272828282828282828282828USARRevisionNovember1995

NineMilePointUnit2FSARConsequently,itisnotconsideredaprobablemissilesource.2.ValvesofANSI900-psigratingandabove,constructedinaccordancewithASMESectionIII,arepressuresealbonnet-typevalves.Forpressuresealbonnetvalves,valvebonnetsarepreventedfrombecomingmissilesbytheretainingring,whichwouldhavetofailbytheyoke,capturingthebonnetorreducingbonnetenergy.Becauseofthehighlyconservativedesignoftheretainingringofthesevalves,bonnetejectionishighlyimprobable.Hence,bonnetsarenotconsideredcrediblemissiles.3.MostvalvesofANSI600-psigratingandbelowarevalveswithboltedbonnets.Valvebonnetsarepreventedfrombecomingmissilesbylimitingthestressesinthebonnet-to-bodyboltingmaterialbytherulessetforthin'ASMESectionIII,andbydesigningtheflangesinaccordancewiththeapplicablecoderequirements.Evenifboltfailureweretooccur,thelikelihoodofallboltsexperiencingasimultaneouscompleteseverancefailureisveryremote.Thewidespreaduseofvalveswithboltedbonnetsandthelowhistoricalincidenceofcompleteseverancefailureofthevalvebonnetsconfirmthatboltedvalvebonnetsneednotbeconsideredascrediblemissiles.4.Valvestemsarenotconsideredpotentialmissilesifatleastonefeatureinadditiontothestem~threadsisincludedintheirdesigntopreventejection.'Valveswithbackseatsarepreventedfrombecomingmissilesbythisfeature.Inaddition,air-ormotor-operatedvalvestemsareeffectivelyrestrainedbythevalveoperators.NocrediblevalvestemmissileswereidentifiedatUnit2.5.PressurizedcompressedgascylindersaremanufacturedtoDepartmentofTransportationstandardsandstampedwitha"DOT-3AA(Pressure)"designation.Thesecylindershavestringentmanufacturingcontrols"whichmeettherequirementsof10CFR50whenusedinmissile-sensitiveareas.ControlssuchasreceiptinspectionandsafehandlingrequirementsinaccordancewithCompressedGasAssociation,Inc.,PamphletsC-6andP-1areimposedbytherequirementsoftheprocurementspecification.Undertheseconditions,thecausesoffailuresarevirtuallyeliminated,andsuchcylindersneednotbeconsideredascrediblemissiles.6.Nuts,bolts,nutandboltcombinations,andnutandstudcombinationshaveonlyasmallamountofstoredenergyandthusareofminimalconcernaspotentialmissiles.USARRevision63.5-7April1994 NineMilePointUnit2FSAR3.5.1.2Internally-GeneratedMissiles(InsideContainment)LocationofStructuresSstemsorComonentsAllsafety-relatedsystemsandcomponentsinsidecontainmentarelistedinTable3.2-1.Theyareprotectedagainstdamagefrominternally-generatedmissilesasdescribedinSections3.5.1.1.4and3.5.1.1.5.3.5.1.3TurbineMissiles3.5.1.3.1TurbinePlacementandOrientationTurbineplacementandorientationforthethreeunitsaffectingtheturbinemissileevaluationforUnit2areshownonFigure3.5-1.TheyaretheturbinesoftheNineMilePointNuclearStation-Unit1(Unitl),Unit2,andJamesA.FitzPatrickPowerStation.ThespinaxesoftheUnit1andUnit2turbinegeneratorsareorientedinaneast-westdirection.TheJamesA.FitzPatrickPowerStationturbinegeneratorhasitsspinaxisorientedwitha15-degclockwiserotationfromanorth-southdirection.Figure3.5-1alsoindicatesthe+25-degmissileejectionzoneforlow-trajectoryturbinemissilesresultingfromlow-pressureturbinediscs@.AplanviewofplantregionslocatedatUnit2isshownonFigure3.5-1alongwiththeturbinegeneratorsofUnit1,Unit2andtheJamesA.FitzPatrickplant.Notethatapplicablelow-trajectorytargetsarethosewithinthe+25-degmissileejectionzones.Forhigh-trajectorymissiles,targetareasareallaboveground,CategoryIstructures.Tables3.5-3through3.5-16providetheprobabilitiesofturbinemissilestrikesinvariousevents.Duetoverylowprobabilityofturbinemissilestrikes,asdemonstratedbytheabove-referenceddata,itisnotnecessarytodesignthesafety-relatedstructuresforturbinemissiles.3.5.1.3.2MissileIdentification,Characteristics,andTargetDescriptionMissileIdentificationandCharacteristicsTheturbinegeneratorslocatedatUnit1,Unit2andJamesA.FitzPatrickPowerStationaremanufacturedbyGeneralElectricCompany(GE).TheturbinetypeforUnit1andUnit2isa38-inlast-stagebucket,whiletheturbinetypefortheJamesA.FitzPatrickplantisa43-inlast-stagebucket.AtUnit2,theoriginalbuilt-uptyperotordesignhasbeenreplacedwithamonoblocktyperotordesignwhicheliminatestheprobabilityofmissilegenerationfromUnit2.USARRevision83.5-8November1995 NineMilePointUnit2FSARForturbinemissileevaluationatUnit1andtheJamesA.FitzPatrickplant,ahypotheticalmissileisconsideredgeneratedinthediscplane.Asitpenetratesthestationaryturbineparts,themissileisdeflectedfromtheverticalplane.Ithasbeendeterminedthatthedeflectionangleisamaximumof5degoneachsideoftheplaneofthediscforinner-stagebuckets.Forlast-stagebuckets,thedeflectionanglesmaybeupto25degoneachsideoftheplaneofthedisc.ThemissilecharacteristicsusedforthisturbinemissilestrikeprobabilityevaluationareprovidedinTables3.5-17and3.5-18"".TaretDescritionSystems,equipment,andcomponentsrequiredforsafeshutdownandtomaintaincoldshutdownofthereactor,ortopreventthereleaseofradiationtowithinallowablelimits,arehousedinthefollowingstructures:1.Reactorbuilding.2.Controlbuilding.3.Dieselgeneratorbuilding.4.Screenwellbuildingservicewaterpumproom.5.Standbygastreatmentbuildingandrailroadaccesslock.6.Radwastebuilding.7.Auxiliaryservicebuildingandnorthandsouthauxiliarybays.8.Intakestructure,pipe,andshaft.9.Mainsteamtunnel.Thesetargetsareconsideredtobethesafety-relatedregionsforturbinemissileevaluation.3.5.1.3.3ProbabilityAnalysisForUnit2,theprobabilityofgenerationandejection(Pl)valuefromaUnit2postulatedmissileisinsignificant(-0),duetothereplacementoforiginalbuilt-uptyperotorwithmonoblocktyperotor.Therefore,theoverallprobability(P4)foraUnit2postulatedmissileisinsignificant(-0).TheevaluationofapostulatedturbinemissilefromUnit1andtheJamesA.FitzPatrickplantisbasedontheprobabilityofmissilegenerationandontheeffectsattributedtoit.Theoverallprobabilityofunacceptabledamagetothecriticalplantregions,P4,istheproductofthreecontributingfactors:USARRevision83.5-9November1995 NineMilePointUnit2FSARWhere:P)Pg=P4=P,xP,xP,Theprobabilityofgenerationandejectionofahigh-energymissileTheprobabilitythatthemissilewillstrikeasafety-relatedregionUSARRevision83.5-9aNovember1995 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKUSARRevision83.5-9bNovember1995 NineMilePointUnit2FSARP~=Theprobabilitythatthemissilestrikewill.damageitstargetinamannerleadingtounacceptableconsequencesP,=TheoverallprobabilityProbabilitofGenerationandE'ectionPAturbinemissilecanbecausedbybrittlefractureofarotatingturbinepartatornearturbineoperatingspeedorbyductilefractureuponrunawayafterextensive,highly-improbablecontrolsystemfailures"'.TheoperatingexperienceofGEturbinesclearlydemonstratesthatthestructuralintegrityrecordofdiscsandrotorhasbeenexcellent.Thisexcellentoperationalrecordcanbeattributedto:1.Carefulcontrolofalloychemistryandforgingheat-treatingcycles.2.Improvedsteelmillpracticesinvacuumpouringandalloyadditionresultinginmoreuniformanddefect-freeforgings.3.Improvedultrasonicandmagneticparticletestingtechniquesthatensuresounddiscs,whichequalorexceedthespecifieddesignstandard.4.Redundancyinthecontrolsystems.Asaminimum,theGEturbineisequippedwithtwoseparateandredundantoverspeedprotectionsystems.Thesefactorsminimizetheprobabilityofmissilegenerat.'ion.Forapostulatedturbinefailure,twospeedfailureswereconsidered:thedesignoverspeedfailure(120percentratedspeed)andthedestructiveoverspeedfailure(180percentratedspeed).TheGEestimatefortheturbinefailurerateis8.67x10~/yr/turbinefordesignoverspeed(120percentratedspeed)for43-inlast-stagebuckets,whereasturbinefailurerateisstatisticallyinsignificantfor38-inlast-stagebuckets"'ordesignoverspeed(120percentratedspeed).Fordestructiveoverspeed(180percentratedspeed),failureratehasbeenestimatedtobe5.0x10'/yr/turbineforboth43-inlast-stagebucketsand38-inlast-stagebuckets"'.Bushhasobtainedafailurerateof3.3x10~to3.1x104/turbineyrforaturbinepopulationcorrectedtoberelevanttonuclearreactors.RG1.115,whichisbasedonBush'sresults,recommendsafailurerateof1.0x104fordesignoverspeedandfordestructiveoverspeedturbinefailures.However,StandardReviewPlan(SRP)3.5.1.3allowsanannualturbinefailurerateof10'subdividedas6x10/turbineyrfordesignspeedfailuresand4x10/turbineyrfordestructiveoverspeedfailures).Hence,inadditiontousingtheturbinemanufacturer'sestimatedfailureUSARRevision63.5-10April1994 NineMilePointUnit2FSARV-(V-V)V2(3.5-16)Where:V=ResidualmissilevelocityafterperforationV~=IncidentmissilevelocityVpIncidentmissi1eve1ocityrequiredtojustperforatethebarrier,calculatedbyconservativeuseofpenetrationdataTheprobabilityofpenetratingaconcretestructure,P~,canbecalculatedbasedonthisresidualvelocity,takingintoaccounttheperforationofmissilebarriers.ProbabilitCalculationandAccetanceCriteriaInRG1.115,theNRCconsidersthevalueof107/yranacceptableriskrateforthelossofanessentialsystemfromasingleeventduetolow-trajectoryturbinemissiles.Also,SRP2.2.3indicatesthatan"expectedrateofoccurrenceofpotentialexposuresinexcessofthe10CFR100guidelinesofapproximately'0'/yrisacceptableif,whencombinedwithreasonablequalitativearguments,therealisticprobabilitycanbeshowntobelower."TheprobabilitycalculationwasbasedonestimatesoftheindividualbuildingsconsideringbothlowandhightrajectoriesandbothdesignanddestructiveoverspeedfailuresfromtheturbinegeneratorsofUnit1,Unit2andtheJamesA.FitzPatrickplant.Thesewerethencombinedtodeterminetheoverallprobabilityofdamage(P4)forUnit2.Theoverallprobabilityofdamage(P4)hasbeenestimatedusingtheturbinefailureprobabilities(P~)suggestedbyboththeturbinemanufacturer(GE)andtheNRC.Theturbinemanufacturer'smissiledata(missileejectionvelocity,missileweight,characteristicdimensions,etc.)havebeenusedtocalculatethestrikeprobability(P~)onthecriticalplantregionsfor.bothlow-andhigh-trajectoryturbinemissiles.Thesedatahavealsobeenusedtoevaluatethepenetrationprobability(P~)definedinSection3.5.1.3.3.Tables3.5-3through3.5-8showthecalculatedprobabilitiesofdamageontheUnit2safety-relatedregionsduetolow-trajectoryturbinemissilesfordesignoverspeedanddestructiveoverspeedturbinefailures.Tables3.5-3through3.5-5showthecalculatedresultsusingtheturbinemanufacturer'sfailurerates,whileTables3.5-6through3.5-8showthecalculatedresultsusingtheturbinefailureratessuggestedbytheNRC.ItshouldbenotedthattheinformationinTables3.5-3through3.5-8wasdeterminedbyconsideringtheentirefrontsurfaceareasandroofareasofallbuildings,containingtheessentialsystems,asshownonUSARRevision63.5-15April1994 NineMilePointUnit2FSARFigure3.5-1.Thisisconservativesinceitismuchgreaterthantheactualprojectedareasoftheessentialsystems.Similarly,Tables3.5-9through3.5-14presentthecalculatedprobabilitiesofdamagetotheUnit2safety-relatedregionsduetohigh-trajectoryturbinemissilesfordesignoverspeedanddestructiveoverspeedturbinefailures,respectively.Theentirefrontsurfaceareasandroofareasofthebuildingscontainingessentialsystemswereusedtodeterminethestrikeprobabilitiesratherthantheareasoftheessentialsystems.TheseprobabilitieswereobtainedfromthesumoftheprobabilitiesduetovariousmissileejectionvelocitiesandduetoallfragmentsforturbinegeneratorsofUnit1,Unit2andtheJamesA.FitzPatrickplant.TheprobabilityofdamageforallUnit2buildingsduetoturbinemissilesgeneratedfromUnit1,Unit2andtheJamesA.FitzPatrickplantforthetwofailuremodesispresentedinTables3.5-15and3.5-16.Itcanbeobservedthattheoverall)probabilityofdamagebyturbinemissilesis0.962x10~/yrforUnit2iftheprobabilityofturbinefailurerateof1.0x104/yrrecommendedbytheNRCisusedforUnit1andtheJamesA.FitzPatrickplant.Theseresultsarewithintheacceptancevalueof10~/yrasoutlinedinSRP2.2.3,andtheacceptancevalueof107/yrasspecifiedinRG1.115.Thesecalculatedfiguresareconservative.TheoverallprobabilityfordamagebyturbinemissilesforUnit2,whenestimatedonamorerealisticbasiswithmanufacturer'sprobability,ismuchlower.3.5.1.3.4TurbineOverspeedProtectionTheturbineisequippedwitharedundant,testableoverspeedtripsystemtominimizethepossibilityofaturbineoverspeedevent.ThesystemanditstestprogramaredescribedinSection10.2.2.2.3.5.1.3.5TurbineValveTestingTurbinevalvetestingandtestfrequencyaredescribedinSection10'.3.5.1.3.6TurbineCharacteristicsTurbinecharacteristics,design,andoperationaredescribedinSection10.2.USARRevision83.5-16November1995 NineMilePointUnit2FSARTABLE3.5-3DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2Manufacturer'sProbabilityDesignOverspeedFailureDestructiveOverspeedFailureSafety-RelatedRegionspiexp>ppQbxpspap1plppQbxpiReactorbuildingControlbuildingDieselgeneratorbuildingScreenwellbuildingservicewaterpumproomStandbygastreatmentandRRaccesslockRadwasteareaAuxiliaryservicebuildingandnorthandsouthauxiliarybaysIntakeanddischargeshaftareaMainsteamtunnelStatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyZnsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyZnsignificant(Reference4)StatisticallyZnsignificant(Reference4)StatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyZnsignificantStatisticallyZnsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.5-6DAMAGEPROBABILITYDUETOLOW-TRAJECTORYTURBINEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2NRCProbabilityDesignOverspeedFailureDestructiveOverspeedFailureSafety-RelatedRegionsP2P2xP2P2xp2xp2P2P2xp2Pxxp2xp2ReactorbuildingControlbuildingDieselgeneratorbuildingScreenwellbuilding-serviceStandbygastreatmentandRRaccesslockRadwastebuildingAuxiliaryservicebuildingandnorthandsouthauxiliarybaysIntakeanddischargeshaftareaMainsteamtunnelStatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyZnsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificantStatisticallyZnsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.5-9DAMAGEPROBABZLZTYDUETOHIGH-TRAJECTORYTURBZNEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2Manufacturer'sProbabilityDesignOverspeedFailureDestructiveOverspeedFailureSafety-RelatedRegionsP2P2xplP2xp2xp2P2P2xp2P2xp2xp2ReactorbuildingControlbuildingDieselgeneratorbuildingScreenwellbuilding-servicewaterpumproomStandbygastreatmentandRRaccesslockRadwasteareaAuxiliaryservicebuildingandnorthandsouthauxiliarybaysIntakeanddischargeshaftareaMainsteamtunnelStatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.5-12DAMAGEPROBABILITYDUETOHIGH-TRAJECTORYTURBINEMISSILESFROMUNIT2STRIKINGPLANTREGIONSATUNIT2NRCProbabilityDesignOverspeedFailureDestructiveOverspeedFailureSafety-RelatedRegionsPip~xpsppQbxpsPxp>xpsPixPHQbReactorbuildingControlbuildingDieselgeneratorbuildingScreenwel1buildingStandbygastreatmentandRRaccesslockRadwastebuildingAuxiliaryservicebuildingandnorthandsouthauxiliarybaysIntakeanddischargeshaftareaMainsteamtunnelStatisticallyInsignificant(Reference4)StatisticallyZnsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyZnsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyZnsignificantStatisticallyInsignificantStatisticallyZnsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantStatisticallyInsignificantUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.5-15SUMOFDAMAGEPROBABILITYDUETOLOW-ANDHIGH-TRAJECTORYTURBINEMZSSZLESGENERATEDFROMTURBINESATUNITS1AND2ANDJAMESA.FITZPATRICKTOPLANTREGIONSOFUNIT2Manufacturer'ProbabilityDesignOverspeedFailureDestructiveOverspeedFailureTrajectoryandTurbineLowtrajectoryfromUnit2pip~xpipixpgxpgStatisticallyZnsignificant(Reference4)pip~ipixp~iStatisticallyInsignificantLowtrajectoryfromUnit1LowtrajectoryfromFitzPatrickHightrajectoryfromUnit2StatisticallyInsignificant(Reference4)1.37x1045.373x1047.361x10RStatisticallyInsignificant(Reference4)1.37x10i1.37x10i4930x10-s6.754x10StatisticallyInsignificantHightrajectoryfromUnit1HightrajectoryfromFitzPatrickTotalStatisticallyInsignificant(Reference4)1.37x10~2.299x10'.150x10'.37x10'.672x10'.051x10"1.37x10i1.37x10~1.37x10i3.862x10-s1.064x10i1.943x105.291x10n1.459x10"2.66x10nThetotalp,p,fordesignanddestructiveoverspeedfailureis0.962x10'.Thetotalp,p~p,fordesignanddestructiveoverspeedfailureis1.078x10".NOTE:Manufacturer'sprobabilityforUnit1andFitzpatrick:p,=1.37x10'SARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.5-16SUMOFDAMAGEPROBABZLITYDUETOLOW-ANDHIGH-TRAJECTORYTURBINEMZSSZLESGENERATEDFROMTURBINESATUNITS1AND2ANDJAMESA.FITZPATRICKTOPLANTREGIONSOFUNIT2NRCProbabilityDesignOverspeedFailureDestructiveOverspeedFailureTrajectoryandTurbinePsPsxpsPsxpsxpsPsPsxPsPsxpsxpsLowtrajectoryfromUnit2LowtrajectoryfromUnit1StatisticallyInsignificant(Reference4)StatisticallyInsignificant(Reference4)StatisticallyZnsignificantLowtrajectoryfromFitzPatrick1x105.373x105.373x101xlOs4.930x104.930x10HightrajectoryfromUnit2StatisticallyInsignificant(Reference4)StatisticallyInsignificantHightrajectoryfromUnit1HightrajectoryfromFitzPatrickTotalStatisticallyInsignificant(Reference4)1x10'.299x10'.299x10s7.672x10s7.672x10s1x10'xlOs3.862x10s1.064x101.943x103.862x10s1.064x10s1.943x10sThetotalp,p,fordesignanddestructiveoverspeedfailureis0.962x10'.Thetotalpspspsfordesignanddestructiveoverspeedfailureis0.962x10'.NOTE:NRCprobabs.lxty(requiredforUnit1andFitzPatrickonly):p,=1x10'.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.5-17TURBZNEMZSSZLEZNFORMATZON43-ZnchLastStageBucketUnitStageGroupz(11zzz('>Stagenumbersingroup:NumberofrepresentativestageMissileDimensionsFragmentgroupNumberoffragmentsingroupSectorangle,degFragmentweight,lbRadius,in*R,BoreR>HubR,VanerootThickness,in*T(HubT,Web1-321202,0002027481601,0002027483300NA10100NA21204,0001827471251602,000182747125600NA10150NA7(Last)21208,20017284527121604,1001728452712C1,400NA10200Approximaterectangulardimensions,in*19x19x3llxllx320x20x510xlOx520x20x148x8x12*SeeFigure3.5-6.USARRevision8lof3November1995

NineMilePointUnit2FSARTABLE3.5-17(Cont'd.)HYPOTHETICALTURBINEMISSILEINFORMATION43-ZnLastStageBucket,1,800rpmLow-PressureTurbinePostulatedspeed:2,160rpm(120%)Lifctimeprobability:2.6x10'onditionalprobabilityofoccurrenceinstagegroupProbabilityofoccurrenceinstagegroupStageGroupINotstatisticallysignificantStageGroupIZNotstatisticallysignificant2.6x10~StageGroupZZZ"'ragmentgroupMinimumMaximumMidpointNotstatisticallysignificantNotstatisticallysignificantEnercCrr102216~celoctt2800420183509EnercCr0530380~voltetFragmentgroupMinimumMaximumMidpointNotstatisticallysignificantNotstatisticallysignificantEnercCr084~cetot0061024301Engr~veloctt0800560USARRevision82of3November1995

NineMilePointUnit2FSARTABLE3.5-17(Cont'd.)43-ZnchLastStageBucketHihSeedBurstPostulatedspeed:3,240rpm(180%)Lifetimeprobability:1.5x10'onditionalprobabilityofoccurrenceinstagegroupProbabilityofoccurrenceinstagegroup3/76.4x10'tageGroupZ"'/76.4x10'tageGroupZZ"'/72.1x10~StageGroupZZZ"'ragmentgroup"'inimumMaximumMidpointEnercCr084b~relearnSner<((~voicet00051087203604510Engr0178.5b~veloart~rneg~velocrt000520167203708510abEne~r~velocrtEne~r~velact2645000536503877039.556019550Fragmentgroup"'inimumMaximumMidpointEngr052.5d~colontEat~a~colont0001,04021,1307301800EnercCrr084d~celocltEere((~colont00093029306601660Ener((r,0168d~rerantEat~a~velocrt00086039806101.5690(OI(n(()(S(NOTES:SOURCE:Foranteriordrsc,(((and5,are5deg,respectively.Fozenddisc,5,and5,are25degand0degor0degand25deg,respectively.Thedeflectionangles5,and5,are5degforinnerstagebuckets.Forlaststagebuckets,thedeflectionanglesare25degand0degor0degand25deg,respectively.Missilesinfoursizeclasses,a,b,c,andd,arepostulatedtooccurperburst.Energyofejectedmissilesisgiveninmillionftlb;velocityinfps.Energiesarepostulatedtobeuniformlydistributedoverstatedranges.GeneralElectricMemoReport.HypotheticalTurbineMissileData,43-inchLastStageBucketUnits.Stone&WebsterEngineeringCorporation,DocumentNo.CD7912100015,March15,1973.USARRevision83of3November1995

NineMilePointUnit2FSARTABLE3.5-18TURBINEMISSILEINFORMATION38-InchLastStageBucketUnitsStageGroupStagenumbersingroup:NumberofrepresentativestageMissileDimensionsFragmentgroupNumberoffragmentsingroupSectorangle,degFragmentweight,lbRadius,in*R,BoreRzHubR,VanerootThickness,in*TgHubT,Web1-31202,000182445103601,000182445103300101001203,000172545125b601,500172545125500101507(Last)1206,5001625452110603,20016254521101,00010200Approximaterectangulardimensions,in*NA19xl9x3llx11x3NA17xl9x510xlOx5NANA19x19x108x8x10SeeFigure3.5-6.USARRevision81of3November1995

NineMilePointUnit2FSARTABLE3.5-18(Cont'.)HYPOTHETICALTURBINEMISSILEINFORMATION38-InchLastStageBuckets,1,800rpmLowPressureTurbineLowSeedBurstPostulatedspeed:2,160rpm(120%)Lifetimeprobability:notstatisticallysignificantStageGroupIStageGroupZZStageGroupZZZ'"ConditionalprobabilityofoccurrenceinstagegroupProbabilityofoccurrenceinstagegroupFragmentgroupMinimumMaximumMidpointFragmentgroupMinimumMaximumMidpointNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantNotstatisticallysignificantUSARRevision82of3November1995

NineMilePointUnit2FSARTABLE3.5-18(Cont'd.)38-InchLastStageBuckets,1,800rpmLowPressureTurbineHihSeedBurstPostulatedspeed:3,240rpm(180%)Lifetimeprobability:1.5x10'onditionalprobabilityofoccurrenceinstagegroup3/7StageGroupI"'/7StageGroupZZ"'/7StageGroupZIZ"'robabilityofoccurrenceinstagegroup6.4x10~6.4x10'.1x10'ragmentgroup"'inimumMaximumMidpointEngr073.5b~velocttEerrrr~veloctt00047066203403440abEngr~veloct.Ene~r~veloat164000038610307802752015.550abEne~r~velocttEe~r~velocr.000145501375073906.5530Fragmentgroup'~'inimumMaximumMidpointEnercCr042d~velocetEne~r~velocet00093021,1306601800cd~Rerg~celacttEe~r~veloctt00006880293036201660cdEe~r~velocr.~caerg~veloct00001391039806.56501.5690InolI~)(SINOTES:Foranteriordxsc,5,and5,are5deg.respectively.Forenddisc,5,.and5,are25degand0degor0degand25deg,respectively.Thedeflectionangles5,and5,are5degforinnerstagebuckets.Forlaststagebuckets,thedeflectionanglesare25degand0degor0degand25deg,respectively.Missilesinfoursizeclassesarepostulatedtooccurperburst.Energyofejectedmissilesisgiveninmillionftlb;velocityinfps.Energiesarepostulatedtobeuniformlydistributedoverstatedranges.SOURCE:GeneralElectricMemoReport.HypotheticalTurbineMissileData,38-inchLastStageBucketUnits.StoneaWebsterEngineeringCorporation,March16,1973.USARRevision83of3November1995 f'bP NineMilePointUnit2FSARTABLE3.6A-72ESSENTIALSYSTEMS/COMPONENTS/EQUIPMENTEVALUATEDFORPIPEFAILURESPART1InsideContainment(QACategoryIPortionsOnlyUnlessOtherwiseNoted)1.Reactorcoolantpressureboundary(uptoandincludingthecontainmentisolationvalves)2.Containmentisolationsystemandcontainmentboundary(includinglinerplate)3.Reactorprotectionsystem(instrumentsassociatedwithSCRAMsignals)4.Emergencycorecoolingsystems(forLOCAonly)a.HPCS(CSH)b.LPCS(CSL)c.LPCI(RHS)d.ADS,includingSVVvalvesanddischargelines(SVV)5.Corecoolingsystems(otherthan'CCS)a.RCIC(ICS)b.RHRshutdowncoolingmode(RHS)6.Controlroddrivesystem7.Containmentheatremovalsystemsa.RHRsuppressionpoolcoolingmode(RHS)b.RHRcontainmentspraymode(RHS)8.Neutronmonitoringsystem(NMS)9.Reactorrecirculationsystemincludinghydrauliclinestohydraulicactuators(includes.Class4portions)(RCS)10.Hydrogenrecombinersystem(HCS)11.Containmentatmospheremonitoringsystem(CMS)USARRevision81of4November1995 NineMilePointUnit2FSARTABLE3.6A-72-(Cont'd.)12.Reactorvesselinstrumentation(ISC)13.Thefollowingequipment/systems,orportionsthereof,arerequiredtoensuretheproperoperationofthoseessentialitemslistedinItems1through12:a~b.Class1EelectricalsystemReactorplantcomponentcoolingwater(CCP)(excludingClass4portions)cInstrumentairtoADS(IAS)d0Safety-relatedinstrumentationandinstrumentationpipingUSARRevision82of4November1995 NineMilePointUnit2FSARTABLE3.6A-72(Cont'd.)PART2OutsideContainment(QACategoryIPortionsOnlyUnlessOtherwiseNoted)1.Containmentisolationsystemandcontainmentboundaryuptoandincludingtheoutermostcontainmentisolationvalves2.Reactorprotectionsystem(instrumentsassociatedwithSCRAMsignals)3.Coreandcontainmentcoolingsystemsa.HPCS(CSH)b.RCIC(ICS)c.LPCS(CSL)d.LPCI(RHS)e.RHRshutdowncoolingmode(RHS)f.RHRcontainmentspraymode(RHS)g.RHRsuppressionpoolcoolingmode(RHS)4.Containmentatmospheremonitoringsystem(CMS)5.Controlroddrivesystem(includingClass4portions)(RDS)6.Spentfuelpoolcoolingsystem(SFC)7.Reactorwatercleanup(ASMEClasses1,2,and3only)(WCS)8.Reactorvesselinstrumentationsystem(ISC)9.Thefollowingequipment/systems,orportionsthereof,arerequiredtoensuretheproperoperationofthoseessentialitemslistedinItems1through8:a~Class1Eelectricalsystems,acanddc(includingdieselgeneratorsystem,emergencybuses,motorcontrolcenters,switchgear,batteries,auxiliaryshutdowncontrolpanel,anddistributionsystems)USARRevision83of4November1995 NineMilePointUnit2FSARTABLE3.6A-72(Cont'd.)b.Servicewatersystem(SWP)includingreactorplantcomponentcoolingwater(CCP)(excludingClass4portions)c.Safety-relatedenvironmentalsystems(HVK,HVN,HVR,HVP,HVY,HVC)d.Safety-relatedinstrumentationandinstrumentpiping/tubing,includingleakdetectioninstrumentatione.Instrumentair(IAS)andneutronmonitoring(GSN)supplytoADS10.Reactorrecirculationsystemhydrauliclinestohydraulicactuators(includesClass4portion)(RCS)USARRevision84of4November1995 NineMilePointUnit2FSARTABLE3.6A-73HIGH-ENERGYPIPINGPARTIInsideContainmentPiinSsteMainsteamsystem(MSS)MainsteamdrainsReactorcoreisolationcooling(RCIC)system-steamReactorcoreisolationcooling(RCIC)system-headsprayFeedwatersystem(FWS)Recirculationsystem(RCS)High-pressurecorespraysystem(HPCS)(reactorpressurevessel(RPV)tofirstcheckvalve)Low-pressurecorespraysystem(LPCS)(reactorpressurevessel(RPV)tofirstcheckvalve)Reactorwatercleanup(RWCU)systemMainsteamventlinesResidualheatremoval(RHR)system(shutdownsuction)Residualheatremoval(RHR)system-low-pressurecoreinjection(LPCI)Controlroddrive(CRD)systemStandbyliquidcontrolsystem(SLCS)Mainsteamsafetyreliefvalve(SRV)piping(betweenthemainsteamlineandthesafetyreliefvalve)USARRevision81of2November1995 NineMilePointUnit2FSARTABLE3.6A-73(Cont'd.)PARTIIOutsideContainmentMainsteamsystem(MSS)MainsteamdrainsFeedwatersystem(FWS)PiinSstemReactorcoreisolationcooling(RCIC)system(steamtoRCICturbine)Controlroddrive(CRD)systemReactorwatercleanup(RWCU)system(includingresidualheatremoval(RHR)feedtofeedwater)USARRevision82of2November1995 UPDTEDLYIFETYEPNINEMILEPOINTNUCLEARSTATION-UNIT2TNIAGARA4MOHAWKVOL.10 A*$

NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleUolumeCHAPTER.11~1121.31.41'1.61.7181.91.101.111.12113CHAPTER2INTRODUCTIONANDGENERALDESCRIPTXONOFTHEPLANTIntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsand"OtherZetailedXnformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit.2,ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingXssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2.12~22.32'2.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3333,4456.78CHAPTER33'3~2333.4DESXGNOFSTRUCTURES~COMPONENTS/EQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3.11Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER5TitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationof.SeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSVolume9,10101010101212121212121212121212135.15.25.35.4Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevisionNovember1995 NineMilePointUnit.2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136.16.26.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77.17.27.37.47.57.67.7Appendixes7A,CHAPTER88.18.28.3Appendix8ACHAPTER9INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystems'equiredforSafetyControl.SystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS1515151516161616.1616161616,1717179.19.29.39.49.5AppendixesCHAPTER1010.110.210.39A,FuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem17181920,2121,222323232324USARRevision8November1995 NineMi'lePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section10'CHAPTER1111111-211311'11.5Appendix11ACHAPTER1212'12'12312.4125CHAPTER1313'13213.313.413.513.6CHAPTER1414~1I14~214.3CHAPTER1515'TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTSourceTermsLiquid'WasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationat,PowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneralVolume24242425252525252525252626262626262626262626,27272727USARRevisionivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15F115215'15'15.515.615.715'Appendices15ACHAPTER16TitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistribution.AnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HIrTECHNXCALSPECIFICATIONSVolume27272727272727272828CHAPTER1717-017~117~2CHAPTER'818.118.2APPENDXXAAPPENDIXBQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameter.DisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATXONSPHASE28282828282828USARRevision8November1995

NineMilePointUnit2FSAR3.6BPROTECTIONAGAINSTDYNAMICEFFECTSASSOCIATEDWITHPOSTULATEDRUPTUREOFPIPING(GESCOPEOFSUPPLY)SeeSection3.6AforanexplanationofGE/SWECscopeofsupply.Thefollowinghigh-energysystemsareinthescopeofSection3.6B.3.6B.1PostulatedPipingFailuresinFluidSystemsOutsideContainmentSeeSection3.6A.1.3.6B.2DeterminationofBreakLocationsandDynamicEffectsAssociatedwiththePostulatedRuptureofPipingInformationconcerningbreakandcracklocationcriteriaandmethodsofanalysisispresentedinthis.section.Thelocationcriteriaandmethodsofanalysisareneededtoevaluatethedynamiceffectsassociatedwithpostulated'breaksandcracksinhigh-andmoderate-energyfluidsystempipinginsideandoutsidetheprimarycontainment.Thisinformationconfirmsthattherequirementsfortheprotectionofstructures,systems,andcomponentsrelieduponforsafereactorshutdownortomitigatetheconsequencesofapostulatedpipebreakhavebeenmet.3.6B.2.1CriteriaUsedtoDefineBreakandCrackLocationandConfigurationThefollowingsectionestablishesthecriteriaforthelocationandconfigurationofpostulatedbreaksandcracks.3.6B.2.1.1CriteriaforRecirculationPipingSystemInsideContainment3.6B.2.1.1.1DefinitionofHigh-EnergyFluidSystemHigh-energyfluidsystemsaredefinedasthosesystems,orportionsofsystems,thatduringnormalplantconditions*areeitherinoperationoraremaintainedpressurizedunderconditionswhereeitherorbothofthefollowingare.met:Maximumoperatingtemperatureexceeds200'F.Maximumoperatingpressureexceeds275psig.3.6B.2.1.1.2DefinitionofModerate-EnergyFluidSystemModerate-energyfluidsystemsaredefinedasthosesystems,orportionsofsystems,thatduringnormalplantconditionsare*Normalplantconditionsaredefinedastheplantoperatingconditionsduringreactorstartup,power,operationhotstandby,orreactorcoldshutdown.USARRevision83.6B-1November1995 NineMile,PointUnit2FSAReitherinoperationoraremaintainedpressurizedunderconditionswherebothofthefollowingaremet:Maximumoperatingtemperatureis200'Forless,andMaximumoperatingpressureis275psigorless.Pipingsystemsareclassifiedasmoderate-energysystemswhentheyoperateashigh-energypipingforonlyshortoperationalperiodsinperformingtheirsystemfunction,butforthemajoroperationalperiodqualifyasmoderate-energyfluidsystems.Anoperationalperiodisconsidered"short"ifthetotalfractionoftimethatthesystemoperateswithintheP-Tconditionsspecifiedforhigh-energyfluidsystemsislessthan2percentoftotaloperatingtimethesystemisdesignedfor.3.6B.2.1.1.3PostulatedPipeBreaksandCracksApostulatedpipebreakisdefinedasasudden,grossfailureofthepressureboundaryeitherintheformofacompletecircumferentialseverance(guillotinebreak)orasdevelopmentofasuddenlongitudinalcrack(longitudinalsplit),andispostulatedforhigh-energyfluidsystemsonly.Formoderate-energyfluidsystems,pipebreaksareconfinedtopostulationofleakagecracksinpipingandbranchruns.Thesecracksaffectthesurroundingenvironmentalconditionsonlyanddonotresultinwhippingofthecrackedpipe.Thefollowinghigh-energypipingsystems(orportionsofsystems)areconsideredtohavepotentialforinitiationofapostulatedpipebreakduringnormalplantconditions,andareanalyzedforpotentialdamageduetodynamiceffects:1.AllpipingthatispartoftheRCPBandsubjecttoreactorpressurecontinuouslyduringplantoperation.2.Allpipingthatisbeyondthesecondisolationvalvebutissubjecttoreactorpressurecontinuouslyduringplantoperation.3.Inadditiontopipingunder1and2,allotherpipingsystemsorportionsofpipingsystemsconsideredhigh-energysystems.Portionsofpipingsystemsthatareisolatedfromthesourceofthehigh-energyfluidduringnormalplantconditionsareexemptedfromconsiderationofpostulatedpipebreaks.Thiswouldincludeportionsofpipingsystemsbeyondanormallyclosedvalve.Pumpandvalvebodiesarealsoexemptedfromconsiderationofpipebreakbecauseoftheirgreaterwallthickness.Ahigh-energypipingsystembreakisnotpostulatedsimultaneouslywithamoderate-energypipingsystemcrack,norisanypipebreakorcrackoutsidecontainmentpostulatedUSARRevision8,3.6B-2November1995 NineMile.PointUnit2FSARconcurrentlywithapostulatedpipebreakinsidecontainment.Onlythehigh-energypipingsystembreakispostulatedexceptwhereapostulatedleakagecrackinthemoderate-energyfluidsystempipingresults".inmoresevereenvironmentalconditionsthanthebreakintheapproximatehigh-energyfluidpipingsystem.3.6B.2.1.1.4ExemptionsfromPipeWhipProtectionRequirementsProtectionfrompipewhipneednotbeprovidedifanyoneofthefollowingconditionsexists:1.Pipingisclassifiedasmoderate-energypiping.2~3~Followingasinglepostulatedpipebreak,pipingforwhichtheunrestrainedmovementofeitherendoftherupturedpipeinanyfeasibledirectionaboutaplastichinge,formedwithinthepiping,cannotimpactanystructure,system,orcomponentimportanttosafety.Pipingforwhichtheinternalenergylevelassociatedwithwhippingisinsufficienttoimpairthesafetyfunctionofanystructure,system,orcomponenttoanunacceptablelevel.Anylinerestrictions(e.g.,flowlimiters)betweenthepressuresourceandbreaklocation,andtheeffectsofeitherasingle-endedordouble-endedflowconditionareaccountedfor,inthedeterminationoftheinternalfluidenergylevelassociatedwiththepostulatedpipebreakreaction.Theenergylevelinawhippingpipeisconsideredinsufficienttoruptureanimpactedpipeofequalorgreaternominalpipesizeandequalorheavierwallthickness.3.6B.2.1.1.5LocationforPostulatedPipeBreaks(ASMESafetyClass1Piping)PostulatedpipebreaklocationsareselectedinaccordancewiththeintentofRG1.46,BTPAPCSB3-1,AppendixB,andasexpandedinBTPMEB3-1.ForASMESectionIII,SafetyClass1pipingsystemsclassifiedashighenergy,thepostulatedbreaklocationsare:1~Theterminalendsofthepressurizedportionsoftherun.(Terminalendsareextremitiesofpipingrunsthatconnecttostructures,components,orpipeanchorsthatactasrigidconstraintstopipingmotionandthermalexpansion.Abranchconnectiontoamainpipingrunisaterminalendforabranchrunexceptwhenthebranchrunismodeledasapartofthepipingsysteminthestressanalysisandisshowntohaveasignificanteffectonthemainrunbehavior.)USARRevision83.6B-3November1995 NineMilePointUnit2FSAR2~Atintermediatelocationsbetweentheterminalendswherethemaximumstressrangebetweenanytwoloadsets(includingzeroloadset)accordingtoASMESectionIIISubarticleNB-3600forupsetplantconditionsandanindependentOBEeventtransient,exceedsthefollowing:a~Ifthestress.rangecalculatedusingEquation10oftheCodeexceeds2.4Sbutisnotgreaterthan3S,nobreaksarepostulatedunlesstheCUFexceeds0.1.b.Thestressranges,ascalculatedbyEquations12or13oftheCode,exceed2.4SoriftheCUFexceeds0.1whenEquation10exceeds3S.3.6B.2.1.1.6OtherHigh-EnergyPipingandModerate-EnergyPipingTherearenopipingcomponentsinthissectionotherthanASMESafetyClass1.3.6B.2.1.1.7RegulatoryGuide1.46RG1.46describesanacceptablebasisforselectingthedesignlocationsandorientationsofpostulatedbreaksinfluidsystempipingwithinthereactorcontainmentandfordeterminingthemeasuresthatshouldbetakenforrestraintagainstpipewhippingthatmayresultfromsuchbreaks.GE-suppliedNSSSanalysis,design,and/orequipmentutilizedinthisfacilityisincompliancewiththeintentofRG1.46throughtheincorporationofthefollowingalternateapproach.SeetheregulatoryguidecommitmentmatrixinSection1.8forcommitment,revisionnumber,andscope.TherecirculationpipingalsohasbeenanalyzedfortheeffectsofhydrodynamicloadsandthepipebreakcriteriaofNUREG-0800.TheanalysisshowsthattheSRPcriteriadonotresultinanyadditionalpipebreaksbeyondthoseusingthedesignbasiscriteria(Section3.6B.2.1.1.5).3.6B.2.1.1.8TypesofBreakstoBePostulatedinFluidSystemPipingThefollowingtypesofbreaksarepostulatedinhigh-energyfluidsystempiping:1~2.Nobreaksneedbepostulatedinpipinghavinganominaldiameterlessthanorequalto1in.Circumferentialbreaksarepostulatedinpipingexceedinga1-innominalpipediameter.USARRevision83.6B-4November1995

.NineMilePointUnit2FSAR3~Longitudinalsplitsarepostulatedonlyinpipinghavinganominaldiameterequaltoorgreaterthan4ln~4~Circumferentialbreaksaretobeassumedatallterminalendsandatintermediatelocationschosentosatisfytheminimumbreaklocationcriteria(Section3.6B.2.1.1.5)forSafetyClass1pipingsystems.AteachoftheintermediatepostulatedbreaklocationsidentifiedtoexceedthestressandusagefactorlimitsofthecriteriaforSafetyClass1pipingsystems,eitheracircumferentialoralongitudinalbreak,orboth,arepostulatedinaccordancewiththefollowing:a.Circumferentialbreaksarepostulatedatfittingjoints.b.Longitudinalbreaksarepostulatedinthecenterofthefittingattwodiametricallyopposedpoints(butnotconcurrently)locatedsothatthereactionforceisperpendiculartotheplaneofthepipingandproducesout-of-planebending.c~Considerationisgiventotheoccurrenceofeitheralongitudinalorcircumferentialbreak.Examinationofthestateofstressinthevicinityofthepostulatedbreaklocationmaybeusedtoidentifythemostprobabletypeofbreak.Ifthemaximumstressrangeinthelongitudinaldirectionisgreaterthan1.5timesthemaximumstressrangeinthecircumferentialdirection,onlythecircumferentialbreakmaybepostulated,andconverselyifthemaximumstressrangeinthecircumferentialdirectionisgreaterthan1.5timesthestressrangeinthelongitudinaldirection,onlythelongitudinalbreakmaybepostulated.Ifnosignificantdifferencebetweenthecircumferentialandlongitudinalstressesisdetermined,thenbothtypesofbreaksareconsidered.5.6.Fordesignpurposes,alongitudinalbreakareaisassumedtobetheequivalentofonecircumferentialpipearea.Forbothlongitudinalandcircumferentialbreaks,afterassessingthecontributionofupstreampipingflexibilities,pipewhippingisassumedtooccurintheplanedefinedbythepipinggeometryandconfigurationforcircumferentialbreaksandout-of-planeforlongitudinalbreaks,andtocausepipemovementinthedirectionofthejetreaction.USARRevision8,3.6B-5November1995 NineMilePointUnit2FSAR7~Foracircumferentialbreak,thedynamicforceofthejetdischargeatthebreaklocationisbasedupontheeffectivecross-sectionalflowareaofthepipeandonacalculatedfluidpressureasmodifiedbyananalyticallyorexperimentallydeterminedthrustcoefficient.Justifiablelinerestrictions,flowlimiters,andtheabsenceofenergyreservoirsareused,asapplicable,inthereductionofthejetdischarge.Thethrough-wallleakagecracksarepostulatedinmoderate-energyfluidsystems(orportionsofsystems).Therearenomoderate-energypipingcomponentsinthissection.3.6B.2.1.2CriteriaforPipingSysteminAreaofContainmentIsolationValvesTherearenocontainmentpenetrationsassociatedwiththissectiononthereactorrecirculationpipingsystem.3.6B.2.2AnalyticalMethodstoDefineBlowdownForcingFunctionsandResponseModels3.6B.2.2.1AnalyticalMethodstoDefineBlowdownForcingFunctionsRuptureofapressurizedpipecausestheflowcharacteristicsofthesystemtochange,creatingreactionforcesthatcandynamicallyexcitethepipingsystem.Thereactionforcesareafunctionoftimeandspaceanddependuponfluidstatewithinthepipepriortorupture,breakflowarea,frictionallosses,plantsystemcharacteristics,pipingsystem,andotherfactors.Themethodsusedtocalculatethereactionforcesforvariouspipingsystemsarepresentedinthefollowingsections.3.6B.2.2.1.1RecirculationPipingSystemThecriteriausedforcalculationoffluidblowdownforcingfunctionsinclude:1~Circumferentialbreaksareassumedtoresultinpipeseveranceandseparationamountingtoatleastaonepipediameterlateraldisplacementoftherupturedpiping.sectionsunlessphysicallylimitedbypipingrestraints,structuralmembers,orpipingstiffnessasmaybedemonstratedbytheinelasticpipewhipanalysis(Section3.6B.2.2.2).2~Foracircumferentialbreak,thedynamicforceofthejetdischargeatthebreaklocationisbasedupontheeffective-cross-sectionalflowareaofthepipeandonacalculatedfluidpressureasmodifiedbyananalyticallyorexperimentallydeterminedthrustcoefficient.Justifiablelinerestrictions,flowUSARRevision83.6B-6November1995

.NineMilePointUnit2FSARlimiters,andtheabsenceofenergyreservoirsareused,asapplicable,inthereductionofthejetdischarge.'orbothlongitudinalandcircumferentialbreaks,afterassessingthecontributionofupstreampipingflexibilities,pipewhipisassumedtooccurintheplanedefinedbythepipinggeometryandconfigurationforcircumferentialbreaksandout-of-planeforlongitudinalbreaks,andtocausepipemovementinthedirectionofthejetreaction.3~Allbreaksareassumedtoattainfullareainstantaneously.Arisetimenotexceeding1msecisusedfortheinitialpulse.Blowdownforcingfunctionsaredeterminedbythefollowingmethod:Thepredictedblowdownforcesonpipesfedbyapressurizedvesselcanbedescribedbytransient(timedependent)andsteady-stateforcingfunctions.TheforcingfunctionsusedarebasedonmethodsdescribedinReference1.Thesemaybesimplydescribedasfollows:1~2~Thetransientforcingfunctionsoccuratpointsalongthepipefromthepropagationofwaves(wavethrust)alongthepipe,andatthebrokenendfromthereactionforceduetothemomentumofthefluidleavingtheendofthepipe(blowdownthrust).Thewavescausevarioussectionsofthepipetobeloadedwithtime-dependentforces.Itisassumedthatthepipeisone-dimensional,inthatthereisnoattenuationorreflectionofthepressurewavesatbends,elbows,andthelike.Followingtherupture,adecompressionwaveisassumedtotravelfromthebreakataspeedequaltothelocalspeedofsoundwithinthefluid.Wavereflectionsoccuratthebreakendandthepressurevesselend,untilasteadyblowdownconditionisestablished.Freespaceandvesselconditionsareusedasboundaryconditions.Theblowdownthrustthatiscausedbyfluidaccelerationfromthebreakandstaticpressureinthebreakitselfcausesatime-dependentreactionforceperpendiculartothepipebreak,reachingafinalsteady-statevalue.3~Theinitialblowdownforceonthepipeistakenasthesumofthewaveandblowdownthrustsandisequaltothevesselpressure(Po)timesthebreakarea(A).Aftertheinitialdecompressionperiod(i.e.,thetimeittakesforawavetoreachthefirstchangeindirection),theforceisassumedtodropofftothevalueoftheblowdownthrust(i.e.,0.7PoA).USAR,Revision83..6B-7November-1995 NineMilePointUnit2FSAR4Timehistoriesoftransientpressure,flowrate,andotherthermodynamicpropertiesofthefluidcanbeusedtocalculatetheblowdownforceonthepipeusingthefollowingequation:~2F=(P-P~)+~AFc(3.6B-1)Where:5.F=BlowdownforceP=PressureatexitplaneP,=AmbientpressureV=Velocityatexitplanep=DensityatexitplaneA=Areaofbreak'g,=Newton'sconstantFollowingthetransientperiod,asteady-stateperiodisassumedtoexist.Steady-stateblowdownforcesarecalculatedconsideringfrictionaleffects.ANS-58.2<'>isthebasedocumentusedfordeterminingthrustcoefficientsinevaluatingthedynamicforceduetojetdischarge.Forfrictionlessflow,thetheoreticalmaximumvalueofthrustcoefficientforsubcooledwateris2.0.Frictionaleffectsarethenconsideredtocalculatetheblowdownforcesfromthistheoreticalmaximumvalue.Thesteady-statethrustcoefficientforfrictionlessflowofsubcooledwaterbasedontheHenry-Fauskemodel@resultsinthefollowingexpression:3~00~861h*g0<h*<0~75Cp3~223~Oh*+0~97h*I0~75<h*<1~0Where:(h~-180)/(h~~~-180)h,=stagnationenthalpy(Btu/ibm)USARRevision8".3.6B-8November1995 NineMilePointUnit2FSARWhere:hsatwatcdsaturatedwaterenthalpyatthestagnationpressure(Btu/ibm)This'odelwasconfirmedbytheexperimentalcomparisonworkofHanson.<"Forallvaluesofh*,Cisnogreaterthan2.0.Forrecirculationlinebreak,ingeneral,C=2.0isusedforconservatismunlessotherwisejustifiedbydocumentedevaluationoftheempiricalequation.3.6B.2.2.2PipeWhipDynamicResponseAnalysesThepredictionoftime-dependentandsteady-thrustreactionloadscausedbyblowdownofsubcooled,saturated,andtwo-phasefluidfromarupturedpipeisusedindesignandevaluationofdynamiceffectsofpipebreaks.AdetaileddiscussionoftheanalyticalmethodsemployedtocomputetheseblowdownloadsisgiveninSection3.6B.2.2.1.Adetaileddiscussionofanalyticalmethodsusedtoaccountforthisloadingisdiscussedbelow.3.6B.2.2.2.1RecirculationPipingSystemThecriteriausedforperformingthepipewhipdynamicresponseanalysesinclude:Apipewhipanalysisisperformedforeachpostulatedpipebreak.However,agivenanalysiscanbeusedformorethanonepostulatedbreaklocationiftheblowdownforcingfunction,pipingandrestraintsystemgeometry,andpipingandrestraintsystempropertiesareconservativeforotherbreaklocations.2~3~4~5.Theanalysisincludesthedynamicresponseofthepipeinquestionandthepipewhiprestraintsthattransmitloadingtothestructures.Theanalyticalmodeladequatelyrepresentsthemass/inertiaandstiffnesspropertiesofthesystem.Pipewhipisassumedtooccurintheplanedefinedbythepipinggeometryandconfiguration,andtocausepipemovementinthedirectionofthejetreaction.PipingcontainedwithinthebrokenloopisnolongerconsideredpartoftheRCPB.Plasticdeformationinthepipeisconsideredapotentialenergyabsorber.Alimitofstrainisimposedsimilartothatonthepipewhiprestraintmaterial(Section3.6B.2.3.3.1,Type1restraintdesignlimits).6~ComponentssuchasvesselsafeendsandvalvesthatareattachedtothebrokenpipingsystemanddonotserveaUSARRevision83.6B-9November1995 NineMilePointUnit2FSARsafetyfunction,orwhosefailurewouldnotfurtherescalatetheconsequencesoftheaccident,arenotdesignedtomeetASMECodeimposedlimitsforessentialcomponentsunderfaultedloading.However,ifthesecomponentsarerequiredforsafeshutdown,oriftheyserveasafetyfunctiontoprotectthestructuralintegrityofanessentialcomponent,thenthesecomponentsaredesignedtoASMECodelimitsforfaultedconditionsandforlimitsnecessarytoensureoperability.ThepipewhipanalysiswasperformedusingthePDA(pipedynamicanalysis)computerprogramtodeterminetheresponseofapipesubjectedtothethrustforceoccurringafterapipebreak+.Theprogramtreatsthesituationintermsofgenericpipebreakconfiguration,whichinvolvesastraight,uniformpipefixedatoneendandsubjectedtoatime-dependentthrustforceattheotherend.Atypicalrestraintusedtoreducetheresultingdeformationisalsoincludedatalocationbetweenthetwoends.Nonlinearandtime-dependentstress-strainrelationsareusedforthepipeandtherestraint.Similartothepopularplastic-hingeconcept,bendingofthepipeisassumedtooccuronlyatthefixedendandatthelocationsupportedbytherestraint.Sheardeformationisalsoneglected.Thepipebendingmoment-deflection(orrotation)relationusedfortheselocationsisobtainedfromastaticnonlinearcantileverbeamanalysis.Usingthemoment-rotationrelation,nonlinearequationsofmotionofthepipeareformulatedusinganenergyconsiderationandtheequationsarenumericallyintegratedinsmalltimestepstoyieldtime-historyinformationaboutthedeformedpipe.AcomprehensiveverificationprogramhasbeenperformedtodemonstratetheconservatismsinherentinthePDApipewhipcomputerprogramandtheanalyticalmethodsutilized.PartofthisverificationprogramincludesanindependentanalysisbyNuclearServicesCorporation(NSC),undercontracttoGE,oftherecirculationpipingsystemforthe1969StandardPlantDesign.Therecirculationpipingsystemwaschosenforstudyduetoitscomplexpipingarrangementandassortedpipesizes.TheNSCanalysisincludedelastic-plasticpipeproperties,elastic-plasticrestraintproperties,andgapsbetweentherestraintandpipe,andisdocumentedinReference3.Thepiping/restraintsystemgeometryandpropertiesandfluidblowdownforceswerethesameinbothanalyses.However,alinearapproximationwasmadebyNSCfortherestraintload-deflectioncurvesuppliedbyGE.ThisapproximationisdemonstratedonFigure3.6B-1.Theeffectofthisapproximationistogivelowerenergyabsorptionofagivenrestraintdeflection.Typically,thisyieldshigherrestraintdeflectionsandlowerrestraint-to-structureloadsthantheGEanalysis.ThedeflectionlimitusedbyNSCisthedesigndeflectionatone-halfoftheultimateuniformstrainfortheGErestraintdesign.TheUSARRevision83.6B-10November1995 NineMile'ointUnit2FSARrestraintpropertiesusedforbothanalysesareprovidedinTable3'B-1.AcomparisonoftheNSC,analysiswiththePDAanalysis(Table3.6B-2)showsthatPDA;.predictshigherloadsin15ofthe18restraintsanalyzed.ThisisduetotheNSCmodelincludingenergy-absorbingeffectsinsecondarypipeelementsandstructuralmembers.However,PDApredictshigherrestraintdeflectionsin50percentoftherestraints.ThehigherdeflectionspredictedbyNSCforthelowerloadsarecausedbythelinearapproximationusedfortheforce-deflectioncurveratherthanbydifferencesincomputertechniques.ThiscomparisondemonstratesthatthesimplifiedmodelingsystemusedinPDAisadequateforpiperuptureloading,restraintperformance,andpipemovementpredictionswithinthemeaningfuldesignrequirementsfortheselow-probabilitypostulatedaccidents.Acomprehensivetestprogramwasperformedtodeveloptherestraintpropertiessuchastheload-deflectionpowerrelationshipsshowninTable3.6B-1.Aseriesofstaticanddynamicdeformationtestsofmodelrestraintswereconducted.Themodelrestraintswerescaleddownfromtherestraintssuitablefor26-insizepipe.Also,thestaticanddynamicmaterialpropertieswereobtainedfromtensiletestsofbarspecimens.Theresultsofthesetestswerestudiedandanalyzedforuseinthedevelopmentofananalyticalmodelthatpredictsthebehaviorofarestraintwhenloadedbyamovingpipe.Testswereperformedonsomefull-scalerestraintsthatshowedthatthepipewhiprestraintswillperformtheirdesignatedfunctionsadequately.3.6B.2.3DynamicAnalysisMethodstoVerifyIntegrityandOperability3.6B.2.3.1JetImpingementAnalysesandEffectsonSafety-RelatedComponentsThemethodsusedtoevaluatethejeteffectsresultingfromthe.postulatedbreaksofhigh-energypipingarepresentedinSection3.6A.3.6B.2.3.2PipeWhipEffectsonSafety-RelatedComponentsThissectionprovidesthecriteriaandmethodsusedtoevaluatetheeffectsofpipedisplacementsonsafety-relatedstructures,systems,andcomponentsfollowingapostulatedpiperupture.3.6B.2.3.2.1PipeWhipEffectsFollowingaPostulatedRuptureoftheRecirculationPipingSystemPipewhip(displacement)effectsonsafety-relatedstructures,systems,andcomponents(nozzles,valves,tees,etc.)thatareinUSARRevision83'B-11November1995 NineMilePointUnit2.,FSARthesamepipingrunastheoneinwhichthebreakoccurredaredeterminedby:1.Thecriteriausedfordeterminingtheeffectsofpipedisplacementsonthein-linecomponentsareasfollows:a~Componentssuchasvesselsafeendsandvalvesthatareattachedtothebrokenpipingsystemanddonotserveasafetyfunction,orwhosefailurewouldnotfurtherescalatetheconsequencesoftheaccident,neednotbedesignedtomeetASMESectionIIIimposedlimits"foressentialcomponentsunderfaultedloading.b.Ifthesecomponentsarerequiredforsafeshutdown,orserveasafetyfunctiontoprotectthestructuralintegrityofanessentialcomponent,limitstomeettheCoderequirementsforfaultedconditionsandlimitstoensureoperability,'frequired,aremet.2.ThemethodsusedtocalculatethepipewhiploadsonpipingcomponentsinthesamerunasthepostulatedbreakaredescribedinSection3.6B.2.2.2.3.6B.2.3.3LoadCombinationsandDesignCriteriaforPipeWhipRestraintsPipewhiprestraints,asdifferentiatedfrompipingsupports,aredesignedtofunctionandcarryloadforanextremelylowprobabilitygrossfailureinapipingsystemcarryinghigh-energyfluid.Thepipingintegritydoesnotusuallydependonthepipewhiprestraintsforanyloadcombination.Whenthepipingintegrityislostbecauseofapostulatedbreak,thepipewhiprestraintactstolimitthemovementofthebrokenpipetoanacceptabledistance.Thepipewhiprestraints(i.e.,thosedevicesthatserveonlytocontrolthemovementofarupturedpipefollowinggrossfailure)aresubjectedtoonce-in-a-lifetimeloading.Thepipebreakeventisconsideredtobeanabnormalconditionfortherupturedpipe,itsrestraints,andthestructuretowhichtherestraintisattached.ThedesignandanalysisofthesecomponentsforthiseventaredescribedinSection3.6B.2.2andthefollowingsections.3.6B.2.3.3.1RecirculationPipingSystemPipeWhipRestraintsThepipewhiprestraintsdesigned,tested,andfabricatedbyGEfortherecirculationlooppipingutilizeenergy-absorbingU-rodstoattenuatethekineticenergyofarupturedpipe.AtypicalpipewhiprestraintisshownonFigure3.6B-2.Aprincipalfeatureoftheserestraintsisthattheyareinstalledwithseveralinchesofannularclearancebetweenthemandtheprocesspipe.Thisallowsforinstallationofnormalpipinginsulationandunrestrictedpipethermalmovements.SelectcriticalUSARRevision83.6B-12November1995 NineMilePointUnit2FSARlocationsinsideprimarycontainmentarealsomonitoredduringhotfunctionaltestingtoprovideverificationofadequateclearancespriortoplantoperation.Thespecificdesignobjectivesfortherestraintsare:1.TherestraintswillinnowayincreasetheRCPBstressesbytheirpresenceduringanynormalmodeofreactoroperationorcondition.2~Therestraintsystemwillfunctiontostopthemovementofapipefailure(grosslossofpipingintegrity)withoutallowingdamagetocriticalcomponentsormissiledevelopment.3.TherestraintsshouldprovideminimumhindrancetoISIoftheprocesspiping.Forthepurposesofdesign,thepipewhiprestraintsaredesignedforthefollowingdynamicloads:1.Blowdownthrustofthepipesectionthatimpactstherestraint.2.Dynamicinertialoadsofthemovingpipesectionthatisacceleratedbytheblowdownthrustandsubsequentimpactontherestraint.3.DesigncharacteristicsofthepipewhiprestraintsareincludedandverifiedbythepipewhipdynamicanalysisdescribedinSection3.6B.2.2.2.4.Sincethepipewhiprestraintsarenotincontactwiththepipingduringnormalplantoperation,thepostulatedpiperuptureeventistheonlydesignloadingcondition.Therecirculationlooppipewhiprestraintsarecomposedofseveralcomponents,eachofwhichperformsadifferentfunction.ThesecomponentsarecategorizedasTypesI,II,III,andIV,asfollows:TypeITypeIIRestraintenergyabsorptionmembers-Membersthat,undertheinfluenceofimpactingpipes(pipewhip),absorbenergybysignificantplasticdeformation(e.g.,U-rods).Restraintconnectingmembers-Componentsthatformadirectlinkbetweentherestraintplasticmembersandthestructure(e.g.,clevises,brackets,pins).TypeIIIRestraintconnectingmemberstructuralattachments-FastenersthatprovidethemethodofsecuringUSARRevision83.6B-13November1995 NineMilePointUnit2FSARTypeIVtherestraintconnectingmemberstothestructure(e.g.,weldattachments,bolts).Structuralandcivilcomponents-Steelandconcretestructuresthatultimatelymustcarrytherestraintload(e.g.,sacrificialshield,trusses).Eachofthesecomponentsistypicallyconstructedofadifferentmaterial,withadifferentdesignobjectiveinordertoperformtheoveralldesignfunction.Therefore,thematerialandinspectionrequirementsanddesignlimitsforeacharesomewhatdifferent.Theserequirementsforeachcomponentaregivenbelow:1~TeIRestraint(e.g.,U-rods)a~throughsignificantplasticdeformationconformto:b.(1)ASMESectionIII,SubsectionNB,BoilerandPressureVesselCodeforSafetyClassIcomponents,or(2)ASTMSpecificationswithconsiderationforbrittlefracturecontrol,or(3)ASMESectionIII,SubsectionNF,BoilerandPressureVesselCode,ifapplicable.(4)GEMaterialSpecifications.Lamaterialsconformto:(1)ASMESectionIII,SubsectionNB,BoilerandPressureVesselCodeforSafetyClassIcomponents(SectionV,NondestructiveExaminationMethods),or(2)ASTMSpecificationsproceduresincludingvolumetricandsurfaceinspection,or(3)ASMESectionIII,SubsectionNF,BoilerandPressureVesselCode,ifapplicable.c~(4)GEMethodsandAcceptanceStandards.DesinLiits(1)DesinlocalstrainThepermanentstraininmetallicductilematerialsislimitedto:USARRevision8,3.6B-14November1995

~NineMile'oint.Unit2,FSAR(a)F.50percentof,theminimumactualultimateuniformstrain(atthemaximumstressonanengineeringstress-straincurve)basedonrestraintmaterialtests,or(b)One-halfofminimumpercentelongationasspecifiedintheapplicableASMESectionIIIBoilerandPressureVesselCodeorASTMSpecifications,whendemonstratedtobeasormoreconservativethantheabove.(2)Desinstead-stateloadThemaximumrestraintloadislimitedto80percentoftheminimumcalculatedstaticultimaterestraintstrengthatthedrywelldesigntemperature.Thisstrainislessthan50percentoftheultimateuniformstrainforallmaterialsusedforTypeIcomponents.(3)DnamicmaterialmechanicalroertiesThematerialselectedexhibitstensileandimpactpropertiesnotlessthan:2~(a)70percentofthestaticpercentelongation,or(b)80percentofthestaticallydeterminedminimumtotalenergyabsorption.TeIIRestraint(e.g.,clevises,brackets,pins)a~MaterialsMaterialselectionconformsto:(1)ASTMSpecificationsincludingconsiderationforbrittlefracturecontrol,or(2)ASMESectionIII,SubsectionNF,BoilerandPressureVesselCode,ifapplicable(3)GEMaterialSpecificationsb.(1)ASME/ASTMrequirementsorprocessqualificationandfinishedpartsurfaceinspectioninaccordancewithASTMmethods,or(2)ASMESectionIII,SubsectionNF,BoilerandPressureVesselCode,ifapplicable.(3)GEMethodsandAcceptanceStandards.USARRevision83.6B-15November1995 NineMilePointUnit2FSARC~DesinLimitsDesignlimitsarebasedonthefollowingstresslimits:(1)Primarystresses(inaccordancewithdefinitionsinASMESectionIII)arelimitedtothehigherof:(a)70percentofSwhereS=minimumultimatestrengthbytestsorASTMspecification(b)S+1/3(S-S)whereS=minimumyieldstrengthbytestorASTMspecification,or3~(2)RecommendedstresslimitsinaccordancewithASMESectionIII,SubsectionNF,forfaultedconditions,ifapplicable.TeIIIRestraint(fasteners)a.MaterialsFastenermaterialconformstoASTM,ASME,orMILrequirements.4~certifiedinaccordancewithapplicableASTM,ASME,orMILspecifications.c.DesinlimitsSameasTypeII.TeIIIRestraintMaterial(welds)a~MaterialsWeldmaterialsforattachmenttocarbonsteelstructuresarelimitedtolowhydrogentypes,orprocessesthatareinherentlylowhydrogen.b.c~Pperformedinaccordancewith:(1)ASTMSpecificationE165,or(2)AWSStructuralWeldingCodes,AWS-D1.1.DesinlimitsDesignlimitsarebasedonthefollowingstresslimits:themaximumprimaryweldstressintensity(twotimesmaximumshear,stress)islimitedtothreetimesAWSorAISCbuildingallowableweldshearstress.d.ProceduresProceduresandweldersarequalifiedinaccordancewiththelatestAWSCodeforweldinginbuildingstructures.USARRevision83.6B-16November1995 NineMilePointUnit2'FSAR5.TeIVRestraint(structuralandcivilcomponents)Material,inspection,anddesignrequirementsforthestructuralandcivilcomponentsareprovidedbyindustrystandardssuchasAISC,ACI,andASMESectionIII,DivisionII,alongwithappropriaterequirementsimposedfoisimilarloadingevents.Thesecomponentsarealsodesignedforotheroperationalandaccidentloadings,seismicloadings,windloadings,andtornadoloadings.Thedesignbasisapproachofcategorizingcomponentsisconsistentinallowinglessstringentinspectionrequirementsforthosecomponentssubjecttolowerstresses.ConsiderablestrengthmarginsexistinTypeIIthroughIVcomponentseventothelimitofloadcapacity(fracture)ofaTypeIcomponent.Impactpropertiesinallcomponentsareconsideredsincebrittletypefailurescouldreducetherestraintsystemeffectiveness.Inadditiontothedesignconsiderationsdiscussedabove,strainrateeffectsandothermaterialpropertyvariationshavebeenconsideredinthedesignofthepipewhiprestraints.Thematerialpropertiesutilizedinthedesignhaveincludedoneormoreofthefollowingmethods:1~Codeminimumorspecificationyieldandultimatestrengthvaluesfortheaffectedcomponentsandstructuresareusedforboththedynamicandsteady-stateevents.2.Notmorethana10-percentincreaseinCodeorspecificationvaluesisusedwhendesigningcomponentsorstructuresforthedynamicevent.Codeminimumorspecificationyieldandultimatestrengthvaluesareusedforthesteady-stateloads.3.Representativeoractualtestdatavaluesareusedinthedesignofcomponentsandstructures.4~Representativeoractualtestdataareusedforanyaffectedcomponent(s)andtheminimumCodeorspecificationvaluesforthestructuresforthedynamicandthesteady-stateevents.3.6B.2.4MaterialtoBeSubmittedfortheOperatingLicenseReview3.6B.2.4.1ImplementationofCriteriaforPipeBreakandCrackLocationandOrientationPostulatedPieBreaksinRecirculationPiinSstemThecriteriaforselectionofpostulatedpipebreaksintherecirculationpipingsysteminsidecontainmentareprovidedinSection3.6B.2.1.ThepostulatedpipebreaklocationsandtypesUSARRevision83.6B-17November1995 NineMile'ointUnit2FSARselectedinaccordancewiththesecriteriaareshownonFigure3.6B-3.3.6B.2.4.2ImplementationofSpecialProtectionCriteriaPieWh'straintsforRecirculationPiinSsteThepipewhiprestraintlocationsfortherecirculationpipingsystemareshownonFigure3.6B-3.ThissystemofrestraintsisprovidedtopreventunrestrainedpipewhipatbreaklocationspostulatedinSection3.6B.2.4.1.3.6B.2.4.3SummaryofJetEffectsAnalysesResultsJetEffectsforPostulatedRuturesofRecirculat'on'Piin~Sste>gThefluidjetthrustforeachoftherecirculationpipingpostulatedbreaklocationsshownonFigure3.6B-3iscalculatedinaccordancewithSection3.6B.2.2.ThejeteffectswillbeevaluatedinaccordancewithSection3.6A.2.3.1andresultswillbepresentedinthissection.USARRevision83.6B-18November1995 NineMilePointUnit2-FSAR3.6B.3ReferencesAmericanNationalStandardsInstitute(ANSI).ANS-58.2(ANSIN176),ProposedAmericanNationalStandardDesignBasisforProtectionofLightWaterNuclearPowerPlantsAgainstEffectsofPostulatedPipeRupture,1980.2.GEReportNEDE-10813A.PDA-PipeDynamicAnalysisProgramforPipeRuptureMovement(ProprietaryFiling).3.NuclearServicesCorporationReportNo.GEN-02-02,FinalReportPipeRuptureAnalysisofRecirculationSystemfor1969StandardPlantDesign.4.Shapiro,A.H.TheDynamicsandThermodynamicsofCompressibleFluidFlow,Vol.1.RonaldPress,NewYork,1965.5.Webb,S.W.EvaluationofSubcooledWaterThrustForces.NuclearTechnology,Vol.31,October1976.6.Hanson,G.H.Subcooled-BlowdownForcesonReactorSystemComponents:CalculationMethodandExperimentalConfirmation.IdahoNuclearCorporationReportIN-1354,June1970.USARRevision83..6B-,19November1995 t~v~

NineMilePointUnit2FSAR3.7SEISMICDESIGNThissectioniscomposedoftwoparts.Section3.7Aisapplicabletotheseismicdesignappliedtostructures,systems,andcomponentswithintheSWECscopeofsupply.Section3.7Bisapplicabletotheseismicdesignofstructures,systems,andcomponentswithintheGEscopeofsupply.3.7ASEISMICDESIGN(SWECSCOPEOFSUPPLY)3.7A.1SeismicInput3.7A.1.1DesignResponseSpectraThedesignresponsespectraaredevelopedinaccordancewithpublishedprocedures<'>andRG1.60(Section3.7A.2.5).Inthismethod,thecriticalparameteristhemaximumexpectedgroundacceleration.Associatedwiththemaximumgroundacceleration,themaximumgrounddisplacementisdeterminedbylinearscalingfromFigures1and2ofRG1.60inproportiontothemaximumexpectedgroundacceleration.Detailedsmoothspectraforanygivenvalueofdampingareobtainedbylocatingcriticalpointsandjoiningthembystraightlinesinatripartitelogarithmicplot.Thesecriticalpointsareobtainedfromgivenamplificationfactorsandcutofffrequencies.Thedesignvalueofthemaximumgroundaccelerationis0.15gfortheSSEand0.075gfortheOBE.Figures3.7A-1and3.7A-2showthesmoothdesignresponsespectraforhorizontalandverticalearthquakesassociatedwiththeSSE.Thesedesignresponsespectraarenotrelatedtoanysite-dependent.groundmotiontimehistory.AsshowninFigures3.7A-1and3.7A-2,theratiosofverticaldesignresponsespectralvaluestothehorizontaldesignresponsespectralvaluescomplywiththepositionofNRCRG1.60.TheratiovariesfordifferentfrequenciesasrequiredbyRG1.60.3.7A.1.2DesignResponseSpectrumDerivationAnartificialearthquakeisgeneratedtogiveresponsespectraenvelopingthedesignresponsespectra.Theartificialearthquakeisgeneratedandcheckedbycomparingspectralvaluesat80periodsbetween0.02and5.0sec.Theperiodsarespacedaccordingtotherule:T=XT,.i(3.7A-1)Where:PeriodninspectrumcomputationT,=Period(n-1)inspectrumcomputationUSARRevision83.7A-1November1995

'NineMilePointUnit2FSAR=1.0724E1Tg121Initialperiod=0.02secT~=Finalperiod=5.0secN=Totalnumberofperiods=80Theaccelerationtimehistoryyieldsgroundresponsespectraatdampingvaluesof1,2,5,7,and10percentthatenvelopthesmoothedsitedesigngroundresponsespectra(SSE)fordampingvaluesasshownonFigures3.7A-3through3.7A-17.ThecalculatedresponsespectraanddesignresponsespectraofRG1.60arecompared.Basedonthiscomparison,theartificialearthquakeisusedasthedesigntimehistoryforstructuralanalysis.DetailsoftheartificialaccelerationrecordanditsdevelopmentarepresentedinSection3.7A.2.5.3.7A.1.3CriticalDampingValues3.7A.1.3.1StructuresSeismicanalysisisperformedusingtotalsystemdampingcharacterizedbymodaldamping.Themodaldampingvalueiscalculatedasaratioofthesumoftheenergydissipatedineachcomponentelement(basedupontheassigneddampingratioofeachelement)tothetotalavailablemodalenergy.FurtherdiscussionofmodaldampingappearsinSection3.7A.2.15.Indeterminingthemodaldampingratios,componentdampingvaluesconsistentwiththestressintensitiesareused.Forexample,componentdampingforweldedstructuralsteelisassignedavalueof2percentforOBEand4percentforSSE.ThedampingratiosinRG1.61andTable3.7A-1forvariouscomponentsareusedinthedesign.3.7A.1.3.2-EquipmentThepercentagesofcriticaldampingvaluesassignedtoCategoryIsystemsandcomponentsareinaccordancewithRG1'.61andarepresentedinTable3.7A-1.3.7A.1.3.3PipingThepercentageofcriticaldampingvaluesusedfortheanalysisofallpipingareconsistentwithRG1.61andarepresentedinTable3.7A-1.USARRevision83.7A-2November1995 NineMilePointUnit2FSARThealternativedampingvaluesusedforUnit2willbethosedescribedinASMECodeCaseN-411(Figure3.7A-34).Theexpectedincreasedpipingdisplacements(resultingfromusingdampingvaluesinASMECodeCaseN-411)willbeverifiedwhenpipingsupportsaremoved,modified,oreliminated.Theverificationwillensurethattherewillbenoadverseinteractionwithadjacentstructures,components,andequipment.3.7A.1.4SupportMediaforCategoryIStructuresMajorCategoryIstructuresarefoundedonsoundrock.Thetopofbedrockisencountered'atelevationsrangingfrom246to240ft.Thefoundation/supportmediainformationforCategoryIstructuresissummarizedinTable3.7A-2.Rockpropertiesincludingwavepropagationvelocities,densities,andshearmoduluscanbefoundinSections2.5.2.5and2.5.4.2.ThestaticpropertiesofCategoryIstructuralbackfillarediscussedinSection2.5.4.5.ThedynamicpropertiesofCategoryIstructuralbackfillarepresentedinSection2.5.4.8.3.7A.2SeismicSystemAnalysis3.7A.2.1SeismicAnalysisMethodsThestructuralresponsesofthereactorbuildingandotherCategoryIstructurestotheapplicationofhorizontalandverticalearthquakegroundmotionsaredeterminedbytheresponsespectrummodalanalysismethod.SeismicresponsesforallCategoryIstructuresaredeterminedfromanapplicationoftwoorthogonalhorizontalandoneverticalearthquakegroundmotions,assumedtoactsimultaneously.TheearthquakegroundmotionsareestablishedintheformofresponsespectrafortheSSEandOBEasdescribedinSection3.7A.1.ThecomputerprogramSTRUDL(Appendix3A)isusedtoobtainthemodeshapes,naturalfrequencies,andresponsesforthemajorCategoryIstructures.TheresponsespectraforthefloorlevelsareobtainedusingtheTIMHIS6computerprogram(Appendix3A).ThecombinationofdesignloadingconditionswithseismicloadingandtheallowablestresslevelsaregiveninSection3.8.ThedynamicmodelsoftheCategoryIstructuresconsistofgeneralizedsystemsoflumpedmasses,eachwith6degoffreedom,connectedbymassless,linearlyelasticsprings.Themassesconsistoffloors,tributarywalls,columns,equipment,andpiping.ThelumpedmassmodelsofthestructuresareshownonFigures3.7A-18through3.7A-20.Sincethemajorstructuresarefoundedonrock,theseismicanalysesareperformedusingfixedbases(Section3.7A.2.4.1).Thesecondarycontainmentandprimarycontainmentstructuresareconnectedonlyatthefoundation;therefore,eachstructurewasmodeledseparately.Eachmodelisconstructedsothatitproperlyrepresentsthefreevibrationofacantileveredstructureinshear,flexure,andtorsion.Generally,massUSARRevision83.'7A-3November1995 NineMilePointUnit2FSARlocationsareselectedatpointswithaconcentrationofmass(e.g.,floorelevations),orwherethereisaspecialinterestintheresponse(equipmentlocations).Inthedynamicmodeling,ofCategoryIstructures,thefloorsaretreatedasrigidplatesordiaphragmsthattransferearthquakeinertiaforcestoframesanddiaphragmwalls,whichinturntransfertheloadstothefoundationmat.Beamtheory,combiningtheeffectsofshear,flexure,'orsion,andaxialdeformation,isusedtoestablishthestiffnesscharacteristicsoftheframe-wallsystems.ThecriteriausedtodetermineanadequatenumberofmassesindynamicmodelingofallCategoryIstructuresare,ingeneral,dictatedbythenumberoffloorelevationsandtheroofelevationsofastructure.Itisatthesepointsthatmassesarelumpedandincludehalfthewallsaboveandbelowthefloor,theflooritself,andmajorpiecesofequipmentrestingonthefloororsupportedfromthewalls.Thisisdonebecausethismassdistributioncloselyapproximatestherealmassdistributionoftheactualstructure.Additionalmasspointsmayalsobeincludedwheremassdistributiondictates.Thecriterionforestablishingtheminimumnumberofmassesisonethatprovidessufficientaccuracyfornaturalfrequenciesbelow33cps,sinceabovethisvaluethereislittleamplificationofearthquakeexcitation.Equipmentstifferthan33cpsrespondsatthemassresponse,andlargererrorsinstructuralfrequenciescanbetolerated.Thenumberofmassesinamodelareconsideredadequateifthenumberofdegreesoffreedomisequaltotwicethenumberofmodeswithfrequencieslessthan33cps.Asufficientnumberofmodeswereconsideredsothattheinclusionofanyadditionalmodewillnotresultina10-percentincreaseinresponses.TheseismicmotionofallCategoryIstructuresisdeterminedbyapplyingtheearthquakegroundmotionstotheappropriatedynamicmodels.Wherenon-CategoryIstructuresareattachedtoCategoryIstructures,theeffectsareanalyzedbyincludingthenon-CategoryIstructureintheseismicmodeloftheCategoryIstructure.Ingeneral,interactionbetweenCategoryIandnon-CategoryIstructuresiseliminatedbyprovidingstructuralgapsandseparatefoundationsforthestructures.Thestructuralgapsaredesignedsothatseismicmotionbetweenthestructuresisunimpededandalgebraicsummationofmaximumrelativedisplacementsofadjacentstructuresundermostcriticalconditionsislessthanthestructuralgap.AtabulationofthestructuralgapssurroundingCategoryIstructuresisshowninTable3.7A-10.Todetermineworstcomputedgapsbetweenthestructures,out-of-phasedeflection(displacement)ofthe'tructures(i.e.,structuresleaningtowardeachother)isassumedduringaSSEevent.Allowableconstructiontolerance,whenaddedtocumulativedisplacements,USARRevision8.3.7A-4November1995 NineMilePointUnit2FSARwillnotexceedstructuralgapprovided.SeeFigurethearrangementofplantstructures.Ascanbeseentabulation,thecumulativedeflection(displacement)eventdoesnotexceedthestructuralgapprovidedinAminimumof3instructuralgapisprovidedbetweenstructuresasacommondesignpractice.1.2-2forfromtheunderaSSEeachcase.theFortheeffectsofhydrodynamicloadsonthestructures,refertotheDesignAssessmentReportforHydrodynamicLoads(DAR)(Appendix6A).Fortheeffectsofpipingontheseismicanalysisofthestructures,refertoSection3.7A.2.3.3.7A.2.2NaturalFrequenciesandResponseLoadsAsummaryofnaturalfrequenciesofvibrationforCategoryIstructuresandthecorrespondingmodeshapesisgiveninTables3.7A-3through3.7A-6.Typicalmodal-responsesfortheprimarycontainmentatseveralselectedelevationsaregiveninTables3.7A-7and3.7A-8.Structuralresponsecharacteristicsintheformofbuildingaccelerationprofilesfortheprimarycontainment,reactorbuilding,controlbuilding,anddieselgeneratorbuildingareshownonFigures3.7A-21through3.7A-32.Amplifiedresponsespectra(ARS)aregeneratedforallCategoryIstructuresatmajorCategoryIequipmentelevationsandpointsofsupporttodefinetheseismicenvironmentforthesubsystemanalyses(Section3.7A.2.5).3.7A.2.3ProceduresUsedforModelingThedynamicmodelsofCategoryIstructuresconsistofsystemsofgeneralizedspring-connectedlumpedmasses.Thelumpedmassesandconnectingspringsofthedynamicmodelaredeterminedinordertoobtainasatisfactoryrepresentationofthedynamicbehavioroftheactualstructure.Ingeneral,massesarelocatedatfloorelevationsandincludethefloorsystem,aportionofthewallsandcolumnsbothaboveandbelowthefloorsystem,andmajorcomponents,equipment,andpiping.Inaddition,massesarelocatedatelevationswhereresponsevaluesarerequired.Thestructuralspringelementsthatconnectmasspointsrepresentthestiffnesscharacteristicsofthewallsandcolumnsections.Thesecharacteristicsaredeterminedfrombeamtheoryforconcretesections,whichincludestheeffectsofshear,flexure,andtorsion,andfromframeanalysisforsteelframeworks.Inthecourseofanalysis,acomparisonofrelativemassandstiffnesspropertiesbetweenconnectedcomponentsisperformedtodeterminewhethercouplingeffectsshouldbeconsideredintheanalysisofthesupportedcomponents.ThisconsiderationispertinenttoallCategoryIsystemsandequipment.Itisadesigngoaltodecouple(dynamically)equipmentfromitsattachedcomponents.USARRevision83.7A-5November1995

.NineMilePointUnit2FSARSomebasicrelationshipsareusedtoallowtheconclusionofdecoupling.Failuretomeetanyoneoftheserequiresthateither(1)additionalrestraintsareprovidedtosuitablyalterstiffnessparametersandtherebydynamicallyuncouplethesystem,or(2)theanalyticalmodelbeformulatedtoincludeboththesupportingandsupportedcomponentsinordertoactuallydeterminethecouplingeffectsofthecombinedsystem.Theprincipalpurposeforsuchconsiderationsistodefinecomponentinterfaceloadsforinclusionincomponentadequacydocumentation,aswellasseismicinputstosupportedcomponents.Thebasicrelationshipsusedasaguidetoconcludedecouplingare:1~2~IfR<0.01,decouplingisacceptableforanyg.If0.01<R<0.1,decouplingisacceptableif0.8>Q>1.25.3~IfR>0.1,anapproximatemodelofthesubsystemisincludedintheprimarysystemmodel.Where:R=TotalmassofthesuortedsubsstemTotalmassofthesupportingsystemR=FundamentalfreuencofthesuortedsubsstemDominantfrequencyofthesupportmotionIfthesubsystemiscomparativelyrigidandalsorigidlyconnectedwiththeprimarysystem,onlythemassofthesubsystemisincludedatthesupportpointintheprimarysystemmodel.Ontheotherhand,inthecaseofasubsystemsupportedbyveryflexibleconnections(e.g.,pipesupportedbyhangers),thesystemisnotincludedintheprimarymodel.Inmostcases,theequipmentandcomponents,whichcomeunderthedefinitionofsubsystems,areanalyzedasadecoupledsystemfromtheprimarystructure,andtheseismicinput,forthesubsystemisobtainedbytheanalysisoftheprimarysystem.3.7A.2.4Soil/StructureInteractionAllCategoryIstructuresaresupportedonnaturalbedrockexceptthatelectricalductline907,partofductline922,andelectricalmanholeno.1aresupportedbyCategoryIstructuralfill(Table3.7A-2).CertainportionsofthefloorslabsinthedieselgeneratorbuildingbeneathwhichgranularfillwasplacedareshownonFigure3.7A-33.Thisfillisusedsolelyasaconstructionformand,asshownonFigure3.7A-33,wasplacedinlimitedareas.Thestaticanddynamicdesignoftheseslabsassumednoloadtransferto,orbearingsupportfrom,theunderlyingbackfill.Walldesign,however,consideredlateralsoilpressuresasshownonFigure2.5-110.TheelectricalductlineisacontinuouslysupportedundergroundstructureUSARRevision8'3.7A-6November1995 NineMilePointUnit2FSARconsistingofconduittotallyencasedinreinforcedconcrete.TheelectricalductlinesareevaluatedforrelativemotionbetweentheportionsofductsupportedonrockandstructuralfillusingASCEprocedures+.Theelectricalductlinesarecapableofwithstandingthestressesandstrainsinducedbytherelativemotionbetweentheportionsofductsupportedonrockandstructuralfill.Manholeno.1isdesignedforseismicloadsusingtheproceduresdescribedinSection3.7A.3.12forCategoryItunnels.SeeFigure3.7A-33fordetailsofthemanholeandductline.AllCategoryIstructuralfillprovidesafactorofsafetyagainstliquefactionaslistedinSection2.5.4.8.ForstaticpropertiesoftheCategoryIfillseeSection2.5.4.5.3.7A.2.4.1Rock/StructureInteractionDynamicanalysesforstructuresfoundedonrockareperformedusingfixedbasemodelsbecauseshearwavevelocityexceeds3,500fps.ThedetailsofthegeophysicalsurveyarediscussedinSections2.5.4.2and2.5.4.4.3.7A.2.5DevelopmentofFloorResponseSpectraARSaredefinedasplotsofthemaximumresponseversusperiodforsingledegree-of-freedomsystemsatvariouslocationsinstructuressubjectedtodynamicloading.Intheanalysisofequipmentwithmassesthataresmallcomparedtothemassesofthedynamicmodelofthesupportingstructure,theresponseofthestructureisindependentoftheresponseoftheequipment.Theproblemcanthenbesolvedintwoparts:theresponseofthestructureduetogroundaccelerationcanbedetermined,andthatresponsecanbeappliedassupportaccelerationstotheequipment.Insuchcases,theuseofARSisanacceptableapproachtotheproblemofdeterminingthedynamicloadsonequipment.Thetimehistorymethodofanalysis,usingtheTIMHIS6computerprogram(Appendix3A),isusedtogeneratetheARSforCategoryIpipingandequipment.Theundampedequationsofmotionforanndegree-of-freedomstructuralmodelaresolvedtodeterminemodaleigenvalues,eigenvectors,andparticipationfactors.Themodalequationofmotionforstructuralresponseinmodeicanbewritten:X~(t)+2D~6)pe(t)+caqX~(t)=I'~Og(t)(3.7A-2)Where:D;Time-dependentmodalamplitudeModaldampingUSARRevision83'A-7November1995

.NineMilePointUnit2FSARModalcircularfrequencyModalparticipationfactorD~(t)=,.GroundaccelerationtimehistoryEquation3.7A-2canbesolvednumericallyforX;(t).Thesolutionforthestructuralresponseinmodeiisthen:(3.7A-3)and:[0~(t)]=[ag]xg(t)(3.7A-4)Where:[U;(t)]=Time-dependentdisplacementvectorinmodeiforthendegree-of-freedomsystem[0;(t)]=,Time-dependentaccelerationvectorinmodeiforthendegree-of-freedomsystem[a)lEigenvectorformodeiThesignificantstructuralresponsesmaybeaddednumericallytoobtainthetimehistoryofaccelerationwhichmaybeappliedtothesupportsofdampedsingledegree-offreedomsystems.Themaximumvaluesofresponseofthesingledegree-of-freedomsystemsproducetheARS.ARSaredevelopedfortwohorizontalandoneverticalexcitation.ThegroundaccelerationO,(t)isanartificialtimehistorywithatotaldurationof15secwhosegroundresponsespectrumenvelopstheresponsespectrumasspecifiedinRG1.60.Anartificialaccelerogramofgroundexcitationthatreproducesthefrequencycontentdisplayedinaresponsespectrumissimulatedstatisticallyinadigitalcomputerbyusingamulti-Pstochasticmodel.Inthismodel,theearthquakemotionisconsideredtobeawide-bandstationaryprocesswhosespectraldensityfunction,duration,andmaximumaccelerationarespecified.Theartificialmotionisgeneratedbymatchingthetargetspectrumforseveralspecifiedpercentagesofcriticaldampingat80oscillatorperiodsdistributedlogarithmicallyfrom0.02sec(50Hz)to5.0sec(0.2Hz).Thesestatisticallyindependentorthogonalgroundaccelerations(twohorizontalsandonevertical)areappliedsimultaneouslytothesupport.TheUSARRevision8.3'A-8November1995 NineMilePointUnit2FSARparticularresponse-'ina,directionofinterestisobtainedbyalgebraicsummationoftheresponseinthatdirectionateachtimeintervalduetoeachofthethreegroundaccelerations.3.7A.2.6ThreeComponentsofEarthquakeMotionThespatialcomponentsfromseismicresponseanalysisarecombinedinaccordancewithRG1.92.AllCategoryIstructuresareanalyzedfromthethreeorthogonalcomponentmotions(twohorizontalandonevertical)oftheprescribedearthquake.Whenresponsespectrumanalysisisperformed,therepresentativemaximumvalueofaparticularresponseofinterestfordesign(e.g.,stress,strain,moment,shear,ordisplacement)ofagivenelementofastructure,system,orcomponentsubjectedtoasimultaneousactionofthethreecomponentsoftheearthquakeisobtainedbytakingthesquarerootofthesumofthesquares(SRSS)ofcorrespondingrepresentativemaximumvaluesofthespectrumresponsetoeachofthethreecomponentscalculatedindependently.Incaseswheretimehistorydynamicanalysisisused,threestatisticallyindependent(maximumcorrelationfactorof0.2)orthogonalgroundaccelerations(twohorizontalandonevertical)oftheprescribedearthquakeareinputsimultaneously.Theparticularresponseinadirectionofinterestisobtainedbyalgebraicsummationoftheresponseinthatdirectionateachtimeintervalduetoeachofthethreegroundaccelerations.3.7A.2.7CombinationofModalResponsesIntheresponsespectrummodalanalyses,themodalresponsesarecombinedusingthegroupingmethodordoublesummethodasdescribedinRG1.92.3.7A.2.8InteractionofNon-CategoryIStructureswithCategoryIStructuresWhenCategoryIandnon-CategoryIstructuresareintegrallyconnected,thenon-CategoryIstructuresareincludedinthemodelwhendeterminingtheresponseoftheCategoryIstructures.Allnon-CategoryIstructuresmeetoneofthefollowingrequirements:1~Thecollapseofanon-CategoryIstructurewillnotcausethenon-CategoryIstructuretostrikeaCategoryIstructureorcomponent.2~Thecollapseofanon-CategoryIstructurewillnotimpairtheintegrityofCategoryIstructuresorcomponents.3~Thenon-CategoryIstructureisanalyzedanddesignedtopreventitsfailureunderSSEconditionsinsuchaUSARRevision83~7A-.9November1995 NineMile,Point'nit2FSARmannerthatthemarginofsafetyofthestructureisequivalenttothatoftheCategoryIstructures.3.7A.2.9EffectsofParameterVariationsonFloorResponseSpectraTheeffectsonthecalculatedvalueoffundamentalstructuralperiodsduetoexpectedvariationsindampingandthestructuralmaterialpropertiesaretakenintoaccount.SWEC-supplied-CategoryIequipmentandpipingsystemsdesignedusingfloorresponsespectraandhavingnaturalperiodswithin+15percentofthepeakresonantperiod(s)areassignedthepeakresponsevalue.Outsidethisrange,thebroadenedpeakisboundedoneachsidebylinesthatareparalleltolinesformingtheoriginalspectrumpeak.DampingvaluesareassignedtosystemsasoutlinedinSection3.7A.1.3.Inadditiontothebroadeningofpeaks,twodynamicmodelswereusedintheseismicanalysisoftheprimarycontainment.ThiswasdonetoaccountforthevariationinthestiffnessoftheprimarycontainmentmembersthatoccurduringaLOCA.Foronemodel,theconcretecontainmentisassumedtobecompletelyuncracked,whiletheothermodelutilizescrackedsectionpropertiesfortheprimarycontainmentwall.Sincetwodifferentmodelsareused,twosetsofresponsespectraineachdirectionaregeneratedateachfloorlevel.Thedesignfloorresponsespectraareobtainedfromanenvelopeofthetwofloorspectraforeachdirectionofexcitation.Theresponsespectrumanalysisisalsoperformedoneachmodel.Themaximumvalueofaparticularresponseofinterest(e.g.,moment,shear,axialforce,displacement)isusedforthedesignoftheprimarycontainmentstructure.3.7A.2.10UseofConstantVerticalStaticFactorsVerticalseismicsystemmultimassdynamicmodelsareusedtoobtainverticalresponseloadsfortheseismicdesignofCategoryIstructures.Therefore,constantverticalloadfactorsarenotusedtoaccountforverticalresponsetoearthquakesofCategoryIstructures.3.7A.2.11MethodUsedtoAccountforTorsionalEffectsCategoryIstructuresmayhavenaturaltorsionalmodesofvibrationduetoeccentricitiesbetweenthecentersofrigidityandcentersofmassofthestructuralelements.Thepresenceofeccentricitiesgeneratescouplingbetweentranslationaldirectionsofmotion,resultingintorsion.Thus,generalthree-dimensionalmodelsaresetup,followedbycompletedynamicanalysesasdescribedpreviously.Theresultsoftheseanalysesincludetorsionaleffects.USARRevision83.7A-10November1995 NineMilePointUnit2FSARSincethethree-dimensionalmodel"accountsforthetorsionaleffects,includingthe,effectsofeccentricitiesbetweenthe'centersofrigidityand'centersofmassofthestructuralcomponents,theadditionaleccentricityof5percentofthemaximumbuildingdimensionisnotconsideredintheanalyses.Additionally,thedesignofthecontrolbuilding,whichisconsideredrepresentativeofCategoryIstructures,wasreviewedforanadditionaltorsionalmomentresultingfromadditionaleccentricityof5percentofthemaximumbuildingdimension.Itwasshownthattheadditionalshearstressesresultingfromthisanalysiswerenotsignificantandwerewithinthedesigncapacities.3.7A.2.12ComparisonofResponsesAtypicalcomparisonofstructuralresponseobtainedbyresponsespectrumandtimehistoryanalysesforselectedpointsthroughouttheplantisgiveninTable3.7A-9.3.7A.2.13MethodsforSeismicAnalysisofDamsTherearenodamsthatwillimpactUnit.2.3.7A.2.14DeterminationofCategoryIStructureOverturningMomentsTheoverturningmomentsinducedbyseismicloadingarecomputedbythespectrummethodofanalysis(Section3.7A.2.1.1)foreachdirectionofexcitationseparately.TheappliedoverturningmomentiscomputedfromtheSRSSofmaximumresponsesfromthreeindividualdirectionsofexcitation.3.7A.2.15AnalysisProcedureforDampingInordertousemodalanalysis,dampingvaluesindifferentelementsofacoupledsystemareaccountedforbyusingstiffnessasaweightingfunctioningeneratingthemodaldampingvalues+.Accordingtothismethod,forasystemvibratinginitsithmode,theithmodaldampingcanbeestimatedbyevaluatingtheratioofthetotalenergydissipatedduetothepresenceofdampingindifferentelementsofthesystemtothetotalstrainenergystoredinthesysteminitsithmode.ThelimitingvaluesofdampingfactorsaregiveninTable3.7A-1forvarioussystemsandcomponents.Twotypesofdampingaregenerallyrecognized:(1)viscous,inwhichtheenergydissipatedpercycleisproportionaltofrequency,and(2)hysteretic,inwhichnofrequencydependenceisseen.Moststructuralelementsdisplayhystereticbehavior,whilesupportingsoilsappeartocombinebothhystereticandviscousdampingmechanisms.Sincethedynamicanalysisisperformedusingafixedbasemodel,onlyhystereticdampingneedbeconsidered.Whitman'sSeismicDesignforNuclearPowerPlants+givesausefulapproximationforthedampingofeachUSARRevision83.7A'-llNovember1995

.NineMilePointUnit2FSARmodewhenmaterialdampingvariesfromelementtoelement.Thisexpressionforthe(equivalentviscous)modaldampingisobtainedbyastrain-energyweightingofelementdamping:ND~E>~(3'A-5)Where:ND.IE'NumberofelementsHystereticdampingratioforelementiStrainenergyinelementiwhendeflectedintomodeshapejEquivalentviscousdampingratio(fractionofcritical)forstructurevibratinginmodejInparticular,whendampingisuniform,i.e.,D;=D,then:DforallmodesWhendampingisnotuniform,modaldampingisweightedtowardthoseelementsthatmakethelargestcontributiontotheenergyofeachmode.3.7A.3SeismicSubsystemAnalysisThedesignofCategoryIsubsystems(i.e.,components,equipment,piping,supports)includesOBEandSSEseismicloadingconditions.TheSSEproducesthemaximumvibratorygroundmotionforwhichCategoryIsystemsandcomponentsaredesignedtoremainfunctional.Thesesystemsandcomponentsarethosenecessarytoensure:1~2~TheintegrityoftheRCPB.JfThecapabilitytoshutdownthereactorandmaintain'tinasafeshutdowncondition.3~ThecapabilitytopreventormitigatetheconsequencesofaccidentsthatcouldresultinpotentialoffsiteUSARRevision83.7A-12November1995 NineMilePointUnit2FSARexposurescomparable.totheguidelineexposuresof10CFR100..'heOBEproducesthevibratorygroundmotionforwhichthosefeaturesofthenuclearpowerplantthatarenecessaryforcontinuedoperationwithoutunduerisktothehealthandsafetyofthepublicaredesignedtoremainfunctional.SystemseismicclassificationisprovidedinTable3.2-1.3.7A.3.1SeismicAnalysisMethods3.7A.3.1.1SeismicQualificationofComponentsThissectionprovidesthequalificationmethodsforequipmentaffectedbyseismicloads.ThemethodsforthequalificationofequipmentaffectedbyhydrodynamicloadsassociatedwithSRVdischargeandthepostulatedLOCAareprovidedintheDAR,Appendix6A,Subsection6A.9.AllCategoryIequipmentisqualifiedforseismicadequacy.Dependinguponequipmentlocation,thebasicsourceofseismicdesigndataiseitherthegroundresponsespectraortheARS,derivedthroughadynamicanalysisofthestructure.ThefourprincipalmethodsofdocumentingadequacyforCategoryIcomponentsarestaticanalysis,dynamicanalysis,dynamictesting,andstaticdeflectiontesting.Thesemethodsareusedsinglyorincombinationtoqualifyequipment.StaticAnalsisStaticanalysisisusedforequipmentthatcanbemodeledasrelativelysimplestructures.Thistypeofanalysisinvolvesthemultiplicationofthecomponentweightsbythespecifiedseismicaccelerations(direction-dependentloadings)toproduceforcesthatareappliedatthecentersofgravityinthehorizontalandverticaldirections.Astressanalysisofcriticalitems,suchassupportpoints,hold-downbolts,andotherstructuralmembers,isperformedtodeterminetheiradequacy.Thedeflectionsofcriticalcomponentsarealsocalculatedandcomparedwithspecifiedtolerances.Inthespecificationofequipmentforstaticanalysis,tworangesofaccelerationdataareprovided:aresonantrangedistinguishedbylowerfrequencieswithamplified,responseaccelerations,andarigidrangecharacterizedbyhigherfrequenciesandessentiallynonamplifiedresponse.Thedivisionbetweenthetworangesistermedthecutofffrequency.Selectionoftheappropriaterangedependsuponthefundamentalnaturalfrequencyoftheequipment.Ifthisvalueisbeyondtheresonantrange(i.e.,higherthanthecutofffrequency),theequipmentisanalyzedtorigidrangeresponseaccelerations.EquipmenthavingafundamentalfrequencyintheresonantrangeoftheARSisanalyzedbyusingthepeakresonantacceleration,USARRevision83.7A-13November1995 NineMilePoint'nit2FSARincreasedbyastaticcoefficientof1.3.,Thisfactoraccountsforpotentialmultimoderesponse(Section3.7A.3.5).Eachofthethreedefineddirectionsofearthquakeinput(twohorizontalandoneverticaltakenorthogonally)areevaluatedseparately.ThecalculatedresultsofthethreeanalysesaresuperimposedusingtheSRSScriterion.Theparticularresponsevalues(e.g.,acceleration,force,stress)tobecombinedareoptional,buttheoptionselectedremainsconsistentthroughout,followingtheguidelinesofRG1.92.DnamicAnalsisAdetaileddynamicanalysisisperformedwhencomponentcomplexityordynamicinteractionprecludesstaticanalysis,orwhenstaticanalysisistooconservative.Aninfinitenumberofcoordinateswouldberequiredtofullydescribethebehaviorofacomponentsubjectedtodynamicloads.Sincecalculationateverypointofacomplexmodelisimpractical,theanalysisissimplifiedbytheselectionofalimitednumberofmasspoints.Thelumpedmassapproachisemployedinwhichthemainstructureisrepresentedinamodelwithmassesinterconnectedbyflexibleelements.Thenatureofthecomponentandthestiffnesspropertiesofthecorrespondingmodelingelementsdeterminetheminimumspacingofthemasspointsandthedegreesoffreedomassociatedwitheachpoint.Incaseswheresomedynamicdegreesoffreedomdonotcontributetothetotalresponse,staticorkinematiccondensationisemployedintheanalysis.Thenormalmodeapproachisemployedfordynamicanalysisofcomponents.Naturalfrequencies,eigenvectors,participationfactors,andtherequiredcomponentdynamicresponses,suchasmodalmember-endforcesandmomentsoftheundampedstructure,arecalculated.ThebasisforcombinationofmodalresponsesisdiscussedinSection3.7A.2.7.Documentedcomputerprogramsinthepublicdomainareusedforperformingdynamicanalysis.However,ifproprietarycomputerprogramsareused,qualificationoftheprogramsisrequired.Eachofthethreedefineddirectionsofearthquakeinput(twohorizontalandoneverticaltakenorthogonally)areevaluatedseparately.ThecalculatedresultsofthethreeanalysesarecombinedbyusingtheSRSSmethod.Theselectedresponsevalues(e.g.,acceleration,force,stress)arecombinedfollowingtheguidelinesofRG1.92.Test~Equipmentthatistoocomplextoanalyzeorwhoseoperabilitycannotbeadequatelydemonstratedbyanalysisisqualifiedbydynamictesting.Theequipmentspecificationtestingrequirementssupplementthetestingmethodsandacceptancecriteriaofapplicableindustrystandards(suchasIEEE-344-1975,USARRevision83.7A-14November1995 NineMilePointUnit2FSARSection3.10),orprovideguidancefortestingwherenosuchccodesareavailable..Theminimumacceptancecriteriaforequipmentadequacyare:1.Nolossoffunction,orabilitytofunction,before,during,ordirectlyaftercompletionoftheproposedtest.2.Nostructural/electricalfailure(i.e.,connectionsandanchorages)thatwouldcompromisecomponentintegrity.3.Noadverseoperationorfaultyoperationbefore,during,oraftercompletionofthe.testthatcouldresultinanimpropersafetyaction.Equipmentvendorsandsuppliersarerequiredtoformulateprogramsforqualifyingtheequipmentinaccordancewiththespecifiedseismicrequirements.Thebasemotionsusedtosimulatetheseismicloadingsconsistofeitherasinglefrequencyormultiplefrequenciesandareappliedeitheralongoneaxisoralonghorizontalandverticalaxessimultaneously.Thechoiceoftheinputmotion,i.e.,frequencyandaxis,dependsonthedynamiccharacteristicsoftheequipmentandonthefrequencycontentoftheseismicloading.ThecriteriaforselectingthesespecificinputtestmotionsareinaccordancewithIEEE-344-1975andRG1.100.Exploratorytestsareruntodeterminetheresponsecharacteristicsoftheequipmentandtoaidinselectingthemethodoftesting.Theexploratorytestconsistsofalow-levelsinusoidalsweepoverthefrequencyrangeofseismicloading(1to33Hz).Thesweeprateis2octaves/minorlowertoexcitealltheresonances.Iftheequipmentisshowntobenonresonantinthefrequencyrangeofseismicloading,itisconsideredarigidbodyandtestedaccordingly.Iftheequipmentexhibitsmultipleresonantresponse,furthertestingprograms,basedonmultifrequencyinput,areconsideredmoreappropriateandareusedinqualifyingtheequipment.MultifreuencTestinMultifrequencyinput,appliedbiaxially,isthepreferredmethodusedforseismicqualification.Othermethodsareusedasjustified.Inputmotionfortestingisappliedtotheverticalandoneofthetwoprincipalhorizontalaxessimultaneously,unlessitisdemonstratedthattheequipmentresponsealongtheverticaldirectionisnotsensitive(coupled)tothevibratorymotionalongthehorizontaldirectionandviceversa.Phase-incoherent(i.e.,statisticallyindependent)inputsintheverticalandhorizontaldirectionsareusetoavoidpurelyrectilinearmotion.Whenthetestfacilitylimitationsdonotallowtheuseofindependentinputs,twotestsareperformed:(1)verticalandhorizontalinputsin-phase,and(2)verticalandhorizontalinputs180degout-of-phase.Thistest.isrepeatedUSARRevision8'3.7A-15November1995 NineMilePointUnit2FSARwiththeequipmentrotated90deginthehorizontalplane.Thetestsetupsimulatesascloselyaspossibletheactualin-serviceinstallation.Equipmentistestedinthemode(energizedorde-energized)thatreflectsitsdesignsafetyfunction.Equipmentoperabilityisverifiedbyperformingtheappropriatefunctionalcycleduringandafterthedynamictests.Thebasicobjectiveofqualificationorprooftestingistoproduceatestresponsespectrum(TRS)thatenvelopstherequiredresponsespectrum(RRS).ARS,whenproperlybroadenedtoaccountforvariationsinstructuralproperties,becometheRRSforqualification.Forthemultifrequencyinputapplied,thetestingmachineinputmust,asaminimum,equalthemaximumflooraccelerationoftheRRS.TheTRSisadjusted'nsuccessivetestrunssothatitenvelopstheRRSovertherequired-frequencyrange.CurvesforidenticaldampingareusedincomparingTRSandRRSinformation.FiveOBE-leveltestsareperformedpriortoSSEqualificationtestingfollowingtherecommendationsofZEEE-344-1975.Multifrequencytestingprovidesbroadbandtestinputmotionwhichproducessimultaneousresponsefromallthemodesoftheequipment.Multifrequencymotionsarederivedusinganyofthefollowingtechniques.1.TimeHistorAnaccelerationmotioninthetimedomain,attheequipmentmountinglocation,obtainedfromdynamicanalysisofthestructure.20Esignalthatisselectively.amplified,orattenuated,inone-thirdorsmallerfrequencyband-widths.ThemotionresultingfromthismodifiedsignalisarrangedsothatitenvelopstheTRS.Thisisthemostcommonlyusedinputmotionformultifrequencytesting.Thepeakaccelerationamplitudeofthismotionequalsorexceedsthezero-periodacceleration(ZPA)oftheRRS.Therandommotionsignalisappliedforaminimumdurationof15sec.3.ColexWaveAcomplexwaveisasumofagroupofdecayingsinusoidalsignalsspacedat1/3octaveornarrowerfrequencyintervalsoverthefrequencyrangeoftheRRS.SinleFreuecTest'nFollowingtherecommendationsinZEEE-344-1975,singlefrequencyinputfortestingisusedonlyifoneofthefollowingconditionsismet:1.Thecharacteristicsoftherequiredinputmotionindicatethatthemotionisdominatedbyonefrequency(i.e.,bystructuralfilteringeffects).USARRevision83.7A-16November1995 NineMilePointUnit2FSAR2.Theanticipatedresponseoftheequipmentisadequatelyrepresentedbyonemode.TheobjectiveistoproduceaTRSaccelerationatthetestfrequencyatleastequaltothatgivenbytheRRS.ThetesttableinputequalsorexceedsthemaximumflooraccelerationoftheRRS.Thesingle-frequencytestconsistsofanexploratorytestandadwelltest.Intheexploratorytest,thetableinputmotionequalsorexceedsthemaximumflooracceleration,i.e.,theZPAoftheRRS.Dwelltestingisperformedatthenaturalfrequencyidentifiedduringtheexploratorytest.Thedwelltestconsistsofapplyingacontinuoussinusoidalinputmotionatthemaximumflooraccelerationforaminimumdurationof20sec.Dwelltestingisalsoperformedusingasinebeatinputinsteadofacontinuoussineinput.Asinebeatconsistsofacontinuoussinusoidatthetestfrequency,amplitudemodulatedbyasinusoidofalowerfrequency.ThedurationandpeakamplitudeofthebeatforeachparticulartestfrequencyarechosentogenerateamagnitudeofequipmentresponsethatisatleastequaltothatimposedbytheRRSattheappropriatedampinglevel.Asaminimum,thepeakamplitudeofthebeatshouldequaltherigidrangeaccelerationoftheRRS.Tencyclesperbeatareused,followingtherecommendationsofIEEE-344-1975.StaticDeflectionTestinAstaticdeflectiontestconsistsofapplyingasustainedstaticloadoncriticalsectionsofthecomponentinsuchawaythatthedeflectioncausedbythisloadduplicatesorexceedsthecalculatedSSEdeflection.Concurrently,thecomponentisoperatedintherequiredmanner,andallapplicabledesignloadsaresuperimposedduringthetest.3.7A.3.1.2SeismicQualificationofPipingSystemsThisisdescribedinSection3.7A.3.8.3.7A.3.1.3OtherDynamicLoadsLoadingcombinationsandstresslimits,includingloadsduetohydrodynamiceffects,aredescribedinSection3.9A.3.1.AfurtherdiscussionofhydrodynamicphenomenaisincludedintheDAR(Appendix6A).3.7A.3.2DeterminationofNumberofEquivalentStressCyclesThefollowingcriteriaareappliedtoallCategoryIsubsystems:1~AtotaloffiveOBEandoneSSEareconsidered.2~Forsubsystems,exceptpiping,20cycles(fullsignreversals)perseismicevent,i.e.,atotalof120cycles,areconsidered.USARRevision83.7A-17November1995

,.NineMilePointUnit2FSAR3.Forallpipingsystems,10maximumstresscyclesperOBE(i.e.,atotalof50cycles)arepostulated.4.Wheretimehistoryanalysisisperformed,aminimumdurationof10secisassumed.3.7A.3.3ProcedureUsedforModelingTheproceduredescribedinthefollowingsectionsisspecificallywrittenforpipingsystems.OthersubsystemsareseismicallyqualifiedasdescribedinSection3.7A.3.1.1.3.7A.3.3.1SummaryPortionsofpipingsystemsthatareboundedbyanchorsorequipmentarestaticallyanddynamicallyindependentfromtheremainderofthepiping.Generally,apipingsystemconsistsofseveralsuchsubsystems.Theanalyticalmodelanditsgeometricboundariesaredescribedindetailinthefollowingsections.3.7A.3.3.2GeometricBoundariesofAnalyticalModelsForthepurposeofanalysis,pipingsystemsaresubdividedintosmallerunits(referredtoasproblems)thatareboundedbystructuralanchors(6degree-of-freedomconstraints)orbyothervirtuallyrigidpointssuchasequipment,penetrations,andpipingofmuchlargerdiameter.Abranchlinewithamomentofinertiaof1/10orlessofthexunpipemaybeignoredinthemodel.However,ifthebranchlineneedstobeanalyzed,itsmodelincludestheeffectoftherunpipe.WhereCategoryIpipingisconnectedtononseismicpiping,theadjoiningportionofthenonseismicpipinguptothefirstanchorisincludedintheanalyticalmodeloftheCategoryIpiping,andallsupports,uptoandincludingthisanchor,aredesignedseismically(Section3.7A.3.13).3.7A.3.3.3ModelThebasicmethodofanalysisusedisafiniteelementcomputerprogram(Appendix3A).Inaccordancewiththismethod,thecontinuouspipingismathematicallyidealizedasanassemblyofelasticstructuralmembersconnectingdiscretenodalpoints.Nodalpointsareplacedinsuchamannerastoisolateparticulartypesofpipingelementssuchasstraightrunsofpipe,elbows,valves,etc.,forwhichforce-deformationcharacteristicscanbecategorized.Nodalpointsarealsoplacedatalldiscontinuitiessuchaspipingsupports,concentratedweights,branchlines,andchangesincrosssection.Systemloadssuchasweights,equivalentthermalforces,fluidtransientdynamicforces,andinertiaforcesareappliedatthenodalpoints.Stiffnesscharacteristicsoftheinterconnectingmembersarerelatedtotheeffectiveshearareaandmomentofinertiaofthepipe.ThestiffnessofpipingelbowsandcertainbranchconnectorsisUSARRevision83.7A-18November1995 NineMilePointUnit2FSARmodifiedtoaccountforlocaldeformationeffectsbytheflexibilityfactorsspecifiedinASMESectionIII,1974,SubarticlesNB-3600(SafetyClass1pipinganalysis)andNC-3600(SafetyClass2and3'pipinganalysis).Theincreasedstiffnessofvalvebodiesistakenintoconsideration.3.7A.3.3.4SelectionofMassPointsThelumpedmassesarelocatedtoadequatelyrepresentthedynamicpropertiesofthepipingsystem.Masspointsaregenerallyselectedinaccordancewiththefollowingguidelines:1.Ateachnodewhereaconcentratedweightisplaced(valves,flanges,orotherin-linepipingcomponents).2.Ateachintersectionwherethreeormorepipingelementsareconnected(branchconnections,tees,andy-fittings).3.Attheendofelbowsandturnofdirection.4.Atnodessubjectedtoinputofdynamicforceexcitation.5.6.Ateachterminal(nodewhereonlyoneelementisconnectedsuchasend'aps,valveoperators).Atleastonemasspointbetweentworestraintsactinginthesamedirection.7.Unlessthereisaconcentratedweight,alumpedmasspointshouldnotbeplacedatadynamicrestraint.Whentheseguidelinesareusedthenumberofdegreesoffreedominthedynamicmodelisgreaterthantwicethenumberofmodeswithfrequencieslessthan33Hz.3.7A.3.3.5NumberofModesandCutoffFrequencyThenumberofmodesusedinthedynamicanalysisofpipingdependsuponthenumberofmasspoints,dynamicdegreesoffreedom,andcutofffrequency.Thecutofffrequenciesusedfordifferentdynamicloadsareasfollows:oadTeCutofFreueczSeismicSRVLOCAHydraulictransients33100100>100USARRevision83.7A-19November1995

,NineMilePointUnit2FSAR3.7A.3.4BasisforSelectionofFrequencies3.7A.3.4.1ComponentsARSdevelopedforthetwoorthogonalandverticaldirectionearthquakesarethebasicsourceofseismicdesignaccelerations.SeismicaccelerationsareselectedfromtheARSbasedonthenaturalfrequencycalculationsofthecomponentswithproperconsiderationofthefrequencycharacteristicsofthecomponentsupports.Appropriateamplificationfactorsareincludedintheseismicloadstoinsuretheadequacyofthedesignofthecomponents.3.7A.3.4.2PipingPipingsystemsaregenerallysupportedinsuchawaythatthelowestnaturalfrequencyofanalyticalsubsystems(pipingboundedbycomponentsand/orstructuralanchors)doesnotoccurinthepeakrangeoftheapplicable'ARS.ForsmallsizeCategoryIpiping,subsystemsaresupportedasoutlinedinSection3.7A.3.8.2.Thelowestnaturalfrequencyforthispipingisabovetheapplicablespectrumpeakrange.3.7A.3.5UseofEquivalentStaticLoadMethodofAnalysisThosecomponentsthatareconsidered,relativelysimpleorrigidaredesigned,byvirtueofnaturalfrequencycalculations,towithstandtheeffectsofamplifiedseismicaccelerationvaluesdependentuponfrequencyandamplituderangesassociatedwiththerelevantARS.Analysisofcomponentstothepeakvalueofresonantresponseisconsideredconservative,sincefundamentalnaturalfrequenciesdonotgenerallycoincidewiththefrequencyatresonanceoftherelevantresponsecurve.Componentshavingfundamentalnaturalfrequencieslessthanthecutofffrequency(Section3.7A.3.1.1)aredesignedtopeakaccelerationvalues,increasedbyafactorof1.3,orasjustified,toaccountforthecontributionofallsignificantdynamicmodesunderaresonantcondition.Justificationfortheuseof1.3asastaticcoefficientcanbefoundinASMEPaper74-NE-6+.Thevalidityoftheuseofthe1.3staticcoefficientfactorisevaluatedforequipmentwherealargenumberofmodesofvibrationwithintheseismicloadfrequencyrangeareanticipated.Anexamplejustifyingtheuseofa1.3factorisdemonstratedthroughacomparisonofresultsobtainedforatypicalequipment.Theequipmentselectedisaninstrumentpanel,2DFM-PNL102,forUnit2.Thispanelwasanalyzedbystaticanalysisusingthe1.3staticcoefficient,andalsobyaresponsespectrummodalanalysis.TheinputresponsespectrausedinthemodalanalysisweremodifiedfromtheactualUnit2spectra,asshownonFigureUSARRevision83.7A-20November1995 NineMilePointUnit2FSAR3.7A-36(Sheets1and2).Thisyieldsconservativeresultsandallowsawideapplicabilityoftheconclusion.StaticAnalsis

Reference:

TechnicalReportNo.18609-83N-2,SpecificationNMP2-C062G,ActonEnvironmentalTestingCorporation/Electro-Mechanics,Inc.FundamentalNaturalFrequency=18.8HzThisfrequencyislessthan33Hz;therefore,thestaticanalysiswasperformedusingthefollowingaccelerations:X-1Direction(Horizontal)=5.51g(4.24gx1.3)X-2Direction(Horizontal)=5.51g(4.24gx1.3)X-3Direction(Vertical)=4.10g(3.15gx1.3)DnamicnalsisTheresponsespectramodalanalysiswasperformedusingthespectraofFigure3.7A-36(Sheets1and2).Allthemodesuptoafrequencyof70Hzwereincludedinthisanalysis.ResutsandConclusioThemaximumresponses(displacements,stresses)fromthetwoanalysesandaratiooftheseresponsesarepresentedinTable3.7A-13.Themarginsevidentfromtheratiooftheseresponsesconcludetheadequacyofthe1.3staticcoefficient.3.7A.3.6ThreeComponentsofEarthquakeMotionThemaximumstructuralresponses(displacements,acceleration,forces,andmoments)duetoeachofthethreecomponentsofearthquakemotionarecombinedbytakingtheSRSSofthemaximumcodirectionalresponses,causedbyeachofthethreecomponentsof,earthquakemotionataparticularpointofthestructureorofthemathematicalmodel.ThisisinconformancewithRG1.92.3.7A.3.7CombinationofModalResponsesThebasisforcomputingcombinedresponseforuseinsubsystemanalysisispresentedinSection3.7A.2.7.3.7A.3.8AnalyticalProceduresforPiping3.7A.3.8.1IntroductionPipingclassifiedasCategoryIisdesignedtowithstandlevelsofloadingimposedbytheOBEandtheSSE.Thepipingsystemsareclassifiedas:USARRevision83.7A-21November1995

,NineMilePointUnit2FSAR1.ThosegovernedbytheASMECodeasSafetyCla'ss1,2,or3piping.2.ThosegovernedbytheANSIB31.1Codeandrequiringseismicanalysis.Theseismicresponseofpipingsystemsisanalyzedbytheresponsespectrummethodorthetimehistorymethod.TheresponsespectrummethodrequiresthatseismicloadingbecombinedfromthedynamicresponseofthesystembasedonanARS,andfromtheresponsetoaquasi-staticdifferentialsupportmovement,alsocalledseismicanchormovement,whichrepresentstheout-of-phasemovementofportionsofthestructuretowhichthesystemisattached.Computeranalysisconsidersallvibrationmodesuptoatleastthemodebeyondwhichthecontributiontotheoverallseismicdynamicresponseisinsignificant.Thestructuraldampingisthesameforallmodesofthepipingsystemandvariesonlywithpipesize(Section3.7A.3.15).Aresponsespectrumcurvecontainsacertaindampingvalueimplicitly.Intimehistoryanalysis,thedampingvalueisaninputparametertotheanalysis.ThenumberofearthquakecyclesneededforfatigueanalysisisgiveninSection3.7A.3.2.PipestressanalysisclassificationsaregiveninTable3.9A-3.Allsafety-relatedpipingsystemsthathavebeenseismicallyanalyzedarereviewedtoverifythatengineeringinputinformationandas-installedconfigurationsareconsistentwiththedesignrequirementsrequiredbyIEBulletin79-14.TheprocessthatgovernsthisisapartofthedesignverificationprogramforallCategoryIpiping.Thereviewconsistsoftwoparts:onethatexaminesdesigninputssuchasARSandanchormotion,andonethatcomparesas-builtdrawingsagainsttheas-analyzedcalculationsofrecord.Forlargeborepiping,thelargeborepipingas-builtdrawingsaredevelopedbasedontheinstallationcontroldrawingforpiping.Thelargeborepipingas-builtdrawingsaremarkedupandcheckedbyanindependentorganizationtoshowtheas-installedconfigurationinaccordancewithrequirements.Forsmallborepiping,theas-builtdrawingsarethepipingdesigndrawingsmarkeduptoshowtheas-installedconfigurationinaccordancewiththespecificationrequirements.Forbothlargeandsmallborepipesupports,theas-builtdrawingsaretheengineeringpipesupportdesigndrawingsandassociatedchangedocumentswhichhavebeenverifiedinaccordancewiththespecificationrequirements.Inallcases,theinformationiscompiledbygroupsresponsibleforthefinalanalysiswhereas-built,as-analyzedcomparisonsareperformed.Eitherthedifferencesinconfigurationorinputinformationarejustifiedonacase-by-casebasisorthenecessarychangesareissuedtothefield.TheengineeringsmallborepipingdesigndrawingsandUSARRevision83.7A-22November1995 NineMi;lePointUnit2FSARlargeborepipingas-builtdrawingsarerevisedtoincorporateas-builtinformation.ThedesignattributesthatarereviewedandthesourcedocumentsthatprovidetheseattributesareprovidedinTable3.7A-11forlargeborepipingandTable3.7A-12forsmallborepiping.Alistofapplicablesafety-relatedpipingsystemsisprovidedinTable3.2-1.LoadcombinationsandstresscriteriaaredescribedinSection3.9A.1.5.ThefinaldocumentationofthisprogramoccursatthetimeofN-5signoff,whenareviewisconductedtoensurethatallinputinformationisstillvalidandthatanyrevisionsthathavetakenplacedonotchangethebasisforthefinalanalysis.3.7A.3.8.2AnalyticalTechniquesGeneralCriteriaPipingsystemsarerigidlysupported,wherepossible,toassureafirstmodenaturalfrequencyabovethepeakfrequencyafterpeakspreading.uglificationofSmallSizePiinThescopeofsmallsizepipingislimitedto:1~ASMESafetyClass1pipingof1-inNPSandsmaller,whichcanbeanalyzedbySafetyClass2rulesinaccordancewithSubsubarticleNB-3630.2~ASMESafetyClass2and3pipingof6-inNPSandsmaller.3.ANSIB31.1piping(SafetyClass4piping)of6-inNPSandsmaller.Ingeneral,theanalysisofsmall-sizeASMESafetyClass1piping(1-inNPSandsmaller)andASMESafetyClass2and3piping(6-inNPSandsmaller)isperformedbymeansofsimplifiedseismicanalysiswithoutcomputerapplication.ForASMESafetyClass1piping(1-inNPSandsmaller)andASMESafetyClass2and3piping(2-inNPSandsmaller),themaximumsupportspansaredeterminedbylimitingthestressestowithinthecodeallowables.ForASMESafetyClass2and3pipingwith21/2-to6-inNPS,thesupportspacingisselectedsothatthefundamentalfrequency(fp)ofthepipingsectionwillalwaysbebeyondtheresonantfrequencyofthestructure,,asdeterminedfromapplicableseismicARS.ThepeakofthefloorresponsespectrafordesignofpipingsupportedbetweentwopointsisusedforthesimplifiedseismicUSARRevision83.7A-23November1995 NineMilePointUnit2FSARanalysis.DeadloadandthermalresponsesarealsocalculatedinaccordancewithSubarticleNC-3600.Thesimplifiedanalyticalapproachistoperformstresscalculationsforconsecutivesectionsofpiping,boundedatsupportpoints,withoutusingcomputerapplication.Thisisjustifiablebecausearigidsystemwithsufficientpipesupportsrepresentsmanyone-dimensional,straight-beamproblemswhereinthecouplingeffectsofthethree-dimensionalpipingsystemsareeliminated.Constraintsareplacednearelbows,tees,andconcentratedmasses,suchasvalves,sothatcouplingeffectsarenegligible.ThesecalculationsofmaximumcombinedstressesprovidesufficientandconservativedatatosatisfytherequirementofSubarticleNC-3600.3.7A.3.8.3DynamicAnalysisModelThemodelingprocedure,includingtheselectionofmasspointsandtheadequacyofnumber-ofdegreesoffreedom,isdescribedinSection3.7A.3.3.ResonseSectrumMethodWhenapipingsystemisanalyzedbymeansoftheresponsespectrummethod,oneofthepipinganalysiscomputerprogramsdescribedinAppendix3AisusedtocalculatethemodalresponseateachnodepointinthepipingsystemduetotheARSexcitationappliedtothesystem.GenerationorselectionoftheappropriatesetofARSforasubsystemsupportedatdifferentelevations,andconsiderationoftheeffectofseismicdifferentialdisplacementsbetweenrestraints,arediscussedinSection3.7A.3.9.ThedampingvaluesforpipingdependonpipesizeandaregiveninTable3.7A-1.Theequationsofmotionandtheirsolutionareaspreviouslydescribedforstructures(Section3.7.2).TimeH'storMethodTheapplicablebasemotiontimehistoryisthestructuralresponseatarepresentativemasspointofthestructuretothegroundmotiontimehistory.TheequationsofmotionandtheirsolutionarethesameasinSection3.7A.2.5,butthescalaraccelerationtermintheexcitationfunctionisnowtheamplitudeoftheaccelerationofthebaseofthesubsystem(pointsofattachment),notoftheground.Theeffectofparametervariationsonthefloorresponsespectraaretakenintoaccount(Section3.7A.2.9).DnamicAnasisFormulationThebasicequationsofmotionandtheirsolutionsarethesameasforstructures(Section3.7.2).AbsoluteaccelerationsatpointsUSARRevision83.7A-24November1995 NineMilePointUnit2FSARonthepipingsystemaresometimesneededforqualificationofcritical,safety-relatedequipment.Withtheresponsespectrummethod,themaximumabsoluteaccelerationatamasspointinmodeiisobtainedfromNewton'slawbydividingtheeffectiveinertiaforcebythemassatthemasspoint:<a)=(M]'Q)(3.7A-6)Where:IM]=Diagonalmassmatrixofthesystem(Q)=EffectiveinertiaforcesinmodeiWiththetimehistorymethod,theabsoluteaccelerationsareobtainedbyaddingthebaseaccelerationtotherelativeaccelerationsofthemasspoints.SeismicDifferentialDislacementsDescritionofInutTheseismicdifferentialdisplacementsarealsocalledseismicanchormovements.ThiseffectisanalyzedinaseparatestaticloadcaseforOBEanchormovements.Theanchormovementsareobtainedfromtheseismicdifferentialdisplacementsofthestructuralnodes.Thedisplacementsareobtainedinthefollowingform,onesetforeachmasspoint,N,ofthebuildingmodel:MassNodeX(East-~WestEarthuakeDirectionVerticalZ(North-~southD)XD2XD3XD)YDgYD3YD,ZD2ZD3ZNXYZWhere:Dg(DgIDN)XYZSRSSofdisplacementsinX(Y,Z)directionduetoearthquakeexcitationinX,Y,andZdirectionsatNodeNUSARRevision83.7A-25November1995 NineMilePointUnit2FSARThesearethemovementsofpointsonthewallsrelativetothefoundationofthebuilding.Relativedisplacementsbetweenmasspointsareusedtodeterminethemovementsofsupportpoints.Supportdisplacementsareimposedonthesysteminaconservativemanner.CombinationofAnchorovementLoadsTheindividualX,Y,andZanchormovementcomponentsofOBEareanalyzedasthreeseparatestaticanchormovementloadcases.TheseloadcasesarethencombinedbytheSRSSmethodandtheresultantloadcaseisusedinthecodestressevaluation.AnchormovementloadcasesareanalyzedusingoneofthepipinganalysiscomputerprogramsdescribedinAppendix3A.CombinedSeisicResonseThesystemresponsetotheresponse-spectrumexcitation(i.e.,displacements,internalforcesandmoments,stresses,andsupportreactions)isobtainedbyfirstcombiningthemodalcontributionsforeachearthquakecomponent.InconformancewithRG1.92,theeffectofclosely-spacedmodesistakenintoaccountbytheproceduredescribedinSection3.7A.2.7.ThecontributionsofeachofthethreecomponentsarethencombinedbytheSRSSmethods.Whentheresponsespectrummethodisused,responsetothedifferentialsupportmotionisconsidered.InSafetyClass1pipinganalysis,thismotioniscombinedwiththeinertialresponsegtheresultisthencombinedwithotherloadcases.Intheanalysisofotherpipingclasses,theseismic.anchormovementiscombinedwithsecondaryloads.Seismicloadcasesarecombinedwithotherloadcases(thermal,weight,pressure,otheroccasionalloads)inaccordancewithASMESectionIII,1974.TheloadcombinationsaregiveninSection3.9A.3.1.FatiueConsiderationsForASMESafetyClass1piping,ifEquation(10)ofSubparagraphNB-3653.1isnotsatisfied,afatigueanalysisisperformedinaccordancewithSubparagraphNB-3653.2orSubarticleNB-3200.ThisanalysisusesthetotalnumberofstresscyclesofallOBEs.ThenumberofearthquakecyclesisdiscussedinSection3.7A.3.2.CouteroramsUsedorSe'smicAnalsisAllanalysesareperformedusingoneofthepipinganalysiscomputerprogramsdescribedinAppendix3A.Theseprogramshandleresponsespectrumandsupportmotiontimehistoryanalyses.ProgramsusedforgeneratingARSinputcurvestoapipinganalysisarealsodescribedinAppendix3A.USARRevision83.7A-26November1995 NineMile'ointUnit2FSARDevelomentofRelativeDislacementsandTheirAlicationtoPiinAnalsisTherelativedisplacementbetweenapointonthereactorbuildingandapointontheprimarycontainmentisobtainedasfollows:1.Thedisplacementtimehistoryateachpointiscalculatedusingasinputthethree-directionalsynthetictimehistoryofgroundmotion.2.Thedisplacementtimehistoryofthefirstpointissubtractedfromthatofthesecondtogetatimehistoryofrelativedisplacement.SomeexamplesofdisplacementsareincludedonFigure3.7A-35.Theeffectofrelativedisplacementbetweenthesupportsisconsideredinthepipinganalysis.Onesupportisselectedasareferencepoint.Dynamicdisplacementsatthisreferencepointaretakeneitheraszeroorasdisplacementsrelativetoagivenstructuralnode.Atthefirst(adjacent)supportfromthereferencepoint,relativedisplacementsbetweenthissupportandthereferencepointaretakenandaddedtothedynamicdisplacementofthereferencepoint(thedirectionofdisplacementsisdeterminedandappliedtothesupportsinrelationtoitsfunction).Theresultantdisplacementsbecomethedynamicdisplacementsofthefirstsupport.Thefirstsupportthenbecomesthenewreferencepoint.Thisprocessisrepeateduntildynamicdisplacementsatallsupportsareobtained.3.7A.3.9MultiplySupportedEquipmentComponentswithDistinctInputsWhenasubsystemisattachedtodifferentpartsofastructure,suchasseparateelevationsononewallorseveralwalls,theresponsespectraofallstructuralnodesforwhichresponsespectraexistandwhichlienearesttothesupportelevationatthesubsystem,bothbelowandabovethesupportelevation,areenveloped,andthisenvelopespectrumisappliedtothesubsystem.Incaseswhereasubsystemrunsbetweentwodifferentbuildings,asingleARSenvelopingthespectraassociatedwithallsupportpointsisused.Inconjunctionwiththeresponsespectrumloading,theloadingfromdifferentialsupportdisplacementsiscalculated,andthetwoloadcasesarecombinedasdescribedinSection3.9A.3.1.Componentsandequipmentgenerallyhavelocalizedsupportsandtheeffectcanbeignored.TheapplicationtopipingisdiscussedindetailinSection3.7A.3.8.3.USARRevision83.7A-27November1995 NineMilePointUnit2FSAR3.7A.3.10UseofConstantVerticalStaticFactorsConstantverticalstaticfactorsarenotused.3.7A.3.11TorsionalEffectsofEccentricMassesForCategoryIpipingsystems,concentratedloadsinthepipingsystem,suchasvalvesandvalveoperators,aremodeledasmasslessmemberswiththemassofthecomponentslumpedatthecenterofgravity.Arigidmemberismodeledconnectingthecenterofgravitytothepipingsothatthetorsionaleffectsoftheeccentricmassesareconsidered.ThestressproducedatthepipeconnectionisgivenintheNUPIPEoutput.3.7A.3.12BuriedCategoryIPipingSystemsandTunnelsTherearenoburiedCategoryIpipingsystemsatUnit2.ThedesignofCategoryItunnelsisperformedinoneoftwoways.1~2~TunnelswhicharephysicallyconnectedtootherCategoryIstructuresarefoundedonrockandareanalyzedanddesignedforseismiceventsaspartsofthesestructures.Tunnelswhicharephysicallyseparatedfromotherstructuresarefoundedonrock(includingburiedCategoryItunnels)andareanalyzedusingthemethodsofSection3.7forseismiceventsorareconservativelydesignedforaccelerationvaluesof0.5gforSSEand0.25gforOBE.Atypicaldynamicanalysiswasperformedtodemonstrateandverifythattheaccelerationvalueschosenwereconservative.PartiallyorcompletelyburiedtunnelsarealsodesignedtoconsiderthestaticanddynamiceffectsofthebackfillusingthepressuredistributionshownonFigure2.5-110.ThedesignofCategoryItunnelsisdescribedinSection3.8.4.4.7.3.7A.3.13InteractionofOtherPipingwithCategoryIPipingInordertopreventpropagationoffailurefromtheseismicallyinducedeffectofnonseismicclasspipingonCategoryIpiping,eachnonseismicclasspipingsystemisgenerallydesignedtobeisolatedfromanyCategoryIpipingsystem.IfitisnotfeasibleorpracticaltoisolatetheCategoryIpipingsystemfromthenonseismicclasspipingsystem,thenadjacentnonseismicclasspipingisseismicallydesignedaccordingtothesamecriteriathatareapplicabletotheCategoryIpipingsystem.ForthenonseismicclasspipingsystemsinterfacingwithCategoryIpipingsystems,theseismicanalysisencompassesthenonseismicclasssystemtothefirstanchorpoint.USARRevision83.7A-28November1995 NineMilePointUnit2FSARIsolationanchorsthatseparateQACategoryIfromnonsafety-relatedpipingaredesignedconsideringseismicloadsfrombothsidesoftheanchor.Ifthenonsafety-relatedsidehasnotbeenseismicallyanalyzed,theseismicloadfromthatsideoftheanchorisassumedtobethreetimestheseismicloadfromtheQACategoryIside.'>TheEngineerwillevaluatethepipingandsupportdesignofthenonsafety-relatedpipingtoensurethattheseismicloadwillnotexceedtheassumedloads.Intheeventthattheassumptioncannotbejustified,theanchorwillbedesignedtosustainthemaximummomentwhichthenonsafety-relatedpipingcanimposeontheanchor.TheloadingconditionsandloadcombinationsareinaccordancewithTable3.9A-14.AllowablestressesdesignatedintheAISCspecificationareusedforthedesignofstructuralmembersandwelds.Whenthemaximummomentisused,theallowablestressesinthestructuralmemberwillbeincreasedto0.9Sy.AllowablestressesforinducedlocalpipewallstressesareinaccordancewithASMEIII,SubsectionNC,1974.Whenthemaximummomentisused,theallowablelocalstresswillbeincreasedto2Sy.3.7A.3.14SeismicAnalysesforReactorInternalsSeeSection3.7B.3.14.3.7A.3.15AnalysisProcedureforDampingThepercentagesofcriticaldampingvaluesassignedtoCategoryIsubsystemsandcomponentsareinaccordancewithRG1.61(Table3'A-1).Inthedynamicanalysisofanyparticularitemofequipment,thesamepercentageofcriticaldampingisusedforallmodalresponses.Incaseswherepipesizedictatestheuseoftwosetsofdampingvaluesforthesameanalysis,thedampingvaluescorrespondingtothepipesizeofthemajorityofthesystemareusedfortheentireanalysis.3.7A.4CriteriaforSeismicInstrumentationProgram3.7A.4.1ComparisonwithRegulatoryGuide1.12Aseismicinstrumentationprogramhasbeenimplementedtomonitorandrecordinputmotionandbehavioroftheplantintheeventofanearthquake.ThisinstrumentationprogramcomplieswiththerequirementsofRG1.12andANSIStandardANSI/ANS-2.2-1978.USARRevision83.7A-29November1995 NineMilePointUnit2FSAR3.7A.4.2LocationandDescriptionofInstrumentation3.7A.4.2.1TriaxialTimeHistoryAccelerographStrongmotiontriaxialtimehistoryaccelerometersareinstalledinthreelocations.Twoaccelerometersensorpackagesareinstalledinthereactorbuildingoutsideoftheprimarycontainment.Onesensorpackageislocatedonthereactormatinthesecondarycontainmentadjacenttotheexteriorreactorbuildingwallatel175ft,andthesecondislocatedapproximately178ftabovethefirstontherefuelingflooratel353ft.Thethirdsensor-packageislocatedontopofthecontrolbuildingmatatel214ft.Thestrongmotiontriaxialtimehistoryaccelerographhasthefollowingphysicalcharacteristics:1.Accelerometersareoftheforce-balancetype,withthecapabilityofrecordingamaximumof1.0gatfullscale.2.Accelerometersaresensitivetofrequenciesintherangeof0to50Hz.3~Theseismicinstrumentationandrecordingsystemisinaquiescentstateuntilactivatedbyseismictriggerssetat0.01g.Theseseismictriggers(bothhorizontalandvertical)activatetherecordingsysteminlessthan100msec.Therecordingsystemwilloperatecontinuouslyduringtheperiodinwhichtheearthquakeexceedsthe0.01gthreshold,plus.10secminimumbeyondthelastseismictriggersignal.Thesystemwillbecapableofaminimumof30mintotalrecordingtime.4.Eachsensorpackagecontainsthreeorthogonalaccelerometers.Allstrongmotionsensorpackagesareorientedtothesameazimuths.3.7A.4.2.2TriaxialPeakAccelerographAlsoinaccordancewithRG1.12,triaxialpeakaccelerographsareinstalledonotherselectedCategoryIstructures,equipment,andcomponentstoverifytheseismicresponsedeterminedanalyticallybyusingthetracesrecordedbytheaccelerographs.Theaccelerographsarelocatedasfollows:1.Reactorpedestal.2.Reactorbuildinghigh-pressurecorespray(CSH)piping.3~Servicewaterpipingindieselgeneratorbuilding.Theseinstrumentsdetectandrecordpeakamplitudesofaccelerationsinaminimumfrequencyrangeof0to26Hz.USARRevision83.7A-30November1995 NineMilePointUnit2FSARTriaxialpeakaccelerographshavethefollowingphysicalcharacteristics:1.Accelerographsareoftheshortperiodtorsionaltype,withasensitivityfrom0.01to10gfullscale.2.Theaccelerographrecordsbyscribingexcursionsofadiamondstylusonareplaceablemetalplate.3.Nopowerisrequiredtooperatetheinstrument.4.Airdampingisusedto60percentofcriticalwithanaccuracyof+5percentofcritical.5.Operatingtemperaturerangeis-40'Fto185'F.3.7A.4.2.3TriaxialResponseSpectrumRecorderThetriaxialresponsespectrumrecordersensesandpermanentlyrecordsinformationdefiningaresponsespectrum.Itisacompletelypassivedevice,coveringtherangefrom1to32Hzin1/3octaveincrements.Sixteenreedsofdifferentlengthsandweights,1foreachfrequency,haveattachedtotheirfreeendadiamond-tippedstylusthatinscribesapermanentrecordofitsdeflectionon16respectiverecordplates.Acalibrationsheetliststheresonantfrequencyandg-sensitivityofeachreedandallowsaplotofaccelerationversusfrequencytobemade.Theseinstrumentshavethefollowingphysicalcharacteristics:1.Dampingfortheoscillatorsisnotlessthan2percentnormorethan5percentofcritical.2.Operatingtemperaturerangeis-404Fto185F.3.Accuracy:frequencyis+1percent;accelerationis+3percentoffullscale;dampingis+0.15percentofnominal.4.Thedynamicrangeforaccelerationis100to1minimum.Fourtriaxialresponsespectrumrecordersareinstalledatthefollowinglocations:1.Reactorbuildingmat(el175ft).2.Controlbuildingmat(el214ft).3.Refuelingfloor(el353ft10in).4.PrimarycontainmentwallpenetrationforRHRpiping(el294ft6in).ThebasisforselectionoftheselocationsistoprovidesomemeasureofredundancytothestrongmotionaccelerographsandUSARRevision83.7A-31November1995 NineMilePointUnit2FSARalsotoprovideadditionaldatatoverifytheseismicresponsedeterminedanalyticallybyusingthetracesrecordedbythestrongmotionaccelerographs.3.7A.4.2.4TriaxialSeismicSwitchOnetriaxialseismicswitchisinstalledonthereactorbuildingmattoprovideanimmediatesignaltothemaincontrolroomtoindicateifspecifieddesignaccelerations(OBE)havebeenexceeded.Theseismicswitchhasthefollowingphysicalcharacteristics:1~Thepackageiscomposedofthreeorthogonalaccelerationtransducers.2~3~Setpointisadjustablefrom0.025to0.25g.Switchremainsclosedfor6to20sec(adjustable)afterdetectionofanaccelerationoverthepresetvalue.4.OperatingtemperaturerangeisfromO'Fto130'F.3.7A.4.3MainControlRoomOperatorNotificationRecordingequipment,seismicannunciators,andresponsespectrumannunciatorsarelocatedintherelayandcomputerroom,el288.TheannunciatorshavebothvisualandaudiblealarmstonotifytheControlRoomOperatorwhenaseismiceventcausestheOBEdesignaccelerationstobeexceeded.Theseismictriggeronthereactorbuildingmatactivatesthetriaxialaccelerographandthemagnetictaperecordingsystemwhentheaccelerationexceeds0.0lg.Theresponsespectrumrecorderonthereactorbuildingmatactivatestheresponsespectrumannunciatorwhenpresetglevelsatcorrespondingfrequenciesareexceeded.ThetriaxialseismicswitchonthereactorbuildingmatsetsofftheseismicannunciatorwhentheaccelerationexceedstheOBElimitsof0.075ghorizontaland0.050gvertical.Theseismictriggerand,hence,thetriaxialaccelerographandthemagnetictaperecordingsystemwillbeactivatedbyaccelerationsfromnonseismiceventssuchasSRVblowdownloadsandhydrodynamicloadsduetoLOCAevents.However,sincethenormaloperatingSRVaccelerationlevel(i.e.,theaccelerationvaluecorrespondingtozeroperiodinthereactorbuildingmatdesignresponsespectra,asdefinedinRG1.12)islessthantheOBEaccelerationlevel,theseismicswitchwillnotbeactivatedbythenormaloperatingnonseismicevents.Therefore,theseeventswillnotinterferewithnormalplantoperations.USARRevision83.7A-32November1995 NineMilePointUnit2FSAR3.7A.4.4ComparisonofMeasuredandPredictedResponsesTodetermineifanuclearpowerplantcancontinuetooperatesafelyfollowingaseismicevent,comparisonsaremadebetweentheseismicresponseasmeasuredbytheseismicinstrumentationandthecomputedresponseusedasadesignbasis.SuchcomparisonsareperformedonlyafterOBEormoresevereseismicconditionsoccur.Tomakesuchcomparisons,thefollowingprocedureisimplemented:1.Magnetictaperecordsaredigitizedandcorrectedfortimesignalvariationsandbaselinedeviations.2.Time-historyrecordsfromtriaxialsensorslocatedonthereactorbuildingmatareusedtodirectlycalculateARSatappropriatecriticaldampingvalues.3~Time-historyrecordsfromthereactorbuildingmatsensorareusedasinput,groundmotionforthereactorbuildingdynamicmodel.ARSarethencalculatedatthelocationsoftheothertwosensorsinthecontainmentstructureforcomparisonandcorrelationwiththeresponsespectradeterminedinItem2.Reasonablecorrelationbetweenthespectraisaccomplishedonaniterativebasisbyvaryingthephysicalpropertiesofthemodels(stiffnessesanddampingcharacteristics)tocalibratethedynamicmodel.Oncethedynamicmodelhasbeencalibrated,additionalverificationofitscorrectnessismadeusingtheaccelerationreadingsfromthepeakrecordingaccelerographs.Theresultsofthecomparisonwillbeusedtoevaluatetheseismiceffectsonthestructuresandequipmentbyformingthebasisforremodeling,detailedreanalysis,andphysicalinspection.Thereanalysisandinspectionresultswillbeusedtodeterminetheappropriateactionsthatarerequiredasaresultoftheearthquake.3.7A.4.5In-serviceSurveillanceRequirementsIn-servicesurveillancewillbeperformedontheseismicinstrumentationattheintervalsspecifiedintheTechnicalSpecifications.USARRevision83.7A-33November1995 NineMilePointUnit2FSAR3.7A.5References1~2~3.Newmark,N.M.,Blume,J.A.,andKapur,K.K.DesignResponseSpectraforNuclearPowerPlants,JournalofPowerDivision,ProceedingsofAmericanSocietyofCivilEngineers,Vol.99,No.P02,November1973.Roesset,J.M.,Whitman,R.V.,andDobry,R.ModalAnalysisforStructureswithFoundationInteraction.JournaloftheStructuralDivision,ProceedingsASCE,pp399-416,March1973.Whitman,R.V.SoilStructureInteraction.SeismicDesignforNuclearPlants.MITPress,Cambridge,MA,pp241-269,1970.4~5.Gwinn,J.M.andGoldstein,N.A.EquivalentStaticLoadsfromAmplifiedResponseCurves.ASMEPaper74-NE-6,presentedattheAmericanSocietyofMechanicalEngineersPressureVesselandPipingConference,Miami,FL,June1974.ASCEStructuralDivisionCommitteeonNuclearStructuresandMaterials,SeismicResponseofBuriedPipesandStructuralComponents,ReportPreparedbyCommitteeonSeismicAnalysis.USARRevision83.7A-34November1995 NineMilePointUnit2FSARTABLE3.7A-1DAMPINGFACTORSItemEuimentorStructureDampingPercentCriticalOBESSEEquipmentandlargediameterpipingsystems,pipediametergreaterthan12inSmalldiameterpipingsystems,diameterlessthanorequalto12inWeldedsteelstructuresBoltedsteelstructuresPrestressedconcretestructuresReinforcedconcretestructuresUSARRevision8.1of.1November1995

'V NineMilePointUnit2FSARTABLE3.7A-11DESIGNATTRIBUTESTOBEREVIEWEDFORVERIFICATIONOFLARGEBORESAFETY-RELATEDPIPINGASREQUIREDBYIEBULLETIN79-14DesinAttributeSourceDocumentPiperunconfigurationandgeometryPipesupportlocationValvelocationSupportdesignandfunctionEmbedmentplate,baseplate,andstructuralsteelPipeclearanceatsupportsOtherpipeclearancesAttachmentstopipeAttachmentstosupportsValveweightsAmplifiedresponsespectraSupportseismicanchormotionOtherdesignattributesL/Bas-builtdrawingL/Bas-builtdrawingL/Bas-builtdrawingEngineeringdesigndrawingEngineeringdesigndrawingandpipesupportinstallationSpecificationNo.NMP2-P301JEngineeringdesigndrawingConstructionSiteInstructionsCSI2.11L/Bas-.builtdrawingandengineeringdesigndrawingEngineeringdesigndrawingVendordrawingPipingDesignSpecificationNo.NMP2-P301APipingDesignSpecificationNo.NMP2-P301APipingDesignSpecificationNo.NMP2-P301AUSARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.7A-12DESIGNATTRIBUTESTOBEREVIEWEDFORVERIFICATIONOFSMALLBORESAFETY-RELATEDPIPINGASREQUIREDBYIEBULLETIN79-14DesinAttributeSourceDocumentPiperunconfigurationandgeometryPipesupportlocationValvelocationSupportdesignandfunctionEmbedmentplatePipeclearanceatsupportsOtherpipeclearancesAttachmentstopipeAttachmentstosupportsValveweightsAmplifiedresponsespectraSupportseismicanchormotionOtherdesignattributesEngineeringdesigndrawingEngineeringdesigndrawingEngineeringdesigndrawingtEngineeringdesigndrawingEngineeringdesigndrawingandS/BpipesupportinstallationSpecificationNo.NMP2-P301FEngineeringdesigndrawingConstructionSiteInstructionsCSI2.11EngineeringdesigndrawingEngineeringdesigndrawingVendordrawingPipingDesignSpecificationNo.NMP2-P301APipingDesignSpecificationNo.NMP2-P301APipingDesignSpecificationNo.NMP2-P301AUSARRevision81of1November1995 NineMile:PointUn'it2FSAR3.7BSEISMICDESIGN(GESCOPEOFSUPPLY)AsdiscussedatthebeginningofSection3.7,thefollowinginputisapplicabletothedesignofsystems,componentsandequipmentwithintheNSSSscopeofsupplybyGE.Allsystems,componentsandequipmentoftheNSSSaredefinedaseitherCategoryIornon-CategoryI.TherequirementsforCategoryIidentificationaregiveninSection3.2alongwithalistofsystems,components,andequipmentthataresoidentified.Allsystems,componentsandequipmentimportanttoplantsafetyaredesignedtowithstandpotentialearthquakesdefinedasfollows.TheSSEisanearthquakebaseduponanevaluationofthemaximumearthquakepotentialconsideringtheregionalandlocalgeology,seismology,-andspecificcharacteristicsoflocalsubsurfacematerial.ThisearthquakeproducesthemaximumvibratorygroundmotionforwhichCategoryIsystemsandcomponentsaredesignedtoremainfunctional.Thesesystemsandcomponentsarethosenecessarytoensure:1.TheintegrityoftheRCPB.2.Thecapabilitytoshutdownthereactorandmaintainitinasafeshutdowncondition.3~Thecapabilitytopreventormitigatetheconsequencesofaccidentsthatcouldresultinpotentialoffsiteexposurescomparabletotheguidelinesexposuresof10CFR100.TheOBEistheearthquakewhich,consideringtheregionalandlocalgeology,seismology,andspecificcharacteristicsoflocalsubsurfacematerial,couldreasonablybeexpectedtoaffecttheplantsiteduringtheoperatinglifeoftheplant.Thisearthquakeproducesthevibratorygroundmotionforwhichthosefeaturesofthenuclearpowerplantnecessaryforcontinuedoperationwithoutunduerisktothehealthandsafetyofthepublicaredesignedtoremainfunctional.3.7B.1SeismicInput3.7B.1.1DesignResponseSpectraSeeSection3.7A.1.1.3.7B.1.2DesignTimeHistorySeeSection3.7A.1.2.USARRevision83'B-1November1995 NineMilePointUnit2FSAR3.7B.1.3CriticalDampingValuesThedampingfactorsindicatedinTable3.7B-1areusedintheresponseanalysisofvarioussystems,components,andequipment,andinpreparationoffloorresponsespectrausedasforcinginputsforpipingandequipmentanalysisortesting.ThesefactorsareincompliancewithRG1.61.3.7B.1.4SupportingMediaforCategoryIStructuresSeeSection3.7A.1.4.3.7B.2SeismicSystemAnalysis3.7B.2.1SeismicAnalysisMethodsAnalysisofCategoryIGE-suppliedsystemsandcomponentsisaccomplished,whereapplicable,usingtheresponsespectrumortimehistoryapproach.Bothutilizethenaturalperiod,modeshapes,andappropriatedampingfactorsoftheparticularsystem.CertainpiecesofequipmenthavingveryhighnaturalfrequenciesmaybeanalyzedstaticallyifthefundamentalfrequencyofthecomponentisgreaterthantheZPAfrequencyoftheexcitation.Insomecases,dynamictestingofequipmentmaybeusedforseismicqualification.lThetimehistoryanalysesinvolvethesolutionoftheequationsofdynamicequilibrium(Section3.7B.2.1.1)bymeansofthemethodsdiscussedinSection3.7B.2.1.2.Inthiscase,thedurationofmotionisofsufficientlengthtoensurethatthemaximumvaluesofresponsehavebeenobtained.Aresponsespectrumanalysisinvolvesthesolutionoftheequationsofmotion(Section3.7B.2.1.1)bythemethoddiscussedinSection3.7B.2.1.3.Thetotalseismicstructuralresponsewillbepredictedbycombiningtheresponsecalculatedfromthetwohorizontalandtheoneverticalanalyses.Whentheresponsespectrumisused,themethodsforcombiningtheloadsfromthethreeanalyseswillbebasedonthemethoddescribedinSection3.7B.3.6.3.7B.2.1.1TheEquationsofDynamicEquilibriumAssumingvelocity-proportionaldamping,thedynamicequilibriumequationsforalumpedmass,distributedstiffnesssystemareexpressedinmatrixformas:[M][6(t)]+[C][u(t)]+[K][u(t)]u,(t)=u(t)+u,(t)[M][u(t)]+[C][~(t)]+[K][(t)]=[P(t)](3.7B-1)(3.7B-2)(3.7B-3)USARRevision83.7B-2November1995 NineMilePointUnit2FSARWhere:[M]=Lumpedmassmatrix(nxn)[Q(t)]=Time-dependentaccelerationvector(1xn)ofnonsupportpointsrelativetothebasesupport[C]=Dampingmatrix(nxn)[6(t)]=Time-dependentvelocityvector(1xn)ofnonsupportpointsrelativetothebasesupport[K]=Stiffnessmatrix(nxn)[u(t)]=Time-dependentdisplacementvector(1xn)ofnonsupportpointsrelativetothebasesupport[g(t)]=[u(t)+u,(t)](3.7B-2)[P(t)]=Time-dependentinertialforcevector(-[M][Q,(t)])actingatnonsupportpoints(1xn)Themannerinwhichadistributedmass,distributedstiffnesssystemisidealizedintoalumpedmassdistributedstiffnesssystemrepresentationoftheNSSScomponentisshownonFigure3.7B-1,alongwithaschematicrepresentationofrelativeacceleration[Q(t)],supportacceleration[Q,(t)],andtotalacceleration[Q,(t)].3.7B.2.1.2SolutionoftheEquationsofMotionbyModeSuperpositionThetechniqueusedforthesolutionoftheequationsofmotionisthemethodofmodesuperpositioninwhichtheequationsofmotionaredecoupledbytheeigentransform.Thesetofhomogeneousequationsrepresentedbytheundampedfreevibrationofthesystemis:[M][Q(t)]+[K][u(t)]=[0](3.7B-4)Sincethefreeoscillationsareassumedtobeharmonic,thedisplacementvector[u(t)]canbewritten:fu(t)]=[~]e(3.7B-5)Where:[0]=Columnmatrixoftheamplitudeofdisplacements[u]~=Circularfrequencyofoscillationt=Timei=4-1USARRevision83'B-3November1995 NineMilePointUnit2FSARSubstitutingEquation3.7B-5anditsderivativesinEquation3.7B-4andnotingthate~isunequaltozeroforallvaluesof~tyields:(3.7B-6)Equation3.7B-6isthecharacteristicequationfortheclassicaleigenvalueprobleminwhichtheeigenvaluesarethefrequenciesofvibrationsco;,andtheeigenvectorsarethemodeshapes,[P,],(i=1,2,....,n).Foreachfrequencyauthereisacorrespondingsolutionvector[p].Itcanbeshownthattheeigenvectorsareorthogonalwithrespecttotheweightedstiffnessmatrix[K]inthen-dimensionalvectorspace.Theeigenvectorsarealsoorthogonalwithrespecttotheweightedmassmatrix[M].Theorthogonalityoftheeigenvectorsisusedtoeffectacoordinatetransformationtothegeneralizedcoordinatesysteminwhichthegoverningequationsofmotionaredecoupled.Thus,theproblembecomesoneofsolvingnindependentdifferentialequationsratherthannsimultaneousdifferentialequations,andsincethesystemislinear,theprincipleofsuperpositionholdsandthetotalresponseofthesystemoscillatingsimultaneouslyinnmodesisdeterminedbydirectadditionoftheresponsesintheindividualmodes.3.7B.2.1.3AnalysisbyResponseSpectrumMethodTheresponsespectrummethodisbasedonthefactthatthemodalresponsescanbeexpressedintermsofasetofconvolutionintegralsthatsatisfythegoverningdifferentialequations.Theadvantageofthisformofsolutionisthatforagivengroundmotiontheonlyvariablesundertheintegralaredampingfactorandfrequency.Thus,foraspecifieddampingfactor,itispossibletoconstructacurvethatgivesamaximumvalueoftheintegralasafunctionoffrequency.Thiscurveiscalledaresponsespectrumfortheparticularinputmotionandthespecifieddampingfactor.Theintegralhasunitsofvelocity;consequently,themaximumoftheintegraliscalledthespectralvelocity.Usingthecalculatednaturalfrequenciesofvibrationofthesystem,themaximumvaluesofthemodalresponsesaredetermineddirectlyfromtheappropriateresponsespectrum.ThemodalmaximaarethencombinedasdiscussedinSection3.7B.3.7.Whentheequipmentissupportedatmorethantwopointslocatedatdifferentelevationsinthebuilding,responsespectrumanalysisisperformedusingtheenveloperesponsespectrumofallattachmentpoints.Insomecases,theworstsinglefloorresponsespectrumselectedfromasetoffloorresponsespectraobtainedatvariousfloorsmaybeappliedidenticallytoallUSARRevision83.7B-4November1995 NineMilePointUnit2FSARfloorsprovidedthereisnosignificantshiftinfrequenciesofthespectrapeaks.Alternatively,multiplesupportexcitationanalysismethodsmaybeusedwhereindividualaccelerationtime-historiesorresponsespectraareappliedatalltheequipmentattachmentpoints.3.7B.2.1.4MultisupportExcitationAnalysisofSystems,Components,andEquipmentAnalyticalproceduresforobtainingforceanddisplacementresponsesengenderedbytime-dependent,basesupportexcitationarediscussedinprecedingsections.Inamultisupportedsystem,therelativemotionamongtheindividualmultisupportpointsgivesrisetotime-varyingdisplacementsatthenonsupportpoints.Thegoverningequationsofmotionofamultisupportedsystem,component,orequipmentundergoingindividualmultisupportexcitationsmaybeexpressedinthefollowingmatrixform:[M](0)+[C](6)+[K](u)=(F)(3.7B-7)Where:(u)=(u(t))=ThecorrespondingdynamicmodelnodaldisplacementvectorofabsolutedisplacementsThegeneralcaseisconsideredinwhichkofthetotalndegrees-of-freedomcorrespondstotheindividualmultisupportpointswhichundergoknowntime-historymotions.Thenodaldisplacementvectorofabsolutedisplacementscanbepartitionedandwrittenas:U~U~+U~(U)=U~Ug(3.7B-8)Where:(u,)(u,)Absolutedisplacementvectoroftheactive(unsupported)degrees-of-freedomKnownabsolutedisplacementvectorcorrespondingtothemultisupporteddegrees-of-freedomThevector(u,)inEquation3.7B-8hasbeenfurtherseparatedintoadynamicpartandapseudo-staticpartwhere:USARRevision83'B-5November1995 NineMilePointUnit2FSAR(u4,}=Dynamicpartof(u,}(u',}=Pseudo-staticpartof(u,}Multisupportexcitationmayrequiretheutilizationofallmodeswhichspanthe{u,}spaceofactive(unsupported)degrees-of-freedominthemodalsuperpositioninordertoobtainreliablesolutionsofEquation3.7B-7.SubstitutionEquation3.7B-8enablesthecircumventingofthatverycostlyrequirement.Onlythedynamicpart(u~,}isobtainedbymodalsuperpositionwhichdoesnotrequireallmodes.Thepseudo-staticpart(u',}isobtainedfromtheknownmultisupportexcitation.ThepartitionedequationsofmotionareobtainedbysubstitutingEquation3.7B-8intoEquation3.7B-7toyield:I~IC,)C,u,+u,'HWhere:(3.7B-9)(u.}Dynamicpart(asdefinedbyEquation3.7B-8)oftheabsolutedisplacementvectoroftheactive(unsupported)degrees-of-freedom(u',}Pseudo-staticpart(asdefinedbyEquation3.7B-8)oftheabsolutedisplacementvectoroftheactive(unsupported)degrees-of-freedom[M,]and[M,][C]and[K]Lumpeddiagonalmassmatricesassociatedwiththeactivedegrees-of-freedomandthemultisupportpoints,respectivelyDampingmatrixandelasticstiffnessmatrix,respectively,relatingtheforcesdevelopedintheactivedegrees-of-freedomtothemotionoftheactivedegrees-of-freedom[C]and[K]Supportforcesduetounitvelocitiesanddisplacements,respectively,ofthemultisupportpointsUSARRevision83.7B-6November1995 NineMilePointUnit2FSAR[C]and[K](F.)(F,)Dampingandstiffnessmatricesdenotingthecouplingforcesdevelopedintheactivedegrees-of-freedomduetothemotionofthesupports,orviceversaPrescribedtime-dependentappliedloadvectorcorrespondingtotheactivedegrees-of-freedomReactionforcevectorcorrespondingtothesystemmultisupportpointsTotaldifferentiationwithrespecttotimewhenappearingoveratimevariableTheprocedureutilizedtoconstructthedampingmatrixisdiscussedinSection3.7B.2.15.Themassmatrixandelasticstiffnessmatrixareformulatedbystandardprocedures.Sincethecomponentsof(u,),henceof(u)and(G,),areknownfunctionsoftime,onlythefirstpartitionedportionofEquation3.7B-9isofinterest.[M](Q}+[M][Q)+[C]{Q)+[C](u}+[C](UJ+[K](ul+[K](u)+[K](UJ=(F)(3.7B-10)Thepseudo-staticdisplacementvectoriswrittenintermsofthemultisupportdisplacementvectorbytaking:Therefore:[K](u',)+[K](G,)=(0)(3.7B-11)(u',)=-[K]'[K](u,}ItfollowsfromEquation3.7B-11that:(3.7B-12)[C](u*,}+[C](u,}=(0)(3.7B-13)ThepartitionedportionoftheequationisreducedtoitsfinalformbysubstitutingEquations3.7B-11,3.7B-12,and3.7B-13intoEquation3.7B-10toyield:[M,](Q4,)+[C](6,)+[K](u~,)=(F,)+[M,][K][K](u,)(3.7B-14)ThesolutionintimeofEquation3.7B-14for(u',)isreadilyobtainedbythestandardnormalmodesolutionmethodology.Once(u~,)isobtained,thetotalsolutionfortheabsolutedisplacementvector(u,},correspondingtotheactiveUSARRevision83.7B-7November1995 NineMilePointUnit2FSARdegrees-of-freedom,isgivenbysubstituting(u4,)fromEquation3.7B-14and(u',)fromEquation3.7B-12intoEquation3.7B-8.Afterobtainingtheabsolutedisplacementvectorresponseoftheactivedegrees-of-freedom,(u,},thesecondpartitionedportionofEquation3.7B-9canbeusedtocalculatethereactionforcevector(F,)correspondingtothemultisupportdegrees-of-freedomsi+ed~(F.)=[M,](<.)+[C](<.)+[C](u,}+[K](u,)+[K](u,)(3.7B-15)Notethat(F,)isthetotalexternalforcevectorappliedtothemultisupportdegrees-of-freedomrequiredtoproducethegivenmultisupportexcitation(0,).Theinteractionforcevector(F,)correspondingtothereactionoftheactivedegrees-of-freedomportionofthedynamicmodelonthemultisupportpointsisgivenby:(F,)=[C~](6,)+[K~](u,)(3.7B-16)Theinteractionforcevector(F,)canalsobeexpressedintermsofthemultisupportexcitationinputmotion(G,}bysubstitutingEquations3.7B-12and3.7B-8intoEquation3.7B-16toyield:(F,)=[C](6,)+[K](u,)-[C][K]'K](u,)[K][K]>[K](G,)(3.7B-17)3.7B.2.1.5DynamicAnalysisofCategoryISystems,Components,andEquipmentTime-historyandresponsespectrumtechniquesareusedasapplicableforthedynamicanalysisofCategoryIsystems,components,andequipmentthataresensitivetodynamicseismicevents.DnamiasisoPiSstemsEachpipelineisidealizedasamathematicalmodelconsistingoflumpedmassesconnectedbyelasticmembers.Thestiffnessmatrixforthepipingsystemisdeterminedusingtheelasticpropertiesofthepipe.Thisincludestheeffectsoftorsion,bending,shear,andaxialdeformationsaswellaschangeinstiffnessduetocurvedmembers.Nextthemodeshapesandtheundampednaturalfrequenciesareobtained.Whenthepipingsystemisanchoredandsupportedatpointswithdifferentexcitations,theresponsespectrumanalysisisperformedusingtheenveloperesponsespectrumofallattachmentpoints.Alternately,themultipleexcitationanalysesmaybeusedwhereaccelerationtime-historiesorresponsespectraareappliedtopipingsystemattachmentpoints.USARRevision83.7B-8November1995 NineMilePointUnit2FSARTherelativedisplacementbetweenanchorsisdeterminedfromthedynamicanalysisofthestructures.Theresultsoftherelativeanchorpointdisplacementareusedforastaticanalysistodeterminetheadditionalstressesduetorelativeanchorpointdisplacements.ssu'tEachcomponentofequipmentisidealizedasamathematicalmodelconsistingoflumpedmassesconnectedbyelasticmembersorsprings.Whentheequipmentissupportedatmorethantwopointslocatedatdifferentelevationsinthebuilding,theresponsespectrumanalysisisperformedusingtheenveloperesponsespectrumofallattachmentpoints.Alternatively,themultipleexcitationanalysismethodsmaybeusedwhereindividualaccelerationtime-historiesorresponsespectraareappliedateachoftheequipmentattachmentpoints.Therelativedisplacementbetweensupportsisdeterminedfromthedynamicanalysisofthestructure.Therelativesupportpointdisplacementsareusedforastaticanalysistodeterminethesecondarystressesduetosupportdisplacements.Furtherdetailsaregivenbelow.e's'cetececemonetsTheprocedureforconsideringdifferentialdisplacementsforequipmentanchoredandsupportedatpointswithdifferentinputmotionisasfollows:Therelativedisplacementsbetweenthesupportingpointinducesadditionalstressesintheequipmentsupportedatthesepoints.Thesestressescanbeevaluatedbyperformingastaticanalysiswhereeachofthesupportingpointsisdisplacedaprescribedamount.Thetime-historyofdisplacementateachsupportingpointisreadilyobtainedfromthecorrespondingmultisupportaccelerationtime-historywhichisprovidedasinputforthedynamicanalysisofthetotalcomponent.Thesedisplacementsareusedtocalculatestressesbydeterminingthepeaknodalresponses.Znthestaticcalculationofthestressesduetorelativedisplacementsintheresponsespectrummethod,themaximumvalueofthenodaldisplacementisused.Therefore,themathematicalmodeloftheequipmentissubjectedtoamaximumdisplacementvectorofitssupportingpointsobtainedfromthenodaldisplacements.Thisprocedureisrepeatedforthesignificantmodes(modescontributingmosttothetotaldisplacementresponseatthesupportingpoint)ofthecomponent.ThetotalstressesduetorelativedisplacementsareobtainedbycombiningthemodalresultsusingtheSRSSmethod.Sincethemaximumdisplacementsfordifferentmodesdonotoccuratthesametime,theSRSSmethodisareasonablemethod.WhenacomponentiscoveredbytheASMEBoilerandPressureVesselCode,thestressesduetorelativedisplacementasobtainedabovearetreatedassecondarystresses.USARRevision83.7B-9November1995 NineMilePointUnit2FSAR3.7B.2.1.6SeismicQualificationbyTestingForcertainCategoryIequipmentandcomponentswheredynamictestingisnecessarytoensurefunctionalintegrity,testperformancedataandresultsreflectthefollowing:Performancedataofequipmentwhich,underthespecifiedconditions,hasbeensubjectedtodynamicloadsequaltoorgreaterthanthosetobeexperiencedunderthespecifiedseismicin-serviceconditions.2.Testdatafrompreviouslytestedcomparableequipmentwhich,undersimilarconditions,hasbeensubjectedtodynamicloadsequaltoorgreaterthanthosespecified.3.ActualtestingofequipmentinaccordancewithoneofthemethodsdescribedinSections3.9B.2and3.10B.3.7B.2.2NaturalFrequenciesandResponseLoadsSeeSection3.7A.2.2.3.7B.2.3ProcedureUsedforModeling3.7B.2.3.1ModelingTechniquesforCategoryISystems,Components,andEquipmentAnimportantstepintheseismicanalysisofCategoryIsystems,components,orequipmentistheprocedureusedformodeling.Thetechniquescurrentlybeingusedformodelingarerepresentedbylumpedmassesandasetofspringdashpotsidealizingboththeinertialandstiffnesspropertiesofthesystem.Thedetailsofthemathematicalmodelsaredeterminedbythecomplexityoftheactualsystemandtheinformationrequiredfromtheanalysis.3.7B.2.3.2ModelingofReactorPressureVesselandInternalsTheseismicloadsontheRPVandreactorinternalsarebasedonadynamicanalysisofthereactorbuildingwiththeappropriateforcingfunctionsuppliedatgroundlevel.ThemathematicalmodeloftheRPVandinternalsisshownonFigure3.7B-2.TheRPVandinternalsmathematicalmodelconsistsoflumpedmassesconnectedbylinearelasticbeamelementmembers.Usingtheelasticpropertiesofthestructuralcomponents,thestiffnesspropertiesofthemodelaredeterminedandtheeffectsofbendingshear,torsion,andaxialloadingareincluded.Masspointsarelocatedatallpointsofcriticalinterestsuchasanchors,supports,andpointsofdiscontinuity.Inaddition,masspointsarechosensothatthemassdistributioninvariouszonesisasuniformaspracticableandthefullrangeoffrequencyofresponseofinterestisadequatelyrepresented.Further,inordertofacilitatehydrodynamicmasscalculations,USARRevision83'B-10November1995 NineMilePointUnit2FSARseveralmasspoints(fuel,shroud,vessel)areselectedatthesameelevation.ThevariouslengthsofCRDhousingsaregroupedintothetworepresentativelengthsshownonFigure3.7B-2.Theselengthsrepresentthelongestandshortesthousingsinordertoadequatelyrepresentthefullrangeoffrequencyresponseofthehousings.ThehighfundamentalfrequenciesoftheCRDhousingsresultinverysmallseismicloads.Furthermore,thesmallfrequencydifferencesbetweenthevarioushousingsduetothelengthdifferencesresultinnegligibledifferencesindynamicresponse.Hence,themodelingofintermediatelengthmembersbecomesunnecessary.Notincludedinthemathematicalmodelarethestiffnessoflightcomponents,suchasjetpumps,in-coreguidetubesandhousings,spargers,andtheirsupplyheaders.Thisisdonetoreducethecomplexityofthedynamicmodelandisjustifiedbecausedynamicinteractionisnotsignificant.Fortheseismicresponsesofthesecomponents,floorresponsespectrageneratedfromthesystemanalysisareused.Thepresenceofthefluidandotherstructuralcomponents(e.g.,fuelwithintheRPV)introducesadynamiccouplingeffect.DynamiceffectsofwaterenclosedbytheRPVareaccountedforbyintroductionofahydrodynamicmassmatrixthatwillservetolinktheaccelerationtermsoftheequationsofmotionofpointsatthesameelevationinconcentriccylinderswithafluidentrappedintheannulus.ThedetailsofthehydrodynamicmassderivationaregiveninSeismicAnalysisoftheBoilingWaterReactor+.TheseismicmodeloftheRPVandinternalshas6degrees-of-freedomforeachmasspointconsideredintheanalysis.Theshroudsupportplateinitsownplaneisextremelystiffandthereforeismodeledasarigidlinkinthetranslationaldirection.Theshroudsupportlegsandlocalflexibilitiesofthevesselandshroudcontributetotherotationalflexibilitiesandaremodeledasanequivalenttorsionalspring.3.7B.2.4Soil-StructureInteractionSeeSection3.7A.2.4.3.7B.2.5DevelopmentofFloorResponseSpectraSeeSection3.7A.2.5.3.7B.2.6ThreeComponentsofEarthquakeMotion(NSSS)DetailsarethesameasthosegiveninSection3.7B.3.6.3.7B.2.7CombinationofModalResponses(NSSS)AllthemodalresponsesarecombinedasdescribedinSection3'B.3SARRevision83.7B-11November1995 NineMilePointUnit2FSAR3.7B.2.8InteractionofNon-CategoryIStructureswithCategoryIStructuresSeeSection3.7A.2.8.3.7B.2.9EffectsofParameterVariationsonFloorResponseSpectraSeeSection3.7A.2.9.3.7B.2.10UseofConstantVerticalStaticFactors(NSSS)ConstantverticalstaticfactorsarenotusedforsystemssuchastheRPV,internals,andlargepiping.SeeSection3.7B.3.10forsubsystemsandcomponents.3.7B.2.11MethodUsedtoAccountforTorsionalEffects(NSSS)TheRPVisanaxisymmetricmodelwithnobuilt-ineccentricity.3.7B.2.12ComparisonofResponses(NSSS)Eitherthetime-historymethodortheresponsespectrumapproachmaybeusedfortheseismicanalysisofNSSScomponents.Generally,theresponsescomputedbybothmethodsarecomparableinmagnitude,withtheloadsdeterminedbytheresponsespectrummethodbeingsomewhatmoreconservative.Asbothoftheseapproachesareacceptable,additionalcomparisonofresultsisunnecessary.3.7B.2.13MethodsforSeismicAnalysisofDamsSeeSection3.7A.2.13.3.7B.2.14DeterminationofCategoryIStructureOverturningMomentsSeeSection3.7A.2.14.3.7B.2.15AnalysisProcedureforDampingInalineardynamicanalysistheprocedureutilizedtoproperlyaccountfordampingindifferentelementsofacoupledsystemmodelisasfollows:2~Thestructuralpercentcriticaldampingofthevariousstructuralelementsofthemodelarefirstspecified.Eachvalueisreferredtoasthedampingratio(Cj)ofaparticularelementthatcontributestothecompletestiffnessofthesystem.Aneigenvalueanalysisofthelinearsystemmodelisperformed.ThisresultsintheeigenvectormatricesUSARRevision83.7B-12November1995 NineMilePointUnit2FSAR(qb;)thatarenormalizedandsatisfytheorthogonalityconditions:Where:(3.7B-18)[K]=Stiffnessmatrix['~;]Diagonalmatrixofcircularnaturalfrequencyofmodei[QY]=Transposeofg,whichisacolumnvectorofqhcorrespondingtothemodeshapeofmodeiThematrixQcontainsalltranslationalandrotationalcoordinates.3~Usingthestrainenergyoftheindividualcomponentsasaweightingfunction,thefollowingequationisusedtoobtainasuitabledampingratio(P;)formodei:(3.7B-19)Where:NTotalnumberofstructuralelementsKqComponentsofmodeieigenvectorcorrespondingtothebeamelementjModaldampingcoefficientformodeiStiffnesscontributionofelementjCircularnaturalfrequencyofmodeiTransposeofpdefinedabovePercentcriticaldampingassociatedwithelementUSARRevision83.7B-13November1995 NineMilePointUnit2FSAR3.7B.3SeismicSubsystemAnalysis3.7B.3.1SeismicAnalysisMethodsTheseismicsystemanalysismethodsdescribedinSection3.7B.2.1areapplicabletotheCategoryIsubsystems,components,andequipment.AdescriptionisgivenofthefollowingmethodsbywhichCategoryIsubsystemsandcomponentsarequalifiedtoensurethefunctionalintegrityofthespecificoperatingrequirementsthatcharacterizetheirCategoryIdesignations.Ingeneral,oneofthefollowingfivemethodsofseismicallyqualifyingtheequipmentischosenbasedonthecharacteristicsandcomplexitiesofthesubsystem:1.Dynamicanalysis.2.Testingprocedures.3.Equivalentstaticloadmethodofanalysis.4.Combinationof1and2,or5.Combinationof2and3.TheequivalentstaticloadmethodofsubsystemanalysisisdescribedinSection3.7B.3.5.Appropriatedesignresponsespectra(OBEandSSE)arefurnishedtothemanufactureroftheequipmentforseismicqualificationpurposes.Additionalinformationsuchasinputtime-historyisalsosuppliedonlywhennecessary.WhenanalysisisusedtoqualifyCategoryIsubsystemsandcomponents,theanalyticaltechniquesmustconservativelyaccountforthedynamicnatureofthesubsystemsorcomponents.BoththeSSEandOBE,withtheirdifferentdampingvalues,areconsideredwhenthedynamicanalysisisperformed.ThegeneralapproachemployedinthedynamicanalysisofCategoryIequipmentandcomponentdesignisbasedontheresponsespectrumtechnique.Thetime-historytechniquedescribedinSection3.7B.2.1.1generatestime-historiesatvarioussupportelevationsforuseintheanalysisofsubsystemsandequipment.Thestructuralresponsespectrumcurvesaresubsequentlygeneratedfromthetime-historyaccelerations.Ateachlevelofthestructurewherevitalcomponentsarelocated,threeorthogonalcomponentsoffloorresponsespectra(twohorizontalandonevertical)aredeveloped.Theresponsespectraarepeakbroadened+15percent.Forvibratingsystemsandtheirsupports,multidegree-of-freedommodelsareusedinaccordancewiththelumped-parametermodelingUSARRevision83.7B-14November1995 NineMilePointUnit2FSARtechniquesandnormalmodetheorydescribedinSection3.7B.2.1.1andthereferenceslistedinSection3.7B.5.PipinganalysisisdescribedinSections3.7B.3.3.1and3.7B.2.1.5.WhentestingisusedtoqualifycategoryIsubsystemsandcomponents,alltheloadsnormallyactingontheequipmentaresimulatedduringthetest.Theactualmountingoftheequipmentisalsosimulatedorduplicated.TestsareperformedbysupplyinginputaccelerationstotheshaketabletosuchanextentthatgeneratedTRSenveloptherequiredresponsespectra.Section3.7B.2.1.6discussesqualificationrequirementsforcertainCategoryIequipmentandcomponentswheredynamictestingisnecessarytoensurefunctionalintegrity.ThemethodologyusedtoaccountfortheeffectsofdifferentialsupportmotionofmultisupportedequipmentisdescribedinSubsection3.7B.2.1.5.ThesecondarystressesduetothesupportmotionsarecombinedwiththecorrespondinginertiastressesbytheSRSSmethod.AlsoseeSection3.7A.3.1.3.7B.3.2DeterminationofNumberofEarthquakeCycles3.7B.3.2.1PipingSystemsAtotalof50peakOBEstresscyclesarepostulatedforfatigueevaluation.3.7B.3.2.2OtherEquipmentandComponentsToevaluatethenumberofcyclescausedbyagivenearthquake,atypicalBWRbuilding-reactordynamicmodelwasexcitedbythreedifferentrecordedtime-histories(May18,1940,ElCentroNScomponent,29.4sec;1952,TaftN69'component,30sec;andMarch1957,GoldenGateS804Ecomponent,13.2sec).Themodalresponsewastruncatedsothattheresponseofthreedifferentfrequencybandwidthscouldbestudied:0to10Hz,10to20Hz,and20to50Hz.Thiswasdonetogiveagoodapproximationtothecyclicbehaviorexpectedfromstructureswithdifferentfrequencycontent.Envelopingtheresultsfromthethreeearthquakesandaveragingtheresultsfromseveraldifferentpointsofthedynamicmodel,thecyclicbehaviorasgiveninTable3.7B-2wasformed.Independentofearthquakeorcomponentfrequency,99.5percentofthestressreversalsoccurbelow75percentofthemaximumstresslevel,and95percentofthereversalsliebelow50percentofthemaximumstresslevel.Insummary,thecyclicbehaviornumberoffatiguecyclesofacomponentduringanearthquakeisfoundinthefollowingmanner:USARRevision83.7B-15November1995 NineMilePointUnit2FSAR1.Thefundamentalfrequencyandpeakseismicloadsarefoundbyastandardseismicanalysis(i.e.,fromeigenvalueextractionandaforcedresponseanalysis).2.~ThenumberofcyclesthatthecomponentexperiencesarefoundfromTable3.7B-2accordingtothefrequencyrangewithinwhichthefundamentalfrequencylies.3~Forfatigueevaluation,0.5percentofthesecyclesareconservativelyassumedtobeatthepeakload,4.5percentatorabovethree-quarterpeak.Theremainderofthecycleshavenegligiblecontributiontofatigueusage.TheSSEhasthehighestlevelofresponse.However,theencounterprobabilityoftheSSEissosmallthatitisnotnecessarytopostulatethepossibilityofmorethanoneSSEduringthe40-yrlifeofaplant.FatigueevaluationduetotheSSEisnotnecessarysinceitisafaultedconditionandthusnotrequiredbyASMEBoilerandPressureVesselCode,SectionIII.TheOBEisanupsetconditionand,therefore,mustbeincludedinfatigueevaluationsaccordingtoASMEBoilerandPressureVesselCode,SectionIII.Investigationofseismichistoriesformanyplantsshowsthatduringa40-yrlife,itisprobablethatfiveearthquakeswithintensities10percentoftheSSEintensity,andoneearthquakewithapproximately20percentoftheproposedSSEintensity,willoccur.Tocoverthecombinedeffectsoftheseearthquakesandthecumulativeeffectsofevenlesserearthquakes,10peakOBEstresscyclesarepostulatedforfatigueevaluation.3.7B.3.3ProcedureUsedforModelingAlsoseeSection3.7A.3.3.3.7B.3.3.1ModelingofPipingSystems~S~myTopredictthedynamicresponseofapipingsystemtothespecifiedforcingfunction,thedynamicmodelmustadequatelyaccountforallsignificantmodes.CarefulselectionmustbemadeoftheproperresponsespectrumcurvesandproperlocationofanchorsinordertoseparateCategoryIfromnon-CategoryIpipingsystems.eecto'sWhenperformingadynamicanalysis,apipingsystemisidealizedasamathematicalmodelconsistingoflumpedmassesconnectedbyweightlesselasticmembers.Theelasticmembersaregiventhepropertiesofthepipingsystembeinganalyzed.ThemasspointsarecarefullylocatedtoadequatelyrepresentthedynamicUSARRevision83.7B-16November1995 NineMilePointUnit2FSARpropertiesofthepipingsystem.Amasspointislocatedatthebeginningandendofeveryelboworvalve,attheextendedvalveoperator,andattheintersectionofeverytee.Onstraightruns,masspointsarelocatedatspacingsnogreaterthanthespanlengthcorrespondingto33Hz.Amasspointislocatedateveryextendedmasstoaccountfortorsionaleffectsonthepipingsystem.Inaddition,theincreasedstiffnessandmassofvalvesareconsideredinthemodelingofapipingsystem.SelecSectuInselectingthespectrumcurvestobeusedfordynamicanalysisofaparticularpipingsystem,curvesarechosenthatmostcloselydescribetheaccelerationsexistingattheendpointsandrestraintsofthesystem.TheprocedureemployedfordecouplingtheNSSSrecirculationpipingsystemswhenestablishingtheanalyticalmodelstoperformseismicanalysisareasfollows:1.Thesmallbranchlines(6-indiameterandless)aredecoupledfromtherecirculationpipingsystemsandanalyzedseparatelyexceptforthebypasslinesaround2RHS*AOV39A,B,whicharenotdecoupledfromtherecirculationpipinganalysis.2~Thestiffnessandmassofalltheanchorsandtheirsupportingsteelarelargeenoughtoeffectivelydecouplethepipingoneithersideoftheanchorforanalyticandcodejurisdictionalboundarypurposes.TheRPVisverystiffandmassivecomparedtothepipingsystemand,thus,duringnormaloperatingconditions,theRPVisalsoassumedtoactasananchor.Penetrationassemblies(fluedheadfittings)arealsoverystiffcomparedtothepipingsystemandareassumedtoactasanchors.Thestiffnessmatrixattheattachmentlocationoftheprocesspipe(i.e.,RCIC,RHRsupply,orRHRreturn)headfittingissufficientlyhightodecouplethepenetrationassemblyfromtheprocesspipe.GEanalysisindicatesthatasatisfactoryminimumstiffnessforthisattachmentpointisequaltothestiffnessinbendingandtorsionofacantileveredpipesectionofthesamesizeastheprocesspipeandequalinlengthtothreetimestheprocesspipeouterdiameter.Forapipingsystemsupportedatmorethantwopointslocatedatdifferentelevationsinthebuilding,theresponsespectrumanalysisisperformedusingtheenveloperesponsespectrumofallattachmentpoints.Theworstsinglefloorresponsespectrumselectedfromasetoffloorresponsespectraobtainedatvariousfloorsmaybeappliedidenticallytoallfloorsprovideditenvelopstheotherfloorresponsespectraintheset.Alternatively,themultiplesupportexcitationanalysismethodsmaybeusedwhereaccelerationtime-historiesorresponsespectraareappliedtoallthepipingattachmentpoints.USARRevision83.7B-17November1995 NineMilePointUnit,2FSAR3.7B.3.3.2ModelingEquipmentFordynamicanalysis,CategoryIequipmentisrepresentedbylumpedmasssystemsthatconsistofdiscretemassesconnectedbyweightlesssprings.Thecriteriausedtolumpmassesare:1~2~Thenumberofmodesofadynamicsystemiscontrolledbythenumberofmassesused.Therefore,thenumberofmassesischosensothatallsignificantmodesareincluded.ThemodesareconsideredsignificantifthecorrespondingnaturalfrequenciesarelessthantheZPAfrequencyoftheexcitation,andthestressescalculatedfromthesemodesaregreaterthan10percentofthetotalstressesobtainedfromlowermodes.Thenumberofdegrees-of-freedomaretakenmorethantwicethenumberofmodeswithfrequencieslessthan33Hz.Massislumpedatanypointwhereasignificantconcentratedweightislocated.Examplesarethemotorintheanalysisofthepumpmotorstandandtheimpellerintheanalysisofthepumpshaft.3.Iftheequipmenthasafree-endoverhangspanwithflexibilitysignificantcomparedtothecenterspan,amassislumpedattheoverhangspan.4~Whenamassislumpedbetweentwosupports,itislocatedatapointwherethemaximumdisplacementisexpectedtooccur.Thistendstolowerthenaturalfrequenciesoftheequipment,whichresultsinaconservativeanalysisbecausetheequipmentfrequenciesareinthehigherspectralrangeoftheresponsespectra.Similarly,inthecaseofliveloads(mobile)andavariablesupportstiffness,thelocationoftheloadandthemagnitudeofsupportstiffnessarechosensoastoyieldthelowestfrequencycontentforthesystem.Thisensuresconservativedynamicloadssincetheequipmentfrequenciesarealwayshigherthanthefrequenciesatwhichthespectralpeaksoccur.Ifnot,themodelisadjustedtogivemoreconservativeresults.3.7B.3.3.3FieldLocationofSupportsandRestraintsThefinallocationofseismicsupportsandrestraintsforCategoryIpiping,pipingsystemcomponents,andequipment,includingtheplacementofsnubbers,ischeckedagainstthedrawingsandinstructionsissuedbytheEngineer.Anadditionalexaminationofthesesupportsandrestrainingdevicesismadetoassurethattheirlocationandcharacteristicsareconsistentwiththedynamicandstaticanalysesofthesystem.Thefinalanalysesoftheas-builtsystemsareperformedasnecessary,andthefinalcertifiedas-builtdesignreportsareissued.USARRevision83.7B-18November1995 NineMilePointUnit2FSAR3.7B.3.4BasisofSelectionofFrequenciesAllfrequenciesintherangeof0.25to33Hzareconsideredintheanalysisandtestingofsystems,components,andequipment.Thesefrequenciesareexcitedundertheseismicexcitation.Ifthefundamentalfrequencyofacomponentisgreaterthanorequalto33Hz,itistreatedasseismicallyrigidandanalyzedaccordingly.Frequencieslessthan0.25Hzarenotconsideredastheyrepresentveryflexiblestructuresandarenotencounteredinthisplant.Thefrequencyrangebetween0.25and33Hzcoverstherangeofthebroadbandresponsespectrumusedinthedesign.Thenumberofmodesusedinthedynamicanalysisofpipingdependsuponthenumberofmasspoints,dynamicdegrees-of-freedom,andcutofffrequency.Thecutofffrequenciesusedfordifferentdynamicloadsareasfollows:ForSRVandLOCAloads,thecutofffrequencyisdeterminedbyevaluatingtheloadingandstructuralcharacteristicssothatthedynamicresponsesofinterestarenotsignificantlyaffectedbytheomissionofmodeswithfrequencieshigherthanthecutoffvalue.Toensurethatconsideredmodesincludeatleast90percentoftheresponse(incompliancewithNUREG-0800,Criterion3.7.2.II.1.a(5)),thefollowingrulesareused:a.Forsystemswithfundamentalfrequencyinthedirectionofexcitationlessthan20Hz,thecutofffrequencyis60Hz.b.Forsystemswithfundamentalfrequencyinthedirectionofexcitationgreaterthan20Hz,thecutofffrequencyis100Hz.2.Ifhydraulictransientsarepostulated,thesystemresponsewillbeobtainedbydirectintegrationoftheequationofmotion,ratherthanmodalintegration.3.7B.3.5UseofEquivalentStaticLoadMethodofAnalysisWhenthenaturalfrequenciesofasystem,component,orequipmentareunknown,itmaybeanalyzedbyapplyinganequivalentstaticcoefficientanalysis.Thisprocedureallowsasimplertechniqueforaddedconservatism.ThestaticaccelerationofacomponentisconservativelyassumedtobethepeakspectralaccelerationoftheRRSwhichenvelopsthemultisupportinputspectra.TheoscillationdampingassociatedwiththeenvelopingRRSmustberepresentativeoftheactualcomponentdamping.USARRevision83'B-19November1995 NineMilePointUnit2FSARTheequivalentstaticaccelerationisthenobtainedbymultiplyingthestaticaccelerationbyastaticcoefficient,Cwhichtakesintoaccounttheeffectsofbothmultifrequencyexcitationandmultimoderesponse.Forverifyingthestructuralintegrityofframe-typecomponentsphysicallysimilartobeamsandcolumns,thestaticcoefficient,Cistakenas1.5.Forequipmenthavingotherthanaframe-typeconfiguration,justificationisprovidedforthestaticcoefficientused.Theequivalentstaticforcesoneachsubcomponentoftheequipmentareobtainedbymultiplyingthesubcomponentmassesbytheequivalentstaticacceleration.Theresultingstaticloadvectorisdistributedovertheequipmentinamannerproportionaltoitsmassdistribution.Thestaticstressanalysisisthenperformedinanormalmanner.3.7B.3.6ThreeComponentsofEarthquakeMotion3.7B.3.6.1ResponseSpectrumMethodThetotalseismicresponseispredictedbycombiningtheresponsecalculatedfromthetwohorizontalandtheverticalexcitations.Whentheresponsespectrummethodisused,themethodsforcombiningtheresponsesduetothethreeorthogonalcomponentsofseismicexcitationareasfollows:R>=PR~~'/a(3.7B-20)Where:Maximum,coaxialseismicresponseofinterest(e.g.,displacement,moment,shear,stress,strain)indirectionsi(duetoearthquakeexcitation)andj(j=1,2,3)Seismicresponseofinterestinidirectionfordesign(e.g.,displacement,moment,shear,stress,strain)obtainedbytheSRSSruletoaccountforthenonsimultaneousoccurrenceoftheR's3.7B.3.6.2Time-HistoryMethodWhenthetime-historymethodofanalysisisused,thetime-historyresponsesfromeachofthethreecomponentsoftheearthquakemotionarecombinedalgebraicallyateachtimestep.Themaximumresponseisobtainedfromthiscombinedtimesolution.Theearthquakemotionsspecifiedinthethreedifferentdirectionsareverifiedtobestatisticallyindependent.USARRevision83.7B-20November1995 NineMilePointUnit2FSAR3.7B.3.7CombinationofModalResponsesTherequirementsofRG1.92aresatisfiedasfollows.Inaresponsespectrummodaldynamicanalysis,ifthemodesarenotcloselyspaced(i.e.;ifthefrequenciesdifferfromeachotherbymorethan10percentofthelowerfrequency),themodalresponsesarecombinedbytheSRSSmethodasdescribedinSection3.7B.3.7.1andRG1.92.Ifsomeorallofthemodesarecloselyspaced,adoublesummethod(Section3.7.3.7.2)isusedtoevaluatethecombinedresponse.Theuseofthetime-historyanalysismethodprecludestheneedtoconsiderclosely-spacedmodes.3.7B.3.7.1SquareRootoftheSumoftheSquaresMethodMathematically,theSRSSmethodisexpressedasfollows:R=P(Rg)~Where:(3.7B-21)R=CombinedresponseR;=Responseduetomodein=Numberofmodesconsideredintheanalysis3.7B.3.7.2DoubleSumMethodThismethod,asdefinedinRG1.92,isexpressedmathematically:k~1a~1Where:(3.7B-22)RepresentativemaximumvalueofaparticularresponseofagivenelementtoagivencomponentofexcitationPeakvalueoftheresponseoftheelementduetomodekn=NumberofsignificantmodesconsideredinthemodalresponsecombinationUSARRevision83.7B-21November1995 NineMilePointUnit2FSARR,=PeakvalueoftheresponseoftheelementattributedtomodesWhere:1+<k~a21(3.7B-23)Inwhich:G>p=6)p[1=Pp]2P>>=Pp+-(3.7B-24)Where:ModalfrequencyinmodekP=Dampingratioinmodekt~=Durationoftheearthquake3.7B.3.8AnalyticalProcedureforPipingTheanalyticalproceduresforpipinganalysisaredescribedinSections3.7B.2.1.5and3.7B.3.3.1.3.7B.3.9MultiplySupportedEquipmentComponentswithDistinctInputsTheprocedureandcriteriaforanalysisaredescribedinSections3.7B.2.1.5and3.7B.3.3.2.3.7B.3.10UseofConstantVerticalStaticFactorsConstantverticalstaticfactorsinanalysisforsubsystemsandcomponentsareusedasdescribedinSection3.7B.3.5.3.7B.3.11TorsionalEffectsofEccentricMassesTorsionaleffectsofeccentricmassesareincludedforCategoryIsubsystems(Section3.7B.3.3.1).USARRevision83.7B-22November1995 NineMilePointUnit2FSAR3.7B.3.12BuriedCategoryIPipingSystemsandTunnelsSeeSection3.7A.3.12.3.7B.3.13InteractionofOtherPipingwithCategoryIPipingWhenother(non-CategoryI)pipingisattachedtoCategoryIpiping,theotherpipingisanalyticallycoupledsufficientlysoasnottosignificantlydegradetheaccuracyoftheanalysisoftheCategoryIpiping.Furthermore,theotherpipingisdesignedtowithstandtheSSEsufficientlytopreventfailureoftheCategoryIpiping.3.7B.3.14SeismicAnalysisforReactorInternalsThemodelingoftheRPVandinternalsisdiscussedinSection3.7B.2.3.2.ThedampingvaluesaregiveninTable3.7B-1.TheseismicmodelisshownonFigure3.7B-2,andasummaryofloadingconditions(includingseismicandhydrodynamic),evaluationcriteria,calculatedmaximumstressesintheselectedlocations,andtheallowablestressesisgiveninTable3.9B-2.3.7B.3.15AnalysisProceduresforDampingAnalysisproceduresfordampingarediscussedinSection3.7B.2'5.3.7B.4SeismicInstrumentationSeeSection3.7A.4.3.7B.5ReferenceLiu,L.K.SeismicAnalysisoftheBoilingWaterReactor,SymposiumonSeismicAnalysisofPressureVesselandPipingComponents,FirstNationalCongressonPressureVesselandPiping,SanFrancisco,,CA,May1971.USARRevision83.7B-23November1995

NineMilePointUnit2FSARTABLE3.7B-1CRITICALDAMPINGRATIOSFORDIFFERENTMATERIALSPercetC'ticalDaminWeldedstructuralassembliesSteelframestructuresEquipmentBoltedorrivetedstructuralassembliesVitalpipingsystemsDiametergreaterthan12inDiameterlessthanorequalto12inReactorpressurevessel,supportskirt,shroud,shroudhead/separatorCRDhousingsandguidetubesFuelassemblyCRDsupportsprings,shroudsupportspring,andstabilizer2'2.02.04.02.01'2'1.06.02.04.04.03'7.03.02.04.02.06.04.0PrimarycontainmentShieldwallPedestal4.04.04.07.07'7.0USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.7B-2NUMBEROFDYNAMICRESPONSECYCLESEXPECTEDDURINGASEISMICEVENTeueTotalnumberofseismiccyclesNo.seismiccycles-0.54cyclesbetween75and1004ofpeakloadsNo.seismiccycles-4.54cyclesbetween50and754ofpeakloads0-11680.87.510-203591.816.220-506433'28.9USARRevision81of1November1995 NineMilePointUnit2FSAR3.8DESIGNOFSEISMICCATEGORYISTRUCTURES3.8.1ConcreteContainmentTheconcretecontainmentstructureisdesignedtohousethereactorvesselandRCPBandispartofthecontainmentsystemwhosefunctionalrequirementistocontrolthereleaseofradioactivity.Themajorcomponentsofthispressuresuppression-typecontainmentsystemaretheprimarycontainmentsteellinerandtheprimarycontainmentconcretestructure.Thissectiondescribesthestructuraldesignconsiderationsfortheprimarycontainment.SincetheoriginaldesignofthiscontainmentprecededtheissuanceofASMESectionIII,Division2,thereinforcedconcreteprimarycontainmentisdesignedandconstructedtotherequirementsoftheAmericanConcreteInstitute,BuildingCodeRequirementsforReinforcedConcreteACI318-71.ExceptforregionsaroundpenetrationsthataredesignedtomeettherequirementsofASMESectionIII,Division2,theprimarycontainmentsteellinerisdesignedfollowingtherequirementsofASMESectionIII,Division1.3.8.1.1DescriptionoftheContainmentTheprimarycontainmentisareinforcedconcretestructurethatconsistsofadrywellchamberlocatedaboveasuppressionchamber,andadrywellfloorwhichseparatesthedrywellchamberfromthesuppressionchamber.Theprimarycontainmentstructureissupportedona10-ftthickreinforcedconcretematwhichalsosupportsthereactorbuilding.Aseriesof24-indiameterdowncomerventpipespenetratesthedrywellfloor.Thedrywellisasteel-linedreinforcedconcretevesselintheshapeofafrustumoftwocones.Itisenclosedatthetopbyadrywellheaddome.Thesteellinerisattachedtotheinsidefaceofthewallandfunctionsprimarilyasaleak-tightmembrane.Theinsidediameterofthedrywellis91ftatthedrywellfloorlevel(el240ft7in)and34ftatthetopoftheprimarycontainment(el326ft10in).Thesuppressionchamberisastainlesscladsteel-linedcylindricalshellwithaninsidediameterof91ft.Itislocateddirectlybelowthedrywellandissupportedona10-ftthickreinforcedconcretematatel175ft.Thesuppressionchambercontainsalargereservoirofwatercalledthesuppressionpool,whichservesasaheatsinktoabsorbenergyreleasedintothesuppressionpoolasaresultofSRVblowdownoraLOCA.Thesuppressionpooliscomposedofaninnerandouterpool,theinnerpoolbeinglocatedinsidethecylindricalreactorpedestalandtheouterpoolbeinglocatedbetweenthepedestaloutsidediameterandtheprimarycontainmentwall.TheinnerandouterUSARRevision83.8-1November1995 NineMilePointUnit2FSARpoolsareconnectedbysixventopeningslocatedinthereactorpedestalwall.Thedrywellfloorisa4-ftthickannularreinforcedconcreteslabseparatingthedrywellfromthesuppressionchamber.Itisanchoredatthereactorsupportpedestalandthecontainmentwall.Itsprimaryfunctionistoseparatethedrywellfromthesuppressionpool.Italsoprovidestheprimarysupportforthedowncomerventlinesandalsosupportsotherpenetrationsandembedments(Section3.8.3).Thetransferofloadsfromthedrywellfloortotheprimarycontainmentconcretewall(Figure3.8-1)ismadethroughthickenedlinersections.TheforceinthereinforcingsteelistransmittedtothelinerbyCadweldsleeveswhichareattached,inline,toeachsideofthethickenedlinerplate(Figure3.8-1).Continuityisthusprovidedtothereinforcingsteelwithoutperforatingthelinerboundary.Theprimarycontainmentwallcontainspenetrationsforprocesspiping,instrumentpiping,andelectricalconductors.Itsupportsfloorbeamseats,andsupportsembedmentsforpiperestraints,pipesupports,conduit,andductsupports.Fiveaccesshatchesandoneairlockpenetratethecontainmentwallandprovideforpersonnelandequipmentegress(Section3.8.1.1.2).OneofthelargerhatchescontainsanadditionalairlockasdescribedinSection3.8.1.1.2.Thecontainmentwallisdesignedtowithstandanticipatedloadswithoutparticipationofthelinerasastructuralcomponent.3.8.1.1.1ReinforcingSteelArrangementThemainreinforcingsteelintheprimarycontainmentwallconsistsofinsideandoutsidelayersofhoopandmeridionalreinforcementanddiagonalreinforcement.Thediagonalreinforcementisplacedintwoorthogonaldirectionsneartheoutsidewallfacetoformahelixwithanangleof45degfromtheverticalaxisoftheshell.Hoopandlongitudinaltensionforcesalongwiththetangentialshearswillberesistedbythehoop,meridionalanddiagonalreinforcingsteel.Toresistthelargeradialshearnearthebaseofthewall,flatsteelbarsinclinedat45degtothehorizontal,andweldedtotheverticalreinforcingsteel,areinstalled(Figure3.8-3).Theweldedflatbarsareterminatedatalevelabovethemat,andsingle-legradialshearreinforcingsteelisplacedasrequiredbytheACI-318code.Supplementaryreinforcingsteel,normaltothefaceofthewall,isprovidedinthelowerportionofthecontainmentstructurewalltoresistsplittingoftheconcreteintheverticalplane.MinimumconcretecoverforallprincipalreinforcingsteeloftheUSARRevision83.8-2November1995 NineMilePointUnit2FSARprimarycontainmentstructureeitherequalsorexceedstherequirementsofACI-318-71.Figures3.8-3and3.8-3ashowtypicaldetailsofreinforcingsteelinthecontainmentwall.Section3.8.1.4describesthereinforcingsteelarrangementathatchopenings,asshownonFigure3.8-4.3.8.1.1.2SteelLinerandPenetrationsteeExceptatvariouspenetrationsandaccessopeningsthroughthewalls,theprimarycontainmentlinerisacontinuoussteelmembrane,backedbyreinforcedconcrete.Thefunctionoftheprimarycontainmentlineristoactasaleak-tightmembranetoprovideabarriertothereleaseoffissionproducts.Generally,thelineris3/8-inthickexceptatdiscontinuitiessuchascorners,penetrations,andbeamseatandpiperestraintattachmentregions,whereitisadequatelythickened.Inthedrywell,thesteellinerplatematerialiscarbonsteel.Inthesuppressionchamberitiscarbonsteelcladwithstainlesssteel,exceptatembedmentsorpenetrationswhicharestainlesssteelthroughout.Theportionoftheprimarycontainmentlinerthatfunctionsasthesuppressionpoolflooris1/4inthickexceptinregionswhereloadtransfersthroughthefloorrequirethatitbethicker.The1/4-inthickfloorlinerisweldedtothewalllinerthroughacornerjunctionembedment.Itisalsoweldedtothereactorpedestalembedmentplates,theSRVT-quencherembedments,andthebridgingbarseamembedmentsthatanchorthemembranetothereinforcedconcretereactorbuildingfloormat.Approximately12inofinsulationconcreteisinstalledoverthefloorlinertoprotectitfromthethermaleffectsoftheDBAandtominimizethecorrespondingloadsontheconcretecontainmentwall.Also,anadditionallinerisprovidedasdescribedbelow.Oter'Ins'dee'CotainmetAnadditionallinerisprovidedovertheinsulationconcretetoserveasawaterproofmembraneforthatconcrete.Thisfloorinsulationlinerisstainlesssteelasisallothersuppressionpoolsteelincontactwithitsatmosphere.Thislineris1/8inthickandisanchoredtotheinsulationconcretethrougharectangulargridofchannelandheadedconcreteanchors,andisanchoredtothe18T-quenchersupports,theprimarycontainmentliner,andthereactorpedestalliner.Itisinstalledaftertheconcreteispoured.Thereactorpedestal(Section3.8.3)isalsolinedwithstainlesssteel.Thislinerservesasaconcreteformduringconstructionandfunctionsasawaterproofmembraneforthepedestalconcreteduringplantoperation.Itisanchoredtotheconcretebyheadedconcreteanchors.USARRevision83.8-3November1995 NineMilePointUnit2FSARThebottomsurfaceofthedrywellfloorisformedwithcorrugatedstainlesssteelandthetopiscoveredwithcarbonsteelliner.Thestainlesscorrugatedsteelonthebottomsurfacefunctionsasaconcreteform.Thesteellineronthetopsurfacefunctionsasapositivegas-tightmembranebetweenthedrywellandthesuppressionchambertoensurethatsteamcanenterthesuppressionchamberonlythroughtheSRVventlinesorthedowncomers.Thislinerisanchoredandseal-weldedtothepedestalwall,theprimarycontainmentlinerknuckle,andallofthedrywellfloorpenetrationsandembedments.tctmetTheloadsfromthestructuralequipmentsupportsinsidethecontainmentaretransferreddirectlytotheconcretewallthroughthickenedandstiffenedlinerinsertembedmentplates.Loadsaredistributedontheseinsertplatesthroughgussetsandshearbarswhichareweldedonthebacksideinanorthogonalgridpatterntoprovidestiffnesstotheplateandtoprovideameanstotransfershearloadstotheconcrete.Thelinerinsertplatesareattachedtotheconcretewallbyeitherstandardheadedconcreteanchorsorlargerfabricatedanchors,dependingupontheloadtobetransferred.Thefabricatedanchorsaremadefrom11/2-inplatestockandaregenerally3inwideand18to24inlongwithaheadorflatplateweldedattheendtodeveloptheconcreteshearconenecessaryforloadtransferdirectlytotheconcrete.Thisensuresthattheloadsarenottransferredtothesteelliner.Equipmentandfloorloadsaretransferredtothewallbyfloorbeamseats,piperestraintseat/embedments,pipesupportembedments,andoverlayplates.Floorbeamseatembedmentsareprovidedtosupportthestructuralsteelframinginsidethecontainment.AtypicaldesignisshownonFigure3.8-5.Piperestraintembedmentsareprovidedtotransferpipingrestraintloadsfrompostulatedaccidents.Theycaneitherbeofadesignsimilartothefloorbeamseatsorofadesignthatacceptstheweldingofarestraintbeamtotheembedment.AtypicalpipewhiprestraintembedmentisshownonFigure3.8-5.Thereactorstabilizerembedmentsareprovidedtotransfertheloadfromthereactorstabilizerstructure(thestartruss)totheconcretewall.Pipesupportembedmentsareprovidedtotransfermoderatepipeandductsupportloadstothewall.Whentheloadsfromtheequipmentsupportsarecomparativelysmall,overlaypadsareattachedtothelinertodistributeandtransferloadsthroughthelinerandthelineranchorageintotheconcretewall.USARRevision83.8-4November1995 NineMilePointUnit2FSARcoeTheprimarycontainmentlinerisinintimatecontactwiththeconcretewallthroughaseriesofanchorstudsweldedtothebacksideofthelinerandembeddedinconcreteonacontrollednodalpointpattern(Section3.8.1.4.2andFigure3.8-1).Thesizeoftheseanchorstudsis5/8indiameterby61/2inlong.Theanchorstudshavebeendesignedtoaccommodatetheloadsduetobothoperatingandpostulatedaccidentconditions.Theprimarycontainmentsuppressionpoolfloorlineratel175ftisanchoredtothematthroughapatternof1/2-by7-inbridgingbarswhichareembeddedonedgeandlocatedateachfloorlinerplateseam(Figure3.8-2).Thebridgingbarsemployfabricatedanchorstoanchortheinsulationconcreteaswellasthefloorlinertothemat.A13ft3-indiameterequipmenthatch(Figure3.8-6)isprovidedinthedrywellatel266ft4inandazimuth315degtoservicethe261ftfloorandnearbyareasduringreactorshutdown.Thehatchbarrelhasaflooratel261ftandhasabolted-flangetypeclosuremountedoutsidethecontainmentwhichcontainsadouble0-ringsealwithaleaktesttapbetweenthe0-ringstoaccommodatetheperiodicTypeBleakratetestrequirements.Thehatchbarrelis5/8-inthickandthethicknessincreasesto3inintheregionoftheclosure.Thehatchcoverisa11/2-inthicksphericalcapandisboltedtothehatchbarrelwith11/4-indiameterswingbolts.CombiatuietatcandPersonneirlocAcombinationequipmenthatchandpersonnelairlock(Figure3.8-6)isprovidedinthedrywellatel266ft4inandazimuth135degtoservicethe261ftfloorandnearbyareaslocatedontheoppositesideofthedrywellfromthe315-degequipmenthatch.Itprovidesaccessforlargeequipmentduringreactorshutdownandaccessforpersonnelwhenrequired.Theequipmenthatchgeometryisthesameasthehatchatazimuth315degexceptthatthehatchcoverthatcontainsthepersonnelairlockisconical.Thepersonnelairlockislocatedinandweldedtothehatchcover.Itis9ft71/2-inoutsidediameter,15ft3inlong,andcontainsa3ft6-inby6ft8-indoorateachend.Thedoorsarelocatedinreinforcedbulkheadsandeachissealedwithadouble-gasketcompressionsealwithaleaktesttapforleakratetestingbetweentheseals.Bothdoorscanbeleakratetestedfromoutsidethecontainment.Themechanicalandelectricalbulkheadpenetrationsalsohaveprovisionsforleakratetesting.Bothdoorsswinginwardsoastoseatunderthepositiveaccidentpressure.Toensurecontainmentintegrity,theyaremechanicallyinterlockedsothatifonedoorisopen,USARRevision83.8-5November1995 NineMilePointUnit2FSARtheothercannotbeactivated.Eachdoorcanbeclosedautomaticallyfromoutsidetheoppositedoortofacilitateentryandegressfromthecontainmentwhentheoppositedoorhasbeenleftopenbythelastpersontoenterorexit.Thedoorsareequippedwithvalvesforequalizingairpressurepriortoopening.Limitswitchesareprovidedonthedoorstoenabletheiroperationtobemonitoredfromoutsideeachdoorandinthecontrolroom.scaeockA5ft6-indiameteremergencyairlock(Figure3.8-6)isprovidedinthedrywellatel264ft9inandazimuth236deg.Thisairlockservesasapersonnelalternateescaperoutetothemainairlockshouldtheneedarise.Italsoprovidesadditionalserviceaccessibilityduringshutdown.Itissimilartothepersonnelairlockinthatitalsohasinterlockeddoors,equalizingvalves,anddouble-gasketcompressionsealshaveprovisionsforleaktestingfromoutsidethecontainment.Dooroperationismanual.Limitswitchesareprovidedonthedoorstoenabletheiroperationtobemonitoredfromoutsideeachdoorandinthecontrolroom.ctsTwo3ft9-indiameterhatchesprovideaccesstothesuppressionchamber(Figure3.8-7).Thehatchesarelocatedatel225ftandatazimuths130deg30minand310deg30min.Eachaccessopeninghasabolted,steelflangedclosuremountedoutsidethecontainmentstructure.Eachhatchhasadouble0-ringsealwithaleaktesttapprovidedbetweenthesealsforperiodictesting.otrieReovaatcA2ft1<<indiameterCRDremovalhatchprovidesaccessfortheCRDassembliesinthedrywellatacenterlinelocationofel263ftandazimuth221deg(Figure3.8-7).Thehatchhasaboltedsteelclosuremountedoutsidethecontainmentstructure.Ithasadouble0-ringsealwithaleaktesttapprovidedbetweenthesealsforperiodictesting.DrelleThedrywellhasaremovable34-ftdiametertopcovercalledadrywellhead(Figure3.8-8),whichprovidesaccessibilitytothetopofthereactorduringrefueling.Itisafreestanding11/8-inthicktorisphericalheadthatutilizesafingerpinquick-disconnectclosurejointdesignedasshownonFigure3.8-8.Thefingerpinconnectionrepresentsanimprovementoverearlierboltedflangesinthatstressdiscontinuitiesarereduced,anditresultsinsavingtimerequiredtoremoveandinstallthehead.Theheadisweldedtoacylindricalskirtthatis,inturn,weldedtoathickenedjointclosure.TheupperportionofthejointclosurefitsinsidetheU-shapedbottomclosure.USARRevision83.8-6November1995 NineMilePointUnit2FSARForty-eight3-indiameterhorizontalpinsengagethetopandbottomtojointhematingpartsasshownonFigure3.8-8.Theflangedesignincorporatesaflat-faced,double0-ringsealwithaleaktesttapbetweenthe0-ringstoaccommodatetheTypeBleakratetestrequirementsdescribedinSection6.2.6.eet'Servicesandcommunicationsbetweentheinsideandoutsideoftheprimarycontainmentareeffectedthroughpenetrations.Allpenetrationsconsistofabasicwallinsertpipeorsleevethatisweldedtoalinerreinforcingplateandanyadditionalitemssuchaspressurepiping,insulation,electrical,ormechanicalcomponentsrequiredfortheindividualservice.Therearethreebasictypesofpenetrations:electrical,instrument,andpiping.Electricalpenetrationsleeveassemblies(Figure3.8-9)consistofaseamlesspipewallinsertsleevethatisweldedtoalinerreinforcingplate.Thesleevedesignissimilartothethermallycoldpipingpenetrationdiscussedbelow.Aweldneckflangeisweldedtotheoutsideendofthesleevetoaccommodatetheelectricalpenetrationboltedflange.Sealingiseffectedbyadouble0-ringsealandaleaktesttapisprovidedbetweenthe0-ringstoaccommodatetheTypeBleakratetests.Thebasicinstrument-typepenetration(Figure3.8-9)issimilartothethermallyhotpipingpenetrationsdescribedbelowinthattheprocesspipeportionislocatedinsidethewallinsertsleeve.Theprocesspipeissocket-weldedtoatransitionforgingthatisinturnweldedtotheoutboardendofthewallinsertsleeve.Theinstrument-typepenetrationincludes:instrumentpenetrations,pipingpenetrationsfortheCRDsystem,andmechanicalpenetrationsfortheTIPdrive.Alsothereisaseriesoftemperature-monitoringinstrumentpenetrations(Figure3.8-9)locatedsymmetricallyaroundtheouterwallofthesuppressionpool.Thewallinsertisaheavywallstainlesssteelpipethatiswelded.tothelinerreinforcingplate.Aspecialstainlessthermowelltipisweldedtotheendofthesleevetoaccommodate'hetemperaturesensor.Pipingpenetrationsfallintotwocategories:thermallyhotandthermallycold(Figure3.8-10).Thermallyhotpenetrationsareprovidedwhenthedesigntemperatureexceeds200'F.Forthermallyhotpenetrationsthewallinsertpipeactsasasleeve.Forthermallycoldpenetrationsthewallinsertservesasasectionoftheprocesspiping.Forthermallyhotpenetrationstheannularspacebetweenthewallinsertpipeandtheprocesspipeprovidesthermalprotectiontothewall.Eachthermallyhotpenetrationisdesignedwithsufficientspacebetweentheinsertpipeandtheprocesspipefortherequiredpipeinsulationtoensurethatthetemperatureoftheconcreteincontactwiththesleeveremainswithin2004Ffornormalconditions.However,ashorttermmaximumof350'Fisallowedforaccidentconditions.TheprocesspipeportionofthepenetrationassemblyisaUSARRevision83.8-7November1995 NineMilePointUnit2FSARcontinuousforging.Itisattachedtothesleevethroughaflued-headtransitionthatisanintegralpartoftheforging(Figure3.8-10).Provisionsforaheatexchangerwereoriginallydesignedxntoeachhotpenetrationsleevebutthesewerefoundtobeunnecessaryconsideringthegeometry,insulation,andcurrenttemperaturelimits.Allpenetrationsaredesignedtobecapableofaccommodatingthestressesimposedonthembythedesignconditions.ThedesignisdiscussedindetailinSection3.8.1.4.2.3.8.1.2ApplicableCodes,Standards,andSpecificationsThedesignandconstructionoftheprimarycontainment,steelliner,equipmentandpersonnelaccesshatches,andpenetrationstexceedtherequirementsofthecodes,standardsandregulationslistedinSection3.8.4.2forthedesignofCateorgyIstructures.3.8.1.3LoadsandLoadCombinations3'.1PrimaryContainmentStructureThereinforcedconcretestructureoftheprimarycontainmentxsdesignedtowithstandtheloadingsandstressesanticipatedd'h40-yroperatinglifeoftheunitwhicharisefromuakenormaoperloperationandotherpostulatedloadssuchasearthqoadsasLOCA,jetimpingement,andsuppressionpoolhydrodynamicloaddefinedinTable3.8-1.Thesteellinerwhichisattachedtoandsupportedbytheconcretealsotransmitsloadstotheconcrete.TheloadcombinationsforwhichthestructureisdesignedaredefinedinTable3.8-1.Designloadcriteriaconformtocurrentcontainmentdesignpractice.Thecriteriacontainvaryingloadfactorsforcombiningdead,pressure,temperature,andearthquakeforces.Thetotalloadingresultingfromthesummationofanyoneofthecombinationsmaycauseamaximumstressconditiondependingon'hetypeofstressandmemberunderconsideration.Theprimarycontainmentisdesignedtowithstandtheapplicablelddeactionforcesduetopostulatedpiperupture(Sectionoasanreac'nment3.6A)incombinationwithotherloads.Theprimarycontaiisalsodesignedforthepostaccidentenvironments.3.8.1.3.2SteelLinerandPenetrationsTable3.8-2liststheloadandsymboldefinitionsforthefollowingportionsoftheprimarycontainmentliner.USARRevision83'-8November1995 NineMilePointUnit2FSAResThewallliner,floorlinerplate,andcornertransitionsectionaredesignedfortheloadsandloadcombinationsdescribedinTable3.8-2sothateithertheresultingstresslevelsdonotexceedtheallowablelimitsgiveninASMESectionIII,Division1,SubsectionNE,1971Editionthrough1973SummerAddenda,orthattheresultingstrainlevelsdonotexceedtheallowablestrainlevelsgiveninASMESectionIII,Division2,SubsectionCC-3700,1975Edition.TheweldedattachmentstotheprimarycontainmentlineraredesignedtomeettherequirementsofSubsectionNE,1974Edition,withWinter1976AddendaandCodeCaseN-224-1.Thelinerisshieldedfromtheapplicationofinternally-generatedconcentratedmissileloads(Section3.5).Jetimpingementeffectsfrompostulatedpiperuptureinsideprimarycontainmentareappliedtotheliner.StructuralattachmentpositionsofthelinerembedmentsthatarebeyondthescopeofASMEIII,Division1,aredesignedusingtheloadcombinationsforstructuralsteeldesign(Section3.8.4.3).ccessLocsandHatchesTheequipmenthatch,equipmenthatch/personnelairlock,escapeairlock,suppressionpoolhatches,andCRDremovalhatcharesubjectedtotheloadsandloadcombinationsdescribedinTable3.8-3~ThedrywellheadissubjectedtotheloadsandloadcombinationsdescribedinTable3.8-4.PenetratinsLoadcombinationsandstressallowablesforthepenetrationsaresummarizedinthefollowingtables:ASMEIIISafetyClass1pipingASMEIIISafetyClass2pipingASMEIIIClassMCcomponentsTable3.8-5Table3.8-6Table3.8-73.8.1.4DesignandAnalysisProcedure3.8.1.4.1ConcretePrimaryContainmentStructureThereinforcedconcreteprimarycontainmentstructureisanalyzedforthevariousloadingconditionsusingtheSHELL1computercode(Appendix3A)forthinshellsofrevolutionthataresymmetricallyaswellasasymmetricallyloaded.Theeffectsofdeadandliveloads,internalpressure,temperature,earthquake,piperupture,andhydrostaticloadsareconsidered.Forthepurposeofanalysisanddesign,theconcreteisassumedtobeUSARRevision83.8-9November1995 NineMilePointUnit2FSARfullycrackedinthehoopdirectionoverthetheverticaldirection,theconcreteisalsocrackedeverywhereexceptforasmallregionfoundationmat.Thestiffnesspropertiesofcalculatedaccordingly.entireheight.InassumedtobefullyadjacenttothethewallareAdditionalreinforcingsteelisprovidedaroundpenetrationsandhatchesinordertominimizetheeffectsfromlocalizedloadconcentrationsandtoprovidecontinuityoftheload-carryingcapabilityofthewall.Theselocaleffects,whichdonotaffecttheoverallanalysis,areconsideredonanindividualbasisfordesign.Aftertheinternalloadsintheshellaredetermined,thereinforcingsteelischeckedforadequacy.Specialattentionisgiventotheeffectsofshearforcesintheshell,withadditionalshearreinforcingbeingprovidedasrequired.Asaresult,diagonalshearbarsareusedtoresistradialshearatthetopoftheuppercone,thejunctionofthetwocones,thecone-to-cylinderjunction,andatthebaseofthewalladjacenttothefoundationmat.TypicalarrangementofreinforcingisshownonFigure3.8-3.Certainareasofthewallrequirespecialanalysisduetogeometricconditions.Oneregionrequiringspecialanalysisisthetopoftheconcretecontainment.Thedesignofthisareaisbasedonasupplementaryanalysisusingafiniteelementapproach,whichaddressesthegeometricandnonlinearmaterialeffects,i.e.,concretecracking.Theparticularmodelusedforthisanalysisisextendedwellintothemembranezoneoftheshellsothatmembraneconditionsareassumedattheboundaries.Figure3.8-3showsthereinforcingdetailinthisarea.Anotherareathatrequireselementapproachisinthereinforcingintheareaof3.8-4.specialanalysisusingthefinitevicinityofthehatches.TypicaltheequipmenthatchisshownonFigureTheseregionsinthewallareanalyzedbymeansofthethree-dimensional,finiteelementcapabilityofthecomputerprogramSTRUDLII(Appendix3A).Becauseofgeometricalsymmetriesintheareaofthehatches,thefiniteelementmodelsselectedfortheseanalysesaresemicircular.Inordertoeliminatetheeffectsofthehatchopeningandthickenedringbeamatthegrid'souterboundary,thesemicircularfiniteelementgridisassumedtohaveamaximumradiusapproximatelyequalto2.5timestheradiustotheouteredgeofthethickenedringbeam.Ageometryofquadrilateralshapesemanatingradiallyfromthecenteroftheopeningisusedtoprovideafinegridinthemeridionalandcircumferentialshelldirections.Threeelementsaretakenthroughthetypicalwallsection,withadditionalelementsaddedoneachsideofthetypicalwallsectiontoaccountforthethickenedringbeamsection.USARRevision83.8-10November1995 NineMilePointUnit2FSARTheSTRUDLIIprogramallowsthemodelingofthestructuralcharacteristicsofthewall(crackedversusuncracked)andtheinclusionofthelinerforthevariousloadingsincludingtemperature.During'naccidentthelinerwillnormallybeinastateofcompressionduetothesharptemperaturerisewithinthecontainmentstructure,andthereforewilladdloadtotheringbeam.Theliner,however,isassumednottocontributetothestructuralcapacityoftheringbeamorwallforanyloadingconditionotherthantheprimarycontainmentstructuralacceptancetest.Toobtainamorerealisticassessmentofthestrains,displacements,andstressesintheareaofthehatches,theringbeamandcylindricalwallareassumedtobefullycrackedandtohaveonlythestiffnessofthereinforcingbars.TheSTRUDLIIprogramyieldsboththediscontinuityeffectsbetweenthecylinderwallandthethickenedringbeamandthepatternofmembraneforcesintheregionofthehatchopenings.Additionalreinforcement(circumferential,meridional,anddiagonal)isprovidedinregionswhereasignificantincreaseoverthetypicalmembraneforcesisobserved.TheprincipalcircumferentialandmeridionalreinforcingbarsareextendedtotheinnerfaceoftheringbeamandareeitherbentatrightanglesorCadweldedtoeachother.Seismicanalysisoftheprimarycontainmentstructureprovidestheaccelerationtowhichtheprimarycontainmentwouldbesubjectedduringanearthquake.Theseaccelerations,whenmultipliedbytheassociatedmasses,areappliedasstaticloadstothestructure.Tangentialshearscausedbyasymmetricloadsareresistedbytheconcreteandthesteelreinforcementinthewall.Strains,compatiblewiththeeffectsofinternalpressure-inducedstresses,areassumedincalculatingthereinforcingsteelrequirementsforearthquakeloads.Thesteellinerplateisconservativelyassumedtoprovidenoshearcapacitytothewallsection.3.8.1.4.2SteelLinerandPenetrationseeThelinerwasanalyzedusingthecomputerprogramKALNINS.Theorthotropiccapabilityisusedtomodelthereinforcingbararrayasanequivalentorthotropicshell.Temperaturevariationswithinthecontainmentareconsideredbyapplyinganequivalentpressurethatsatisfiestheequilibriumequationsofthelinerandconcretevessel.Theprimarycontainmentisconservativelyassumedtobecompletelycrackedtoobtainthemaximumlinerdeformation.Theboundaryconditionatthewall-to-mat)unctionisassumedtobecompletelyfixedtoobtainthemaximumlinerstressintensityrange.USARRevision8November1995 NineMilePointUnit2FSARThelinerstructuralintegrityagainstbucklingisobtainedfromtheresultsofananalysisperformedusingtheANSYScomputerprogram.Resultsshowthattheanchorstudshaveasafetyfactorofatleast2.0againstprogressivefailure.eans'ScTheouteredgeofthesuppressionpoolfloorlinerplateandthecornertransitionsectionareanalyzedusingthecomputercodeSHELL1(Appendix3A)forthinshellsofrevolution.Thelinermodelextendstothefirstrowofwalllinerplateanchorstuds.Atthisanchorstudlocation,theforcesobtainedfromthecontainmentlineranalysisareimposedonthecornerjunction.TemperaturedistributionsfollowingaDBAarecalculatedusingthefinitedifferencecomputercodeTAC-2D(thermalanalysiscode-two-dimensional)(Appendix3A).ThetemperaturesdeterminedbyTAC-2DareusedasinputforSHELL1todeterminethermalstresses.HotieetatiosSeevedThehot(sleeved)pipingpenetrationassembliesareanalyzedforstressusingthefiniteelementcomputercodeASAAS(asymmetricstressanalysisofaxisymmetricsolids)(Appendix3A).Thisprogramiscapableofevaluatingtheeffectsofsymmetricandasymmetricloadsaswellaspressureandtemperatureloads.TemperaturedistributionsinthepenetrationsareevaluatedusingTAC-2D.ThetemperaturesasdeterminedbyTAC-2DareusedasinputforASAAStodeterminethermalstresses.FortheASMECodeClass1penetrations,pressureandtemperaturetransientsareanalyzedforallmodesofoperation.FortheASMECodeClass2penetrations,onlysteady-statetemperaturesareconsidered.ThestressesarelimitedtotheallowablesinTable3.8-5forCodeClass1pipingpenetrationsandTable3.8-6forCodeClass2pipingpenetrations.FortheportionsofthepenetrationsthatformpartoftheprimarycontainmentboundaryandareclassifiedMC,thestressesarelimitedtotheallowablesinTable3.8-7.o'eetatosUseevedThecold(unsleeved)pipingpenetrationsthroughtheprimarycontainmentareanalyzedusingtheprogramASAAS.Stressconcentrationfactorsforthejunctionofthepipeandthecontainmentwallaredevelopedusingthisprogram.TheallowablestressesfortheseSafetyClass2penetrationsaregiveninTable3.8-6.earnSeataeestaintbedmentsTheembedmentsforbeamseatsandpiperestraintsareanalyzedfortheloadsimposedbythedesignandoperatingconditions.Theanchor-concreteinterfacepatternisassumedanalogoustoaUSARRevision83.8-12November1995 NineMilePointUnit2FSARreinforcedconcretebeam,andanchorloadsandstressesinreinforcingsteelaredetermined.ThefrontfaceoftheembedmentisdesignedbyconventionalsteeldesignmethodsusingAISCSpecificationforDesign,FabricationandErectionofStructuralSteelforBuildings.TheanchorconcreteinterfaceisdesignedtotheguidelinesoutlinedinACI-318-71.csTheequipmenthatches,suppressionpoolaccesshatches,andCRDremovalhatchareanalyzedusingclassicalequationsandtheANSYSfiniteelementcomputerprogram(Appendix3A)foraxisymmetricshells.Whererequired,naturalfrequenciesaredeterminedandseismicloadingsareappliedaccordingly.ThesuppressionpoolandCRDhatchesareassumedtoberigidlysupportedbytheconcretewall.Theequipmenthatchbarrelsaresupportedbytheconcretearounda90-degarcatthebottomandrigidlyrestrainedatthelinerreinforcingplate-to-barreljunction.AnalysisoftheescapelockandthepersonnellockisperformedusinghandcalculationsandbytheNASTRAN(Appendix3A)computerprogram.Theescapelockisassumedtoberigidlyrestrainedbytheconcretewall.Thepersonnellockisassumedtobesupportedbytheequipmenthatchcoverweldedtoitsbarrel.TheNASTRANfiniteelementmodelsusebarandplateelementsforanalysisofthebulkheads.eeThedrywellheadisanalyzedasafiniteelementshellofrevolutionusingaxisymmetricconicalshellelements.ThestructuralanalysisprogramusedisANSYS(Appendix3A).Theanalysisisperformedforpressure,deadweight,seismic,thermal,andjetimpingementloadings.ThefingerpinclosureisanalyzedusingthesameANSYSprogramusedforthedrywellhead.Itisalsomodeledasanaxisymmetricshellandincludesaportionoftheshellaboveandbelowtheclosure.Thefingerpinswhichjointheupperandlowerclosurefingersaremodeledastwoequivalentringsinthetwo1/8-ingapsbetweenthefingers.Loadsobtainedfromtheheadanalysesareappliedattheupperboundaryoftheclosureanalysis.Theconcreteisconservativelyassumedtoprovideafixedsupportatthelowerboundaryofthestraightportionoftheshellatthetopofthecontainment.3.8.1.5StructuralAcceptanceCriteria3.8.1.5.1PrimaryContainmentStructureThedesignoftheprimarycontainmentstructurefollowsACI-318-71.Thebasiccriterionforconcretestrengthdesignisexpressedas:USARRevision83.8-13November1995 NineMilePointUnit2FSARRequiredstrength<calculatedstrengthAllmembersoftheprimarycontainmentstructureareproportionedtomeetthiscriterion.Therequiredstrengthisexpressedintermsofdesignloadsortheirrelatedinternalmomentsandforces.Designloadsaredefinedasloadsthataremultipliedbytheirappropriateloadfactors(Section3.8.1.3).CalculatedstrengthiscomputedbyprovisionsoftheACI-318-71Code,includingtheappropriatecapacityreductionfactors.Themodulusofelasticityofreinforcingsteelis29,000,000psi.APoissonratioof0.167isusedforreinforcedconcrete.Tangentialshear(v)resultingfromasymmetricloadingswillberesistedbyeithertheconcreteortheconcreteandsteelreinforcingbars.Themaximumallowablestressfortangentialshear(v)intheconcretealoneis40psi.TheactualandallowablestressesforthecontainmentstructurearegiveninTable3.8-8.3.8.1.5.2SteelLinerandPenetrationsTheallowablestressesandstrainsfortheprimarycontainmentlinerarelimitedbyeitherthestresscriteriagiveninASMESectionIII,Division1,1971EditionthroughtheSummer1973Addenda,orthestraincriteriagiveninASMESectionIII,Division2,1975Edition.TheallowablestressesandstrainsfortheprimarycontainmentpenetrationsarelimitedbythecriteriagiveninASMESectionIII,Division1,1971EditionthroughtheSummer1973Addenda.Inparticular:1.Wallliner,floorliner,corner)unctiontransitionandlinerinsertplateembedments(Table3.8-2andSection3.8.2).2.Accesslocksandhatches(Table3.8-3andSection3.8.1).3.DrywellHead(Table3.8-4andSection3.8.1.3.2).4.Penetrations(Tables3.8-5through3.8-7fortheASMESafetyClass1,2,andMCportions,respectively,andSection3.8.1.3.2).5.TheminimumallowablestressesforASTMA500GradeBtubesteel(forweldedattachmentstotheliner)areasspecifiedinCodeCaseN-224-1.3.8.1.6Materials,QualityControl,andConstructionTechniques3.8.1.6.1ConcretePrimaryContainmentStructureThematerialsusedintheconstructionoftheprimarycontainmentarethesameasthoseusedforotherCategoryIstructures(Section3.8.4.6).ThequalitycontrolprogramfortheprimaryUSARRevision83.8-14November1995 NineMilePointUnit2FSARcontainmentstructuremeetsorexceedstherequirementsoutlinedinSections3.8.4.2and3.8.4.6forprocurement,fabrication,testing,andconstructionofCategoryIstructures.Therearenospecialtechniquesusedintheconstructionoftheconcretep'rimarycontainmentstructure.3.8.1.6.2SteelLinerandPenetrationsAllmaterialsusedinthefabricationoftheprimarycontainmentlinerandlinercomponentsareinaccordancewithapprovedmaterialslistedinSectionIIIDivision1AppendixesoftheASMEBoilerandPressureVesselCodeforNuclearPowerPlantComponents,1971EditionthroughSummer1973Addenda.TheweldedattachmentstothelinermeetthematerialrequirementsofSubsectionNE,1974Edition,withWinter1976Addenda,andCodeCaseN-224-1.AlllinermaterialsaretestedandcertifiedinaccordancewithASMEBoilerandPressureCodeSectionII,1971EditionthroughSummer1973Addenda.Thesteellinerisfabricated(butnotstamped)inaccordancewithASMESectionIII,SubsectionNE.ExceptionsarediscussedinSection3.8.1.6.3.Materialselectedforconstructionofthelinerisferriticsteelwithappropriateductility.AllferriticmaterialsformingpartoftheprimarycontainmentboundaryareCharpyV-notchtestedat-104F(exceptboltingat+404F)andconformtoASMESectionIII,SubarticleNE-2300.Theweldedattachmentstothelinerareimpact-testedinaccordancewithASMESectionIII,1974Edition,withWinter1976Addenda,SubarticleNE-2300.Allferriticmaterialsthatformpartofthepressureboundaryandaremorethan5/8inthick,exceptasnotedbelowunderaccesslocks,arealsodropweighttestedinaccordancewithSection15ofASTME208atasettemperatureof104ForlesstoverifythattheNDTTisequaltoorlessthanO'.AllweldingproceduresandtestsrequiredbyASMESectionIXareadheredtofortheselectionofweldfillermaterial,heattreatment,theperformanceofweldingmachines,andthequalifyingofweldingproceduresandWeldingOperatorswhoconstructtheprimarycontainmentliner,exceptasnotedinTable1.8-1,RG1.19,Item4.Theweldingqualificationincludes180-degbendtestsofweldmaterial.Theseproceduresensurethattheductilityofweldedseamswillbecomparabletotheductilityofthecontainment,linerplatematerial.Linersurfacesexposedtothesuppressionchamberatmospherearemadefromthefollowingmaterials:stainlesssteelplateforembedments,carbonsteelplatecladwithstainlesssteelfortheliner,andcarbonsteelplateoverlaidwithstainlesssteelsheetfortheknuckle.Allcarbonsteelweldseamsinthesuppressionpoolwalllinerareweldoverlaidwithstainlesssteel.StainlesssteelplateisfurnishedbythesuppliertotheUSARRevision83.8-15November1995 NineMilePointUnit2FSARrequirementsofSA-240Type304Linthesolution-annealedcondition.SurfacesofthelinerexposedtothedrywellatmosphereinsidethecontainmentarecoatedinaccordancewithRG1.54.Thebacksideofthelinerincontactwiththeconcretehasadequatecorrosionprotectionandisnotpainted.TheprimarycontainmentwalllinerplateandsuppressionpoolfloorlinerplatematerialisSA-537Class2,quenchedandtemperedwithaspecifiedminimumtensilestrengthof80,000psi,aminimumguaranteedyieldstrengthof60,000psi,andaguaranteedminimumelongationof22percentinastandard2-inspecimen.Thewalllinerhasa3/8-innominalbasethickness,andthefloorlineris1/4inthick.ThewalllinerinthesuppressionpoolisSA-537Class2thathasbeenroll-bondedunderheatandpressurewithstainlesssteelcladplate,orhasbeenwallpaperedwithstainlesssteeltoensureadequateprotectionfromcorrosion.AllcladdingisSA-240Type304LstainlesssteelmadetoSA-264,andis20percentofnominalbasemetalthicknesswitha0.0375-inminimumthicknessandabondshearstrengthof30,000psi.Allwallpaperedcladdingis1/8-inthickSA-240Type304stainlesssteel.Thickenedembedmentplatesinsertedintothelinerwhichtransferstructuralequipmentloadstothereinforcedconcreteinthedrywellare11/2-inthickSA-537Class2LukensLectrifinetoenhancethecross-transverse(Z-axis)properties.Insertplatesinthesuppressionpoolare11/2-inthickSA-240Type304Lstainlesssteel.Linerconetransitionsarethickenedplatesof11/4-inthickSA-537Class2material.TheprimarycontainmentlinerplateswereorderedtoconformtomillpracticewithregardtothicknessandtoleranceinaccordancewithASTM-A20.Theconstructiontolerancesspecifiedforthelinerare:1~Themaximumdifferencein.cross-sectionaldiametersofthesteellinershallbeinaccordancewithASMESectionIII,SubparagraphNE-4221.1.2~3~4~Theout-of-roundtolerancemeasuredatthetopoftheknuckleorstarterplateshallnotexceed+0.25percentofthenominalinsidediameter.Thetopoftheknuckleplateshallbelevelwithin+3/8in.Themaximumdeviationfromastraightlineorfromcircularformmeasuredanywhereinthelinershallnotexceed+1/4inina14-inspan.Thecylindricalportionofthelinershallbeplumbwithin23/4inatanyheightofthelinermeasuredfromanestablishedverticallineextendingupfromthebaseofthematliner.Forconicalsections,thelinershallbewithin23/4inofbasicasafunctionofelevation.USARRevision83.8-16November1995 NineMilePointUnit2FSAR5.ThemaximummisalignmentbetweenlinerplatesshallbeinaccordancewithASMESectionIII,ParagraphNE-4232.Nondestructivetestingforthesteellinerwasperformedasr'equiredbyRG1.19(oracceptablealternativeasdescribedinTable1.8-1)ortheapplicablecodefornoncode-stampedcomponents.ProceduresforthesteellinerwereinaccordancewiththerequirementsofASMESectionV,1971EditionthroughSummer1973Addenda,exceptthatradiographicexaminationwasalsoperformedtotherequirementsofthe1977EditionthroughtheSummer1978Addenda.AcceptancestandardsforradiographicexaminationareinaccordancewithASMESectionIII,1971EditionthroughSummer1973Addenda,or1977EditionthroughSummer1978Addenda.Formagneticparticleandliquidpenetrantexamination,theevaluationofindicationsandtheacceptancestandardsareinaccordancewithASMESectionIII,1971EditionthroughSummer1973Addenda.FortheseexaminationsconductedafterNovember1,1978,theevaluationofindicationsandacceptancestandardsisinaccordancewithParagraphsNE-5341,NE-5342,NE-5351,andNE-5352ofASMESectionIII,1977Edition,andCodeCaseN-339.AcceptancerequirementsforallothernondestructivetestingproceduresareinaccordancewithASMESectionIII,1971EditionthroughSummer1973Addenda,SubarticleNE-5300.Leak-tightnesstestingofallwallandfloorlinerseamweldswascompletedduringconstruction.Whenleakagewasdetected,repairweldingwasperformedandtheweldwasretestedbythesamemethodsappliedtotheoriginalweld.TheCadweldsleevesweldedtothelinertoaccommodatethedrywellfloorandpedestalinterfaces(Section3.8.1.1.2)werequalifiedbysisterspliceswhichweretensile-testedtofailure.CadweldsistersplicesweretestedtosubstantiatethestructuralintegrityoftheCadweldsleeve-to-platejointbydemonstratingthatfailureoccurredeachtimeintherebar.Asisterspliceplateiscomposedofmaterial,thickness,andconfigurationidenticaltotheproductionpiece.coSudsAnchorstudmaterialisASTMA108Grades1010-1020,withaminimumtensilestrengthof60,000psi.TheanchorstudsareweldedasanASMESectionIXP-1,Group1material.Weldingofanchorstudsisnotperformedwhenthebasemetaltemperatureisbelow50F.Theareastowhichthestudsaretobeweldedarebrushedorgroundfreeofscaleorrust.Thenormaltoleranceforlocatingthecenterlineofaconcreteanchorstudonthe3/8-inlineris11/2inhorizontallyandmeridionally.Additionalanchorstudsareaddedtothelinerifinterferencesexistwithreinforcingsteel,andaredocumentedtoassurethattheydonotexceedtheminimumspacingrequirements.Ananchorstudmaybebentupto10degtoavoidreinforcingsteel.However,ananchorstudmaybebentupto20deginorderUSARRevision83.8-17November1995 NineMilePointUnit2FSARtoavoidinterferencewithreinforcingsteelifnootheranchorstudwithinan18-inradiusisbentmorethan10deg.Anyanchorstudthatisnotacceptablebytheprecedingcriteriawillbereplacedbylocatinganadditionalanchorstudwithina31/2-inradius.Foreachshift,studwelderswerequalifiedbysuccessfullyweldingtwostudstoasisterplate.Aftertheweldcooled,eachstudwasbent30degbystrikingthestudwithahammer.Iffailureoccurredintheweldofeitherstud,theprocedurewascorrectedandtwosuccessivestudsweresuccessfullyweldedandtestedbeforeworkproceeded.Sisterplateswereofmaterialsimilartothatoftheproductionpieceandhadthesamethicknessastheproductionpiece,exceptthata1-insisterplatewasacceptableforproductionitemslargerthan1in.Allstudswerevisuallyinspected.Studsonwhichafull360-degweldflashwasnotobtainedwerereplacedorrepairedasaminimumforcompliancetoAWSD1.1.ccesstcesadocsThematerialsusedintheconstructionoftheaccesslocksandhatchesareinaccordancewithASMESectionIII,Division1,1971EditionthroughSummer1973Addenda,andaretestedandcertifiedinaccordancewithSectionIIoftheabovecode.Theaccesshatches,personnelairlock,andescapelockarefabricatedbutnotstampedinaccordancewithASMESectionIII,SubsectionNE.Themajorcomponents(panel,cover,andflanges)forthesuppressionchamberhatchesarebuiltwithSA-240Type304Lstainlesssteelwithaminimumtensilestrengthof70,000psiandaminimumyieldstrengthof25,000psi.Themajorcomponents(panel,cover,andflanges)oftheequipmenthatch,equipmenthatch/personnelairlock,escapeairlock,andCRDhatcharebuiltwithSA-516Grade70withaminimumtensilestrengthof70,000psi,andaminimumyieldstrengthof38,000psi.SA-516Grade70material21/2inandlargerisusedinthehatchcloserjointsinthequenchandtemperedconditionwithoutdropweighttests.BoltingmaterialisSA-193GradeB7andthe0-ringismaterialethylenepropylene-diene-monomer(EPDM).TheplatesconformtostandardmillpracticewithregardtothicknessandtoleranceinaccordancewithASTMA-20.Allwelding,weldingprocedurequalification,andwelderqualificationsareinaccordancewithASMESectionIII.ThemethodsofnondestructiveexaminationofaccessopeningweldsareinaccordancewithASMESectionIII,SubarticleNE-5200.NondestructiveexaminationsareinaccordancewithRG1.19(exceptasnotedinTable1.8-1,RG1.19,Item5)andarequalifiedinaccordancewiththemethodsandtechniquesdescribedinASMESectionIII,Division1,AppendixX,1971EditionthroughUSARRevision83.8-18November1995 NineMilePointUnit2FSARSummer1973AddendawithacceptancerequirementsinaccordancewithASMESectionIII,SubarticleNE-5300.ThedrywellheadisfabricatedtotherequirementsofASMESectionIII,Division1,1971EditionthroughSummer1973Addenda.ThetorisphericalheadisbuiltwithSA-516Grade70withaminimumtensilestrengthof70,000psi,minimumyieldstrengthof38,000psi,andaguaranteedminimumelongationof21percentinastandard2-inspecimen.TheclosureflangeisSA-240Type304.TheclosurepinmaterialisSA-564Grade630withCodeCase1388-2.The0-ringmaterialisEthylene-Propylene-Diene-Monomer(EPDM).AllweldingproceduresforthefabricationofthedrywellheadareinaccordancewithASMESectionIII,Division1,ClassMCrequirements.NondestructivetestingproceduresarequalifiedinaccordancewiththemethodsandtechniquesasdescribedinASMESectionIII,Division1,AppendixX,1971EditionthroughSummer1973AddendawithacceptancecriteriaaccordingtoASMESectionIII,SubarticleNE-5300.Theelevationtoleranceofthedrywellheadflangeis+2to0inandthelevelnesstoleranceis1/8in.Out-of-roundnessdoesnotexceed0.75in.Variationinclosurecircumferencedoesnotexceedi0.375in.Thecenterlineoftheinstalledclosurejointwithrespecttothecontainmentcenterlineisconcentricwithina2-indiametercircle.Themaximumgapbetweenthesealingsurfaceswithoutthe0-ringsinplacedoesnotexceed0.031inaftershopfabricationand0.051inafterfieldinstallation.PeetatiosThepenetrationpipesleeves(ClassMCboundary)arefabricated(butnotstamped)inaccordancewithASMESectionIII,SubsectionNEexceptforParagraphsNE-4121andNE-4125andSubparagraphNE-4621.1.TheprocesspipesarefabricatedandstampedinaccordancewithASMESectionIII,SubsectionNBorNCasapplicable.Thematerialsusedforthepenetrationassembliesarediscussedbelow.oteetraionsi3.8-10AllcarbonsteelintegralfluedheadforgingsformingaportionofapipingsystemareeitherSA-105Grade2,orSA-508Class1,includingASMECodeCase1332-6,exceptthattheintegralforgingsforthefeedwatersystemareSA-508Class2.StainlesssteelfluedheadforgingsforapplicablepipingsystemsareSA-182TypeF304L.ThecarbonsteelsleevesinthedrywellassembliesareSA-333Grade6andSA-106GradeB,exceptforthemainsteamandfeedwatersleeveswhichareSA-155GradeCMSH80.SleevesforthestainlesssteelforgingsareSA-312Type304LandSA-240Type304LforseamlessUSARRevision83.8-19November1995 NineMilePointUnit2FSARpipeupto10inindiameter,andareSA-312Type304forweldedpipesover10inindiameter.TheASMESectionIIISafetyClass1and2penetrationpipeferriticforgingwithprocesspiperegionsthickerthan5/8inwillbeCharpyV-notchtoughnesstestedforacceptanceatt40oFanddropweighttestedat10'FinaccordancewithASMESectionIIISubarticleNB-2300.Allwelding,weldingprocedurequalifications,andwelderqualificationsforASMESectionIIIpipingSafetyClass1or2componentsareinaccordancewiththerequirementsofASMESectionIII.ForfabricationsoftheClassMCportions,theweldingrequirementsarethesameasthoseforthesteelplateliner.ThemethodsofnondestructiveexaminationofSafetyClass1and2pipingpenetrationweldsareinaccordancewithASMESectionIIISubarticlesNB-5200andNC-5200,respectively.NondestructivetestingproceduresarequalifiedinaccordancewithASMESectionVwithacceptancerequirementstoSubarticleNE-5300fortheClassMCitems.TermalColdPenetrationsFiure3.8-10ThecarbonsteelservicepipeformingaportionofthepipingsystemisSA-333Grade6orSA-106GradeB,fine-grainedandnormalized.StainlesssteelservicepipingforapplicablepipingsystemsisSA-312Type304Lor316Lforpipesizesupto10indiameterandSA-312Type304forpipesizesover10indiameter.Carbonsteelprocesspipeswiththicknessgreaterthan5/8inareimpacttestedanddropweighttestedasdescribedaboveunderthermallyhotpenetrations.CDandstrmentPenetrationsFiure3.8-9TheinnerpipeformingaportionofthepipingsystempressureboundaryisSA-312Type304L.TheforgedadapterwhichalsoformspartofthepipingsystemboundaryinadditiontoattachingtheinnerpipetothecontainmentsleeveisSA-182Type304L.ThecontainmentsleevesinthesuppressionchamberareSA-312Type304L.ThecontainmentsleevesinthedrywellareSA-333Grade6.Therequirementsofweldingandtesting(examination)oftheseitemsarethesameasthosedescribedunderThermallyHotPenetrations.ect'enetratioSleevesFiure3.8-ThematerialfortheelectricalpenetrationsinthedrywellisSA-333Grade6,fine-grainedandnormalized.ThestainlesssteelelectricalpenetrationsinthesuppressionchamberareSA-312Type304L.TheweldneckflangethataccommodatestheboltedelectricalinsertisSA-105inthedrywellandSA-182Type304Linthesuppressionchamber.PrimarycontainmentlinerreinforcementplatesinthedrywellareSA-537Class2material.LinerreinforcementplatesinthesuppressionchamberareSA-240Type304L.USARRevision83.8-20November1995 NineMilePointUnit2FSARThemeridionalslopeandthecircumferentialslopeforthepenetrationsarespecifiedas+1/2inattheendofthepenetrationfarthestfromtheplaneofthereinforcementplate-to-penetrationweld.Thespecifiedslopetolerancesforthemainsteamandfeedwaterpenetrationsare+1in.TolerancesforservicepipeandsleevewallthicknessesforforgedpenetrationsareinaccordancewithASTMA530exceptthatthemaximumthicknessismoretightlycontrolledtoaccommodatemachiningoperationsandtolimiteccentricitybetweentheoutsideandinsidediameters.3.8.1.6.3Exceptionsand/orClarificationstoASMECodeTheexceptionsand/orclarificationstotheASMEBoilerandPressureVesselCode,Division1,1971EditionthroughSummer1973Addenda,areasfollowsfornoncode-stampeditemsonthecontainment:NA-1120DefinitionofNuclearPowerSystemComponentsandContainmentVesselsNA-3500ResponsibilitiesofInspectionAgenciesEngineeringSpecialistsandInspectorsNA-4000QualityAssuranceNA-5000InspectionNA-8000NamePlates,Stamping,andReportsNE-1110AspectsofConstructionCoveredbyTheseRulesNE-1120RulesforClassMCContainmentVesselsNE-4121MeansofCertification-NE-4121hasarequirementfortheapplicationofthecodesymboltothecontainment'tructure,butifthecontainmentlinerisbackedbyconcrete,itdoesnotqualifyasaMCvessel.NE-4125TestingofWeldingMaterials-NE-4125hasarequirementthatdefinesa"lot"ofweldmaterialbasedonheatsofmetalordrybatch.CodeCases1567and1568wereinvokedtodefinea"lot"ofweldmaterialtobebasedontimeandquantityofproductionruns.NE-4311StudweldingRestrictionsNE-4322MaintenanceandCertificationofRecordsNE-4421BackingRingsUSARRevision83.8-21November1995 NineMilePointUnit2FSARNE-4429NE-4621.1WeldingofCladParts-Thissectionrequiresthatanyweld-depositedcladdingbeexaminedbyaliquidpenetrantmethod.Inlieuof100-percentliquidpenetrantexamination,somecategoriesofweld-depositedcladdingonthesuppressionchamberlowerknucklewerevisuallyexamined.Asmallportionofthecladdinginoneofthesecategorieswasinaccessibleforvisualexaminationandisacceptedbasedonthesatisfactoryvisualexaminationresultsfortheaccessiblecladding.Materials.ExemptedfromPost-WeldHeatTreatment-NE-4621.1containsarequirementinSubparagraphNE-4621.1(b)topostweldheattreatallsubassembliespriortoinsertionintotheshell.SubparagraphNE-4622.1,whichexemptsweldmentsupto11/2-inthick(embedments)frompostweldheattreatment,isusedinplaceofSubparagraphNE-4621.1(b)sincethelinerinsertportionoftheembedmentistapereddowntothelinerthickness.NE-5211CategoryAandBWeldsNE-5212ExaminationofEmbeddedWeldsofVesselsNE-5231ButtWelds-Thissectionrequiresthatforbuttweldsinnonpressure-retainingstructuralpartsattachedtopressure-retainingparts,theportionofthebuttweldwithin16t,wheretisthethicknessofthestructuralpart,shallbeexaminedbyaradiographicmethodinaccordancewithAppendixX.Inlieuoftheradiographicexaminationinbuttweldswithinthis16t,theweldswillbeexaminedbyanultrasonicmethod,amagneticparticlemethod,oraliquidpenetrantmethodallinaccordancewithASMEV.NE-5232NonbuttWeldsinNon-CategoryJoints-Thissectionrequiresthatfornonbuttweldsinnonpressure-retainingstructuralpartsattachedtopressure-retainingparts,thenonbuttweldswithinthelimitof16t,wheretisthethicknessofthestructuralpart,shallbeexaminedbyanultrasonicmethod,amagneticparticlemethod,oraliquidpenetrantmethod,allinaccordancewithAppendixX.Thenonbuttweldofthestructuralparttothepressure-retainingpartwillbeexaminedinaccordancewiththerequirementsofNE-5232usingthemethodsofASMEVinlieuofAppendixX.Thenonbuttweldsinnonpressure-retainingstructuralpartswithinthelimitof16twillbeexaminedinaccordancewiththegoverningstructuralfabricationcoderequirements.USARRevision3.8-22November1995 NineMilePointUnit2FSARNE-5522NE-5610VerificationbyInspectorofPersonnelQualificationVesselMaterials-ExaminationNE-6000NE-8000TestingNameplates,Stamping,andReportsTheexceptionsand/orclarificationstotheASMEBoilerandPressureVesselCode,Division1,1974EditionthroughWinter1976Addenda,areasfollowsfornoncode-stampedattachmentstotheprimarycontainmentliner:NA-1120DefinitionofNuclearPowerSystemItemsNA-3500ResponsibilitiesofInspectionAgencies,InspectionSpecialists,andInspectorsNA-4000QualityAssuranceNA-5000InspectionNA-8000CertificatesofAuthorization,Nameplates,Stamping,andReportsNE-1110AspectsofConstructionCoveredbyTheseRulesNE-1120RulesofClassMCContainmentVesselsNE-4121MeansofCertificationfortheapplicationofcontainmentstructure,isbackedbyconcrete.MCvessel.-NE-4121hasarequirementthecodesymboltothebutthecontainmentlinerItdoesnotqualifyasaNE-4125NE-4311.TestingofWeldingMaterials-NE-4125referstoNE-2400whichhasarequirementthatdefinesa"lot"ofweldmaterialbasedonheatsofmetalordrybatch.CodeCases1567and1568wereinvokedtodefinea"lot"ofweldmaterialtobebasedontimeandquantityofproductionruns.StudweldingRestrictionsNE-4322MaintenanceandCertificationofRecordsNE-4421BackingRingsNE-5210CategoryAWeldsNE-5220CategoryBWeldsUSARRevision3.8-23November1995 NineMilePointUnit2FSARNE-5261NE-5262ButtWelds-Thissectionrequiresthatforbuttweldsinnonpressure-retainingstructuralpartsattachedtopressure-retainingparts,theportionofthebuttweldwithin16t,wheretisthethicknessofthestructuralpart,shallbeexaminedbyaradiographicmethod.Inlieuoftheradiographicexaminationinbuttweldswithinthis16t,theweldswillbeexaminedbyanultrasonicmethod,amagneticparticlemethod,oraliquidpenetrantmethod,allinaccordancewithASMEV.NonbuttWeldsinNon-CategoryJoints-Thissectionrequiresthatfornonbuttweldsinnonpressure-retainingstructuralpartsattachedtopressure-retainingparts,thenonbuttweldwithinthelimitof16t,wheretisthethicknessofthestructuralpart,shallbeexaminedbyanultrasonicmethod,amagneticparticlemethod,oraliquidpenetrantmethod,allinaccordancewithASMEV.Thenonbuttweldofthestructuralparttothepressure-retainingpartwillbeexaminedinaccordancewiththerequirementsofNE-5262.Thenonbuttweldsinnonpressure-retainingstructuralpartswithinthelimitof16twillbeexaminedinaccordancewiththegoverningstructuralfabricationcoderequirements.NE-5522VerificationbyInspectorNE-5610VesselMaterialsNE-6000TestingNE-8000Nameplates,Stamping,andReportsTheaboveexceptions/clarifications,forthemostpart,reflectthefactthatthecontainmentliner,beingbackedupbyconcrete,doesnotqualifyasanASMESectionIIIClassMCvesselandtheexaminationrequirementsofRG1.19apply.Therefore,itcouldnotbestampedMCandthustheportionsofthecodethataddressdefinitions,stamping,thirdpartyinspection,anddatareportsdonotapply.Theptionsand/orclarificationsto'theASMEBoilerandeexcep'o~~~~itionPressureVesselCodeSectionIII,Dzvxsxon1,1974Ed'throughWinter1976Addenda,fortheinstallationofcode-stampedelectricalpenetrationsmechanicallyattachedtoanoncode-stampeditemonthecontainmentlinerareasfollows:NA-1280-InstallationNA-3300-ResponsibilitiesofanNCertificateHolderNA-3400-ResponsibilitiesofanNPTCertificateHolderUSARRevision83.8-24November1995 NineMilePointUnit2FSARNA-3500-ResponsibilitiesofanNACertificateHolderNA-4000-QualityAssuranceNA-5000-InspectionNA-8000-CertificatesofAuthorizationNameplates,Stamping,andReportsNE-8000-Nameplates,Stamping,andReportsTheelectricalpenetrationshavebeendesigned,manufactured,andshop-testedinaccordancewiththeapplicableportionsoftheASMEBoilerandPressureVesselCodeSectionIII,Division1,1974EditionthroughWinter1976Addenda.Theelectricalpenetrationsareinstalled,inspected,andfield-testedinaccordancewithSWECQualityStandards(QAandEAproceduresrelatingtoCategoryIinstallationofsafety-relatedequipment)whichconformto10CFR50AppendixB.Acceptabilityoftheinstallationoftheelectricalpenetrationswillbebasedonafield-performedleakratetestasdescribedinSection8.3ofIEEE-317-1976.3.8.1.7TestingandIn-serviceInspection3.8.1.7.1ConcreteContainmentP'tainmetesTheprimarycontainmentissubjectedtoastructuralacceptancetestinwhichitispressurizedinternallyto1.15timesthe45psidesignpressure.Itispressurizedinincrementsof10psifromatmosphericpressuretoitspeakvalueof51.75psiandthendepressurizedinasimilarmannertoatmosphericpressure.Attheendofeach10psistepchange,thepressureisheldforatleast1hr.Strainanddeflectionmeasurementsarerecordedandcomparedtopredictedvalues.ThestructuralacceptancetestforprimarycontainmentequalsorexceedstherequirementsofRG1.18fornonprototypecontainments.Thestrainmeasurementsaremadebyusingstraingaugesthathavebeeninstalledattwoazimuthsontheinsideandoutsidemeridionalandhooprebarsatvariouselevations.Theradialdisplacementsofthecontainmentaremeasuredusingdirectcurrentdifferentialtransducers(DCDTs)atseveralpointsalongsixmeridiansspacedaroundthecontainment.Inadditiontothis,additionalstraingaugesandDCDTsaremountedaroundthepersonnelhatchtorecordthestrainsanddisplacements,respectively.ThesemeasurementsarecomparedtothepredictedvalueswhichareshowninTable3.8-15.ThepredictedresponseofthestructureisbasedontheanalysisproceduresdescribedinSection3.8.1.4.ThemeasuredmaximumdeflectionsatpointsofUSARRevision83.8-25November1995 NineMilePointUnit2FSARmaximumpredicteddeflectionareacceptableiftheydonotexceedthepredictedvaluesbymorethan30percent.Thisrequirementmaybewaivedifthedeflectionrecoverywithin24hraftercompletedepressurizationisgreaterthan80percent.ThesetolerancesarebasedonthetolerancesallowedinASMEIII,Division2.Crackpatternsqxceeding0.01ininwidthbefore,during,orafterthetestaremapped.DreloorTestThedrywellfloorissubjectedtothedesigndifferentialpressureof25psi.Thestructuraladequacyofthefloorwillbedeterminedbyavisualinspectionforsignsofpermanentdamagetotheconcreteafterreturntotheatmosphericpressure.Theresponseofthecontainmentismeasuredduringthetestusingproceduressimilartotheonesusedfortheprimarycontainmenttest.3.8.1.7.2SteelLinerandPenetrationsTheprimarycontainmentlinerisrequiredtowithstandthepressureof115percentofthedesignpressurebytheacceptancetestdescribedinSection3.8.1.7.1.Theprimarycontainmentleakageratetest(Section6.2.6)isconductedafterthestructuralacceptancetestincompliancewiththerequirementsofAppendixJof10CFR50.Testchannelsareprovidedforallseamscoveredbyconcreteorotherwisemadeinaccessibleaftercompletionofconstructionandallbasiclinerseamweldsinthesuppressionchamber.Thiswillenableleak-tightnesstestingoftheselocalareastobeperformedatanytimeduringthelifeoftheplantshouldtheneedarise.ccessatcesandDreledThepersonnelairlocksandtheescapeairlocksweresubjecttoashopacceptancetestinaccordancewithArticleNE-6000ofASMESectionIII,Division1.Theywerealsosubjecttoashoppressuredecaytest.Thesealsfortheairlocksweresubjecttoahalogenleaktest,andthesealsforthedrywellheadweresubjecttoapressuredecaytest.Thesealsforthedrywellhatchesweresubjecttoahalogenleaktest,andthestainlesssteelsuppressionpoolhatchsealswerepressuredecaytested.Testchannelsareprovidedfortheconvenienceofleaktestingduringconstructionforallcontainmenthatch-to-linerreinforcementplatewelds.Thisalsowillenableleak-tightnesstestingoftheseweldjointstobeperformedatanytimeduringthelifeoftheplantshouldtheneedarise.USARRevision83.8-26November1995 NineMilePointUnit2FSARenetat'sAllpenetrationsweresubjecttoashophydrostaticacceptancetestinaccordancewithNB-6000orNC-6000,asapplicable,ofASMEIII,Division1,1971EditionthroughSummer1973Addenda.Additionally,penetrationsZ-32(neutronmonitoring-GSN),Z-46AandZ-47(closedloopcooling-CCP),Z-46C(fireprotection-FPW),Z-99AthroughDandZ100AthroughD(reactorcorecoolinghydraulicsystem-RCS)werehydrostaticallytestedafterinstallationinaccordancewithParagraphNC-6129ofASMEIII,1977Edition,Winter1978Addenda.Testchannelsareprovidedonlyforallcontainmentpenetrationinsert-to-linerreinforcementplateweldswhichareweldedfromonesidewithabackingstriptoenableleak-tightnesstestingoftheseweldjointstobeperformedatanytimeduringthelifeoftheplantshouldtheneedarise.TheintegralfluedheadforgingdesignofthethermallyhotpipingpenetrationpermitsISIoftheprocesspipetotransitionregion.TheendsofthepipingforgingaredimensionedtofacilitateISIoftheprocesspipewelds.3.8.2NotApplicable3.8.3ConcreteandSteelInternalStructuresofthePrimaryContainment3.8.3.1DescriptionofInternalStructuresTheinternalstructuressupporttheRPV,provideshielding,andformthepressuresuppressionsystem.Theinternalstructuresincludethefollowing:1.Drywellfloor.2.Reactorvesselpedestal.3.Biologicalshieldwall.4.Startruss.5.Floors.SteellinearsupportsforRCSsystemsaredescribedinSection3.9A.ThecontainmentinternalstructuresareCategoryIandareshownonFigure3.8-11.TheBSWisacompositestructureofpressurevesselqualitysteelandheavy-densityfillmaterial.Thedrywellfloorandpedestalareheavilyreinforcedconcretestructures.TheconcretestructuresaredesignedforDBAconditionsandprovideradiationshielding.TheDBAradiationsourcetermshavebeenevaluatedanddonotadverselyaffectUSARRevision83.8-27November1995 NineMilePointUnit2FSARthesestructures(Section12.3).ThestartrussisconstructedanddesignedtowithstandDBAconditions,includingtemperatureeffects,alongwithseismicandotherapplicableloads.3.8.3.1.1DrywellFloorThedrywellfloor(Figures3.8-12and3.8-13)isareinforcedconcreteannularslab,4ftthick,havinganinnerdiameterof30ftsupportedbythepedestal,andanouterdiameterof91ftsupportedbytheprimarycontainmentwall.Thedrywellfloorservesbothasapressurebarrierbetweenthedrywellandsuppressionchamberandasthelateralsupportstructureforthereactorpedestalandanchorsupportforthedowncomers.Thedrywellfloorisrigidlyconnectedtothecontainmentwalltherebypreventingrelativemotionbetweenthetwostructures.Thisalternativeapproachisusedasasubstitutefortherequirementofadrywellfloorseal.Afullmomentandshearconnectionisprovidedbycadweldingthereinforcingbarstothereinforcedlinerplate(Figure3.8-13).Thermalexpansionisconsideredinthecontainmentdesign,andtheresultingforcesandmomentsonthefloorareaccommodatedwithintheallowablestresslimits.Thedrywellflooratel240ftispenetratedby11824-indiameterstainlesssteeldowncomerpipes,andfour24-indiametertruncateddowncomersforvacuumbreakers.AdescriptionofthedowncomerventsisgiveninSection6.2.1.Figure3.8-12showsthearrangementofthedowncomers.Thedrywellfloorisalsopenetratedby1812-indiameterSRVlines,1821/2-indiameterSRVventlines,and204-indiameterfloordrains.SRVlinepenetrations12inindiameterarefluedhead-typepenetrationsasshownonFigure3.8-13.SRVventlinepenetrations21/2inindiameterarecollar-typepenetrationssimilartoinstrumentpenetrationsasshownonFigure3.8-9.Thesealforthedrywellslabisprovidedbya3/16-inthicklinerthatisplacedontopofthefloorslab(Figure3.8-13).Aminimumof6-inthickreinforcedconcreteinsulationslab,slopedfordrainage,isplacedontheliner.Thecavityfloorslab,locatedatel232ft,is3ftthickandiswithinthepedestalshellwalls.Thisslabisanextensionofthedrywellfloorbutis8ftlowerthanthedrywellfloortoavoidinterferencewiththeCRDassemblies.Theslabispenetratedbyeightdowncomerpipesandonefloordrain.Afullmomentandshearconnectionisprovidedbetweentheslabandpedestal.Similartothedrywellfloor,thisslabprovidesapressurebarrierbetweenthedrywellandsuppressionchamber.USARRevision83.8-28November1995 NineMilePointUnit2FSAR3.8.3.1.2ReactorVesselPedestalThereactorvesselpedestalisa91-ft61/2-inhigh,heavilyreinforcedconcreterightverticalcylindricalshellwitha20-ft3-ininsidediameterandathicknessthatvariesfrom4ftatthebaseto5ft11/2inabovethedrywellfloor.Thewallthicknessincreasesto7ft91/2inatthetopportionwhichsupportstheRPVandtheBSW.Atlowerelevationsthepedestalalsosupportsthedrywellfloor,thecavityfloorslab,variouspiperupturerestraints,radialbeams,andpipesupports.ThepedestalislocatedconcentricwiththeRPVcenterlineandissupportedonthereactorbuildingfoundationmat(Figure3.8-14).Afullmomentandshearconnectionatthejunctionofthepedestalandmatisprovidedbyreinforcementextendingintothemat.ThetopofthepedestalcontainsembeddedanchorboltsforanchorageoftheRPVandBSW.Thereactorvesselisanchoredbytwo3-indiameterboltsatevery6degofpedestalcircumference;theBSWisanchoredbytwo21/4-indiameterboltsatapproximatelyevery5degofpedestalcircumference.Allpedestalconcretesurfacesinthesuppressionchamberarelinedwitha1/4-instainlesssteellinerplate.Thelinedsurfaceincludesthebottomofthecavityfloorontheinsideofthepedestalandextendstothedrywellfloorontheoutsideofthepedestal.Thepedestallinerplateisanchoredtotheconcretebyheadedconcreteanchorstuds.3.8.3.1.3BiologicalShieldWallTheBSWconsistsoftwoconcentricsteelcylindersconnectedbyinternalhorizontalandverticalstiffeners(Figure3.8-15).Theshieldwallis48ft4inhighandhasaninnerradiusof14ft3/4inandanouterradiusof15ft91/4in.Theshieldwallissupportedbythereactorpedestalandisattachedtothepedestalbyembeddedanchorbolts(Figure3.8-15).Theinnerandouterwallsandthestiffenersare11/2inthick,ASTMA537Class1steelplatesconnectedbyfullpenetrationwelds.Thespacebetweenthewallsisfilledwithnonstructuralheavy-densityfillmaterial(acombinationofcementandironore)forradiationshieldingpurposes.Theshieldwallispenetratedbyairductopenings,inspectionandaccessopenings,instrumentationlines,andpipingpenetrationsforvarioussystems.AttachedtotheBSWarepiperestraints,startrussandstabilizersupports,insulationsupportbrackets,andmiscellaneoussupportsforstructuralsteelfloorbeams.TheBSWprotectstheRPVfrompipewhip,jetimpingement,andmissileloads,andprotectsdrywellstructuresfromtheeffectsofrecirculationandfeedwaterlinebreaksintheannularregion.USARRevision83.8-29November1995 NineMilePointUnit2FSAR3.8.3.1.4StarTrussThestartruss(Figure3.8-16)isatubularstructurespanningbetweentheBSWandtheprimarycontainmentwall(Figure3.8-16),whosefunctionistoprovidelateralsupporttotheBSW,whichinturnprovideslateralsupporttotheRPV.ItisweldedtotheringgirderextensionontopoftheBSWatsixequallyspaced,circumferentiallocations.Thisweldedconnectionprovidesafixedsupportforthestartrussextendingtotheprimarycontainmentwall.Thestartrussconnectionattheprimarycontainmentwallallowsunrestrainedradialandverticaltranslationbutpreventstangentialtranslation.3.8.3.1.5FloorsFloorsarelocatedwithinthecontainmenttoprovidesupportforandaccesstoequipment.Thefloorsgenerallyareconstructedofsteelframingwithsteelgratingorcheckeredplatedecks.Thesteelgratingorcheckeredplateflooringissupportedbysteelbeamswhich,inturn,aresupportedbyradialornonradialsteelgirdersspanningfromthereactorpedestalortheBSWtotheprimarycontainmentwall.Thisfloorframingsystemisbracedagainstlateralmovement.Thesteelgirdersaresimplysupportedattheprimarycontainmentwallbybeamseatarrangementsandarepinconnectedtotheembedmentplatesatthereactorpedestalend.3.8.3.2ApplicableCodes,Standards,andSpecificationsThedesigncodes,standards,specifications,andregulationsusedinthedesign,procurement,fabrication,andconstructionofthesteelandconcretecontainmentinternalstructures,meetorexceedtherequirementsoutlinedinSection3.8.4.2forthedesignofCategoryIstructures.Theprocurementspecificationrequirementsforconcrete,reinforcingsteel,andothermaterialsusedinthedrywellfloorandtheRPVpedestalaredescribedinSection3.8.4.2.ThesummaryoftheprocurementanderectionspecificationsfortheBSWandthestartrussaregiveninSections3.8.3.2.1and3.8.3.2.2,respectively.3.8.3.2.1BiologicalShieldWallDesignandconstructioncriteriafortheBSWare:1~2~esiStressesAISCSpecificationfortheDesign,Fabrication,andErectionofStructuralSteelforBuildings,1969.uaitooTesting,inspection,anddocumentation,ANSIN45.2.5and10CFR50AppendixB.3~WedeualcationASMESectionIXorAWSD1.1.USARRevision83.8-30November1995 NineMilePointUnit2FSAR4.~ed~nqAWSD1.1withtheexceptiontoSection3.3thatanoffsetof1/2inmaximumispermitted.5.NDEEamiatoforWeldinUltrasonicinspectionorprogressive<magneticparticlemethodofinspection.6.acS'toraeadandliofMaterialsANSIN45.2.2andRG1.38.7~XWJlllLZil'allplates,stiffeners,baseplate,soleplate,doors,andboltsover1indiameter.8.~~t~RG1.54.9.~ErectioAISCSpecificationfortheDesign,Fabrication,andErectionofStructuralSteelforBuildings,1969,andAWSD1.1.3.8.3.2.2StarTrussDesignandconstructioncriteriaforthestartrussare:1.esitessesASMESectionIII,SubsectionNF,1977,unstamped.2~3~4~5~litCotTesting,inspection,anddocumentation-10CFR50AppendixB,ASMESectionIII,SubsectionNF.'catoaeld'SMESectionIII,SubsectionNF,unstamped,AWSD1.1.EtioforWedinASMESectionIII,SubsectionNF,ASMESectionV,progressivemagneticparticleinspection.caSiinStoraeandHandlinofMaterialsANSIN45.2.2andRG1.38.6~~~~RG154.7.~yet~AWSD1.1andASMESectionIII,SubsectionNF,unstamped.3.8.3.3LoadsandLoadingCombinations3.8.3.3.1DrywellFloorandReactorVesselPedestalTheloadsimposedontheseconcretestructures,thenotationsused,andtheloadcombinationsarethesameasthoselistedinSection3.8.1.3forconcretestructures.USARRevision83.8-31November1995 NineMilePointUnit2FSAR3.8.3.3.2BiologicalShieldWallFornormaloperatingloadingcombinations,thedesignstressesfortheBSWareinaccordancewiththeAISCSpecificationfortheDesign,Fabrication,andErectionofStructuralSteelforBuildings;however,forabnormaland/orextremeenvironmentaldesignloadcombinations,theallowableelasticstressesareincreasedinaccordancewithfactored(e.g.,1.6,1.8,2.0)sectionalstrengthsasshowninloadcombinationequations3through6ofTable3.8-9.TheBSWisanalyzedanddesignedforavarietyofindividualpiperuptureforcesandassociatedpressures.EachsectionoftheBSWisdesignedtosatisfythemaximumpipeloadingconditionforthatarea.TheloadcombinationequationsusedforthedesignoftheshieldwallarepresentedinTable3.8-9.TheBSWisalsodesignedforhydrodynamicloadcombinationslistedinTable3.8-10,PartII.3.8.3.3.3StarTrussThestartrussloads,notations,andloadcombinationsarethesameasthoselistedinSection3.8.4.3forsteelstructures.Additionally,thestartrussischeckedfortheeffectofSRVloadingresultingfromsuppressionpoolhydrodynamics,inadditiontootherconcurrentloadingaslistedinTable3.8-10,PartII.3.8.3.4DesignandAnalysisProcedures3.8.3.4.1DrywellFloorThedrywellfloorisanalyzedanddesignedfortheloadcombinationsoutlinedinSection3.8.4.3.TheanalysisprocedureusedisoutlinedinSection3.8.3.4.2.ThefollowingeffectsofapotentialLOCAoccurringwithinthedrywellareconsideredinthedesign:1.Jetimpingementforcesonthedrywellfloor.2.Impactloadstransmittedtothedrywellfloorbyanyattachedpipewhiprestraints.3.Differentialpressureacrossthedrywellfloorof:a.25psi(drywellpressuregreaterthansuppressionchamber).b.10psi(suppressionchamberpressuregreaterthandrywell).Additionally,thedrywellfloorisdesignedfordeadload,seismic,thermal,andhydrodynamicloading(Appendix6A).USARRevision83'-32November1995 NineMilePointUnit2FSARAllloadsappropriatelycombinedwillnotcompromisetheintendedfunctionofthedrywellfloortoprovideabarrierbetweenthedrywellandsuppressionchamber.StressresultantsarecalculatedusingelasticmethodsinaccordancewithACI-318andtheAISCSpecificationfortheDesign,Fabrication,andErectionofStructuralSteelforBuildings,asapplicable.ReinforcementarrangementsinthedrywellfloorareshownonFigure3.8-13.3.8.3.4.2ReactorPedestalThepedestalisanalyzedanddesignedfortheloadcombinationsoutlinedinSection3.8.4.3.Inertialoadingsfromearthquakesareobtainedfromthedynamicanalysesofthereactorbuilding,asoutlinedinSection3.7A.2.ThereactorpedestalanddrywellfloorareanalyzedusingSHELL1,afiniteelementcomputerprogram(Appendix3A).Thestructuresaremodeledusingaxisymmetricshellelements.Theasymmetricloadings(e.g.,seismicloads)arerepresentedbyaseriesofFouriercoefficients.Theboundaryconditionsforthepedestalareconsideredtobefixedatthejunctionwiththefoundationmat.Fortheboundaryconditionsatthetopofthepedestal,forcesatthebaseoftheBSWandRPVresultingfromtheloadsdefinedinSections3.8.3.3.2and3.8.4.3,respectively,wereappliedtotheSHELL1model.Theboundaryconditionsforthedrywellflooratthejunctionwiththeprimarycontainmentreflectthestiffnessoftheprimarycontainmentatthejunction.DesignofthepedestalconformstotherequirementsofACI-318-71.Arrangementsofreinforcementatthemat-pedestalandpedestal-BSWinterfaceandinthepedestalwallareshownonFigure3.8-14.ThetopportionofthepedestalisdesignedtoresistallseismicandpiperuptureforcestransmittedfromthereactorvesselskirtandthebaseoftheBSW.Piperuptureforcesanddiscontinuityforcesatthebaseof"theBSWresultingfrompressurizationoftheannulusbetweenthereactorvesselandBSWduringarecirculationorfeedwaterlinebreakareusedtoanalyzeanddesignthepedestalincombinationwiththeseismicforcesdeterminedfromthedynamicanalysisofthereactorbuilding.Inaddition,thepedestalisanalyzedanddesignedforjetimpingementandpiperuptureloads.ToensurethatthepedestalcrackingproblemthatoccurredintheJamesA.FitzPatrickNuclearPowerPlantdoesnotoccurintheUnit2pedestal,theconstructiontechniqueandtheanchoragedetailfortheBSWaremodified.BecauseoftheBSWconstructiontechniquedescribedinSection3.8.3.6.2,theweldshrinkageanddistortionusuallyencounteredduringfabricationandassemblyhavestabilizedpriortotheBSW'sattachmenttothereactorpedestal.Inaddition,theBSWisdesignedtoallowradialUSARRevision83'-33November1995 NineMilePointUnit2FSARmovementduetothermaleffectswithlimitedeffectonthereactorpedestal.Therefore,thereactorpedestalisadequatelydesignedandwillmaintainitsstructuralintegrityfortheeffectsofBSWloading.3.8.3.4.3BiologicalShieldWallTheBSWisanalyzedanddesignedfortheloadcombinationsdescribedinSection3.8.3.3.2.Analysisofthewallisperformedusingthetwo-dimensionalfiniteelementcapabilityoftheSTRUDLcomputercode.Bothplanestressandplatebendingelementswereused.Asthestructureissufficientlysymmetrical,onlyone-halfofthestructure(i.e.,180deg)needbemodeled.Theboundaryconditionatthetopofthestructureapproximatestheeffectofthestartrussstructure.Theboundaryconditionatthebottomofthestructureisconsideredanequivalentofspringsconnectedtothepedestalinthecircumferentialandverticaldirectionsandunrestrainedinradialdirection.Theuseofa180-degmodelallowsfortheanalysisofasymmetricloadingsbyapplyinghalfoftheloadtothemodelwithsymmetricboundaryconditionsandhalfwithasymmetricboundaryconditions.Theresultsofthetwoanalysesarethensuperimposedforthenetresults.Inaddition,classicalbeamtheoryandplateandshelltheoryareusedfortheanalysisanddesignoflocalareas.ThefollowingloadsareconsideredintheanalysisanddesignforLOCAeffects:1.JetimpingementforcesontheBSW.2.ImpactloadstransmittedtotheBSWbyanyattachedpiperupturerestraints.3.PressurizationoftheannulusbetweentheBSWandreactorvessel.4.Thermaleffects.TheseloadsarecombinedinaccordancewithSection3.8.3.3.2,takingaccountofthepostulatedfailurelocationsandtypes.Ithasbeenconcluded,becauseofthedynamiccharacteristicsoftheBSW,thatthepeakrestraintimpactloadsarelocalimpulsiveloadsontheBSW.Theseimpactloadsoccurinthefirstmillisecondsafterrupture.Theshieldwallisallowedtoyieldlocallyatregionsofimpactloadsprovidedthat:1~Overallcapabilityoftheshieldwalltoresistelasticallytheotherforceslistedisnotaffected.2~Localyieldingdoesnotproduceeffectsthatjeopardizethesafetyofothercomponents.USARRevision83.8-34November1995 NineMilePointUnit2FSAR3.8.3.4.4StarTrussThestartrussisacantileveredplanetrussthattransmitshorizontalforcebetweenthetopoftheBSWandtheprimarycontainmentwall(Section3.8.3.1.4).ThetrussjointsattheBSWendareconsideredfixed.Thesupportattheprimarycontainmentwallendisconstrainedinthecircumferentialdirectionsothatonlytangentialhorizontalforcecanbetransmittedtotheprimarycontainmentwall.ThestartrussisanalyzedusingtheSTARDYNEcomputerprogram(Appendix3A)andisdesignedfortheloadcombinationslistedinSection3.8.3.3.Thecompletestructureismodeledusingacombinationofbeamandplateelementsforthefiniteelementmodel.Thebeampartofthemodelrepresentsthestartrusspartofthestructure,whiletheplateelementsrepresenttheremainingpartsofthestructure.ThestructureisdesignedusingtheSTARDYNEcomputerprogramforeachindividualloadingcondition,andthestressesarecalculatedbysuperimposingtheapplicableloadswithappropriateloadfactorsforeachloadcombinationdescribedinSection3~8~3~3~3.8.3.4.5FloorsThestructuralsteelframingsystemforfloorswithintheprimarycontainmentareanalyzedusingtheSTRUDLcomputerprogram,asnecessary,fortheloadsandloadcombinationsoutlinedinSection3.8.4.3.Thefloorframingsaresupportedverticallyatthecontainmentendaswellasatthereactorpedestalend.Theconnectionatthepedestalendistreatedasapinnedconnectionwhereastheconnectionatthecontainmentendprovidesslidingsupporttotheframingmembers.TheSTRUDLcomputerprogram(Appendix3A)isusedtoanalyzethefloorsandplatforms.Theeffectsofdynamicloading,suchasSRV,seismic,andLOCA,areconsideredwhileanalyzinganddesigningthesemembers.Thedesignparameters,allowablestresses,andmaterialproperties,asdescribedinSection3.8.4,areselectedinaccordancewiththerequirementsoftheAISCSpecificationfortheDesign,Fabrication,andErectionofStructuralSteelforBuildings.3.8.3.5StructuralAcceptanceCriteriaForconcretestructures,theallowablestresses,loadfactors,andcapacityreductionfactorsareinaccordancewithstrengthdesignmethodsofACI-318-77,withthefollowingexception:designforhorizontalshearforcesisinaccordancewiththerequirementsofACI-318-71whichincorporatesthecombinedeffectsofshearandtensilestressesintothenominalallowableshearstress,vtobecarriedbytheconcrete.USARRevision83.8-35November1995 NineMilePointUnit2FSARTangentialshearstress(v)resultingfromearthquakeloadingwillberesistedbytheconcreteorbytheconcreteandsteelreinforcingbars.Thetangentialshearstress(v,)carriedbytheconcreteistakenequaltooneofthefollowingvalues:v,=12,000pforp<0.01,orv,93+2,700pfor0.01~<<0.025Where:p=Lesserofthesteel-to-concreteratiosintheverticalorcircumferentialdirectionv,=Tangentialshearstress,psiForsteelstructures,theallowablestressesandsafetyfactorsareinaccordancewiththeAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings,withthefollowingexceptions:1~Nocreditistakenforthe331/3-percentincreaseinallowablestresses,S,permittedintheAISCCodewhenearthquakeandwindloadsarepresentintheloadcombinations.2~Thestructuralmembersofthestartrussaredesigned(unstamped)inaccordancewithASMEBoilerandPressureVesselCode,SectionIII,Division1,SubsectionNF,1977EditionincludingSummer1978addenda.TheallowablestresslimitssetforthinAppendixXVIIofthiscodeareusedindesigningthestructures.3.8.3.6Materials,QualityControl,andSpecialConstructionTechniquesTheconstructionmaterialsandthequalitycontrolrequirementsusedforthecontainmentinternalstructuresarethesameasthoseusedforotherCategoryIstructures,asdescribedinSection3.8.4.6.Whennecessary,thespecialmaterialsandthespecialconstructiontechniquesareusedasdescribedinSections3.8.3.6.1through3.8.3.6.3.3.8.3.6.1ReactorVesselPedestalandDrywellFloorPrecastconcretebeamsandstainlesssteelbeamsareusedasstay-in-placeformstosupportthedrywellfloorduringconstruction.Thesupportsystemforthedrywellfloorbetweenthereactorvesselpedestalandprimarycontainmentatel240ftconsistsof20precastbeamsspanningradially.Stainlesssteelbeamsspanbetweentheprecastbeams.Insidethereactorvesselpedestal;thesupportsystemfortheslabatel232ftconsistsoftwoprecastconcretebeamssupportingstainlesssteelbeams.USARRevision83.8-36November1995 NineMilePointUnit2FSARThelineronbothsidesofthereactorvesselpedestalinthesuppressionchamberservesastheformforpouringconcrete.Aregularformisusedfortheupperpoxtionofthepedestal.3.8.3.6.2BiologicalShieldWallTheBSWinnerandouterwalls,stiffeners,andbaseplatearemanufacturedinaccordancewiththeASTMA537Class1specification.Inaddition,thestiffenersandbaseplatecontainamaximum0.01percentsulfurtoincreasethethrough-thicknessdirectionproperties.TheASTMA537Class1steelplatesare100-percentultrasonicallytestedtotheASTMA578LevelIspecification.TheBSWanchorboltsaremanufacturedtoASMESA-193GradeB7specificationandarenondestructivelyexaminedbyeithermagneticparticleorliquidpenetrantmethodsinaccordancewithASMESectionIII,SubparagraphNF-2581.1.TheBSWisfilledwithaheavy-densityfillmaterialthatisinstalledusingapressuregroutingtechnique.Thetechniqueconsistsofpumpingheavy-densityfillmaterialatthebaseoftheshieldwallandallowingittoflowupwardthroughthecompartmentstoapredeterminedliftheightforcinganytrappedairaheadofthefillmaterial.ThisprocesscontinuescircumferentiallyandverticallyaroundtheBSWuntiltheentirestructureisfilled.TheBSWisshopfabricatedinthreerings,fthigh.Eachringisfabricatedinthreesectionsareassembledatthesitetoformwhicharethenstackedandweldedtogethereachapproximately16120-degsections.Thethree360-degringstoformtheBSW.3.8.3.6.3StarTrussThematerialusedinthestartrussassemblyisSA-537,Class1,LukensLectrefine,exceptthatthediagonalmembersofthetrusssystemaretubularincrosssection,conformingtoSA-333Grade6.TheringgirderatthetopoftheBSWismadeofASTMA537,Class1,LukensLectrefinematerial.Thetrussconnectionsareweldedconnectionswithfullpenetrationwelds.3.8.3.7TestingandIn-serviceSurveillanceRequirementsDrywellpressurizationtestsareperformedinaccordancewiththerequirementsofTechnicalSpecificationsandAppendixJto10CFR50.TestingoftheconstructionmaterialsreferencedinthissectionisdescribedinSection3.8.4.6.AdrywellfloorstructuraltestisperformedandisdescribedinSection3'.1'SARRevision83.8-37November1995 NineMilePointUnit2FSAR3.8.4OtherSeismicCategoryIStructures3.8.4.1DescriptionoftheStructuresAsshowninTable3.2-1,otherseismicCategoryIstructures(e.g.,dieselgeneratorbuilding,controlbuilding)thatcontainorsupportsafety-relatedsystemsand/orequipmentaredesignedtowithstandtheSSE.Thesestructures,exceptforthemainstack,arealsodesignedtowithstandtornadoloadsincludingtornado-generatedmissiles.Seismicloadsarenotconsideredtoactsimultaneouslywithtornadoloads.Table3.2-1identifiesseismicCategoryIequipmentandstructuresthataretornadoprotected.Ingeneral,seismicCategoryIstructures,hereincalledCategoryIstructures,arecompletelyindependentofadjacentstructures.Adequatespaceisprovidedbetweenstructurestoretaintheirindependentfunctionalcharacteristics,andtoallowforrotation,translation,anddeformationunderseismicloading.Thespaceshaveflexibleseals(Figure3.8-17).StructureshavingbothCategoryIandnonseismiccategoryelementsaredesignedusingtheCategoryIcriteriafortheCategoryIportionsofthestructures.TheCategoryIstructuresorportionsofthestructuresarealsoinvestigatedtodeterminetheeffectoffailureofnonseismiccategorystructuresorportionsofthestructures.Ifitisdeterminedthattheirfailure(underCategoryIloadingconditions)couldendangertheintegrityoftheCategoryIportionsofthestructures,thenthenonseismicstructuresorportionsarealsodesignedtoCategoryIcriteria.Intheseinstances,whereCategoryIstructuresareintegrallyconnectedtotheotherstructures,theCategoryIstructuresareanalyzedanddesignedconsideringtheeffectoftheinterconnectionandmodeledwiththeconnectingstructure(s)asaunit.ThoseportionsoftheCategoryIstructureslocatedbelowtheDBFLareprovidedwithwaterstops(Figure3.8-17).Vermiculite,.vermiculiteconcrete,orcompressiblematerialsareusedbetweentheexteriorfaceofsubstructureconcretewallsandtheexcavatedfaceofrocksurfaces,asdescribedinSection2.5.4.10.Nouniquematerialsorfeaturesareusedinthedesignorconstructionofthestructuresdescribedinthissection.TherelativelocationsoftheCategoryIstructuresareshownonFigures1.2-1and1.2-2.ThegeneralarrangementofoperatingpersonnelaccessbetweenthebuildingsisshownonFigures1.2-3through1.2-5.ThegeneralarrangementsoftheCategoryIbuildingsareillustratedinthefollowingfigures:Reactorbuildingincludingauxiliarybays,Figures1.2-6through1.2-12Auxiliaryservicebuilding,Figures1.2-7and1.2-8Radwastebuilding,Figures1.2-13and1.2-14USARRevision83.8-38November1995 NineMilePointUnit2FSARStandbygastreatmentbuilding,Figures1.2-35and1.2-36Controlroombuilding,Figures1.2-15and1.2-16Screenwellbuildingincludingservicewaterpumproom,.Figures1.2-26through1.2-28Intaketunnels,Figures1.2-29and1.2-30Mainstack,Figure1.2-31Dieselgeneratorbuilding,Figures1.2-17and1.2-18Offgasrooms,Figures1.2-19through1.2-25Intakestructure,Figure1.2-29and1.2-30ThegeneralarrangementsofthemajorbuildingsthatarenotCategoryIareillustratedinthefollowingfigures:Turbinebuilding,Figures1.2-19through1.2-25Natural-draftcoolingtower,Figures1.2-38and1.2-39Servicebuilding,Figure1.2-19and1.2-22Regenerationandcondensatedemineralizerregenerativerooms,Figures1.2-19through1.2-25Auxiliaryboilerbuilding,Figure1.2-34Normalswitchgearbuilding,Figures1.2-32and1.2-33Hydrogenstoragearea,Figure1.2-40CSTbuilding,Figure1.2-37TheCategoryIstructuresotherthantheprimarycontainmentanditsinternalstructuralcomponentsaredescribedinthefollowingsections.Fortheprimarycontainmentanditsinternalstructuralcomponents,refertoSections3.8.1and3.8.3,respectively.3.8.4.1.1ReactorBuildingThereactorbuildingcompletelyenclosesthereactorandtheprimarycontainment.Thereactorbuildinghousestherefuelingandreactorservicingequipment,newandspentfuelstoragefacilities,andotherreactorauxiliaryorserviceequipment,includingtheRCICsystem,reactorwatercleanup(RWCU)system,SLCsystem,CRDsystemequipment,corestandbycoolingsystems,RHRsystems,andelectricalequipmentcomponents.TheprimarypurposesforthesecondarycontainmentaretominimizegroundlevelreleaseofairborneradioactivematerialsandtoprovideUSARRevision83.8-39November1995 NineMilePointUnit2FSARmeansforacontrolledelevatedreleaseofthebuildingatmosphereifanaccidentshouldoccur.Thereactorbuildingwallisa166-ftIDreinforcedconcretecylinderwithvaryingwallthickness,extendingfromthetopofthematatel175fttothepolarcranelevelatel386ft10in.Thewallfromthecranerailelevationtotheroofatel430ft1in(approximately40ft)issteelframingwithinsulatedmetalsiding.Themetalsidingpanelshavesealedjointstominimizeairleakage.Roofconstructionconsistsofsteeltrusses,whichsupportmetaldecking,coveredwithinsulation,andasphaltandgravelbuilt-uproofing.Thestructuralsteelframeofthereactorbuildinguppersuperstructureisdesignedtowithstandthetornadowindwiththemetalsidingremaininginplaceduringatornadicevent.Thereactorbuildingroofdeckingisdesignedfornormalwindloading.Whenthedesignvelocityisappreciablyexceeded,thedeckingmayblowoff.Thereactorbuildingmetalsidingisdesignedtowithstandwindloadsgeneratedduringatornadicevent.Variousfloorlevelsformdiaphragmswithinthesecondarycontainmenttoprovidesupportforandaccesstoequipment.Thefloorandwallthicknessesmeetbothshieldingandstructuralrequirements.Thereactorbuildingsuperstructurefloorsandwallsareentirelyseparatedfromtheprimarycontainmentstructurebyaspacethatpreventsthereactorbuildingfromrestrainingtheprimarycontainmentunderanycondition.Therefuelingfloorlevelcontainsthefuelpoolandissupportedbythereactorbuildingwallandthefuelpoolgirders.ThearrangementdetailsofthereactorbuildingwallandreinforcedconcretefloorlevelsareshownonFigures1.2-6through1.2-12.Aportionofthemainsteamtunnelisanintegralpartofthereactorbuildingbetweentheprimarycontainmentandthereactorbuildingwall.Thereactorbuilding,includingtheauxiliarybays,isfoundedonarock-bearing,reinforcedconcretematandisdesignedfortheloadcombinationsinSection3.8.4.3.Thematactstosupportthereactorbuilding,auxiliarybays,andtheprimarycontainment.Theauxiliarybaysarerigidlyattachedtothereactorbuildingandconsideredpartofthesecondarycontainmentstructure.ThedrainagesystemaroundthereactorbuildingisdescribedinSection2.5.4.6.USARRevision83.8-40November1995 NineMilePointUnit2FSAR3.8.4.1.2ControlRoomBuildingThecontrolroombuildingisaCategoryIstructure.Itisafive-storyconcreteandsteelstructure96by134ftinplanandisdesignedforearthquakeandtornadoloads.Theexteriorwallsandroofareconstructedofaminimumof2-ftthickreinforcedconcreteandaredesignedtoprovidetornadomissileprotection.Theinteriorfloorsareconcretedeckingsupportedbysteelframing.Thebuildingisfoundedonbedrockandissupportedbyareinforcedconcretematatel209ft6in.Thecontrolroombuildinghousesthecontrolroom,safety-relatedswitchgear,batteries,andassociatedequipment.Theupperfourfloorsarereinforcedconcreteslabsonsteeldecksupportedbystructuralsteel.Twosteel-framedgratingstairwaysareprovidedforaccesstotheupperfloors.Inaddition,accesstotheturbinebuildingisprovidedateachfloor.Undergroundconcretetunnelsconnectthecontrolroombuildingtothreepointsofentryintothereactorbuilding.Thesetunnelsaredesignedtoresistbothtornadoandearthquakeloads.Thedieselgeneratorbuildingislocatedsouthofandadjacenttothecontrolroombuilding.3.8.4.1.3DieselGeneratorBuildingThedieselgeneratorbuildingisasingle-story,CategoryIstructure87by98ftinplan,enclosingthethreedieselgeneratorsandtheir.associatedequipmentwithagroundfloorslabatel261ft.Thedieselgeneratorsaresupportedonreinforcedconcretepedestals.Thebuildingisdividedintothreeroomsseparatedbyfirewalls,eachhousingonedieselgenerator.Threefueloilstoragetanksarelocatedbelowthebuilding,withtheirfueloilpumpshousedintheindividualdieselgeneratorrooms.Thedieselgeneratorbuildingisareinforcedconcretestructurefoundedonbedrockandsupportedbywallfootings.Theexteriorwallsandroofareaminimumof2ftthickandaredesignedtoprovidetornadomissileprotection.Allventilationintakesarearrangedtoprecludepenetrationfromtornado-generatedmissiles.Thedieselgeneratorexhaustsilencerisnotprotectedbyamissilehood;however,anexhaustreliefvalveisprovidedtomaintainthedieselgeneratorfunction,andthisexhaustreliefvalveisprotectedagainstmissiles(seeSections9.5.8.1and9.5.8.2).Thebuildingislocatedsouthofthecontrolroombuilding.Personnelaccesstothebuildingisprovidedfromthecontrolroombuilding.3.8.4.1.4ScreenwellBuildingThescreenwellbuildingconsistsofaconcretesubstructureandasteelframesuperstructure.Thesubstructure,includingtheservicewaterpumproom,isdesignatedCategoryI,whereastheUSARRevision83.8-41November1995 NineMilePointUnit2FSARsteelframesuperstructureincludingthecirculatingwaterpumpandwatertreatmentareaisdesignedasanon-CategoryIarea.Thescreenwellbuildingincludestheservicewaterpumprooms,thedieselandelectricfirepumprooms,thewatertreatmentarea,thecirculatingwaterpumps,andotherassociatedequipment.Stoplogs,travelingscreens,trashrakes,etc.,aresetintheconcretewalls,asrequiredtodiverttheflowofwater,andformaintenancepurposes,respectively.Thesecomponentsarebuilt-upstructuresofsteelandconcreteguidedandsupportedbythereinforcedconcretewallsandfloors.Thescreenwellbuildingconcretesubstructureconsistsofwallsandslabsarrangedtodirecttheflowoflakewaterandtosupportequipmentincludingcirculationwaterpumps,trashracks,andscreens.Thescreenwellbuildingsuperstructureisasteelbuilding140by220ftwithinsulatedmetalwallpanels.Thesteelroofdeckiscoveredwithinsulationandfour-ply,built-uproofing.Thesafety-relatedservicewaterpumpsareenclosedinatornado-resistant,concretestructurewithinthescreenwellbuilding.Thedieselandelectricfirepumpsareenclosedinseparateconcreteroomsinthescreenwellbuilding.Northofthescreenwellbuilding,thereareconcretechambersthathousethereverseflowgates.Thesegatesarelocatedadjacenttotheintakeanddischargeshafts.Theshaftsextendverticallydownintobedrocktoel120ftandterminateattheintakeanddischargetunnels.3.8.4.1.5IntakeStructuresThetwoCategoryIintakestructuresarehexagonal-shapedreinforcedconcretestructuresconnectedtotheintakeanddischargetunnels.Thestructuresrestonatremieslabfoundedonbedrockatthelakebottomandareanchoredtotheconcrete-encasedsteeltiedownsembeddedintotherock.Eachhexagonal-shapedintakestructurehasaface-to-facedimensionofapproximately29ftandaheightof10ft6in.Thecontinuityofwaterflowintotheintaketunnelisassuredbymeansofelectricallyheatedbarracks,oneateachfaceofthehexagon.3.8.4.1.6Intake(andDischarge)TunnelsThegeneralarrangementanddetailsofintake(discharge)tunnelsareshownonFigure1.2-29.AsnotedonSheet2ofFigure1.2-29,thetunnelsarelinedwith31/2inshotcrete.Thetwotunnels(13ft5inx13ft5in)extendfromthescreenwellshaftabout1,400and1,300ft,respectively,eastwardandnorthwardunderLakeOntariototheintakestructures.Thenonseismiccategorydischargetunnelextendsanadditional500ftUSARRevision83.8-42November1995 NineMilePointUnit2FSARbeyondtheintakestructuretothedischargediffusers.Thetunnelsarelinedwith31/2inshotcrete.WithinTunnelNo.1,theintakewaterflowsthrougha4ft6inIDformedopeningin~an8ft4inwideby6ft9inhighCategoryIconcreteencasement.Thedischargewaterflowsaroundtheconcreteencasementwithinthetunnelandiseventuallydischargedintothelakeviaadischargediffuser.Thetunnelsarenormallyflooded.3.8.4.1.7ElectricalTunnelsandPipingTunnelsCategoryIelectricaltunnelsandpipingtunnels(Figure1.2-2)containCategoryIsystemsandareconstructedofreinforcedconcrete.Thetunnelwallsandroofareofsufficientthicknesstoresistpenetrationbytornadicmissiles,orthetunnelsareburiedundergroundasrequiredformissileprotection.Tunnelsareisolatedfromadjoiningstructuresbyaspaceexceptthattheyareintegrallyconnectedtotheadjacentstructureswhenrequiredtopreventslidingoverturningand/orflotation.CategoryIelectricalandpipingtunnelsareprotectedfromexternalfloodingby:1.Sealingthespacebetweenthetunnelsandtheadjoiningstructuresusingwaterstopsandflexibleseals(Figure3.8-17).2.Providingallpenetrationsbelowgradewithairandwaterseals,asapplicable.3.8.4.1.8MainStackTheCategoryIunlinedconcretemainstacklocatedonthenortheastsideofthepowerstationisdesignedandconstructedtoprovideelevatedreleaseofoffgas,standbygastreatment,turbinebuildingventilation,andothersystems.TheoperatingconditionsforthemainstackaredescribedinSections6.5.1,9.4.4,and11.3aspartofthesystemdescription.Thebaseofthematisatel242ft.Theground-levelslabisatel261ftandthetopslabisatel276ft.Theinsidebasediameterisapproximately26ftandtheinsidetopdiameterisapproximately6ft.Theheightofthestackisapproximately430ft.3.8.4.1.9StandbyGasTreatmentBuildingandRailroadAccessLockAreaThestandbygastreatment(SGT)buildingandrailroadaccesslockareaareclassifiedCategoryIstructuresuptoel286ft.Theportionofthebuildingaboveel286ftisclassifiedasnonseismic.USARRevision83.8-43November1995 NineMilePointUnit2FSARTheSGTbuildingisatwo-story,reinforcedconcreteandsteel-framedstructureapproximately40x90ft.Thestructuresharesacommonwallwiththerailroadaccesslockadjacenttothereactorbuilding.Thereinforcedconcretefloorslabisprovidedatthegradelevelofel261ft.Theroofissteeldeckwithinsulationandfour-ply,built-uproofing.Arailroadaccesslockapproximately25x90ftisprovidedadjacenttothereactorbuilding.Thisbuildingisareinforcedconcreteandsteel-framedstructureandsharesacommonwallwiththeSGTbuilding.Thereinforcedconcretefloorslabisprovidedatthegradelevelofel261ft.Theroofissteeldeckwithinsulationandfour-ply,built-uproofing.Interlockingswingingdoorsareprovidedateachendofthestructure.Theexteriordoorisdesignedtowithstandtornado-generatedmissiles.Doorsaregasketedtominimizeairleakage.Theinterlocksbetweenthesetsofdoorssafelypreventthedoorsatoneendfrombeingopeneduntilthedoorsattheotherendhavebeenclosedandsealed.Thisbuildingisdesignedtoaccommodatea66-ftlongrailroadcar,plus8ftforatrack-mobileengine.3.8.4.1.10AuxiliaryServiceBuildingTheauxiliaryservicebuildingisatwo-story,reinforcedconcreteandsteel-framedstructureapproximately55x76ftinplan.Theauxiliaryservicebuildingbelowel261ftisclassifiedasaCategoryIstructure.Thebuildingissurroundedbythereactorbuilding,turbinebuilding,andcontrolbuilding.Thebasementfloorisaconcreteslabpouredoverelectricaltunnels.Theflooratel261ftisaconcreteslabonsteeldecksupportedbystructuralsteel.Theroofissteeldeckwithinsulationandfour-ply,built-uproofing.3.8.4.1.11RadwasteBuildingTheradwastebuildinghousestheradioactivewastesystemandisanalyzedtoseismicconditions.Itisafive-story,concreteandsteelbuilding,approximately110x150ft.Theexteriorwallsarereinforcedconcrete.Arollingsteeldoorisprovidedinthenorthwallfortruckaccessintothebuilding.TheradwastebuildingisclassifiedasshowninTable3.2-1.Whererequiredforshieldingpurposes,interiorconcretewallsareprovided.Thebasementfloorisaconcretematonrock.Theupperfourfloorsareconcretesupportedbysteeldeckandbeams.Theroofconsistsofsteelframingwithsteeldeck,insulation,andfour-ply,built-uproofing.Twosteel-framedgratingstairwaysareprovidedforaccesstotheupperfloors.Thedecontaminationareaislocatedsouthoftheradwastebuilding.Itisanextensionoftheturbinebuildingandtheradwastebuilding.Thestructureisafour-storybuildingofconcreteandsteelapproximately110x105ftinplan.Theexteriorwallsareofreinforcedconcrete.ThesuperstructureisUSARRevision83.8-44November1995 NineMilePointUnit2FSARcoveredwithinsulatedsteelroofdeckwithfour-ply,built-uproofing.3.8.4.1.12TurbineBuildingTheturbinebuildingcomplexincludestheturbinebuilding,heaterbays,mainsteamtunnel,andcondensatedemineralizerregenerativeandoffgasarea.Thecomplexhousestheturbinegenerator,condenser,moistureseparator,etc.,intheturbinebuildingareas,heatersandrelatedpumpsandaccessoriesinheaterbayareas,andoffgassystemequipmentandtanksinoffgasareas.Aportionofturbinebuilding,mainsteamtunnelarea,andoffgasareaareanalyzedtoseismicconditions,whereastheremainingportionsaredesignedasnonseismic.Theturbinebuildinghousestheturbinegeneratorandassociatedauxiliarysystems.Theheaterbaywhichhousesthefeedwaterheatersisadjacenttoandnorthoftheturbinebuilding.Eastoftheturbinebuilding,themainsteamtunnelconnectstheturbinebuildingwiththereactorbuilding.Northoftheturbinebuildingandwestoftheheaterbay,theregenerationandcondensatedemineralizerarea,offgasroom,buildingserviceequipmentarea,andturbinebuildingrailroadpassagearelocated.Theturbinebuildingisaconcreteandsteel,three-storybuilding,approximately130x333ft.Aslabisprovidedatel250ft.Allfourwallsareofreinforcedconcreteuptoel261ft.Abovethiselevation,thestructureissteelframed.Whereexteriorconcretewallsarerequiredforshieldingpurposes,thestructuralsteelisencasedintheconcretewalls.Insulatedmetalwallpanelsareusedforexteriorwalls.Thesteeldeckroofiscoveredwithrigidinsulationandfour-ply,built-uproofing.Smokeventsareinstalledontheroof.Theturbinebuildingoperatingfloorisconcretesupportedbysteeldeckandbeams.Exceptwhereconcretefloorsarerequiredforshielding,themezzaninefloorissteel-supportedgalvanizedsteelgrating.Accesstotheuppertwofloorsoftheturbinebuildingisprovidedbythreesetsofsteel-framedgalvanizedgratingstairsandthreeelectricelevators.Theturbinepedestalsupportisofreinforcedconcreteandlocatednearthecenteroftheturbinebuilding.Thesupportisisolatedfromtheturbinebuildingbyvibrationjointsatthemezzaninefloorel277ft6inandattheoperatingfloorel306ft.Thethree-storyheaterbayislocatednorthoftheturbinebuildinganddividedintothreeareasbyconcretewalls.Theexteriorwallsareinsulatedmetalsiding.Roofdeckwithsteelframeconstruction,rigidinsulation,andfour-ply,built-uproofingcoverstheroof.Thegroundfloorisaslabatel250ft,withthemezzaninefloorbeingsteel-supportedgalvanizedUSARRevision83.8-45November1995 NineMilePointUnit2FSARsteelgrating.Theoperatingfloorisconcreteonmetaldeckandsteelframing.Asetofsteel-framedgalvanizedgratingstairsineachofthethreeheaterareasprovidesaccesstothemezzanineandoperatingfloors.Themainsteamtunnel,whichconnectstheeastendoftheturbinebuildingwiththereactorbuilding,isaconcretestructure.Thethicknessofthewall,slab,androofconcretemeetsbothstructuralandshieldingrequirements.Westoftheheaterbayandnorthoftheturbinebuildingistheregenerationandcondensatedemineralizerarea,theoffgasroom,andbuildingserviceequipmentarea.Thestructureistwostoriesofconcreteandsteelconstruction.Thewall,floor,androofconcretemeetshieldingandstructuralrequirements.Whereshieldingisnotrequiredforthebuildingserviceequipmentarea,insulatedmetalwallpanelsandsteelroofdeckareused.Theroofiscoveredwithrigidinsulationandfour-ply,built-uproofing.Thereisasteel-framedrailroadpassagetotheturbinebuildingatel261ftunderthebuildingserviceequipmentarea.Theexteriorwallsconsistofinsulatedmetalwallpanels.Arollingsteeldoorisprovidedintheoutsidewallandalsowheretherailroadenterstheturbinebuilding.Personnelaccessdoorsarealsoprovided.3.8.4.2ApplicableCodes,Standards,andSpecificationsCodes,specifications,standards,andregulatoryguidesthatareusedinestablishingdesignmethods,analyticaltechniques,andmaterialpropertiesforCategoryIstructuresarelistedherein.ThecriteriaforthestructuraldesignofCategoryIstructuresaredevelopedusingthefollowingregulatoryguidesandCodeofFederalRegulations:RG1~10(1~12(1~15(119'~31'37'~50'~54(1~55'~60(1~61(1~66'~69'~76(1~85'~94'~117~AppendixAof10CFR50,Criteria1,2,4,and5ofGeneralDesignCriteriaforNuclearPowerPlantsThedegreeofcompliancetothesedocumentsisdiscussedinSections1.8and3.1,respectively.ThecodesandstandardsusedinthestructuraldesignofconcreteandsteelcomponentsoftheCategoryIstructuresareasfollows:ACI-211.1-1974,1977AmericanConcreteInstitute,RecommendedPracticeforSelectingProportionsforConcreteACI-214-1965(1977tAmericanConcreteInstitute,RecommendedPracticeforEvaluationUSARRevision83.8-46November1995 NineMilePointUnit2FSARofCompressionTestResultsofFieldConcreteACI-301-1972,1975ACI-304-1973AmericanConcreteInstitute,SpecificationforStructuralConcreteforBuildings(ExceptionstothiscodearelistedinSection3.8.4.6.)AmericanConcreteInstitute,RecommendedPracticeforMeasuring,Mixing,Transporting,andPlacingConcreteACI-305-1972ACI-306-1966ACI-307-1979ACI-315-1974AmericanConcreteInstitute,RecommendedPracticeforHotWeatherConcretingAmericanConcreteInstitute,RecommendedPracticeforColdWeatherConcretingAmericanConcreteInstitute,SpecificationfortheDesignandConstructionofReinforcedConcreteChimneysAmericanConcreteInstitute,ManualofStandardPracticeforDetailingReinforcedConcreteStructuresACI-318-1971I1977ACI-347-1968AmericanConcreteInstitute,BuildingCodeRequirementsforReinforcedConcrete(ExceptionstothiscodearelistedinSection3.8.4.6.)AmericanConcreteInstitute,RecommendedPracticeforConcreteFormworkAISC1969,1978AISC1972,1976AmericanInstituteofSteelConstruction,SpecificationfortheDesign,Fabrication,andErectionofStructuralSteelforBuildings,includingSupplements1,2,and3(November1,1970,December8,1971,andJune12,1974)CodeofStandardPracticeforBuildingsandBridges,AISCManualAISI1968AmericanIronandSteelInstitute,SpecificationfortheDesignofUSARRevision83.8-47November1995 NineMilePointUnit2FSARColdFormedSteelStructuralMembers,including1972PrintingwithAddendumNo.1.ASMEIII-1971Divisions1,5,9ASMEIII-1974Division1ASMEIII-1977SubsectionNFAWSD1.1-1975through1982AWSD1.1-83AWSD12.1-75AmericanSocietyofMechanicalEngineers,BoilerandPressureVesselCode,1971EditionthroughSummer1973Addenda,SectionsII,III,Divisions1,5,and9,includingapplicablecodecases(ExceptionstothiscodearediscussedinSection3.8.1.)AmericanSocietyofMechanicalEngineers,BoilerandPressureVesselCode,1974Editionthrough1976Addenda(ExceptionstothiscodearediscussedinSection3.8.1.)AmericanSocietyofMechanicalEngineers,BoilerandPressureVesselCode,1977Edition,SubsectionNF(ExceptionstothiscodearediscussedinSection3.8.3.)AmericanWeldingSociety,StructuralWeldingCode(ExceptionstothiscodearelistedinSections3.8.4.6and3.8.3.2.)AmericanWeldingSociety,StructuralWeldingCode(ThisappliestotheminimumfilletweldsizeforSMAWofstudsonly.)AmericanWeldingSociety,RecommendedPracticeforWeldingReinforcingSteelMetalInserts,andConnectionsinReinforcedConcreteConstructionAWSD1~4-79NCIG-01,Rev.2,May7,1985AmericanWeldingSociety,StructuralWeldingCode-ReinforcingSteelVisualWeldAcceptanceCriteria(VWAC)forStructuralWeldingatNuclearPowerPlants,PreparedbyNuclearConstructionIssuesGroup(NCIG)USARRevision83.8-48November1995 NineMilePointUnit2FSARU.S.DepartmentofLabor,OccupationalSafetyandHealthAdministration.OccupationalSafetyandHealthStandards(October18,1972).NewYorkStatebuildingcodes,asrequired.Theanalysisanddesignofplantstructuresfollowthecurrentdatesoftheapplicablecodesandspecificationsatthetimeofdesign,aslistedherein.3.8.4.3LoadsandLoadCombinationsExceptwhenotherwisenotedhereinandinSections3.8.1.3,3.6.2.3,and3.8.3.3,theloadcombinationsforCategoryIreinforcedconcreteandsteelstructuresarelistedinTables3.8-11and3.8-10,respectively.TheloadcombinationsforintaketunnelsarelistedinTable3.8-12.Thereinforcedconcretestructureswithintheprimarycontainment,theexteriorreactorbuildingwall,andthereactorbuildingfoundationmatarealsodesignedtowithstandSRVandsuppressionpoolhydrodynamicloading,usingappropriateSRVloadcombinationslistedinTable3.8-11,PartII.Additionally,thesteelstructureswithintheprimarycontainment(e.g.,BSW,startruss)andsteelframingforfloorandequipmentsupportsinthereactorbuildingaredesignedtowithstandSRVandsuppressionpoolhydrodynamicloading,usingappropriateSRVloadcombinationslistedinTable3.8-10,PartII.3.8.4.4DesignandAnalysisProceduresAllotherCategoryIstructuresareanalyzedanddesignedasdescribedherein.ThestructuresareanalyzedanddesignedfortheloadcombinationsasoutlinedinSection3.8.4.3.CategoryIstructuresaresupportedonreinforcedconcretematorwallfootings.ThedesignofreinforcedconcretecomponentsofthestructuresfollowsACI-318,whereasthestructuralsteelcomponentsofthestructuresaredesignedusingtheAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings.Theexteriorwallsandroofofthestructuresareofminimum2-ftthickreinforcedconcreteandaredesignedtowithstandthemostcriticalloading,asapplicable,includingthetornado-generatedmissileimpactloads.Theexteriorwallsbelowgradearedesignedforearthpressure,hydrostaticpressure,andsurchargeloads,asapplicable,includingthedynamiceffectoftheseloadingsduringOBEorSSEevents.Theroofandfloorsofthestructuresaregenerallysupportedonsteelframing.Thefloorsystems,includingtheroof,serveassheardiaphragmtotransferlateralloadstotheexteriorandUSARRevision83.8-49November1995 NineMilePointUnit2FSARinteriorconcretewallsactingasshearwalls.Thesewallsaredesignedtowithstandgravityloads,inadditiontoactingasshearwalls,andtransmitallloadstothefoundation.Thesewallsaredesignedforin-planeshearforcesinaccordancewiththerequirementsofSection11.16ofACI-318.Masonrywallconstructionofsolidorhollowconcreteblocks,bondedtogetherbyalayerofmortar,grout,orconcretetoformarigidwall,isnotincorporatedinCategoryIapplications.However,forequipmentaccessopenings,removable,solidconcreteblockscontainedinpositionbystructuralsteelsupportsandadjacentconcretestructuresareusedinCategoryIareasforequipmentreplacementandshielding.TheseremovablewallsarenotusedtosupportCategoryIsystemsorcomponentsandarenotconsideredtoactasshearwalls.Thesewallsaredesignedsoasnottodamageanysafety-relatedstructure,system,orcomponentbyvirtueoftheirbeingcompletelyenclosedbystructuralsteelelements.ThestructuralsteelmembersandadjacentconcretewallsprovidingcontainmentandlateralsupportfortheconcreteblocksaredesignedtowithstandtheapplicableloadsandloadcombinationslistedinSection3.8.4.3.CategoryIstructuresareessentiallyconsiderednonventedstructuresfortornadicloading.Exteriorwalls,roof,andexteriordoorsareconservativelydesignedtowithstandamaximumof3psipressuredropandothertornadicloads,inadditiontootherapplicablegravityloads.Theexteriordoorsareeitherprotectedfrompostulatedtornado-generatedmissileimpingementbyprovidingprotectivestructuresaroundthem,ordesignedtowithstandthetornado-generatedmissiles.3.8.4.4.1ReactorBuildingThereactorbuildingwall,floorlevels,andsuperstructureareanalyzedanddesignedfortheloadcombinationsoutlinedinSection3.8.4.3.TheexteriorwallisanalyzedusingSHELL1,afinitedifferencecomputerprogramdescribedinAppendix3A.Thebuildingmodelconsistsofaconcretecylindricalshellwithsevenbranchesrepresentingtheconcretefloorslabs.Sincetheroofsupportsystemconsistsofsteeltrussessupportedbystructuralsteelcolumns,theroofloadsareappliedasanexternalloadingtotheshell.Thereactorbuildingwallisinvestigatedforbothseismicshearandlateralearthpressureloadsthataregeneratedduringanearthquakebythebackfillagainsttheexteriorwall.Theforces,moments,andshearsintheexteriorwallaredeterminedusingtheSHELL1computerprogram.TheinertialoadingsfromthedynamicanalysisoutlinedinSection3.7.2AareincorporatedintotheSHELL1resultstoaccountfortherigidattachmentoftheauxiliarybaystothecylindricalreactorbuildingwall.USARRevision83.8-50November1995 NineMilePointUnit2FSARWindpressureisdistributedalongtheentireheightofthereactorbuildingandisanalyzedusingtheSHELL1computerprogram.ThewindpressuredistributionusedintheanalysisisoutlinedinSection3.3.1.ToaccountforthestructuralsteelroofframingintheSHELL1model,thewindpressureexertedontheroofisappliedtothetopoftheconcreteshellasanexternalload.TheequivalentwindpressurefromtornadoconditionsispresentedinSection3.3.2,andthereactorbuildingisanalyzedusingtheSHELL1computerprogram.Thebuildingisalsoanalyzedforapressuredropof3psi(Section3.3.2)andfortheimpactoftornado-bornemissilesusingmethodsdescribedinSection3.5.3.ThetornadoloadsaredistributedonthestructuralsteelroofframingandsidingasoutlinedinSection3.3.2.ThereactorbuildingwallisnotsubjectedtothedirectpressureortemperatureloadingresultingfromaDBA,butthediscontinuityforces,moments,andshearsatthebaseofthewalloccurasasecondaryeffectresultingfromthedeformationsofthematduringtheDBA.Thesediscontinuityforcesareobtainedfromthematanalysis(Section3.8.5)'ndareincludedinthewalldesign.ThedesignofreinforcingsteelfortheconcretecomponentsconformstoACI-318.ArrangementsofreinforcingsteelfortypicalportionsofthereactorexteriorbuildingwallareshownonFigure3.8-18.ThestructuralsteelcomponentsofthestructurearedesignedusingtheAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings.Thedeadandliveloadsassociatedwithheavyequipmentandcasklaydownareprovidedforintheanalysisanddesignofthereactorbuilding.ThedynamiceffectofimpactcausedbydroppingacaskisnotconsideredintheanalysisanddesignsincetheUnit2plantmakesuseofaredundantcrane.TheconsequencesofdroppingotherheavyloadsisdescribedinSection9.1.4.Thespentfuelpoolandthereactorinternalsstoragepoolaresupportedbytwononprismaticdeepgirdersthatspanthereactorbuildingandareinturnsupportedonfourpilastersthattransmitverticalloadsintothereactorbuildingfoundationmat(Figure3.8-19).Theendsofthegirdersarebuiltintegrallywiththereactorbuildingwallandthusarepartiallyrestrainedagainstrotationattheirends.Themajorportionofloadonthegirdersisthecontributionfromthedeadweightofthegirdersthemselvesplusvariouswallsandfloorslabsthatframeintothem.Additionalsourcesofloadonthegirdersinclude:USARRevision83.8-51November1995 NineMilePointUnit2FSAR1~2~3~4~Water,fuel,andfuelracksinthespentfuelpool.Waterandliveloadinthereactorinternalspoolunderrefuelingconditions.Liveloadsonfloorsframingintothegirders.Temperaturegradientsthroughwallsandfloors.5.Earthquakeloads.Thesequenceofdesignandanalysisproceduresfollowedtoensurethestructuraladequacyofthegirdersundertheprecedingloadingsisasfollows:1~PerformashellanalysisofthereactorbuildingusingtheSHELL1computercodetodeterminethedegreeofrestraintattheendsofthegirders.Thiswasaccomplishedbyapplyingunitloadstoamathematicalmodelofthereactorbuildingshellincludingvariousfloorslabs.Theloadswereappliedovertheareaofbuildingshellcoveredbythegirderendsandinthiswayequivalentspringsweregeneratedtorepresenttherestraintprovidedbytheshell.Theseequivalentspringsserveastheboundaryconditionsforthegirderanalysisdescribedasfollows.2~ModelthegirderforthefiniteelementanalysisusingthefiniteelementcapabilitiesoftheSTRUDLIIcomputercode.Componentsofthegirderswererepresentedbyplanestrainfiniteelementstoaccountforstretchingandin-planeshear.Inaddition,platebendingelementswereusedtooverlaytheplanestrainelementstoaccountfortransversebendingandshear.3.4~Performfiniteelementanalysesusingthemodelgeneratedinsteps1and2fortheloadingcasespreviouslydescribed.Integratethestressesobtainedfromstep3toobtaincross-sectionalforceresultantsalongthelengthofthegirderandcombinetheindividualloadingconditionstoobtaindesignvalues.Theeffectsofearthquake-inducedloadswereincorporatedintothedesignvaluesbyanequivalentstaticmethodwheretheappliedloadingwasincreasedusingtheZPAvaluesfromtheseismicanalysis.5.ProvidereinforcementinaccordancewithACI-318usingultimatestrengthmethodstoresistshearsandmomentsgeneratedabove.AdditionalhorizontalandverticalreinforcingwasprovidedalongthefacesofthegirdertoresistshearloadsassuggestedintheACIcodeunderSpecialProvisionsforDeepGirders.BondandUSARRevision83.8-52November1995 NineMilePointUnit2FSARanchoragerequirementswerealsodeterminedbasedonACIcodeallowables.Inadditiontotheprecedingprocedures,theeffectsofcertaindesignvariablesthatcouldinfluencethefinalresultswereconsidered.Theseadditionalconsiderationswereprimarilytheeffectsofshrinkage,creep,andconcretecrackingontheresultingconcretestrainsanddeflectionsandalsotheeffectofthedegreeofendrestraintonfinaldesignmomentsalongthespanofthegirders.Toensureproperclearances,thedeflectionsofthegirderswerecalculatedusingthefiniteelementresultsmodifiedwithappropriatefactorsforshrinkage,creep,andconcretecracking.3.8.4.4.2ControlRoomBuildingThecontrolroombuildingisdesignedasareinforcedconcretestructuresupportedonamatfoundation.Sincethecontrolbuildingisstructurallyconnectedtothedieselgeneratorbuilding,aseismicanalysisisperformedbymodelingbothbuildingsasaunit.ThecontrolbuildingisdesignedforallpostulatedeventsandapplicableloadcombinationsoutlinedinSection3.8.4.3usingconventionaldesignprocedures.3.8.4.4.3DieselGeneratorBuildingThedieselgeneratorbuildingisdesignedasareinforcedconcretestructuresupportedonwallfootings.Thedieselgeneratorbuildingisintegrallyconnectedtoandthereforemodeledasaunitwiththecontrolbuildingfordeterminationofseismicresponseofthestructures.Thedieselgeneratorfueloiltanksarelocatedunderneaththestructureandareencasedinreinforcedconcrete.Thedieselgeneratorsupport.pedestalsareisolatedfromtheotherportionsofthestructureatgradelevelandextendapproximately19ftbelowgrade,supportedonrock.Inadditiontothedeadandliveloadsandresultingmomentsandforces,thesupportpedestalsarealsodesignedtowithstandseismiceventsandthemomentsandforcesgeneratedduringthedieselgeneratorstartup.ThedieselgeneratorbuildingisdesignedforallpostulatedeventsandapplicableloadcombinationsoutlinedinSection3.8.4.3,usingconventionaldesignprocedures.3.8.4.4.4ScreenwellBuildingThescreenwellbuildingisusedasasourceofwatertotherecirculatingandservicewaterpumps.Reinforcedconcreteconstructionwithalowwater-cementratioisusedtominimizewaterleakage,andthereinforcingsteelhasa3-inminimumUSARRevision83.8-53November1995 NineMilePointUnit2FSARprotectivecoverwheretheconcretesurfaceisincontactwithwater.Thestructuralcomponentsaredesignedfortheloadconditionsthatincludedeadloads,liveloads,equipmentloads,maximumbuoyantandupliftforces,craneload,loadsduringequipmenthandlingandmaintenance,andtornadicandseismicloads,asapplicable,inaccordancewiththeloadcombinationsdescribedinSection3.8.4.3.3.8.4.4.5IntakeStructuresTheintakestructuresaredesignedfordeadloads,liveloads,maximumbuoyantandupliftforces,forcesgeneratedbywaveaction(Section3.4.2),andseismicloads.Reinforcedconcreteconstructionwithalowwater-cementratioisusedtominimizewaterleakage,andthereinforcingsteelhasa3-inminimumprotectivecover.Theconcrete-encasedsteeltiedownsembeddedintotherockaredesignedformaximumupliftforcesgeneratedduetothemostcriticalenvironmentalconditionthatcanbepostulated(Section3.4).3.8.4.4.6Intake(andDischarge)TunnelsTheportionsofthetunnelsthatencasetheintakesystemaredesignedtowithstandallpossibleloadingeffectsincludingimpact/impulseeffectsduetorockfallandthermalstresses.Thisencasementisanalyzedandreinforcedasaninfinitebeamrestingonacontinuouselasticfoundation.Thesidesoftheencasementaretreatedascolumnswithamaximumductilityfactorof1.3.Allreinforcingsteelhasa3-inminimumprotectivecoverandhigh-strengthconcretewithalowwater-cementratioisused.TheencasementsarealsodesignedforinternalandexternalpressuresandOBEandSSEseismicforcesincombinationwithotherloading,asdescribedinSection3.8.4.3.4.3.8.4.4.7ElectricalTunnelsandPipingTunnelsElectricaltunnelsandpipingtunnelshousingsafety-relatedsystemsareconstructedofreinforcedconcrete.Thetunnelsaredesignedforgravityloadsinadditiontootherapplicableloads,suchashydrostaticloads,seismicloads,andearthpressure,inaccordancewiththeloadcombinationsdescribedinSection3.8.4.3.Inadditiontotheseloadings,thetunnelroofandwallsaredesignedtocarrytheapplicablecraneloadsresultingfromthemovementofcranesduringandafterconstruction.Thetunnelroofisdesignedforsurchargeloading,seismicortornadicforces,whicheveriscritical,inadditiontootherapplicableloadingsinaccordancewiththeloadcombinationsoutlinedinSection3.8.4.3.USARRevision83.8-54November1995 NineMilePointUnit2FSAR3.8.4.4.8MainStackThemainstack(Figure1.2-31)isanalyzedinaccordancewiththemethodsandproceduresoutlinedinACI-307.Thisstructureisnotdesignedforatornado;however,thedistancebetweenthisandotherCategoryIplantstructuresisfarenoughtoprecludedamagetoanyCategoryIstructuresintheeventthemainstackstructurecollapsespartiallyorcompletely(Figure1.2-2).ThemainstackisdesignedtowithstandseismicandotherapplicableforcesfromtheloadcombinationsofSection3.8.4.3.3.8.4.4.9StandbyGasTreatmentBuildingandRailroadAccessLockAreaTheCategoryIportionsofthesestructuresaredesignedtomeetalltheloadconditionsdescribedinSection3.8.4.3,inadditiontomeetingshieldingrequirementsforthearea.Therailroadaccesslockareaisalsodesignedtowithstandmovingwheelloadsfroma66-ftlongrailroadcarandatrack-mobileengine.3.8.4.4.10AuxiliaryServiceBuildingTheauxiliaryservicebuildingbelowel261ftmslisdesignedtowithstandtheloadsandloadcombinationsdescribedinSection3.8.4.3.3.8.4.4.11RadwasteBuildingTheradwastebuildingisdesignedasareinforcedconcretestructuresupportedonamatfoundation.ThefoundationmatisanalyzedanddesignedusingthefiniteelementcapabilityoftheSTRUDLprogram.ThestructuralsteelandreinforcedconcretecomponentsofthisbuildingaredesignedinaccordancewiththeAISCManualofSteelConstructionandACI-318,respectively.TheloadcombinationsdescribedinSection3.8.4.3areusedindesigningthestructure,exceptthatprotectionagainsttornadiceventsisnotprovided.Intheeventofapostulatedtankrupture,thebasematandexteriorwallsaredesignedtoretainthespillagewithinthebuilding.Thebasematandtheexteriorconcretewallsarelinedwithasteellineruptoel242ft2intocontainaspillage.3.8.4.4.12TurbineBuildingTheturbinebuildingcomplexisconstructedpartiallyonspreadfootingsandpartiallyonamatfoundation.StructuralsteelandreinforcedconcretecomponentsofthisbuildingaredesignedusingloadcombinationsinaccordancewiththeAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings,andACI-318,respectively.Thisbuildingcomplexisconstructedofreinforcedconcretefloorsandwallsuptotheoperatingfloorlevel.ThestructureabovetheoperatingfloorUSARRevision83.8-55November1995 NineMilePointUnit2FSARlevelisconstructedofastructuralsteelframingsystembracedbyverticalandhorizontalbracingsystemsuptorooflevel,enclosedbymetalsiding.Asteelroofdeckwithroofingisprovidedatthetopofthestructure.Topreventcollapseofthesteelsuperstructureonthenearbystructures,thestructuralsteelsuperstructureabovetheoperatinglevelisanalyzedanddesignedusingthefiniteelementcapabilityoftheSTRUDLcomputerprogramforthetornadicorseismicloads,whicheveriscritical,inadditiontoothergravityloads.Themetalsiding,roofdecking,girts,etc.,areassumedtoblowawayduring.atornadicevent;however,themainstructuralsteelmembers,suchascolumns,beams,andbracingmembers,aredesignedtoremaininplace.3.8.4.5StructuralAcceptanceCriteriaForthesteelstructures,theallowablestressesandfactorsofsafetyareinaccordancewiththeAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings,withthefollowingexceptions:1.Safety-relatedstructuresasidentifiedinTable3.2-1arecapableofwithstandingtheSSEloadsincombinationwithapplicabledeadandliveloads.2~Thesesafety-relatedstructuresarealsocheckedusingOBEloadsincombinationwithapplicabledeadandliveloads.Forthisloadingcondition,allowablestressesarethenormalworkingstresses,insteadofapplyinga33-percentincreaseinallowablestresses,asallowedbyAISCspecification.Forconcretestructures,theallowablestresses,loadfactors,andcapacityreductionfactorsareinaccordancewithstrengthdesignmethodsofACI-318-77.Therequiredstrengthisexpressedintermsofdesignloads,ortheirrelatedinternalmomentsandforces.Designloadsaredefinedasloadsthataremultipliedbytheirappropriateloadfactors(safetyfactors).CalculatedstrengthisthatcomputedbytheprovisionsofACI-318,includingtheappropriatecapacityreductionfactors.CapacityreductionfactorsaretakenasgiveninSection9.3ofACI-318.3.8.4.6Materials,QualityControl,andSpecialConstructionTechniquesThematerialsforconstructionofCategoryIstructuresareprocured,fabricated,anddeliveredtothesiteinaccordancewiththecodes,standards,andspecificationsdescribedinSection3.8.4.2.Theshipping,storage,andhandlingofmaterialsduringconstructionfollowtherequirementsofANSIN45.2.2.ThemajormaterialsforconstructionofCategoryIstructuresaredescribedherein.ThemajorcodesandtheappropriateAmericanSocietyforTestingandMaterials(ASTM)USARRevision83.8-56November1995 NineMilePointUnit2FSARstandardsusedinprocurement,fabrication,andtestingofCategoryImaterialsarereferencedherein,asapplicable.ThecurrenteditionsoftheASTMstandardsadoptedbythevendors'abricatingfacilitiesatthetimeofprocurement,fabrication,andtestingofthesematerialsareutilized.3.8.4.6.1ConcreteACI-301,SpecificationforStructuralConcreteforBuildings,togetherwithACI-347,RecommendedPracticeforConcreteFormwork,andACI-318,BuildingCodeRequirementsforReinforcedConcrete,formthegeneralbasisfortheconcretespecifications.ACI-301issupplementedasnecessarywithmandatoryrequirementsrelatingtotypesandstrengthsofconcrete,includingminimumconcretedensities,proportioningofingredients,reinforcingsteelrequirements,jointtreatments,andtestingrequirements.Admixtures,typesofcement,bondingofjoints,embeddeditems,concretecuring,additionaltestspecimens,additionaltestingservices,cementandreinforcingsteelmilltestreportrequirements,andadditionalconcretetestrequirementsarespecifiedindetail.AllcementconformstotheSpecificationforPortlandCement,ASTMC150,TypeII,lowalkali.Aggregatesaretestedinitiallyandmonitoredthroughouttheconstructionphaseoftheprojecttoassurethatthereisnoadversereactionbetweenthecementandtheaggregates.InitialexaminationofaggregatesbyASTMC295andtestsbyASTMC289andASTMC227(orASTMC586)areusedtomakethisdetermination.TheASTMC227(orASTMC586)testneednotbecompletedpriortoaggregateusagewhenASTMC289resultsareacceptableandwhenusinglow-alkalicement(Na,O+0.658K~O(0.6percent).Certifiedcopiesofthemilltestreport,showingthatthecementmeetsorexceedstheASTMrequirementsforportlandcement,arefurnishedbythemanufacturer.Anindependenttestinglaboratoryisretainedtoperformperiodictestsonthecementforcompliancewiththespecifications.Anair-entrainingagentisusedintheconcreteinanamountsufficienttosatisfyACI-301,Section3.4.1.ThisagentconformstotherequirementsofASTMC260.Beforeusinganair-entrainingadmixture,acertificateofcompliancefromthemanufacturerisobtainedstatingthattheadmixtureconformstotheapplicablerequirements,whentestedinaccordancewithASTMC233.Theaircontentofconcreteistestedatthesiteeachtimeasetofconcretecompressivestrengthspecimensismade.Air-entrainedcementisnotused.Mixingwaterand/oriceiscleanandfreefrominjuriousamountsofoils,acids,alkalies,salts,organicmaterials,orothersubstancesdeleterioustoconcreteorsteel.ThemixingwaterisperiodicallycheckedandtestedforsuitabilitybycomparingtheresultsofASTMC109,ASTMC151,andASTMC191withthoseobtainedusingdistilledwater.EachsourceofmixingwaterUSARRevision83.8-57November1995 NineMilePointUnit2FSARand/oriceissubjecttothesetestspriortouseinproductionconcrete,andevery6monthsthereafter,toassurecontinuedacceptability.Fineand.coarseaggregatesconformtoASTMC33whentestedtothefollowingASTMandCorpsofEngineersrequirements:ASTMC40ASTMC88ASTMC117ASTMC123OrganicImpuritiesSoundnessMaterialFinerthanthe200SieveLightweightPiecesASTMC131orC535LosAngelesAbrasionASTMC136ASTMC142SieveAnalysisFriableParticlesASTMC227andC289PotentialAlkaliReactivityASTMC295CRDC119PetrographicExaminationFlatandElongatedParticlesAnindependenttestinglaboratoryteststheaggregatesinitiallyforconformancetoalltheaboverequirements.ASTMC87isperformedonlyafterfailureofASTMC40tests.ASTMC666isperformedonlyafterfailureofASTMC88.Inaddition,duringconcreteproductiononsite,theindependenttestinglaboratoryperformsASTMC88,ASTMC289,andASTMC131orASTMC535testsevery6months.TestsbyASTMC39areperformedonlyuponfailureofASTMC131orASTMC535tests.Whenlimestoneaggregateistested,ASTMC586isusedasabasisforacceptance.Thefollowingtestsareperformedatthefrequencyindicatedduringconcreteproductiononsite:ASTMC136ASTMC117ASTMC566ASTMC40ASTMC123ASTMC142ASTMC235DailyDailyDailyWeeklyMonthlyMonthlyMonthlyUSARRevision83.8-58November1995 NineMilePointUnit2FSARCRDC119At6-monthintervalsSamplingofaggregatesconformstoASTMD75.TestsforunitweightconformtoASTMC29.TestsforspecificgravityandabsorptionconformtoASTMC127andASTMC128andareperformedwhenthesedataarerequired.Inadditiontotheabovetesting,appropriatetestsareperformedwhenanewsourceistobeused.ProportioningofstructuralconcreteconformstoACI-301,Chapter3.Ingeneral,structuralconcretemixeshavea28-dayminimumspecifiedstrengthof3,000psi.Whenhigherstrengthconcreteisrequired,higherminimumspecifiedstrengthconcretemixesareused.Concreteusedforshieldingpurposes,i.e.,themajorityofconcreteusedinfloors,walls,roofs,andfoundations,hasaweightnotlessthan135lb/cuft,whenair-driedinaccordancewithACI-301Section3.3.ReferencetolightweightconcreteinACI-301Section3.3isalsoconsideredapplicabletoregularstructuralconcreteindeterminingtheunitweightofconcrete.ProportionsofingredientsforstructuralconcretemixesaredeterminedandtestsconductedinaccordancewiththemethoddetailedinACI-301andACI-211.1forcombinationsofmaterialstobeestablishedbytrialmixes.Concreteprotectionforreinforcement,preparation,cleaningofconstructionjoints,concretemixing,delivering,placing,andcuringisequaltoorexceedstherequirementsofACI-301,withthefollowingexceptions:1~2~Themaximumslumpformassiveconcretewillbe3iningeneral.However,upto5-inmaximumslumpispermittedincongestedareastopermitplacingconcreteintheheavilyreinforcedstructures.Theminimumcuringperiodis1weekunlessotherwisenotedelsewhereinthissection.3~4~InlieuofSection14.5.4,useSection12.3.3.MaximumplacingtemperatureoftheconcretewhendepositedconformstotherequirementsofACI-301andACI-305,RecommendedPracticeforHotWeatherConcreting,exceptfortheplacingofmassconcrete.Theplacingtemperatureofmassconcretedoesnotexceed80'F.ACI-301indicatesplacementofmassconcretesectionsto70oF.ThislimitisbasedonconcreteusingstandardorcommonTypeIcement.TypeIIcement,whichisusedforthisproject,generates80to85percentoftheheatofhydrationofTypeIcement.ACI-207statesthattheheat-generatingcharacteristicofTypeIIcementcorrespondscloselytothatofTypeIcementat10'Flowerplacingtemperatures.USARRevision83'-59November1995 NineMilePointUnit2FSAR5.Allmassconcreteplacedatatemperatureabove754FiswatercuredinaccordancewithACI-301,Chapter12,andasdescribedelsewhereinthissection.6.Section4.3ofACI-347andSection2.4ofACI-347formthebasisforestablishingformworktolerances,exceptthatwhenasteelplate(liner)isusedforformwork,thelinertoleranceswillgovern.Also,whenthesideofawalloppositethesteellineristobeformedusingsomethingotherthanaliner,thetheoreticalformlinewillbeestablishedbymeasuringthethicknessofthewallfromthesteellinerontheoppositeface.Oncethetheoreticalformlineisestablished,thevariationinthicknesswillbegovernedbythetolerancesgiveninACI-301andACI-347,asapplicable.BatchingandmixingconformtoACI-301,Chapter7,andACI-304.Concreteingredientsarebatchedinabatchplantandtransferredtotransitmixtrucksformixing,agitating,anddeliveringtothepointofplacement,orarebatchedandmixedinacontrolledmixerandtransferredtoatruckfordelivery.Placingofconcreteisbybottomdumpbuckets,chuting,concretepump,orconveyorbelt.Therateofplacingconcreteiscontrolledsothatconcretemaybeeffectivelyplacedandcompactedbyvibratingwithparticularattentiongivenaroundembeddeditemsandneartheforms.Verticaldropsgreaterthan6ftforanyconcretearenotpermitted,exceptwheresuitableequipmentisprovidedtopreventsegregation.Inconstructionjointswherekeysarerequiredbydesign,theyareprovidedbeforetheconcretehasreacheditsfinalset.Whenkeysarenotprovided,thesurfaces.ofallconstructionjointsarethoroughlycleanedbysatisfactorymeanstoremovelaitanceandtoexposeclean,soundaggregate.Excesswaterfromjointcleaningnotabsorbedbytheconcreteisremoved.Horizontalconstructionjointsarecoveredbyaminimum1/2-inthicklayerofsand/cementgrout,whichhasacompressivestrengththatisequaltoorexceedsthatoftheconcrete,andnewconcreteisthenplacedimmediatelyagainstthefreshgrout.Asanalternatetothisprocedure,acoatingofsurfaceretarderisappliedtodelaythesettingoftheconcretesurfaceasdescribedinsubsections6.1.4.2and6.1.4.3ofACI-301.Thehorizontalsurfaceisthenpreparedforthenextpourbyusinghigh-pressurejetspraytoremovetheretardedmortar.Thesurfaceisthencuttoexposetheaggregatessuchthatanirregularsurfaceatleast1/4indeepisexposedpriortoplacingthenextlayerofconcrete.USARRevision83.8-60November1995 NineMilePointUnit2FSARCuringandprotectionoffreshlydepositedconcreteconformstothefollowing:1~2~Concretetobecuredwithwateriskeptwetbycoveringwithanapprovedwater-saturatedmaterial,orbyasystemofperforatedpipesormechanicalsprinklers,orbyanyotherapprovedmethodsthatwillkeepsurfacescontinuouslywet.Waterusedforcuringisgenerallycleanandfreefromanyelementsthatmightcauseobjectionableeffects.Thesurfacesonwhichcuringcompoundsmaybeusedarespecified.Curingcompoundsarenotusedonsurfacestowhichadditionalconcreteistobebonded.3~4~Allconcreteiscuredforatleast7daysunlessotherwisenotedinItems5,6,and7below.Forallconcrete,whenthemeandailytemperatureofthesurroundingairislessthan40oF,thetemperatureoftheconcreteismaintainedatbetween50'Fand70'Ffortherequiredcuringperiod(7days).Changesintemperatureoftheairimmediatelyadjacenttotheconcreteduringandimmediatelyfollowingthecuringperiodarekeptasuniformaspossibleanddonotexceed54Finany1-hror504Finany24-hrperiod.ForCategoryIwatertightconcrete,thereactorcontainmentmat,theturbinepedestalandpedestalmat,andthelargefoundationmats7ftorgreaterinthickness,curingiswithwaterfor7daystomaintainconcretesurfacemoisture.Forthedolosseusedintheconstructionoftherevetmentditch,theatmosphericpressuresteamcuringofconcretemethodisusedinaccordancewithACI-517-70.5.6.ForotherCategoryImassiveconcretesectionsnotincludedintheprecedingparagraph,theconcreteiswatercuredfor48hrfollowingcompletionoftheplacement,theneitheracuringcompoundmaybeappliedorwatercuringmaybecontinued,andthetemperatureoftheconcretemaintainedasabove,untilatleast7daysaftertheplacement.Alternatively,formassivestructureslessthan7ftthick,twofield-curedcylinderskeptadjacenttotheplacementandcuredbythesamemethodsmaybetestedforcompressivestrengthatanytimeafterthefirst48hrofcuring.Iftheaveragecompressivestrengthofthetwocylinderstestedequalsorexceeds70percentofthespecifiedcompressivestrengthofthemixbeingused,thencuringmaybeterminated.Porousconcretecontainingcalciumaluminatecementiswatercuredforaminimumof24hr.Two-courseUSARRevision83.8-61November1995 NineMilePointUnit2FSAR7~floortopping,deferredplacement,iswatercuredforsevendays.AllotherCategoryIconcretenotdesignatedasmassiveconcreteiscuredfor7dayseitherbywatercuringorapplicationofacuringcompoundimmediatelyafterremovalofformsorfinishingofexposedsurface.However,forallotherconcrete,curingmaybeterminatedwhentheaveragecompressivestrengthoffield-curedcylinderskeptadjacenttothestructureandcuredbythesamemethodshavereached70percentofthespecifiedstrengthofthemix.CoceteestinCompressivestrengthtestsofconcreteplacedinCategoryIstructuresareperformedinaccordancewithACI-301,TechnicalSpecifications,forevery100cuydofconcreteoraminimumofonesetper8-hrshift,whicheverisgreater.Thetestspecimensforcompressivestrengthare6-indiameterby12-inlongcylinders.Eachsetconsistsofatleastthreespecimens.Atleastoneistestedafter7daysandtwoafter28daysor60daysage,asapplicable.ConcretestrengthtestsareevaluatedinaccordancewithACI-214,RecommendedPracticeforEvaluationofCompressionTestResultsofFieldConcrete,andACI-301,Chapter17.Thestrengthofconcreteisconsideredsatisfactoryaslongasthefrequencyofoccurrenceofthefollowingislessthan1in100if:1~Theaveragesofallsetsofthreeconsecutivestrengthtestresultsofthelaboratory-curedspecimensatthespecifiedageisequaltoorgreaterthanthespecifiedcompressivestrength,f'oftheconcrete.2.Noindividualstrengthtestresultfallsbelowthespecifiedstrength,f'bymorethan500psi.ThefieldtestsforslumpofconcreteareinaccordancewithASTMC143.Anybatchnotmeetingspecifiedrequirementsisrejected.Slumptestsaremadeperiodicallyduringconcreteplacementandeachtimeconcretecompressivestrengthtestspecimensaretaken.Ifcylindersshouldfailtomeettheconcretestrengthrequirementsatthespecifiedage,strengthdevelopmentanddesignstrengthrequirementsarereviewed.Anevaluationisperformedandifrequired,coretestsareconductedinaccordancewithASTMC42,MethodofObtainingandTestingDrilledCoresandSawedBeamsofConcrete.ShouldcoretestsbeinconclusiveorimpracticabletoobtainandstructuralanalysisdoesnotconfirmUSARRevision83.8-62November1995 NineMilePointUnit2FSARthesafetyofthestructure,loadtestsareperformed.Concretework)udgedinadequatebystructuralanalysisorbyloadtestsisreinforcedwithadditionalconstructionorisremovedandrebuilt.StatisticalqualitycontroloftheconcreteismaintainedbyacomputerprogrambasedonanarticleinACIPublicationSP-16,ComputerApplicationsinConcreteDesignandTechnology.ThisprogramanalyzescompressivestrengthtestresultsbythetestinglaboratoryinaccordancewithmethodsestablishedbyACI-214,RecommendedPracticeforEvaluationofStrengthTestResultsofConcrete.3.8.4.6.2ReinforcingSteelReinforcingsteelbars,sizesN3throughN6,conformtoGrade40,andN7throughN11conformtoGrade40orGrade60oftheStandardSpecificationforDeformedBillet-SteelBarsforConcreteReinforcement,ASTMA615andSupplementS-1.Forfuelpoolbeamsandcertainotherareasofthereactorbuilding,speciallarge-sizereinforcingbars,N14andN18,conformtoGrade60ofASTMA615.Grade60N8reinforcingbarsareusedformissileenclosureofvalvesinthescreenwellbuilding.Milltestreportsshowingactualchemicalandphysicalproperties,includingbendtests,arefurnishedforeachheatofsteelusedinmakingallreinforcingsteel.Exceptwhenotherwisenotedherein,reinforcingbarsN14andN18willbecontrolledchemistrysteelof50,000psiminimumyieldpoint,conformingtotheStandardSpecificationforDeformedBillet-SteelBarsforConcreteReinforcement,ASTMA615,asmodifiedtomeetthefollowingchemicalandphysicalrequirements:CarbonManganeseSiliconPhosphorousSulfurMinimumyieldstrengthElongationTensilestrength0.35percentmaximum1.25percentmaximum0.15to0.25percent0.05percentmaximum0.05percentmaximum50,000psi13percentminimuminan8-intestsample70,000psiminimumUSARRevision83.8-63November1995 NineMilePointUnit2FSARForthesespecialchemistrybars,allingotsareidentifiedandallbilletsarestampedwithidentifyingheatnumbers.Allbundlesofbarsaretaggedwithaheatnumberastheycomeoffthecoolingbedoftherollingmill.Aspecialmarkisrolledintoallbarsconformingtothisspecialchemistrytoidentifythemaspossessingthechemicalandmechanicalqualitiesspecified.ThechemicalvariationsallowedforspecialchemistrybarsareinaccordancewithASTMA29.PlacingofreinforcingsteelconformstotherequirementsofChapter5ofACI-301,StructuralConcreteforBuildings,andChapter7ofACI-318,BuildingCodeRequirementsforReinforcedConcrete.Tackweldingofdesignedreinforcingsteelthatdoesnotbecomeanintegralpartoftheweldmentisnotpermitted.Structuralductilityismaintainedbystaggeringcriticalspliceswhereverpossibletoensurethatsmalladverseeffectsofmultiplesplicesinthesameplanewillnotoccur.Full-scalepressuretestsconductedinMay1967onacompletedconcretecontainmentstructure,inwhichcadweldsplicesandweldedspliceswereusedinasimilarmannertothatproposedhere,showednostressconcentrationsorlackofstructuralductility.Locationsofsplicegroupswerenotdiscerniblefrominspectionofthetestcrackpatterns.eioxc'eelIset'oandest'heengineers'nspectorswitness,onaxandombasis,thepouringoftheheatsandthephysicalandchemicaltestsperformedbythemanufacturerforthespecialchemistryreinforcingsteel.Barsfailingtoconformtorequiredchemistryandphysicalrequirementsarerejected.Milltestreportsshowingactualchemicalladleanalysis,physicalproperties,bendtest,andvariationsinweightwillbeobtainedfromthemanufacturerforeachheat.Inaddition,confirmatorytensiletestsforeach50tonsofeveryheatofsteelforeverybarsizewillbemadetodeterminephysicalproperties.Full-sizetestspecimensofallrebarsaretestedonatestingmachineusingan8-ingaugelength.TheloadingrateforthesetestsisasspecifiedinASTMA370.TheacceptancestandardsareinaccordancewithASTMA615.Atleastonefulldiameterspecimenfromeachbarsizeistestedforeach50tons,orfractionthereof,ofreinforcingbarsproducedfromeachheat.Theprecedingfrequencyoftesting,testprocedures,andacceptancestandardsconformtoRG1.15.ThedegreeofcompliancetoRG1.15isdiscussedinSection1.8.USARRevision83'-64November1995 NineMilePointUnit2FSARcaThemechanicalsplicecriteriafollowtherequirementsofNRCRG1.10,Rev.1,asdiscussedinSection1.8.ThedesignbasisdescribedinthePreliminarySafetyAnalysisReport(PSAR)andapprovedbytheNRCintheSafetyEvaluationReport(SER)fortheconstructionpermitincludedtheuseofthisregulatoryguide.UseofthisregulatoryguideprovidesadequateassurancethattheCategoryIstructuresperformtheirintendedsafetyfunction.p1byEricoProducts,Inc.,Cleveland,OH,areusedtospliceN14andN18reinforcingbars.Allcadweldsplicesaremadeinaccordancewiththeinstructionsfortheiruseissuedbythemanufacturer.ThedegreeofcompliancetoRG1.10isdiscussedinSection1.8.Inareaswherespaceorotherrequirementsmakecadweldsplicesunsuitable,N14andN18reinforcingbarsarebutt-weldedinamannerconformingtotherequirementsofAWSD12~1'einforcingbarsNo.11andsmalleraregenerallylapspliced.Wherelapsplicingisimpractical,andwherethreadedrebarsplicesarenotused,splicingisaccomplishedby:1.CadweldasmanufacturedbyEricoProducts,Inc.,orequal,usingthesleevesthatdevelopthefulltensilestrengthofthereinforcingbars,or2.Butt-weldinginaccordancewiththerequirementsofAWSD12.1~InordertoqualifyOperatorsformakingcadweldproductionjoints,eachOperatorisrequiredtopreparetwosatisfactoryqualificationsplicesforeachofthesplicepositionstobeused.Testingisbytensiletestingacadweldthatsimulatesfieldconditionsandusesthesame.materialsasthosetobeusedinthestructure.Theendsofthereinforcingsteelbarstobejoinedbythecadweldprocessaresawcut,flamecut,orshearcut.Theendsofthebarsarethoroughlycleanedofallrust,scale,grease,oil,water,orotherforeignmatterbeforethejointsaremade.CadwelestinandsectioCadweldprocesssplicesarevisuallyinspectedinaccordancewithRG1.10.Visualinspectionincludesrandominspectionoftheendsofthebarsfordrynessandcleanlinesspriortofittingthesleeveovertheends.InspectionismadeofthecompletedspliceforproperlyfilledjointsthathavefillermetalvisibleatbothendsofthesleeveforT-seriessplicesandtheexposedendforB-seriessplicesandatthetapholeinthecenterofthesleeve.Splicesthatdonotmeetalltheseinspectioncriteriaarerejected.USARRevision83.8-65November1995 NineMilePointUnit2FSARRandomlyselectedcadweldsplicesbasedonseparatetestcyclesforhorizontal,vertical,anddiagonalbars,sizeofrebar,andcadwelderareremovedfromthestructureandtensiletested,oracombinationofproductionandsistersplicesaretestedinaccordancewithASTMA370.Testingisinaccordancewiththefollowingscheduleifonlyproductionsplicesaretested:1outoffirst10splices.1outofnext90splices.2outofnextandeachsubsequentunitof100splices.Ifcombinationsofproductionandsistersplicesaretested,thesamplefrequencyisasfollows:1productionspliceoutofthefirst10productionsplices.1productionand3sistersplicesoutofthenext90productionsplices.3splices,eitherproductionorsistersplices,forthenextandsubsequentunitsof100splices.Atleastone-fourthofthetotalnumberofsplicestestedareproductionsplices.Thesamplefrequencyforsplicesincurvedbarswitharadiusofcurvaturelessthan60ftisasfollows:1sisterspliceforthefirst10productionsplices.4sistersplicesforthenext90productionsplices.3sistersplicesforthenextandsubsequentunitsof100productionsplices.Sistersplicesaremadeusingstraightbars.Thetensilestrengthofeachsampletestedshouldequalorexceed125percentofthespecifiedminimumyieldstrengthforthegradeofreinforcingbarused.Failureofanysplicetoachieve125percentofthespecifiedminimumyieldstrengthisevaluatedinaccordancewithSection5oftheProcedureforSubstandardTensileTestResultsasgiveninRG1.10.DidaeadbasteSicesDywidagthreadbarsystemsplicingisused,onalimitedbasis,forbarsizesNo.6throughandincludingNo.11instructures,andwillconformtothemechanicalsplicecriteriaofACI-318BuildingCodeRequirementsforReinforcedConcrete.AllDywidagsplicesaremadeinaccordancewiththeinstructionsfortheiruseissuedbythemanufacturer,DywidagSystemsInternational,LincolnPark,NJ.USARRevision83.8-66November1995 NineMilePointUnit2FSARUnstaggeredDywidagsplicesmaybeusedintheradwastebuilding.DywidagthreadbarsplicesystemisnotusedinanyQACategoryIstructure.Weld'eioc'teelAllweldingofreinforcement(i.e.,rebartoplateorrebartorebar)conformstoRecommendedPracticesforWeldingReinforcingSteel,MetalInserts,andConnectionsinReinforcedConcreteConstruction,AWSD12.1.Certifiedmaterialtestreportsforweldingelectrodesareobtainedfromtheelectrodemanufacturer.Theendsofthebarstobe)oinedbybuttweldingarepreparedbysawcuttinganddressingbygrinding,wherenecessary.Inordertoqualifyweldersforworkonthereinforcingsteelbars,eachweldermakestestweldsineachpositionhewillberequiredtouseduringproduction.Eachtestweldistensiontestedandeachisrequiredtomeetorexceedtheminimumtensilestrengthofthereinforcingbar.Structuralductilityismaintainedbystaggeringcriticalspliceswhereverpossibletoassurethatsmalladverseeffectsofmultiplesplicesinthesameplanedonotoccur.Generally,weldingofreinforcingsteelbarsisemployedinisolatedinstancesonlywhenmechanical(cadweld)splicingisnotfeasibleduetospacerestrictionsorclearanceproblems.Specifically,thereinforcingbarsinsizeNos.4to18areweldedtothesteelplates,etc.,asrequiredduetospacerestrictionorclearanceproblemsortoprovideanchorage.Inallcases,thewelddetailsareprequalifiedinaccordancewithAWSD12.1.Weldingofreinforcingsteelbarstoplatesisusedinconstructionofprimarycontainment,drywellfloor,reactorpedestal,andscreenwellbuilding.AlthoughweldingofN14andN18rebarsispermitted,norebartorebarweldinghasbeenusedonseismicCategoryIstructures.Withtheexceptionofmainsteamtunnelarea,rebartorebarbuttweldinghasnotbeenusedinanyotherseismicCategoryIstructure.Inmainsteamtunnelarea1-No.7and32-No.8,rebardowelsatel239'-0",244'-0",and250'-0"werebuttweldedtothesamesizebars.sectdestoReinfoc'nSteeledsAllweldsarevisuallyinspected.Anycracks,porosity,orotherdefectsareremovedbychippingorgrindinguntilsoundmetalisreached,andthenrepairedbywelding.Peeningisnotpermitted.Completedwelded)ointsinreinforcingsteelareselectedonarandombasisfromCategoryIstructuresandradiographicallyinspectedinaccordancewiththefollowingschedule:1outoffirst10splices.USARRevision83.8-67November1995 NineMilePointUnit2FSAR3outofnext100splices.1outofnextandsubsequentunitsof100splices.Cracksandanyexcessiveamountofcontainedvoids,asspecifiedinAWSD12.1,arecauseforrepairorremovalandreplacement.Replacedweldsareexaminedinasimilarmanner.Reinforcingsteelbarsweldedtosteelembedmentsaretestedbysistersplice,inaccordancewiththefollowingschedules:1sisterspliceoutofthefirst10productionsplices.4sistersplicesforthenext90productionsplices.3sistersplicesforthenextandeachsubsequentunitof100.3.8.4.6.3StructuralSteelStructuralsteelmaterialandfabricationtolerancesareinaccordancewiththeAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings,includingthesupplements(Section3.8.4.2).StructuralsteelerectiontolerancesareinaccordancewithCodeofStandardPracticeforBuildingsandBridges,exceptthatforcolumnsotherthancranecolumnsandelevatorhoistwaycolumns,11/2intoleranceatanypointinitsheightispermitted.Ingeneral,steelusedforstructuralframingconformstoASTMA36.Inareaswherethedesignindicatesthatahigherstrengthsteelisrequired,ASTMA440,A441,A572,A588,orA242steelisused.Inthesuppressionpoolarea,stainlessstructuralsteelconformingtoASTMA167isused.CertifiedcopiesofmilltestreportsshowingactualchemicalandphysicalpropertiesarefurnishedforeachheatofsteelusedinmakingCategoryIstructuralsteel.WeldingofstructuralsteelisinaccordancewithAWSD1.1withthefollowingclarifications:AWSD1.1Section2.4.3requiresfillers1/4inandlargertobeextendedbeyondtheedgeofthespliceplateorconnectionmaterial.However,fillersgreaterthanorequalto1/4inareinstalledusingrequirementsofAWSD1.1Section2.4.2inthefollowingconditions:1~Restrictionsduetospacelimitations.2~Presenceoftaperedgapsduetofabricationorerectiontolerancesrequiringuseofmultipleshims.3~Whenstressescannotbetransferredthroughthefillerplates.USARRevision83.8-68November1995 NineMilePointUnit2FSARThestructuralweldingcodecontainstherequirementthatundercutwillnotexceed0.01indeepwhenthedirectionistransversetotheprimarytensilestressinthepartthatisundercut.Unlesssonoted,allweldingperformedundertheAWSCodeisinspectedforamaximumundercutof1/32in.InspectionstoAWSD1.1maybeperformedwiththeexceptionthattheinspectorneednotidentifywithadistinguishingmarkallpartsorjointsthathehasinspectedandaccepted.TheseinspectionsmustbedocumentedbytheContractor'sQAprogram.ASTMA515GR65maybeconsideredanAWSD1.1,prequalifiedgroupno.1material.AWSD1.1Section3.3.1requiresthatthelegofafilletweldbeincreasediftheseparationbetweenthepartstobejoinedis1/16inorgreater.Unlessnoted,allweldingperformedundertheAWSCodeshallhavethelegofthefilletweldincreasediftheseparationisgreaterthan1/16in.Alternatively,thevisualinspectionofAWSD1.1structuralweldsfortheitemslistedbelowmaybeperformedusingthecriteriainVisualWeldAcceptanceCriteriaforStructuralWeldingatNuclearPowerPlants(VWAC),issuedbytheNCIGasdescribedinNCIG-01,Rev.2,May7,1985(includingthecorrespondingNCIGtraining).ThisdocumentisacceptedbytheNRCintheirletterofMay26,1985,fromJ.P.KnightofNRCtoD.E.DuttonofNCIG.TheimplementationdateofNCIG-01Revision2isdocumentedontheappropriatespecificationchangeapprovaldocuments.Theitemsare:1.Structuralsteel.2.Cabletraysupports.3.Conduitsupports.4.Ductsupports.5.Instrumentationsupports.6.Equipmentsupports.Thematerialinstallationandinspectionofhigh-strengthboltsconformtotherequirementsoftheSpecificationforStructuralJointsusingASTMA325orA490Bolts.WelderperformancequalificationinaccordancewithASMEIXshallqualifytheweldertoperformweldingtoAWSDl.l.ThewelderperformancequalificationinaccordancewithASMEIXwillmeetallessentialvariablesofAWSD1.1,withthefollowingexceptions:USARRevision83.8-69November1995 NineMilePointUnit2FSAR1.Theperformancetestcouponwitha371/2deg+21/2degbevelisacceptableinlieuofthe221/2deg+21/2degbevelrequiredbyAWSD1.1.2~InadditiontowelderperformancequalificationestablishedonmaterialpermittedbyAWSD1.1,welderperformancequalificationonanASMEIXP1-listedmaterialshallqualifytheweldertoweldAWSD1.1prequalifiedmaterials.3.8.4.7TestingandIn-serviceSurveillanceRequirementsNofull-scalestructuraltestingorin-servicesurveillanceisanticipatedforthestructuresdescribedinSection3.8.4.1.Fortestingofthematerialsusedinconstruction,refertoSection3.8.4.6.3.8.5FoundationsandConcreteSupports3.8.5.1DescriptionoftheFoundationandSupportsTable3.8-13liststhefoundationsystemsthatareusedformajorCategoryIstructures.MajorCategoryIstructuresarefoundedonorbelownaturalbedrocksurface.Foundationswithbasesonorwithinthetop10ftofthenaturalbedrockaredesignedforanallowablebearingloadof10tons/sqft.Foundationswithbasesdeeperthan10ftbelowthenaturalbedrocksurfacearedesignedforanallowablebearingloadof20tons/sqft.WhenCategoryIstructures(suchaselectricalductlines)arefoundedonCategoryIstructuralfill,theyaredesignedtosatisfytheCategoryIloadingcombinationsasdescribedinSection3.8.4.3.AllowablebearingpressureontheCategoryIstructuralfillis2tons/sqft.Thenormaldesignlevelforgroundwaterisel255ftmsl.Themaximumdesignfloodwaterlevelisel261ftmsl.ThefoundationsofmostmajorCategoryIstructuresarebelowthegroundwaterlevel.Waterstopsareprovidedatverticalandhorizontalconstructionjointsbelowthefloodlevelof261ftmsltopreventseepageofwaterthroughthejoints.AllCategoryIstructuresareconstructedinsuchamannerthataminimum6-inspaceisprovidedbetweentheextremitiesofthefoundationsandtheexcavatedrocksurfaces.Thisspaceisfilledwithcompressiblematerialssuchasvermiculite,vermiculiteconcrete,orcompressiblefillermaterial.AdditionalinformationiscontainedinSection2.5.4.3.8.5.1.1ReactorBuildingThereactorbuilding,primarycontainment,reactorsupportpedestal,andauxiliarybaysarefoundedonacommonmat,sittingonrockatel164ft.Thematisareinforcedconcretestructure10ftthickand183ftindiameterwithtworectangularauxiliaryUSARRevision83.8-70November1995 NineMilePointUnit2FSARbaywings.Figure3.8-20showsthefoundationmatconfiguration.Thematisreinforcedwithbothtopandbottomlayersofreinforcingsteel(Figures3.8-22and3.8-23).Shearreinforcingsteel,forradialshearforces,isplacedintheverticaldirection.Thereinforcementforthebottomofthematisinanorthogonalgridpatternwithlayersat90degtoeachotherwithsomeadditionalbarsintheradialdirection.Reinforcementforthetopofthematconsistsofconcentriccircularbarsandradialbars.Thereinforcingpatternforthetopofthematisarrangedtomaintainauniformspacingofthebarswhichextendintothematfromtheverticalwallsabove.Matreinforcingbarsarenotsplicedatthejunctionofthematandverticalwalls.Thereactorsupportpedestal,theprimarycontainmentwall,andthesecondarycontainmentwallareadequatelyconnectedtothemattoresistdiscontinuitymomentsandshearsbytheuseofverticalreinforcingdowels(Figure3.8-20).Atleast8inofporousconcretetoppedby1/4inofsealconcretelayerisplacedunderthereactorbuildingmattointerceptthegroundwater,whichisthenchanneledthrough6-inporousconcretepipestothesumpslocatedbelowthemat.Inadditiontothis,anindependentwatercollectionpipingsystem,usinghalf-round8-indiameterpipes,isprovidednearthetopofthemattocollecttheleakageintotwostandpipesinthereactorbuilding.ThedetailsofthegroundwaterdrainagesystemforthereactorbuildingandvicinityareaarecoveredinSection2.4.13.3.8.5.1.2FoundationsforOtherStructuresFoundationsforallmajorCategoryIstructuresandtheturbinebuildingareeitherreinforcedconcretematsorspreadfootings.InsomeinstancestheCategoryIstructuresaresupportedbytheunderlyingCategoryItunnels,whichinturnarefoundedonbedrockusingareinforcedconcretematsystem.ThesebuildingfoundationsarelistedinTable3.8-13.SincemajorCategoryIstructuresarefoundedonnaturalbedrock,nopotentialforliquefactionexists.CategoryIstructures,whenfoundedonCategoryIstructuralfill,areevaluatedagainstthepossibilityofanyliquefaction(Section2.5.4.8).Figure3.8-21showsatypicalreinforcingpatternatthejunctionofreinforcedconcreteverticalstructuralelementsandafoundationmat.3.8.5.2ApplicableCodes,Standards,andSpecificationsThedesigncodes,standards,specifications,andregulationsthatareusedforthedesignandconstructionofCategoryIfoundations,includingthereactorbuildingmat,arelistedinSection3.8.4.2.USARRevision83.8-71November1995 NineMilePointUnit2FSAR3.8.5.3LoadsandLoadCombinationsTheloadsandloadingcombinationsforthereactorbuildingmatarethesameasthosefortheprimarycontainmentstructure(Section3.8.1.3).TheloadsandloadingcombinationsforthefoundationsofotherCategoryIstructuresarethesameasthoseusedindesigningtheCategoryIstructures(Section3.8.4.3).Inaddition,thefollowingloadcombinationsareusedtocheckagainstslidingandoverturningduetoearthquakes,winds,andtornadoes,andagainstflotationduetofloods:1.D+H+OBE2.D+H+W3.D+H+SSE4~D+H+W,5.D+F'here:D,OBE,W,SSE,andW,(definedinSection3.8.4.3)H=LateralearthpressureF'Buoyantforceofthedesignbasisflood3.8.5.4DesignandAnalysisProceduresThereactorbuildingmatisanalyzedanddesignedfortheloadingcombinationsdefinedinSection3.8.5.3.TheMAT-6program,adigitalcomputerprogrambaseduponthegeneralmethodsdescribedinAppendix3A,isusedtodeterminethestressesinthematduetostaticallyappliedaxisymmetricloads.Thisprogramanalyzesanaxisymmetricallyloadedcircularplateonanelasticfoundationandmaintainscompatibilitybetweentheplateandconcentricwallssupportedbytheplate.ThematanalysisincludestheeffectsoftheprimarycontainmentpressureloadsgeneratedbytheDBA,hydrodynamicloads,loadsfromtemperatureduetooperatingconditionsandtheDBA,stiffnesscharacteristicsofthecylindricalshellsthatareconsideredaselasticconstraintsonthemat,deadloads,andcharacteristicsofthesupportingmedia.ThesubgradestiffnessisbasedupontheBoussinesqtheory,whichassumesthesubgradetobeahomogeneousisotropicelasticmedium.Thediscontinuitymomentsandshearsatthejunctionsoftheprimarycontainment,secondarycontainment,andreactorpedestalwallwiththematarecomputedbytheprogrambyapplyingcompatibilityconditionsattheinterfaceofthematwitheachoftheabove.Appendix3ApresentsthedesigncontrolmeasuresthathavebeenemployedtodemonstratetheapplicabilityandvalidityoftheMAT-6program.USARRevision83.8-72November1995 NineMilePointUnit2FSARDynamicanalysisofthereactorbuildingprovidesaccelerationprofilesforthereactorbuildingwhichareappliedasstaticloadsonthestructure.Sincetheseloadsareasymmetric,thematisanalyzedusingSHELL1,afinite-differencecomputerprogram(Appendix3A).SinceboththeMAT-6andSHELL1programscanhandleonlyaxisymmetricstructures,theeffectofauxiliarybaysonthematisinvestigatedbythree-dimensionalfiniteelementanalysisusingtheICESSTRUDLIIcomputerprogram.Theresultsofthisanalysisareincorporatedinthematdesign.ThematisanalyzedforhydrodynamicloadswhicharedescribedintheDesignAssessmentReportforHydrodynamicLoads(DAR)(Appendix6A).ThefoundationsofothermajorCategoryIstructuresareanalyzedbyeitherhandcalculationsorusingthefiniteelementcapabilityoftheSTRUDLII/STARDYNEcomputerprograms(Appendix3A).ThefoundationsofsmallstructuressuchastunnelsareanalyzedasframedstructureseitherusingtheSTRUDLIIcomputerprogramorbyhandcalculations.Theloadsonspreadfootingsforwallsandcolumnsareobtainedbyanalyzingthestructureusingtheframeanalysisapproach.AllthefoundationsofCategoryIstructuresareanalyzedanddesignedfortheapplicableloadcombinations(Section3.8.4.3).3.8.5.5StructuralDesignCriteriaStructuraldesignofallfoundations,includingthereactorbuildingmat,isinaccordancewithACI-318,usingultimatestrengthdesign.CapacityreductionfactorsareusedasgiveninChapter9ofACI-318.ThestructuralanalysisoftheCategoryIstructuresprovidesfactorsofsafetyagainstoverturning,sliding,andflotationandareasfollows:imumFactosof.SetLoadCob'tioOverturnin~SlidinFlotation1.D+H+OBE2~D+H+W3~D+H+SSE4~D+H+W,5~D+F'.51.5NA1.51.5NANANANANAMajorCategoryIplantstructuresarecheckedforoverturning,sliding,andflotation.Table3.8-14providesasummaryofstabilityanalysesofmajorCategoryIstructures.USARRevision83'-73November1995 NineMilePointUnit2FSAR3.8.5.6Materials,QualityControl,andSpecialConstructionTechniquesMaterials,qualitycontrol,andspecialconstructiontechniquesusedfoxtheconstructionoffoundationsarethesameasforotherCategoryIstructures(Section3.8.4.6).3.8.5.7TestingandIn-serviceSurveillanceRequirementsTestingandISIisnotplannedforanyfoundationstructure.3.8.6Reference1.Timoshenko,S.P.andGere,J.M.TheoryofElasticStability,2ndEdition.McGraw-HillBookCompany,NewYork,NYI1961.USARRevision83.8-74November1995 NineMilePointUnit2FSARTABLE3.8-1LOADCOMBINATIONSFORCONCRETEPRIMARYCONTAINMENTPARTILoadCombinationsWithoutSRVDischargeLoadingServiceConditiosLoadCombiationTestConstructionDesinConditionsS=1.0D+1.0L+1.15Pa+1.0ToS=1.0D+1.0L+1.0ToNormalSevereenvironmentalExtremeenvironmentalAbnormalAbnormal/severeenvironmentalAbnormal/extremeenvironmentalU=U=U=U=1.4D+1.7L+1.3(To+Ro)1.4D+1.7L+1.9E+1'(To+Ro)1.0(D+L+To+Ro+E')1.0(D+L+Ta+Ra)+1.5Pa1.0(D+L+Ta+Ra+Rj+Rr+Rm)+1.25(E+Pa)1.0(D+DF+L+TF+E)1.0(D+L+Ta+Ra+Rj+Rr+Rm+Pa+E')PARTIILoadCombinationsWithSRVDischargeLoadingToaccountfortheeffectsofSRVdischargeloadingandsuppressionpoolhydrodynamicloading,theprimarycontainmentischeckedforthefollowingcombinations:DesinConditiosNormalwithouttemperatureLoadCombinat'onU=1.4D+1.7L+1.0Po+1.5SRV~U=1.4D+1.7L+1.0Po+1.5SRV~yUSARRevision81of6November1995 NineMilePointUnit2FSARTABLE3.8-1(Cont'd.)DesinConditionsLoadCombinatioNormalwithtemperatureNormal/severeenvironmentalAbnormalU=1.0D+1.3L+1.0Po+1.0To+1.0Ro+1.3SRV~1.0D+1.3L+1.0Po+1.0To+1.0Ro+1.3SRVy1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.25E+1.25SRV1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.25E+1.25SRV1.0D+1.0L+1.25Pb+1.0Ta+1.0Ra+1.25SRV~1.0D+1.0L+1.25Pb+1.0Ta+1.0Ra+1.25SRV,~1.0D+1.0L+1.25Pa+1.0Ta+1.0Ra+1.0SRVAbnormal/severeenvironmental10D+10L+1~+1.0Ta+1.0Ra1.0D+1.0L+1.+1.0Ta+1.0Ra1.0D+1.0L+1~+1.0Ta+1.0Ra1E+11Pb+1~1SRVaa,1E+11Pb+11SRV~y1E+1.1Pa+1.0SRVINormal/extremeenvironmentalU1.0D+1.0L+1~+1.0Ro+1.0ED+1.0L+1~+1.0Ro+1.0E'Po+1.0To+1.0SRV~0Po+1.0To+1.0SRV~Abnormal/extremeenvironmentalU1.0D+1~OL+1~+1.0Ta+1.0RaRm+1.0Rr+1.01'D+1'L+1~+1.0Ta+1.0RaRm+1.0Rr+1.01.0D+1.0L+1~+1.0Ta+1.0RaRm+1.0Rr+1.00E'1.0Pb+1.0Rj+1.0SRV~0E'1.0Pb+1.0Rj+1.0SRV~OE'+1.0Pa+1.0Rj+1.0SRV~)USARRevision82of6November1995 NineMilePointUnit2FSAR'ABLE3.8-1(Cont'd.)NOTES1~2~Normalwindandtornadoloadsdonothaveaneffectonthestructuresinceitissurroundedbythereactorbuildingwall,whichisdesignedfortornadicloading(includingmissiles).Variationsinthedeadloadofthestructureareprovidedforbyusing5percentofthedeadloadcoefficientprovidedintheaboveformulas.3~andshutdown.D=Deadloads,includinghydrostaticandpermanentequipmentloads.L=Liveloads,includinganymovableequipmentloadsandotherloadsthatvarywithintensityandoccurrence,suchassoilpressures.To=Thermaleffectsandloadsduringnormaloperatingorshutdownconditionsasapplicable,basedonthemostcriticaltransientorsteady-statecondition.Ro=Pipereactionsduringnormaloperatingorshutdownconditionsasapplicable,basedonthemostcriticaltransientorsteady-statecondition.4~Po=Pressureloadduringnormaloperatingcondition.CostructionLoadsLoadsappliedtothestructurefromstarttocompletionofconstructionincludingtheloadsgeneratedduringtheerectionoftheRPV.D,L,andToaredefinedinNote3.Normalloadsareapplicable,buttheconstructionvalueisused.5~6.structuralintegritytest.D,L,andToaredefinedinNote3.Normalloadsareapplicable.PaistheDBApressureloadasdefinedinNote8.evereEirometalLoadsEventsandtheresultingloadsoccurringonlyinfrequently.TheloadsassociatedwithfloodingthecontainmentwithwaterandtheOBEareincludedinthiscategory.ThedefinitionsinNote3apply,inadditiontothefollowing:USARRevision83of6November1995 NineMilePointUnit2FSARTABLE3.8-1(Cont'd.)DFLoadsduetoaccelerationfromtheOBEandincludingthelateralorverticalacceleration,oracombinationofboth,wheretheeffects(asmeasuredbythestressesresultingfromtheseparateaccelerationcomponents)oflateralandverticalgroundaccelerationsarecombinedalgebraically.Hydrostaticloadsassociatedwithfloodingthecontainmentwithwater.TFThermalloadsassociatedwithfloodingthecontainmentwithwater.7.ExtremeandtheEnvironmentalLoadsHighlyimprobableeventsresultingloads.8.bormalLoasLoadsgeneratedbytheDBA.PaDesignpressureloadwithinthecontainmentgeneratedbytheDBA,includingLOCA.Pb=DesignpressureloadgeneratedbySBAorZBA.NOTEPaandPbincludethesuppressionpoolhydrodynamicloadsfromeffectsofchuggingand/orcondensationoscillation.TaRaThermaleffectsandloadsgeneratedbytheDBAincludingTo.PipereactionfromthermalconditionsgeneratedbytheDBAincludingRo.RrLoadonthecontainmentgeneratedbytheDBA,e.g.,reactionofarupturedhigh-energypipeduringthepostulatedevent.Thetime-dependentnatureoftheloadandtheabilityofthestructuretodeformbeyondyieldareconsideredinestablishingthestructuralcapacitynecessarytores'isttheeffectsofRr.RjLoadonthecontainmentgeneratedbytheDBA,e.g.,jetimpingementfromarupturedhigh-energypipeduringthepostulatedevent.Thetime-dependentnatureoftheloadandtheabilityofthestructuretodeformbeyondyieldareconsideredinestablishingthestructuralcapacitynecessarytoresisttheeffectsofRj.USARRevision4of6November1995 NineMilePointUnit2FSARTABLE3.8-1(Cont'd.)Rm=Equivalentstaticmissileimpactloadactingonastructuregeneratedbyorduringthepostulatedaccident.Loadincludesanappropriatedynamicloadfactorappliedtothepeakofthemissileimpact.-timecurve.E'Loadduetoaccelerationfromthesafeshutdownearthquakeandincludingthelateralorverticalacceleration,orcombinationofboth,wheretheeffects(asmeasuredbythestressesresultingfromtheseparateaccelerationcomponents)oflateralandverticalgroundaccelerationsarecombinedalgebraically.9.bnormalSevereEvironmentalLoadsCombinationsthatresultfromthepostulatedcombinedoccurrenceofabnormalandsevereenvironmentaleffects,whentheoccurrenceofaspecifiedsevereenvironmentalcategoryloadconditionattheplantsiteimposeseffectsthatsignificantlyincreasetheprobabilityofabnormalcategoryloadconditions,orwhenthespecifiedabnormalorsevereenvironmentalcategoryloadconditionisofsuchextendeddurationthatasignificantprobabilityexiststhatloadsinthesetwocategorieswilloccursimultaneously.10.bnormalExtreeEnvironmentalLoadsCombinationsthatresultfromthepostulatedcombinedoccurrencesofabnormalandextremeenvironmentaleffects,whentheoccurrenceofaspecificextremeenvironmentalcategoryloadconditionattheplantsiteimposeseffectsthatsignificantlyincreasetheprobabilityoftheoccurrenceofabnormalcategoryloadconditions,orwhenthespecifiedabnormalorextremeenvironmentalcategoryloadconditionisofsuchextendeddurationthatasignificantprobabilityexiststhatloadsinthesetwocategorieswilloccursimultaneously.11.UistherequiredsectionstrengthbasedonthestrengthdesignmethodsdescribedinACI-318.Incomputingtherequiredsectionstrength,actualcompressivestrengthofconcretemaybeusedinplaceofspecifiedminimumcompressivestrengthofconcrete.Theactualcompressivestrengthofconcreteshallbedeterminedfromthecompressivestrengthtestreportsoftheconcretepourunderconsideration.ThisprovisionmaybeusedtoestablishdesignadequacyinisolatedUSARRevision85of6November1995 NineMilePointUnit2FSARTABLE3.8-1(Cont'd.)caseswherethespecifiedminimumstrengthofthematerialispotentiallyexceeded.12.SistherequiredsectionstrengthbasedonalternatedesignmethodandtheallowablestressdescribedinACZ-318.13.SRVdischargeloadsaredefinedasshownbelow:SRV~SRVloadsduetosequential(i.e.,allvalves)actuation.SRV~SRV~SRVloadsduetoautomaticdepressurizationsystem(ADS)(sevenvalves)actuation.SRVloadsduetoasymmetric(threevalves)actuation.SRV~iSRVloadsduetosinglevalveactuation.USARRevision86of6November1995 NineMilePointUnit2FSARTABLE3.8-8STRESSStressComponentLocation(el)GoverningEquationActualStressAllowableConcreteStressMembraneandbendingRadialshearReinforcementStressMeridional175'80'=1.0D+1.0L+1.0Ta+1.5Pa+1.0RaU=1.0D+1.0L+1.0Ta+1.25Pb+1.0Ra+1.25SRV2,800psi3,000psivu=37psivc=37psiInsidelayerOutsidelayer175'01'=1.0D+1.0L+1.0Ta+1.5Pa+1.0RaU=1.0D+1.0L+1.0Ta+1.1Pb+1.0Ra+1.1E+1.1SRV44.9ksi44.5ksi45ksi45ksiHoopInsidelayerOutsidelayerRadialshearDiagonal220'20'60'01'=1.0D+1.0L+1.0Ta+1.5Pa+1.0RaU=1.0D+1.0L+1.0Ta+1.1Pa+1.0RaU=1.0D+1.0L+1.0Ta+1.25Pa+1.0Ra+1.25E+1.0(Rj+Rm+Rr)U=1.0D+1.0L+1.0Ta+1.5Pa+1.0Ra43.8ksi43.7ksi35.7ksi45.0ksi45ksi45ksi42.5ksi45.0ksiKEY:vu=Nominaldesignshearstressresistedbyconcrete.vc=Nominalpermissibleshearstresscarriedbyconcrete.NOTE:SymbolsareidentifiedinTable3.8-1.USARRevision8lof1November1995

NineMilePointUnit2FSARTABLE3.8-9LOADCOMBINATIONSFORTHEBIOLOGICALSHIELDWALLNormal0eatinLoa1~2~S=1.0D+1.0ES=(1.0)D+(1.0)To+(1.0)Ro+Eet3~5.6.1.6S=(1.0)D+(1.0)To+(1.0)Ro+E'.6S=(1.0)D+(1.0)Td+(1.0)Ra'(1.0)Pd1.8S=(1.0)D+(1.0)Td+(1.0)Ra'(1.0)Pd+1.0(Rr+Rj+Rm)+E2.0S=(1.0)D+(1.0)Td+(1.0)Ra'(1.0)Pd+1.0(Rr+Rj+Rm)+E'EY:DEE'dRa~RjRoRrDeadloadofshieldwall,equipment,andattachedpipingLoadduetooperatingbasisearthquake(OBE)Loadduetosafeshutdownearthquake(SSE)PressuredifferentialacrossbiologicalshieldwallduetoapiperupturePipereactionsunderthermalconditionsgeneratedbythepostulatedaccidentEquivalentstaticjetimpingementloadactingonastructuregeneratedbyarupturedhigh-energypipeduringthepostulatedaccident.ThepeakvalueofRjisusedunlessatime-historyanalysisisperformedtojustifyotherwise.Equivalentstaticmissileimpactloadonastructuregeneratedbyorduringthepostulatedaccident.ThepeakvalueofRmisusedunlessatime-historyanalysisisperformedtojustifyotherwise.Pipereactionduringoperatingcondition.Equivalentstaticreactionloadfromtherupturedhigh-energypipeduringthepostulatedaccident.ThepeakvalueofRrisusedunlessatime-historyanalysisisperformedtojustifyotherwise.RequiredsectionstrengthisbasedonelasticdesignmethodswhichareusedindesignastheallowablestressesdefinedintheAISCspecificationexceptthatthe331/3percentUSARRevision81of2November1995 NineMilePointUnit,2FSARTABLE3.8-9(Cont'd.)TdToincreaseinallowablestressesforseismicloadingisnotused.Effectoftemperaturegradientacrossbiologicalshieldwall,includingincreaseoftemperatureduetopiperuptureandpressurebuildup.Effectoftemperaturegradientacrossbiologicalshieldwallduringoperatingcondition.USARRevision82of2November1995 NineMilePointUnit2FSARTABLE3.8-10DESIGNSTRENGTHFORLOADCOMBINATIONSONCATEGORYISTEELSTRUCTURESPARTILoadCombinationsWithoutSRVDischargeLoading"0eratinCond'tiosNormalLoading:1~S=1'[D+L]SevereEnvironmentalLoading:2.S=1.0[D+L+E]3.S=1.0[D+L+W]DesinConditionsExtremeEnvironmentalLoading:4.1.6S=1.0[D+L+To+Ro+E']5.1.6S=1.0[D+L+To+Ro+Wt]AbnormalLoading:6.1.6S=1.0[D+L+Ta+Ra+Pa]7.1.8S=1.0[D+L+Ta+Ra+Rr+Rj+Rm+Pa+E]8.2.0S=1.0[D+L+Ta+Ra+Rr+Rj+Rm+Pa+E']9.1.6S=1.0[D+Ls]PARTIILoadCombinationsWithSRVDischargeLoading""ToaccountfortheeffectofSRVdischargeloadingandsuppressionpoolhydrodynamicloading,thesteelstructuresandsteelframingwithinthereactorbuildingarecheckedforthefollowingcombinations:USARRevision81of3November1995 NineMilePointUnit2FSARTABLE3.8-10(Cont'd.)es'tiosNormalWithoutTemperature:1~2~S~1.0D+1.0L+1.0Po+1.0SRV~S=1.0D+1.0L+1.0Po+1.0SRV~NormalWithTemperature:3~4~S=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.0SRV~S=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.0SRV~Normal/SevereEnvironmental:5~6.Abnormal:S=1.0D+1.0L+1.0Po+1.0Ro+1.0To+1.0E+1.0SRV~S=1.0D+1.0L+1.0Po+1.0Ro+1.0To+1.0E+1.0SRV~7.1.6S=1.0D+1.0L+1.0Pb+1.0Ta+1.0Ra+1~0SRV~8.1.6S=1.0D+1.0L+1.0Pb+1.0Ta+1.0Ra+10SRV~y9.1.6S=1.0D+1.0L+1.0Pa+1.0Ta+1.0Ra+1.0SRVAbnormal/SevereEnvironmental:10.1.8S=1.0D+1.0L+1.0E+1.0Pb+1.0Ta+1.0Ra+1.0SRV~11.1.8S=1.0D+1.0L+1.0E+1.0Pb+1.0Ta+1.0Ra+1.0SRV~12.1.8S=1.0D+1.0L+1.0E+1.0Pa+1.0Ta+1.0Ra+1'SRVUSARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.8-10(Cont'd.)Normal/ExtremeEnvironmental:13.1.6S=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1~0E'1~0SRV~14.1.6S=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.0E'1.0SRV~Abnormal/ExtremeEnvironmental:15.2.0S=1.0D+1.0L+1.0E'1.0Pb+1.0Ta+1.0Ra+1.0Rj+1.0Rm+1.0Rr+1.0SRV~16.2.0S=1.0D+1.0L+1.0E'1.0Pb+1.0Ta+1.0Ra+1.0Rj+1.0Rm+1.0Rr+1.0SRV17.2.0S=1.0D+1.0L+1.0E'1.0Pa+1.0Ta+10Ra+10Rj+1.0Rm+1.0Rr+1.0SRV~,IfthermalstressesduetoToandRoarepresentandareself-limitinginnature,a50-percentincreaseinallowablestresseswillbepermitted.ThepeakvaluesofPa,Pb,Ta,Ra,Rr,Rj,andRmareusedunlessatime-historyanalysisisperformedtojustifyotherwise.LocalstressesduetotheconcentratedloadRj,Rm,orRrmayexceedtheallowables,buttherewillbenolossoffunction.NOTES:1.KeytonotationsfollowsTable3.8-12.2.Loadsresultingfromthermalstratification,ifapplicable,areincludedwherevertemperatureloadsareconsidered.USARRevision83of3November1995

NineMilePointUnit2FSARTABLE3.8-11REQUIREDSTRENGTHFORLOADCOMBINATIONSONCATEGORYICONCRETESTRUCTURESPARTILoadCombinationsWithoutSRVDischargeLoading0eratinConditionsNormalLoading:1.U=1.4D+1.7L+1.3[To+Ro]SevereEnvironmentalLoading:2.U=1.4D+1.7[L+W]+1.3[To+Ro]3.U=1.4D+1.7L+1.9E+1.3[To+Ro]DesinConditionsExtremeEnvironmentalLoading:4.U=1.0[D+L+E'+To+Ro]5.U=1.0[D+L+Wt+To+Ro]6.U=1.0[D+L+F+To+Ro]AbnormalLoading:7.U=1.0[D+L+Ta+Ra]+1.5Pa~'~Abnormal/SevereEnvironmentalLoading:8.U=1.0[D+L+Ta+Ra+Rj+Rr+Rm]+1.25[Pa+E]""Abnormal/ExtremeEnvironmentalLoading:9.U=1.0[D+L+Ta+Ra+Rj+Rr+Rm+Pa+E']<'~>10.U=1.0[D+Ls]USARRevision81of3November1995

.NineMilePointUnit2FSARTABLE3.8-11(Cont'd.)PARTIILoadCombinationsWithSRVDischargeLoadingToaccountfortheeffectofSRVdischargeloadingandsuppressionpoolhydrodynamicloading,theconcretestructureswithinthereactorbuildingarecheckedforthefollowingcombinations:DesinConditionsNormalWithoutTemperature:1~2~U=1.4D+1.7L+1.0Po+1.5SRVU=1.4D+1.7L+1.0Po+1.5SRVNormalWithTemperature:3~4~U=1.0D+1.3L+1.0Po+1.0To+1.0Ro+1.3SRV~U=1.0D+1.3L+1.0Po+1.0To+1.0Ro+1.3SRV~NormalSevereEnvironmental:5.6.Abnormal:U=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.25E+1.25SRV~U=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.25E+1.25SRV~7.U=1.0D+1.0L+1.25Pb+1.0Ta+1.0Ra+1.25SRV~8.U=1.0D+1.0L+1.25Pb+1.0Ta+1.0Ra+1.25SRV~9.U=1.0D+1.0L+1.25Pa+1.0Ta+1.0Ra+1.0SRV~)Abnormal/SevereEnvironmental:10.U=1.0D+1.0L+1.1E+1.1Pb+1.0Ta+1.0Ra+1.1SRV,g,USARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.8-11(Cont'd.)11.U=1.0D+1.0L+1.1E+1.1Pb+1.0Ta+1.0Ra+1.1SRV~12.U=1.0D+1.0L+1.1E+1.1Pa+1.0Ta+1.0Ra+1.0SRV~INormal/ExtremeEnvironmental:13.U=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.0E'1.0SRV~14.U=1.0D+1.-0L+1.0Po+1.0To+1.0Ro+1.0E'1.0SRV~15.U=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.0Wt+1.0SRV~16.U=1.0D+1.0L+1.0Po+1.0To+1.0Ro+1.0Wt+1.0SRV~Abnormal/ExtremeEnvironmental:17.U=1.0D+1.0L+1.0E'1.0Pb+1.0Ta+1.0Ra+1.0Rj+1.0Rm+1.0Rr+1.0SRV~18.U=1.0D+1.0L+1.0E'1.0Pb+1.0Ta+1.0Ra+1.0Rj+1.0Rm+1.0Rr+1.0SRV~19.U=1.0D+1.0L+1.0E'1.0Pa+1.0Ta+1.0Ra+1'Rj+1'Rm+1'Rr+1'SRVThepeakvaluesofPa,Ta,Ra,Rr,Rj,andRmwillbeusedunlessatime-historyanalysisisperformedtojustifyotherwise.LocalstressesduetotheconcentratedloadRmmayexceedtheallowables,buttherewillbenolossoffunction.Usecapacityreductionfactor=1.0.NOTE:KeytonotationsfollowsTable3.8-12.USARRevision83of3November1995 I~I, NineMilePointUnit2FSARTABLE3'-12LOADCOMBINATIONSFORINTAKETUNNELS*0eratinConditionsNormalLoading:1.U=1.4D+1.7L+1.3To+1.4PdSevereEnvironmentalLoading:2.U=1.4D+1.7L+1.9E+1.3To+1.4PdDesinConditionsExtremeEnvironmentalLoading:3.U=1.0[D+L+E'+To]+1.4PdAbnormalLoading:4.U=1.0[D+L]+1.4Pd+1.7QL+1.25E*TheseloadcombinationsareusedindesigningtheCategoryIreinforcedconcreteportions(e.g.,concreteencasement)ofintaketunnels.Inadditiontotheseconditions,theconcreteencasementisdesignedforthetest(orpreoperational)conditionsconsideringtheconstructiontruckloading,theinternaltestpressure(Pi),ortheexternaltestpressure(Pe),asapplicable.KEYTONOTATIONSFORTABLES3.8-10THROUGH3.8-12:EE'LDeadloadsandtheirrelatedmomentsandforces,includinganypermanentloadsandhydrostaticloads.Loadsgeneratedbytheoperatingbasisearthquake.Loadsgeneratedbythesafeshutdownearthquake.Allforcesandmomentsrelatedtohydrostaticandsaturatedsoilpressuresduetothepostulatedmaximumflood(PMF).Forthisloading,exteriorwallsandfoundationsaredesignedforahydrostaticheadtoel261ft.Liveloadsandtheirrelatedmomentsandforces,including:1.Movableequipmentloads.2.Lateralsoilpressures.USARRevision81of4November1995 NineMilePointUnit2FSARTABLE3.8-12(Cont'd.)PaPbPdPoQLRaRjRo3.Snowloadduringnormaloperatingorsevereenvironmentconditions.4.Pressuredifferencesduetovariationinheatingandcoolingandoutsideatmosphericchanges.5.Anyotherloadsthatvarywithintensityandoccurrence.Pressureequivalentstaticloadwithinoracrossacompartmentand/orbuilding,generatedbythepostulatedaccident(i.e.,designbasispipebreakaccidentwithLOCA),andincludinganappropriatedynamicloadfactorappliedtothepeakofthepressure-timecurve.Pressureequivalentstaticloadwithinoracrossacompartmentand/orbuilding,generatedbythesmallpipebreakaccident(SBA)ortheintermediatepipebreakaccident(IBA)events.Pressuredifferentialbetweentheintakeanddischargewater(i.e.,betweeninsideandoutsideoftheencasement)duringthemostcriticaloftheoperatingordesignconditions.Pressureloadson.astructureduringoperatingcondition.Loadcausedbyapostulatedrockfallcondition.Pipereactionsunderthermalconditionsgeneratedbythepostulatedaccident.Equivalentstaticjetimpingementloadactingonastructuregeneratedbyarupturedhighenergypipeduringthepostulatedaccident.Loadincludesanappropriatedynamicloadfactorappliedtothepeakofthejetpressureloadtime-history.Equivalentstaticmissileimpactloadactingonastructuregeneratedbyorduringthepostulatedaccident.Loadincludesanappropriatedynamicloadfactorapplied.tothepeakofthemissileimpact-timecurve.Pipereactionsduringnormaloperatingorshutdownconditions,basedonthemostcriticaltransientorsteady-statecondition.Reactionequivalentstaticloadontherupturedhigh-energypipeduringthepostulatedaccident,andincludinganappropriatedynamicloadfactorappliedtothepeakofthereaction-timecurve.AllowabledesignstrengthwhenusingtheallowablestressesdefinedinPartIoftheAISCSpecificationfortheDesign,FabricationandErectionofStructuralSteelforBuildings,1969and1978.The331/3percentincreaseinallowableUSARRevision82of4November1995 NineMilePoint-Unit2FSARTABLE3.8-12(Cont'd.)stressesforseismicorwindloadingsisnotpermitted.Incomputingtheallowabledesignstrength,actualyieldstressofthematerialmaybeusedinplaceofspecifiedminimumyieldstressofthematerial.Theactualyieldstressofthematerialshallbedeterminedfromthetest.reportsofthematerialunderconsideration.Thisprovisionmaybeusedtoestablishdesignadequacyinisolatedcaseswherethespecifiedminimumstrengthofthematerialispotentiallyexceeded.SRV=SRVloadsaredefinedasfollows:SRV~SRV~SRV~SRV~)SRVloadsduetosequential(i.e.,allvalves)actuation.SRVloadsduetoautomaticdepressurizationsystem(ADS)(sevenvalves)actuation.SRVloadsduetoasymmetric(three.valves)actuation.SRVloadsduetosinglevalveactuation.TaToUThermaleffectsandloadsgeneratedbythepostulatedaccident.Thermaleffectsandloadsduringnormaloperatingorshutdownconditions,basedonthemostcriticaltransientorsteady-statecondition.Requiredstrengthtoresist.thedesignloadsbasedonthestrengthdesignmethods,asmodifiedbytheapplicationofcapacityreductionfactorsasdescribedinSection9.3,ACI-318-77.Incomputingtherequiredsectionstrength,actualcompressivestrengthofconcretemaybeusedinplaceofspecifiedminimumcompressivestrengthofconcrete.Theactualcompressivestrengthofconcreteshallbedeterminedfromthecompressivestrengthtestreportsoftheconcretepourunderconsideration.Thisprovisionmaybeusedtoestablishdesignadequacyinisolatedcaseswherethespecifiedminimumstrengthofthematerialispotentiallyexceeded.Loadsgeneratedbythedesignwindspecifiedfortheunit(Section3.3.1).USARRevision83,of4November1995 NineMilePointUnit2FSARTABLE3.8-12(Cont'd.)WtLsLoadsgeneratedbythedesigntornadospecifiedfortheunit.Theyincludeloadsduetothetornadowindpressure,thetornado-createddifferentialpressure,andthetornado-generatedmissiles(Sections3.3.2and3.5).Snowloadorprobablemaximumprecipitation(PMP)duringabnormal/extremeenvironmentalcondition.USARRevision84of4November1995 NineMilePointUnit2FSARTABLE3.8-14FACTORSOFSAFETYFOROVERTURNING,SLIDINGANDFLOATATIONOFMAJORCATEGORYISTRUCTURESStructureOverturningLoadingConditionsSlidingLoadingConditionsFloatationLoadingConditionControlandDieselGeneratorBuildingsNorthandSouthElectricalTunnelsMainStackReactorBuildingScreenwellBuildingStandbyGasTreatmentBuilding2.91.53.64.21.71.22.32.12.11.51.51.519.81.432.3ul5.111.61.71.31.2D+H+ED+H+WD+H+E'+H+W+D+F'ndj.catesthattheloadingconditionyieldsafactorofsafetyhigherthanthoselistedherein.USARRevision81of1November1995

PDTEDFETYLYIEPION-UNIT2NINEMILEPOINTNUCLEARSTATTNIAGARAUMOHAWKVOL.11 v~1, NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER11.11.2131.41.51.61.71~81.91.101.111.12113CHAPTER2INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTIntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOther'DetailedInformationConformancetoNRCRegulatory-GuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2.12'2.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13.23.33.4DESIGNOFSTRUCTURESICOMPONENTSgEQUIPMENTIANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMile'ointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section3.53.6A3.6B3e7A3.7B3'3'A3'B3.10A3.10B311AppendixesCHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER53ATitleMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMS~Volme99,10101010101212.1212,121212121212135.15'5.35.4Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B13131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLE,OFCONTENTS(Cont'd.)~secticCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume6'6.26.36.46.56'Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystems'FissionProduct'Removal-andControlSystemsIn-serviceInspectionofSafetyClass2,andClass3Components131415151515CHAPTER77.17'737.47.57.67'AppendixesCHAPTER88.18.28.3Appendix8A7A,INSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS1515151616161616161616,17179.19.29.39.49.5Appendixes9A,CHAPTER1010.110.210'FuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem17181920,2121,222323232324USARRevision8November1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section10.4CHAPTER1111'11.211.311.411.5Appendix11ACHAPTER1212.112'12'12'12'CHAPTER1313'13.213~313.413.513.6CHAPTER1414.1I14.214.3CHAPTER15150TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTSourceTermsLiquidWaste-Management-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessand-EffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneralVolume24242424'525252525252525262626262626262626262626,27272727USARRevisionivNovember1995 Nine.MilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.115.215.315.415.515.615.715.8AppendicesCHAPTER16CHAPTER1717.017.1172CHAPTER1818.118.2APPENDIXAAPPENDIXBTitleDecreaseinReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistribution-AnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveRelease.FromSubsystemsorComponentsAnticipatedTransientsWithoutScram15ANIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASEthrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISVolume272727272727272828282828282828282828USARRevisionvNovember1995 hJ NineMilePointUnit2FSAR3.9MECHANICALSYSTEMSANDCOMPONENTSThissectionisdividedasfollows:Section3.9AappliestosystemsandcomponentswithinSWECscopeofsupplyandSection3.9BappliestosystemsandcomponentswithinGEscopeofsupply.3.9AMECHANICALSYSTEMSANDCOMPONENTS.(SWECSCOPEOFSUPPLY)3.9A.1SpecialTopicsforMechanicalComponents3.9A.1.1DesignTransientsTable3.9A-1liststheplanteventsthatwereusedforthedesignandanalysisofASMESectionIIISafetyClass1componentsandsupports.Thetablealsoshowsthenumberofcyclespereventandeventclassification.Applicationofthesetransientsisdiscussedunderloadcombinationsin.Section3.-9A.3.1.3.9A.1.2ComputerProgramsUsedinAnalysesThecomputerprogramsusedinanalysesaredescribed,andtheirapplicabilityandvalidityaredemonstratedinAppendix3A.3.9A.1.3ExperimentalStressAnalysisExperimentalstressanalysisforthedesignofbalance-of-plant(BOP)equipmentwasnotused.3.9A.1.4ConsiderationfortheEvaluationoftheFaultedCondition3.9A.1.4.1EquipmentandComponentsTheelasticanalysistechniquesdescribedinSection3.7A.3areutilizedinthequalificationofCategoryIASMECodeandnon-Codeequipment.StresslimitsutilizedforthefaultedplantconditionareoutlinedinSection3.9A.3.1.Designconditionsandstresslimitsdefinedareapplicableforanelasticsystem(andequipment)analysis.Inelasticanalyseshavenotbeenused.3.9A.1.4.1.1ASMEIIIComplianceCategoryIASMESafetyClass1,2,and3componentsaredesigned,analyzed,andcertifiedinaccordancewiththeappropriateASMEIIICodeeditionandaddendaasdefinedintheirdesignspecifications.However,ifCodenameplatesareremovedfrominstalledequipment,traceabilityisprovidedinaccordancewithASMEIII1980Edition,Winter1981Addendum,SubsectionNCA,Subarticle8240(b).3.9A.1.4.2PipingSystemsCategoryIASMESafetyClass1,2,and3pipingandpipesupportsareanalyzedanddesignedinaccordancewithrequirementsofASMEUSARRevision83.9A-1November1995 NineMilePointUnit2FSARSectionIII,SubsectionsNB,NC,ND;-andNF,respectively.TheanalysesalsocomplywithAppendixFofASMESectionIII.The1974Editionisusedwiththefollowingexceptions:Buildingsettlements,notapplicabletothefaultedcondition,areanalyzedaccordingtothe1977Edition.203.4~5.ThenumberofOBEloadcyclesisbasedonAppendixNofthe1977Edition,Winter1978Addenda.Forpipesupports,the1974EditionisusedwiththeadditionalrequirementsdescribedinSection3.9A.3.4.1.TheboundaryofjurisdictionofASME'CodeSectionIII,Class1,2,or3processpipingextendstoandincludestheseatoftherootvalvetotheinstrument.TheappropriatequalitygroupextendsfromtherootvalvetotheinstrumentandshallbedesignedtoASMESectionIII.SeismicCategoryIsupportsshallbeinstalledwitha10CFR50AppendixBprogramdescribedinSection3.9A.3.4.1.MaterialupgradedbymaterialmanufacturerwillmeettheprovisionsofASMEIII,1977Edition,Summer1977Addenda,SubsectionNCA.6.InstallationofClass1,2,andaccomplishedinEdition,WinterSubsectionsNB,attachmentstoCategoryIASMESafety3pipingsystemsaftertestingistobeaccordancewithASMESectionIII,19801981Addenda,Subarticle4436,NC,andND.7~8.9.TheselectionofthetypeandcertificationofpenetrometersrequiredfornondestructiveexaminationisgovernedbyASMESectionVasinvokedbyASMESectionIII.The1974Edition,includingSummer1974Addenda,isused.TheinsidecornerradiusinNote6dofFiguresNCandND3673.2(b)-1isasdefinedinASMEIII,1980Edition,Winter1980Addendum.Thisradiusisrequiredontheinsidewalloftherunpipeatweldedbranchconnectionsgreaterthan4in.Theradiusisnotrequiredfornominalbranchpipesizesmallerthan4in.TherequirementsforthestampingofN-typenameplatesareasdefinedinthesubparagraphsNCA-8220andNCA-8320ofthe1980EditionofASMEIII.ThearrangementshallbesubstantiallyasshownonFigureNCA-8212-1ofthe1980ASMEIIICode.USARRevision83'A-2November1995 NineMilePointUnit2FSAR10.NondestructiveexaminationisgovernedbyASMESectionVasinvokedbyASMESectionIII,1980EditionofASMESectionVincludingSummer1980Addenda,isusedforevaluationcriteriaofscatteredradiation.Toestablishacceptablecriteriaforventingduringsystemfilloperation,ASMESectionIII,1981SummerAddenda,SubarticlesNB-6211,NC-6211,andND-6211areused.12.13~14.15.Therequirementsforexaminationofsocketweldcomponentsduringin-processrepairpriortoreusearedefinedinASMEIII,1980Edition,NB-4121.3.TherequirementsfortheeliminationofsurfacedefectsareasdefinedinSubparagraphNC-4452ofASMESectionII,1983Edition,Summer1984Addenda.ASMEIII,SubsectionsNB-6211,NC-6211,andND-6211,Summer1980Addenda,maybeusedforhydrostatictesting.ASMEIII,paragraphNCA-1273,Summer1980Addendaisusedwhendefiningfluidconditionerandflowcontroldevicesotherthanvalves.16.17.ASMEIIIAppendicesFigureI-9.2ofthe1983Editionisusedfordeterminationofacceptablestresslimitsforstainlesssteelpipingduringthepreoperationandpowerascensionphasesofthepipingvibrationtestprogram.UseofASMESubparagraphNB-3630(d)(2)ofASMESectionIII,Division1,Summer1976Addenda,ispermittedforstressanalysisofClass1pipinginaccordancewithrequirementsofSubsectionNC.18.Residualheatremoval(RHS)supplyanddischargelinesconnectedtotherecirculationpipinginprimarycontainmentareanalyzedinaccordancewiththeapplicableASMEIIICodegoverningtherecirculationpiping.Loadingsconsideredinthefaultedconditionincludethefollowing:1~2~Loadingassociatedwithnormalplantconditions,includinghydrodynamicloadsassociatedwithsuppressionpoolphenomena.LoadingassociatedwiththepostulatedSSE.USARRevision83.9A-3November1995 NineMilePointUnit2FSAR3.Dynamicsystemloadingassociatedwithfaultedplant.conditions,i.e.,DBA,breakofaMSL,orrecirculationline.4.Dynamicsystemloadingassociatedwiththeintermediatebreakaccident(IBA)andsmallbreakaccident(SBA).ProceduresfordevelopingtheloadingfunctionsinItems1and2abovearedescribedinSections3.9A.1.5and3.7A.3.8.LoadingfunctionsinItems3and4aredescribedinSection3.6A.2.LoadsassociatedwiththesuppressionpoolphenomenaaredescribedintheDAR(Appendix6A).3.9A.1.5AnalysisofPipingSystemsCategoryIpipingsystems(ASMESafetyClass1,2,3)areanalyzedinaccordancewithASMESectionIII,1974Edition,SubarticlesNB-3600,NC-3600,anceND-3600unlessotherwisenotedasanexceptioninSection3.9A.1.4.2.ANSIB31.1seismicallysupportedandnonseismicpipingsystemsareanalyzedinaccordancewithANSIB31.1Code,1973Edition,includingAddendumC,datedDecember18,1973.Inaddition,high-energypipingsystemsareanalyzedforpiperupturecriteria.AllseismicallysupportedandnonseismicallysupportedANSIB31.1systemsmaybehydrostaticallytestedinaccordancewithalaterCodeeditionthanpreviouslyspecified.LatereditionsofANSIB31.1areconsideredwhendefiningminimumweldingdimensionsrequiredforsocketweldingcomponentsotherthanflanges.AnalyticalmodelingandseismicanalysisaredescribedinSection3.7A.3.8.StaticanalysisandotherdynamicanalysesthatcontributetheremainingstressesintheCodestresscriteriaaredescribedinthefollowingsections.PipingengineeringanddesignspecificationsforUnit2allowtheuseofvarioustypesofbranchconnections,includingpipe-to-pipe.Unlessaspecificbranchconnectionisindicatedinthespecificationoronthepipingdrawings,anunreinforcedpipe-to-pipeconnectionisusedinthepipestressanalysis.Nofurtheractionisrequirediftheallowablestressesaremet.Iftheallowablestressesarenotmet,thenthepipingstresscalculationidentifiesthereinforcementofthebranchconnectionthatisrequired.Forcaseswherethebranchlineisdecoupledfromtherunpiping,theproperstressintensificationfactorisusedintheanalysisofboththebranchline~andthemainrunpiping.Ifreinforcementformechanicalloadsisrequired,itissoidentifiedinthepipingstresscalculationanddrawings.USARRevision83.9A-4November1995 NineMilePointUnit2FSARReinforcementrequirementsformechanicalloads,identifiedbythepipestresscalculations,areincorporatedonthepipingdrawings.PressurereinforcementcalculationsrequiredbyASMEIII,paragraphNB-3643,andANSIB31.1,paragraph104.3,areperformedbythepipingfabricator,andadditionalreinforcement,ifrequired,isidentifiedandaddedtothefabricatedpipe.3.9A.1.5.1StaticAnalysisThestaticequationofequilibriumfortheidealizedsystemmaybewritteninmatrixform,asfollows:KU=P-Q(3.9A-1)Where:KStiffnessmatrixfor-assembledsystemNodaldisplacementvectorExternalforces,weights,etc.LQ=Equivalentthermalforces=ABxTdC0A=CrosssectionareaE=Young'sModulusac=ThermalexpansioncoefficientT=Averagewalltemperatureless70'FinstallationtemperatureCoordinatealongpipeaxisL=LengthofpipeTheunknownnodaldisplacementsareobtainedfromoneofthepipinganalysiscomputerprograms(Appendix3A)bysolvingthisequationusingtheGaussianmethod.Thenodaldisplacementsarethenappliedtotheindividualmembers,andmemberstiffnessesareusedtofindinternalforces.Thenodaldisplacementsatsupportlocationscanbeusedalongwiththesupportstiffnesstodeterminesupportreactions.DeadLoadsWeihtPressureandLiveLoadsITheeffectofpressure,andthecombinedeffectsofweight,contents,andinsulation,arecalculatedusingoneofthepipinganalysiscomputerprograms(Appendix3A).Theanalysisfordeadweightassumesallflexiblerestraints,suchasspringUSARRevision83.9A-5November1995 NineMilePointUnit2FSARhangers,toberigid.,Ifapipehasdifferentcontents(medium)andthereforedifferentweightsinvariousflowmodes,thisistakenintoconsideration.OtherdetailsarediscussedinSection3.7A.3.8.3.Liveloadsareconsiderediftheyareexpectedtoconstituteasignificantcomponentofthetotalmechanicalload.ThefillingofMSLswithwaterduringvesselfloodingandalternateshutdowneventsisindicatedonthemainsteamthermaltransientsandconsideredinpipestressanalysisinaccordancewithNB-3600.Springhangersaredesignedtocarrythefullwater-filledpipingloadduringhydrotest.AdditionaldeadweightstressasaresultoffillingthepipingwithwaterisconsideredintheNB-3600analysisofthesystem.ThemainsteamSRVdischargepipinghasbeendesignedandqualifiedforthesteamhammerloadduetosteamblowdown.TheresultsoftheBWROwners'roup(BWROG)SafetyReliefValveTestProgram,inwhichUnit2hasbeenaparticipant,showthatthemeasuredspringandsupportresponsewassignificantlylessforwaterthansteam.Thetestreport,asdocumentedinNEDE-24988-P,statedthat"themaximumpiperesponseduetoliquiddischargewasgenerallylessthan30percentofthatduetosteamdischarge."ThetestprogramwasestablishedtomeasuretheSRVdischargeline(SRVDL)responseforalternateshutdowncoolingconditionsandtocomparetheseloadswithsteamloads.Additionaldeadweightstressresultingfromwater-filledmainsteamsafetyreliefisconsideredintheND-3600analysisofthemainsteamreliefvalvelines.InitialDislacementsAnchorMovementsThepipinganalysiscomputerprograms(Appendix3A)permitcalculationofthethermalinitialsupportdisplacementscombinedwiththethermalresponseduetotheaveragepipewalltemperaturechange.Earthquakeanchormovementsareconsidered(Section3.7A.3.8.3).InASMESafetyClassIanalysistheloadsduetoOBEanchormovementsarecombinedwiththeOBEinertialoadsviaabsolutesummation.InASMESafetyClass2and3analysistheCodepermitstheirexclusionfromoccasionalloadsiftheyareincludedwiththethermalexpansionloads.ThermalLoadsApipingsystemmayexperiencevariousoperatingmodes.Alloperatingmodesaremodeledasfollows:Portionsofpipingwithflowingmediumhavethetemperatureofthemedium,whileinactivebrancheshaveambienttemperature.Nonuniformtemperaturedistributionsalongthepipenearbranchconnectionsofactiveandinactivelegsareconsidered.USARRevision83.9A-6November1995 Nine"Mile,PointUnit~2,FSARInSafetyClassIanalysis,stressesduetotemperaturedistributionacrossthethicknessofthepipewallandgeometricandmaterialdiscontinuitiesduringthermaltransientsmustbeconsidered.ThesearerepresentedinASMESectionIII,SubarticleNB-3600,'by:EochTEachT~,andE~(a,T,-a,T~)(3.9A-2)Basedongeometry,fluidtype,insulation,thermaltransients,environmentaldata:ocETocbT~,andE~(a,T,-u,T,)(3.9A-3)areobtainedfromtheHTLOADprogram(Appendix3A),orhandcalculations.3.9A.1.5.2OccasionalDynamicLoads-ExcludingSeismicandHydrodynamicInertiaLoadsOccasionalloadsarealsoanalyzedusingoneofthepipinganalysiscomputerprograms(Appendix3A).Inthematrixequationofmotion:MO+cO+KU=F(c)(3.9A-4)Where:M=MassmatrixC=DampingmatrixK=StiffnessmatrixU=DisplacementvectortheforcingfunctionF(t)isappliedasasetofforcetimehistories,oneforeachmassdegree-of-freedomthatexperiencesadynamicload.F'dasientsFluidtransientsareconsideredinthefollowingsystems:1~2~3~4~Mainsteamandmainsteambypasssystems.MainsteamSRVdischargesystem.Moistureseparator/reheatersafetyreliefsystem.Feedwatersystem.USARRevision83.9A-7November1995 NineMilePointUnit2FSAR5.ECCS,includingECCS,pressurereliefvalvedischargepiping.6.SWPsystem.7.RHRsystem.8.RCICsystem.9.RWCUsystem.10.SLCSsystem.11.CRDsystem.Thecomputerprograms(Appendix3A)usedtocalculatetheseforcetime-historiesduetowaterhammer,steamhammer,andpipewithairtrappedinwaterlines,areWATHAM,STEHAM,andWATAIR,respectively.JetIminementTheeffectsofdirectjetimpingementonpipingareevaluatedafterallotherpipinganalysesarecompletedandtargetsfromallpostulatedbreakshavebeenidentified.ReliefValveReactionsOtherThanMainSteamSRVsValvesthataresubjectedtojetreactionforcesaresupportedbystaticrestraintsadjacenttothevalvesuchamannerthattheeffectsonthepipingoutsiderestraintscanbeneglected,orthepipingsystemisreliefvalvedischargeloadcase.eitherbody,intheseanalyzedforSuressionPoolInducedDnamicLoadsintheReactorBuildinTheseloadsaredescribedandassessedintheDAR(Appendix6A).3.9A.1.5.3Field-RunPipingThereisnofield-runASMEsafetyclasspipinginUnit2.3.9A.1.5.4LoadCombinationsandStressCriteriaIndetailedanalysesofASMEsafetyclasspipingsystems,theindividualloadcasesarecombinedasshowninTable3.9A-2.Inthesimplifiedanalysisforsmallborepiping(Section3.7A.3.8)thesameprincipleisfollowed;however,theresultingseismicspans,thermaloffsets,andsupportloadsareboundingvaluesdeterminedfromseveralfundamentalconfigurations.TheclassificationforASMESafetyClass1,2,and3pipingsystemsaccordingtotypeofanalysisisgiveninTable3.9A-3.USARRevision83.9A-8November1995 Nine.MilePointUnit2FSAR3.9A.1.6Safety-RelatedHVACDuctworkandSupportsSafety-relatedductsystemsaredesignedforinternalpressure,deadweight,anddynamicloadswhichresultfromseismiceventsandplantoperatingconditions.Dynamicloadsareappliedstaticallyas'g'orcestakenfrombuildingARScurves.The'g'aluesaretakenaseithermaximumorthe'g'orrespondingtothesystemnaturalfrequency.DuctworkisqualifiedtotheSMACNADuctConstructionStandardsandtheAISICode;ductsupportsarequalifiedtotheAISCCode.3.9A.2DynamicTestingandAnalysis3.9A.2.1PipingVibration,ThermalExpansion,andDynamicEffectsAdetailedpreoperationaltestprogramwassubmitted60daysbeforethestartofthetests,asrequiredbyRG1.68.3.9A.2.1.1FlowModesTabulatedflowmodesforvarioussystemsareprovidedaspartoftheabovetestprogram.3.9A.2.1.2PreoperationalVibrationTestingSafety-relatedpipingsystemsdesignatedasSafetyClass1,2,or3aredesignedinaccordancewithASMESectionIII.Eachsystemisdesignedtowithstanddynamicloadings.fromoperationaltransientconditionsthatareencounteredduringexpectedserviceasrequiredbyParagraphsNB-3622,NC-3622,andND-3622oftheASMECode.Toverifythatpipingsystemswouldwithstandoperationalvibrationconditions,avibrationmonitoringprogramwasimplementedwhichincludedbothsafety-relatedandnonsafety-relatedprocesspipingandinstrumentlines.Avibrationmonitoringtestspecificationwaspreparedtocategorizetherequirementsforthetestprogram.Safety-relatedsystemsarecategorizedasfollows:a~SystemsWithFlow-Accessiblelines(includingattachedinstrumentlines)weremonitoredvisuallyorwithhand-heldinstruments,andinaccessiblelinesandlineswithtransientvibrationsweremonitoredbyremoteinstrumentation.b.OtherSystems-Notestingwasrequired.Instrumentlinesconnectedtoinaccessibleprocesslineswerenotindividuallymonitored.Instrumentlineswereconsideredacceptablefromasteady-statevibrationpointofviewifthevibrationoftheprocesspipetowhichtheinstrumentlinesareconnectedwaswithintheacceptancetestlimits.IftheUSARRevision83.9A-9November'1995 NineMilePointUnit2FSARvibrationlevelsintheprocesspipewereabovetheacceptabletestlimits,considerationwasgiventotheconnectedinstrumentlines.Duringthevibrationmonitoringprogram,vibrationtestingwasperformedeitherduringthepreoperationorpowerascensiontestingphasesonthesystemsidentifiedbelow.~Sste]gPreoperationPhasePowerAscensionPhase*Low-PressureCoreSpray(CSL)High-PressureCoreSpray(CSH)ReactorWaterCleanup(WCS)Feedwater(FWS)SpentFuelPoolCooling(SFC)ServiceWater(SWP)ResidualHeatRemoval(RHS)MainSteam(MSS)MainSteamSafetyRelief(SVV)AirStartupStandbyDieselGenerator(EGA)ServiceAir(SAS)ReactorCoreIsolationCooling(ICS)Condensate(CNM)StandbyLiquidControl(SLS)ControlBuildingChilledWater(HVK)InstrumentAir(IAS)ReactorBuildingClosedLoopCoolingWater(CCP)NitrogenSystem(GSN)StandbyGasTreatment(GTS)ContainmentPurgeSystem(CPS)ReactorCoolantRecirculation(RCS)ControlRodDrive(RDS)NuclearBoilerInstrumentation(ISC)XXXXXXXXXXXXXXXXXXXXXXXXXSeeSection3.9B.2.1forvibrationtestingofGE-suppliedsystems.Vibrationmeasurementswereconductedforsteady-stateandtransientconditionssuchaspumpstartsandvalveoperation.Also,visualinspectionstodeterminevibrationresponsewereperformed,withemphasisplacedonvents,drains,andbranchpiping.*TestingonthesesystemsisaccomplishedduringthestartuptestphaseasdescribedinTable14.2-303.USARRevision83.9A-10November1995 NineMilePointUnitFSAR3.9A.2.1.3PreoperationalThermalExpansionTestingPreoperationaltestsforBWRsareconductedatnearambientconditions;therefore.,thermalexpansiontestingduringthepreoperationaltestphaseisverylimited.ForthesystemsdelineatedinSection3.9A.2.1.2thatareoperatedatotherthanambientconditionsduringthepreoperationaltestphase,pipedeflectionsareobservedormeasuredatselectedlocations.ThestartupexpansiontestingprogramisdiscussedinfurtherdetailinSection3.9B.2.1.2.3.9A.2.1.4MeasurementLocationsTheexactlocationsofmeasuringdevicesandidentificationofvisualinspectionpointsaresuppliedinthetestprogram.Measurementstakenatpointswithdynamicinstrumentationshowwhetherthestressandfatiguelimitsarewithinacceptablelevels,andmeasurementstakenatpointswithexpansioninstrumentationinanexpansiontest,excludingdynamiceffects,arecheckedagainstdisplacementcriteria.3.9A.2.1.5AcceptanceCriteriaAcceptancecriteriaforvibrationsweredependentuponwhethersteady-stateortransientvibrationwasmeasured.Forsteady-statevibrations,acceptancecriteriawerebasedonANSI/ASMEOM3-1982rules.Themajorityofthepipingwastestedbyatwo-phaseprocess.Phase1consistedofvisuallyobservingthepipetodetermineifavibrationwasperceived.Ifvibrationwasnotobserved,thatportionofthepipewasacceptable.Ifvibrationwasobserved,Phase2wasimplemented.Thisconsistedoftakinglocalmeasurementsusinghand-heldinstrumentsatpointswheresteady-statevibrationwasobserved.Vibrationvelocitywasmeasuredand,ifitwaslessthan0.5in/sec,thepipingwasacceptable.Atvelocitiesequaltoorgreaterthan0.5in/sec,displacementmeasurementsweretakenandforwardedtoengineeringforresolution.Fortheremainingpiping,wheresignificantsteady-statevibrationwasanticipated,orwhereinaccessiblefornormalviewing,vibrationwasmonitoredbyfixeddisplacementtransducers(lanyardpotentiometers)withremotereadouts.TherecordeddisplacementswerecomparedtotheacceptancecriteriaasdeterminedbyANSI/ASMEOM3-1982.-Iftheacceptancecriteriawereexceeded,therecordeddisplacementswereevaluatedbyengineeringtodeterminearesolution.Forallsteady-statevibration,OM3-1982guidelineswereused;however,displacementsforcarbonsteelwerebasedon80percentofstressendurancelimitsdividedbyafactorof1.3.Displacementsforstainlesssteelpipingwerebasedonstressallowablesfor10E11cycles,asshownonFigureI-9-2ofASMEIIIofthe1983Code.CurveCofthefigurewasusedforinitialUSARRevision83.9A-11November1995 Nine'ilePointUnit2FSARscreening.Ifdetailedanalysiswasrequired,CurveBwasusedinaccordancewithCoderequirements.Fortransientvibrationtesting,vibrationalsowasmeasuredbyfixeddisplacementtransducers(lanyardpotentiometers)withremotereadouts,andtwolevelsofacceptancecriteriawereused.1~2~Level1criteriaestablishthemaximumlimitsforthelevelofpipemotionwhich,ifexceeded,mandatesatestholdortermination.Level1criteriaensurethatthepipestresslevelwillnotexceed1.2S~,theapplicableCodeallowable.ThedisplacementlimitsforLevel1criteriaweredeterminedfromthosepredictedforloadingconditionsthatwereusedto,evaluatetheapplicableCodeequationforanoccasionalload.IfanyLevel1criteriawere-exceeded,anengineeringevaluationwasperformedtodevelopcorrectiveactionorshowthatthemeasuredresultswereacceptable.Level2criteriaarebasedonpipestressesasanalyzedandpredictedforthefluidtransientfortheparticularevent.IfanyLevel2limitswereexceeded,adetailedengineeringevaluationwasperformedtodevelopcorrectiveactionorshowthatthemeasuredresultswereacceptable.AcceptancecriteriaforvibrationonsystemslistedinSection3.9A.2.1.2arespecifiedinthevibrationtestprogram.Thestresscalculatedbasedonmeasureddisplacementsrepresentsthecombinedstressofpressure,deadweight,andfluidtransientloads,andwascombinedwiththeanalyticalstressoftheloadcasesnotsimulated,suchastheOBE,andthencomparedwiththecombinedanalyticalresult.TheallowablestressesarelistedinTable3.9A-2.Thelimitsforthermaldisplacementsdependontheequipmentdesignparameters.Underallplantconditionsthepipingisnotpermittedtotouchanotherobjectthatmayinterferewiththeoperationof.thepipingsystemorequipment.3.9A.2.1.6CorrectiveActionsIfduringthevibrationtestitshouldbenotedthatthevibrationsarebeyondtheacceptabledesignlevel,additionalsupportsandrestraintsmaybeprovided.Thepossibilityofpipingreroutingwouldalsobeconsidered,andareanalysisorretestwouldbeperformedtoassurethatthedesignmeetstheacceptancecriteria.Similarly,ifthedesigntolerancesforthermaldisplacementsarenotsatisfiedatapointalongthepiping,theequipmentaffectedUSARRevision83'A-12November1995 NineMilePoint'Unit2FSARcanusuallyberealigned.Otherwise,supportsandrestraintswouldberearranged,andpipereroutingwouldalsobeconsidered.3.9A.2.2SeismicQualificationofSafety-RelatedMechanicalEquipmentThissectionprovidesthequalificationcriteriaandmethodsforequipmentaffectedbyseismicloads.ThemethodsforthequalificationofequipmentaffectedbyhydrodynamicloadsassociatedwithSRVdischargeandthepostulatedLOCAareprovidedintheDAR,Appendix6A,Subsection6A.9.3.9A.2.2.1SeismicQualificationCriteriaThepurposeofqualifyingCategoryImechanicalequipmentistodemonstrateitsabilitytoperformasafety-relatedfunctionduringandafterapostulatedseismicoccurrenceofamagnitudeuptoandincludingtheSSE.Equipmentthatdoesnotperformanysafety-relatedfunction,butwhosefailurecouldjeopardizethefunctionofCategoryIequipment,isrequiredonlytomaintainitsstructuralintegrity.SeismicqualificationofequipmentisaccomplishedbyoneofthefourmethodsdiscussedinSection3.7A.3.1.Analysisisusedtodemonstratestructuralintegrityoftheequipment.Whenmechanicalequipmentisqualifiedbyanalysis,thecalculatedstressesaremaintainedwithinthespecifiedallowablesthatcontaintherequiredmarginsofsafetydescribedinSection3.9A.2.2.2.Wheretheequipmentisclassifiedasactive,additionaldeflectionanalysisand/ortestingisperformed.DetailsofqualificationmethodsforspecificequipmentarecontainedinTable3.9A-4.Thesemethodsareappliedtomechanicalequipmentasfollows.A~nalsisThelistingbelowisforequipmentwherethemaintenanceofstructuralintegrityonlyisrequiredtoassureperformanceofthedesign-intendedfunction.Thisequipmentisqualifiedbyanalysis:1~2~3~4~5.Piping.Ductwork.Tanksandvessels.Heatexchangers.HVAC-passivecomponents.6.Pumpandvalvepressureboundarypartsthatarenotrequiredtooperateandperformasafetyfunction.USARRevision83'A-13November1995 NineMile'oint'nit2FSARAnalysisisalsousedtoqualifyrotatingmachineryitemswhereverificationmustbeobtainedtodemonstratethatdeformationsresultingfromseismicloadingsdonotcausebindingoftherotatingelement,totheextentthatthecomponentcannotperformitsdesign-intendedfunction.Componentsinthiscategoryinclude:1.Activepumpsandvalves.2.Fansanddampers.Thelargesizeandweightofsomeofthesecomponents,togetherwiththedifficultiesencounteredinapplyingoperatingloadsduringdynamictesting,servetomakeanalysisthemostviablequalificationmethodfortherotatingmachineelements.DnamicTestinThefollowingequipmentwhosefunctionalcapabilitycannotbeadequatelydemonstratedbyanalysisisqualifiedbydynamictesting:1.Standbydieselgeneratorcomponents.2.Hydrogenrecombinercontrolpanels.3~Electricmotorvalveactuators,includinglimitswitches.4.Pneumaticandhydraulicvalvelimitswitchesandsolenoidvalves.5.Electricalcontrolpanels,relayboards,switchgearandMCCs,andradiationmonitoringequipment.6.Controlinstrumentationsuchasflowswitches,thermocouples,andtransmitters.7.Batteries,batterychargers,andinverters.8.Electricalpenetrations.CombinationofAnalsiswithTestinAcombinationofanalysiswithstaticordynamictestingisusedforseismicqualificationofactivevalves,asfollows:1~2~Thenaturalfrequenciesofthevalveassemblyaredeterminedbyanalysisortest.Astaticdeflectiontestisperformedtoverifythatdeformationduetoseismicloadingsdoesnotcausebindingofinternalvalveparts,whichpreventsvalveoperationswithinspecifiedtimelimits.USARRevision83.9A-14November1995 Nine,Mile.PointUnit2FSAR3.Theelectricmotor-driven,pneumatic,andhydraulicvalveactuatorandotherelectricalappurtenancesarequalifiedbydynamictesting.Forthoseactivevalvesthataresimpleindesignordonothavesignificantextendedstructuresorelectricalappurtenances,seismicqualificationisachievedbyanalysisalonetoensurethatthevalvecanperformitsdesign-intendedfunction.Equipmentthatisqualifiedbytestingismountedandoperatedinamannersimilartothatoftheactualsystem.FortestingproceduresrefertoSection3.7A.3.3.9A.2.2.2AcceptanceCriteriaTheacceptancecriteriausedareasfollows:2~Tests,whenused,demonstratethatthecomponentperformsitsrequiredsafetyfunctionduringandafterthetest.TheTRSenvelopetheapplicablefrequencyrangeoftheRRSwiththerequired10-percentmargininaccordancewithIEEE-323-1974.WheretheTRSdoesnotenvelopetheRRSwiththesuggestedmarginsofIEEE-323-1974,ajustificationisprovided.Analysis,whenused,verifiesthatstressesdonotexceedthespecifiedallowablestresslimitsfortheloadingconditionsshowninTables3.9A-5and3.9A-6andthatdeformationsdonotexceedthosewhichwillnotpermitthecomponenttoperformitsdesign-intendedfunction.ForASMEcomponents,thespecifiedallowablestresslimitsarethoseshowninTables3.9A-7and3.9A-8.Fornon-ASMEcomponents,theDesignConditionIloadinghasallowablestresseslimitedto75percentoftheminimumyieldstrengthatthedesigntemperatureofthematerial,inaccordancewithapplicableASTMspecification.FortheDesignConditionIIloadingthestressesdonot,exceedthesmallerof:l.100percentoftheminimumyieldstrength,or2.70percentoftheminimumultimatetensilestrengthofthematerial(attemperature),inaccordancewiththeASTMorequivalentspecificationforthematerial.FordefinitionsofDesignConditionsIandII,seeSection3.9A.3'.2.USARRevision83,-9A-15November1995

.NineMile'Point'nit2FSAR3.9A.2.2.3Seismic,QualificationofSpecificNon-NSSSMechanicalEquipment~Pi~inAllsafety-relatedpiping,includingpipinginpipetunnels,isseismicallyanalyzedinaccordancewithSection3.7A.3.8.TanksThesafety-relatedtankshavebeenseismicallyqualifiedasfollows.Theseismicanalysisontheburiedstandbydieselgeneratorfueloilstoragetankconsistedofthefollowing:1.Selectionoftheapplicableseismicaccelerationfactorsattheelevationinthedieselgeneratorbuildingatwhichthetankisinstalled.2~Calculationofthelowestnatura'linfrequencyofthefilledtankinitsburiedenvironmeiit.'taking'intoaccountboththemassandspringrateofthisenvironment.Thisfrequencyoccursintherigidrange.3.Choiceofthecorrectseismicfactorsbycombininganalysisparameters1and2.4.Determinationofloadsonboththetankandsupportringsbystaticanalysiswithseismicg-factorsappliedtoalltankandsandmasses.5.ASMECodemethodsforthedesignofthetankshell,heads,stiffening,andsupportringswereused.Localstressanalysis,byBIJLAARDorothermethods,asappropriate,wasusedindeterminingstressesatnozzlesandsupportrings.6.Analyseswereperformedforbothnormalandupsetconditions(includingliveanddeadloads,thermalandpressurestresses,andOBEseismicfactors)andfaulted,conditionscomposedofliveanddeadloadsplusfullSSEinertialloads.7.Adequacyofthetankat.designpressurewasdetermined.Thetankwashydrotestedat1.5timesdesignpressureincompliancewithASMECode.Theseismicanalysisfortheairdamper/accumulators,thechilledwaterexpansiontanks,theskimmersurgetanks,andthestandbydieselgeneratorfueloildaytanks,consistedofthefollowing:1.Ananalysisofthevesselwasperformedtoprovethatithasrigidcharacteristics,i.e.,thenaturalUSARRevision83'A'-16November1995 NineMilePointUnit2FSARfrequencyofvibrationofthepredominantmodeofthesupportedvesselisintheflatportionoftheapplicableresponsespectrumcurves.Theapplicableseismicaccelerationcoefficientswerechosenaccordingtothelocationofeachvessel.2~Theseismicaccelerationcoefficientswereappliedstatically,andastaticanalysiswasperformedontheequipmentandsupports.Theverticalandhorizontalseismiceffectswereappliedsimultaneouslytothesubjectvesselatitsgravitationalcenterfortheseismicloadcalculationanddesign.3.Determinationofloadsforboththetanksandsupportsbystaticanalysiswithseismiccoefficientsappliedtoalltankmasses.4.Theremainderoftheanalysiswasperformedaccordingtoprecedingsteps5through7forsafety-relatedtanks.SincetheADSandmainsteamSRVaccumulatorsarelocatedinsidethereactorbuilding,seismicaswellashydrodynamiceffectswereconsideredintheiranalysis.TheprecedingSteps1and2werethereforeperformedwiththeapplicableaccelerationcoefficients.~PummQualificationofpumpsisshowninTable3.9A-9andfurtherdiscussedinSection3.9A.3.2.TheresultsoftestsandanalysesaredescribedinTable3.9A-4forpumpslistedinTable3.9A-9.ValvesThequalificationofactivevalvesisdiscussedinSection3.9A.3.2.TheresultsoftestsandanalysesaredescribedinTable3.9A-4forthevalveslistedinTable3.9A-12.Therearenomanuallyoperatedvalveswhichmustchangepositionforanysafetysystemtoperformitsfunctionintheshortterm,followinganyevent.Theoperationofcertainmanualvalvesmayberequiredinthelongterm.ThesevalvesincludethosenecessarytoreplenishfueloiltothedieselgeneratorfueloilstoragetanksandnitrogentotheADSvalveaccumulatorreceivingtanks,andtoaccomplishboronreplenishmentintheSLCSfollowingananticipatedtransientwithoutscram(ATWS)event.TheonlyothervalveswhichmayberequiredtochangepositiontoaccomplishasafetyfunctionarethoseRHRvalveslocatedintheSFC/RHRinterties.AsdiscussedinSection9.1.3.3,theseintertiesmaybeusedtoprovideadditionalfuelpoolcoolingfollowingafullcoreoffload.USARRevision83'A-17November1995 NineMilePointUnit2FSAROtherMechanicalEuimentThequalificationmethodformechanicalequipmentotherthantheaboveisdiscussedinSection3.7A.3.ThequalificationresultsaredescribedinTable3.9A-4.ElectricalEuimentandInstrumentationTheseismicqualificationcriteriaandmethodsofqualificationofCategoryIelectricalequipmentandinstr'umentation,otherthanthoseitemsdiscussedinthissection,aredescribedinSection3.10.CranesCranesareseismicallyqualifiedinaccordancewiththefollowingcriteria:1.Thepossibilityofthecranebeingdislodgedbyaseismicdisturbanceisprecluded.2.Nopartofthecranebecomesdetachedandfallsduringanearthquake.3.Thecraneloadwillnotlowerinanuncontrolledmannerduring,orastheresultof,anearthquake.3.9A.3ASMECodeClass1,2,and3Components,ComponentSupports,andCoreSupportStructures3.9A.3.1LoadingCombinations,DesignTransients,andStressLimitsThedesignbasisforallsafety-relatedpiping,,components,equipment,andsupportsconsidersallappliedloadssuchaspressuretemperature,deadweight,externalmechanical,thermal,fluidtransient,seismic,andhydrodynamicloads.HydrodynamicloadsareuniquetotheMarkIIcontainmentofUnit2andothersimilarsuppressionpool-typecontainments.Thedesignbasisforallsafety-relatedpiping,components,andequipmentsubjectedtohydrodynamicloadsmeetstherequirementsofthefollowingNRCdocuments:NUREG-0487,Supplements1and2,MarkIIContainmentLeadPlantProgramLoadEvaluationandAcceptanceCriteria.2~3~NUREG-0808,MarkIIContainmentProgramLoadEvaluationandAcceptanceCriteria.NUREG-0802,Safety/ReliefValve-QuencherLoadsEvaluationReports-BWRMarkIIandIIIContainments.USARRevision83..9A-18November1995 NineMilePointUnit2FSAR4.NUREG-0783,SuppressionPoolTemperature'LimitsforBWRContainments.5.NUREG-0763,GuidelinesforConfirmatoryInplantTestsofSafety-ReliefValveDischargesforBWRPlants.Allsafety-relatedequipment,piping,andcomponentsandtheirsupportslocatedinthereactorbuildingareevaluatedusinghydrodynamicloads.Allotherstructuresarenotaffectedbyhydrodynamicloads.SeeAppendix6A,-DesignAssessmentReport,forfurtherdetails.3.9A.3.1.1ASMESectionIII,Class1ComponentsASMEIII,Class1mechanicalequipment,i.e.,valves,pumps,andcoolingcoils,isdesignedinaccordancewithASMESectionIII,SubsectionNB.LoadingcombinationsandserviceconditionsareoutlinedinTable3.9A-5.CorrespondingstresslimitsinaccordancewithArticleNB-3000arelistedinTable3.9A-7.ThisequipmentislistedinTable3.9A-4.TheseloaddescriptionsincludeDynamicLoad1,DynamicLoad2,andDynamicLoad3notations,whichareloadcombinationsforequipmentinthereactorbuildingonly,resultingfromconsiderationofhydrodynamicloadingconditions;forequipmentoutsidethereactorbuilding,thesereducetoOBE,SSE,andOBE,respectively.Fortheconditionsspecified,theallowablestresslimitsdefinedinTable3.9A-7areapplicabletostressresultsobtainedbyelasticanalysistechniques.TheanalysismethodsdescribedinSection3.7A.3areusedinimplementingthiscriterion.ComputerprogramsusedintheseanalysesarediscussedinAppendix3A.~Pi~inThepipestressanalysisloadcombinationsandstresslimitsforASMEClass1pipingaregiveninTable3.9A-2.ThedesigntransientsandnumberofassociatedstresscyclesforthevariousplantconditionsaregiveninTable3.9A-l,whichincludesthedynamicloadeventsOBE,SSE,LOCA-relatedloadcases,andSRVdischargecases.ThesuppressionpooleventsarediscussedinAppendix6A.ThereareseveralSRVcases.InTable3.9A-2SRVreferstotheenvelopeoftheresponseofallSRVcasesapplicabletoaparticularloadcombination.ThenumberofloadcyclesusedfordifferentSRVcasesisgiveninTable3.9A-1.Underemergencyandfaultedconditionsnofatigueanalysisneedbeperformed.Figures3.9A-6through3.9A-67aretypicalexamplesofresponsespectrafortheloadconditionsof:USARRevision83'A-19November1995 Nine'MilePoint'Unit2FSAR1.SeismicOBE.2.SeismicSSE.3.SRVloads.4.,LOCA-related'oadsa.Chugging.b.BasicCO.c.ADSCO.5.SeismicOBE2-5percentdampinginaccordancewithCodeCaseN-411.6.SeismicSSE2-5percentdampinginaccordancewithCodeCaseN-411.Theseresponsespectrasareprovidedatthefollowinglocations:1.TopofRPV.2.TopofBSW.3.Primarycontainmentatthesuppressionpoolwaterlevel.4.Reactorbuildingmat(onlyhydrodynamicloadsareprovided).TheprovidedresponsespectrahavebeenbroadenedinaccordancewithRG1.122.B'othverticalandhorizontalspectraareprovidedforeachlocation.Inordertoensuretheir-continuedoperationduringemergencyandfaultedevents,ECCSandotheressentialsystemsarerequiredtomeetthefunctionalcapabilitycriteriaofNED0-21985,FunctionalCapabilityCriteriaofEssentialMarkIIPiping,September1978.ASMEClass1pipingmeetsthecriteriaofASMESectionIII,1974Edition,and10CFR50.55a,Section(d).AnalysisoftheindividualloadcasesisdescribedorreferredtoinSection3.9A.1.5.ASMECodeClass1pipingfatigueevaluationwasperformedforthe:SRVpipinginthesuppressionpoolarea.AllofthethermalanddynamicloadsandrespectiveoperatingcycledatawereusedforevaluationoftheSRVline.TheCUFobtainedfromtheanalysisislessthan1.0;hence,nofatiguecrackisanticipatedduetoalloftheprescribedloads.ASMECodeClass1pipingfatigueevaluationwasperformedforthedowncomers.TheCUFobtainedfromtheanalysisislessthan1.0;.USARRevision83.9A-20November1995 NineMilePointUnit2FSARhence,nofatiguecrackisanticipatedduetoalloftheprescribedloads.3.9A.3.1.2ASMEClass2and3ComponentsTables3.9A-6and3.9A-8listloadingconditionsandstresslimitsforASMESectionIII,Class2and3componentsoftheCategoryIfluidsystemsconstructedinaccordancewithASMESectionIII,SubsectionsNCandND.Theseconditionsare:1.DesinCoditionIIncludesthespecifieddesignloads(temperature,pressure,etc.),plusDynamicLoad1loads.2.DesinConditionIIIncludes-thespecifieddesignloads(asabove),plusDynamicLoad2loads,pluspiperuptureloads(ifapplicable).ThedesignloadcombinationsareanalogoustoeithertheCodeClass1normalorupsetconditionsforDesignConditionIandtothefaultedconditionforDesignConditionII.SeeTable3.9A-5forthedefinitionsofDynamicLoad1andDynamicLoad2.Theserequirements,whichsupplementthepresentscopeofASMESectionIII,SubsectionsNCandND,areconsistent.withthepresentCodeformatandphilosophy.Furtherextensionofterminology(normal,upset,etc.)isnotrequired,sinceCodeClass2and3systemsarenotgenerallyevaluatedforsuchvarietiesofoperatingconditionsandtransients,butrathertodesignconditionswhichconservativelyenvelopalloperatingconditions.Generally,onlydesignconditionsofpressureandtemperaturearenecessarytosatisfyASMECoderequirements.Theseconditionsenvelopallservicelevelconditionsforthecomponentsuchasnormal,upset,emergency,andfaultedplantconditions.Useofdesignconditionsplusseismicloadingisthereforeaconservativecriterion.ThestresslimitsanddesignconditionspresentedinTable3.9A-8areintendedtoensurethatnogrossdeformationofthecomponentoccurs.Theselimitsareapplicableforanelasticsystem(andcomponent)analysis.NoinelasticanalysishasbeenperformedforanyASMEClass2or-3component.PiinSstemsTheloadcombinationsandstresslimits-forASMEClass2and3pipingaregiveninTable3.9A-2.TheyconformtothecriteriaofASMESectionIII,whichimplyelasticanalysis.Underfaultedcondition,withprimarystresslimit2.4S,grossinelasticdeformationsthatmayoccurarepermittedbytheCode.USARRevision83.9A-21November1995 NineMilePoint'Unit2FSARAnalysisoftheindividualloadcasesisdescribedorreferredtoinSection3.9A.1.5.TheapplicationofdetailedorsimplifiedanalysisdependsoncriteriastatedinTable3.9A-3.TypicalexamplesofARSusedinthedesignofpipingsystemsaredescribedinSection3.9A.3.1.1.3.9A.3.1.3CompliancewithRegulatoryGuide1.48Unit2compliancetotheregulatoryguideisdocumentedinTable1.8-1.3.9A.3.2PumpandValveOperabilityAssuranceThissectionprovidestheoperabilityassuranceprogramsforpumpsandvalvesaffectedby.seismicloads.TheoperabilityassuranceprogramsforpumpsandvalvesaffectedbyhydrodynamicloadsassociatedwithSRVdischargeandthepostulatedLOCAareprovidedintheDAR,Appendix6A,Subsection6A.9.Activepumpsandvalvesarethosewhoseoperabilityisreliedupontoperformasafetyfunctionsuchassafeshutdownofthereactorormitigationoftheconsequencesofapostulatedaccident.PumpsandvalvesinstalledinseismicCategoryIpipingsystemsaredesignedinaccordancewiththerequirementofASMESectionIII,SubsectionsNB,NC,andND.ActivepumpsandvalvesarelistedinTables3.9A-9and3.9A-12,respectively.Activevalvesarequalifiedbytestingandanalysis,andactivepumpsbytestingandanalysiswithappropriatestresslimitsandnozzleloads.Thecontentoftheseprogramsisdetailedinthefollowingsections.3.9A.3.2.1PumpOperabilityProgramAllactivepumpsarequalifiedforoperabilitybybeingsubjectedtotestsbothpriortoinstallationintheplantandafterinstallationintheplant.Thein-shoptestsinclude:1.HydrostaticteststoASMESectionIIIrequirements.2~Performancetestswhilethepumpisoperatedwithflowtodeterminetotaldeveloped"head,minimumandmaximumhead,netpositivesuctionhead(NPSH)requirementsandotherpump/motorparameters.Asaresultofthesetests,acertifiedpumpcurveisdevelopedforeachpumpthatmaybeused-toverifycontinuedsatisfactoryoperationsubsequenttopumpinstallation.Propersealfunctionisverifiedduringtheperformancetest.Alsomonitoredduringtheseoperationaltestsarebearingtemperaturesandvibrationlevelsthatareshowntobebelowappropriatelimitsspecifiedtothemanufacturerfordesignofeachactivepump.USARRevision83.9A-22November1995 NineMilePointUnit2FSARAfterthepumpisinstalledintheplant,itundergoescoldhydrotests,preoperationaltests,andtherequiredperiodicISIandoperationaltestsasapplicable.Thesetestsdemonstrate-reliabilityofthepumpforthedesignlifeoftheplant.Inadditiontothesetests,activepumpsarequalifiedforoperabilityduringaSSEconditiontoassurethat1)thepumpisnotdamagedduringtheseismicevent,and2)thepumpcontinuesoperatingwhensubjectedtotheSSEloads.Thepumpmanufacturerisrequiredtoshowthatthepumpoperatesnormallywhensubjectedtothemaximumapplicableamplifiedseismic(floor)accelerations,attachedpipingnozzleloads,anddynamicsystemloadsassociatedwiththefaultedplantoperatingcondition.AnalysisproceduresareutilizedinaccordancewiththoseoutlinedinSection3.7A.3.Naturalfrequenciesaredeterminedinordertoobtainmaximumseismicaccelerationsbasedonapplicableamplified(floor)responsespectra.Inordertoavoiddamageduringthefaultedplantcondition,thestressescausedbythecombinationofnormaloperatingloads,SSE,anddynamicsystemloadsarelimitedtothevaluesindicatedinTable3.9A-8.Themaximumseismicnozzleloadsarealsoconsideredinananalysisofthepumpsupportstoassurethat.asystemmisalignmentcannotoccur.Astaticshaftdeflectionanalysisoftherotorisperformedwithhorizontalandverticalaccelerationsbasedonfloorresponselevels.Thedeflectionsdeterminedfromthestaticshaftanalysisarecomparedtoallowablerotorclearances.Theresultsofthepumpstress/deflectionanalysesaresummarizedinTable3.9A-10.Performingtheseanalyseswiththeconservativeloadsstated,andwiththerestrictivestresslimitsofTable3.9A-8asallowables,assuresthatcriticalpartsofthepumparenotdamagedduringtheshortdurationofthefaultedcondition;therefore,thereliabilityofthepumpforpostfaultedconditionoperationisnotimpairedbytheseismicevent.Inadditiontothepostfaultedconditionoperation,itisnecessarytoassurethatthepumpfunctionsthroughouttheSSE.Thepump/motorcombinationisdesignedtorotateataconstantspeedunderallconditionsunlesstherotorbecomescompletelyseized,i.e.,norotation.Typically,therotorcanbeseized5fullsecondsbeforeacircuitbreakertripshutsdown"thepumptopreventdamagetothemotor.However,thehighrotaryinertiaintheoperatingpumprotor,andtherandomnatureandshortdurationloadingcharacteristicsoftheseismiceventpreventtherotorfrombecomingseized.Inactuality,theseismicloadingscauseonlyaslightincrease,ifany,inthetorque(i.e.,motorcurrent)necessarytodrivethepumpattheconstantdesignspeed.Therefore,thepumpdoesnotshutdownduringtheSSEandoperatesatthedesignspeeddespitetheSSEloads.USARRevision83.9A-23November1995 NineMilePoint"Unit2FSARWhenseismictestingofthepumpassemblyisimpractical,aseismicanalysisisperformedonthepumpassemblytoensureoperability.Theanalysisconsidersthepump,motor,andsupportingstructurestogether.Inaddition,thepumpmotorisindependentlyqualifiedforoperationduringthemaximumseismicevent.Anyauxiliaryequipmentthatisidentifiedtobevitaltotheoperationofthepumporpumpmotor,andthatisnotqualifiedforoperationduringthepumpanalysisormotorqualifications,isseparatelyqualifiedforoperationattheaccelerationsthatitwouldexperienceatitsmounting.ThepumpmotorandvitalauxiliaryequipmentarequalifiedbymeetingtherequirementsofIEEE-344-1975.Thefunctionalabilityofactivepumpsafterafaultedconditionisassuredsinceonlynormaloperatingloadsandsteady-statenozzleloadsexist.Sinceitisdemonstratedthatthepumpswouldnotbedamagedduringthefaultedcondition,thepostfaultedconditionoperatingloadsareidenticaltothenormalplantoperatingloads.Thisisassuredbyrequiringthattheimposednozzleloads(steady-stateloads)fornormalconditionsandpostfaultedconditionsarelimitedbythemagnitudesofthenormalconditionnozzleloads.Thepostfaultedconditionabilityofthepumpstofunctionundertheseappliedloadsisprovenduringthenormaloperatingplantconditionsforactivepumps.TheactivepumpmotorsarequalifiedtooperatesatisfactorilywhensubjectedtotheirsurroundingenvironmentalconditionsforbothnormaloperationandpostaccidentoperationbymeetingtherequirementsofIEEE-323-1974(Section3.11).3.9A.3.2.2ValveOperabilityProgramSafety-relatedactivevalvesarerequiredtoperformtheirmechanicalfunctionduringand/orafterthecourseofapostulatedaccident.Assurancemustbesuppliedthatthesevalvescanoperateduringand/orafteraseismicevent.Qualificationtestsaccompaniedbyanalysesareconductedforallactivevalves.Valveswithoutsignificantextendedstructuresareconsideredseismicallyadequateasaresultofpipingseismicadequacy.Forvalveswithoperatorshavingsignificantlyextendedstructures,ananalysisisperformedforstaticequivalentseismicSSEloadsappliedatthecenterofgravityoftheextendedstructure.Themaximumstresslimitsallowedintheseanalysesensurethemaintenanceofstructuralintegrity.ThelimitsusedforvalvesareshowninTables3.9A-7and3.9A-8,dependingupontheclass.Thesafety-relatedvalvesarealsosubjectedtoaseriesoftestspriortoserviceandduringtheplantlife.Priorto'nstallation,thefollowingtestsareperformed:shellhydrostatictesttoASMESectionIIIrequirements;backseatandmainseatleakagetests;dischydrostatictest;andfunctionalUSARRevision83.9A-24November1995 NineMilePointUni.t2FSARteststoverifythatthevalveopensandcloseswithinthespecifiedtimelimits,whensubjectedtothedesigndifferentialpressureandoperabilityqualificationofmotoroperatorsfortheenvironmentalconditionsovertheinstalledlife(i.e.,aging,radiation,accident'environmentsimulation,etc.)accordingtoIEEE-323-1974.Coldhydroqualificationtests,preoperationaltests,periodicISIs,andperiodicin-serviceoperationareperformedtoverifyandassurethefunctionalabilityofthevalve.Inadditiontothesetestsandanalyses,representativeactivevalvesofeachdesigntype,pressure,andsizegrouparetestedforverificationofoperabilityduringasimulatedseismicevent,bydemonstratingoperationalcapabilitieswithinthespecifiedlimits.Thebasiccriteriausedinselectingtherepresentativevalueforqualificationtestingisbasedonanevaluationofthefollowingparameters:1.Assemblyweight2.Size,type,andpressureratings3.Actuatortypeandperformancecharacteristics4.MountingarrangementandappurtenancesThemethodologyutilizedinassessingthedegreeofsimilarityofevaluatingthedifferencesfollowsgenerallytheguidelinesofANSIStandardB16.41-1983,FunctionalQualificationRequirementsforPowerOperatedActiveValveAssembliesforNuclearPowerPlants.Theproposedtestingproceduresareasfollows.Thevalveismountedinamannerthatconservativelyrepresentstheactualvalveinstallation.Thevalveassemblyincludestheoperatorandallappurtenancesnormallyattachedtothevalveinservice.TheoperabilityofthevalveduringaSSEisdemonstratedbysatisfyingthefollowingcriteria:1~2~Alltheactivevalvesarerequiredtohaveafundamentalnaturalfrequencythatisgenerallygreaterthan33Hz.Thisisshownbysuitabletestoranalysis.Thevalve'isoperatedinthenormalunloadedpositionforbaselinedata.Theactuatorandyokeofthevalvesystemarethenstaticallyloadedby-anamountequaltothatdeterminedfromananalysisasrepresentingSSEaccelerationsappliedatthecenterofgravityoftheoperatorabouttheweakeraxisoftheyoke.Thedesigndifferentialpressureofthevalveissimultaneouslyappliedtothevalveduringthestaticdeflectiontests.USARRevision83'.9A-25November1995 NineMile'Point"Unit2FSAR3~Thevalveisthenoperatedwhileinthedeflectedposition,i.e.,fromthenormaloperatingmodetothefaultedoperatingmode.Thevalveisagainoperatedinthenormalpositionafterthestaticloadisremoved.Thevalveisrequiredtoperformitssafety-relatedfunctionwithinthespecifiedoperatingtimelimitsinboththedeflectedandthenormalposition.4.ElectricmotoroperatorsandotherelectricalappurtenancesnecessaryforoperationarequalifiedinaccordancewithIEEE-323-1974andIEEE-344-1975.5.EnvironmentalqualificationofnonmetalliccomponentsinaccordancewithEQDSection4.1.3.Theaccelerationsusedforthevalvequalificationaregenerally3.0ghorizontaland3.0gvertical.Thepipingdesignmaintainsthemotoroperatoraccelerationstotheselevelswithanadequatemarginofsafety.SelectionofparentvalveoperatorsfortestinggenerallyfollowsthemethodologyoutlinedinAppendixAofIEEE-382-1980,IEEEStandardforQualificationofSafety-RelatedValveActuators.Thisstandardprovidesacomprehensivemethodofanalyzingalltherelevantparametersofvalveoperatorssuchas:type,size,weight,electricalcharacteristics(ac/dc,voltage,current)performancecharacteristics(speed,motortorque),andmaterialsfortheselectionofavalveoperatorforqualificationtesting.Considerationisalsogiventotheeffectsofthermalandvibrationaginginconjunction,.withapplicablemarginsbyutilizingtheworst-caseparametersinqualification.Testingisconductedonarepresentativenumberofvalvesfromeachoftheprimarysafety-relateddesigntypes.Selectedvalvesizesarequalifiedbythetestsandtheresultsusedtoqualify,thatgroupofvalveswhichthetestedvalverepresents.Stressanddeformationanalysesareusedtosupporttheinterpolation.Anassessmentofthestressesatthepipe/valveinterfacegenerallyindicatesthatdistortion,ifany,duetoseismicloadswillnotcausebindingofinternalcomponents.Therefore,additionsofpipingandloadsduringtheoperabilitytestsisunnecessary.Forvalveswherestressesinthevalvebodycouldbesignificant,thepipingandloadswereimposedduringtheoperabilitytests.Examplesincludesolenoidvalvesandair-operatedcontrolvalves.Forselected"active"valvecategoriesspecificqualificationprogramsareconductedtodemonstrateoperability.Themethodofqualificationforthesevalvesisdetailedasfollows:USARRevision83.9A-26November1995 NineMilePointUnit2FSAR1~ButterflValves,Thecontainmentanddrywellvent/pipeisolationvalvesareevaluatedforoperabilityduringandafterapostulated.accidentbybothanalysesandtestingmethods.a~Thevalveassemblyisanalyticallyevaluatedandshowntoperformitssafety-relatedfunction(i.e.,toclosewithintherequiredresponsetime).Valveanalysisconsidersseismic,hydrodynamic,operating,airflow,andLOCAloads.b.ThevalveassemblyisstaticallyloadedbyanamountequalinmagnitudetothedynamicforceandappliedattheactuatorC.G.Thedesignpressureofthevalveissimultaneouslyappliedandthevalveisoperatedwhileinthedeflectedposition.C~Electricalappurtenances(limitswitchesandsolenoid-operatedvalves[SOVs])arequalifiedaccordingtotherequirementsofIEEE-323-1974andIEEE-344-1975.d.Inaddition,assuranceofoperabilityisdemonstratedbythefollowingtests:(1)In-shopshellhydrostatictests(2)Coldcyclictests(3)Seatleakagetests(4)Pre/postinstallationfunctionaltests2~CheckValvesCheckvalvesarecharacteristicallysimpleindesign,andtheiroperationisnotaffectedbyseismicaccelerationsortheappliedpipingendloads.Checkvalvedesigniscompact,andtherearenoextendedstructuresormasseswhosemotioncouldcausedistortionsorrestrictoperationofthevalve.Thepipingendloadsduetomaximumseismicexcitationdonotaffectthefunctionalabilityofthevalvesinceclearanceisprovidedbetweenthevalvediscandthecasingwall.Thisclearancearoundthediscpreventsthediscfrombecomingboundorrestrictedduetoanycasingdistortionscausedbypipingendloads.Therefore,thedesignofthesevalvesissuchthatwhenthestructuralintegrityofthevalveisassured,usingstandarddesignoranalysismethods,theabilityofthevalvetooperateisassuredbythedesignfeatures.InUSARRevision83.9A-27November1995 NineMilePoint'nit2FSARadditionto.thesedesignconsiderations,'hevalvesarealsosubjectedtothefollowingtestsandanalysis:a~Stressanalysis,includingtheSSEloads.b.In-shophydrostatictest.c.In-shopseatleakagetest.d.Periodicinsituvalveexercisingandinspectiontoassurethefunctionalabilityofthevalve.Forthefeedwatercheckvalve,theoperabilityfollowingapostulatedfeedwaterlinebreakisalsodemonstrated.The'maximumdiscimpactvelocityandthepressuredifferentialacrossthediscaredetermined.Astressanalysisofthevalve,whichconsiderstheimpactandtheseismicinertialoads,demonstratesvalvedesignadequacy.3.SafetReliefValvesSRVsareevaluatedforoperabilityduringandafterapostulatedaccidentofbothanalysesandtestingmethods.a~b.Thevalveisanalyticallyevaluatedforseismic/hydrodynamicandoperatingloadsandshowntoperformitssafety-relatedfunctions.Thevalveisstaticallyloadedbyanamountequalinmagnitudetothedynamicforce.Apressure,representativeofthedesignpressure,issimultaneouslyappliedandthevalveisoperatedwhileinthedeflectedpositions.c.Inaddition,assuranceofoperabilityisdemonstratedbythefollowingtests:(1)In-shophydrostaticseatleakagetests.(2)In-shophydrostaticbodyleakagetests.(3)Performancetests.(4)Periodicinsituvalveinspectionsandanapplicableperiodicvalveremoval,refurbishment,andperformancetesting.Usingthemethodsdescribed,allthesafety-relatedvalvesinthesystemarequalifiedforoperabilityduringaseismicevent.Thesemethodsconservativelysimulatetheseismic-eventandensure'thattheactivevalvescanperformtheirsafety-relatedfunctionwhennecessary.\USARRevision83.9A-28November1995 NineMilePoint"Unit2FSAR3.9A.3.3DesignandInstallationDetailsforMountingofPressure-ReliefDevicesPressure-relievingde*vicesforASMESafetyClass1and2systemcomponentsare:1.MainsteamSRVs.2.SRVsforprotectingRHRsystemheatexchangers.ThedesignandinstallationofmainsteamSRVsisdescribedinSection3.9B.3.3.ThedesignandinstallationofSRVsforprotectingtheRHRsystemheatexchangers(Section5.4.7.2.3)isinaccordancewithASMESectionIII,ArticleNC-7000,andRG1.67.PipingtoandfromSRVsisdesignedinaccordancewithASMESectionIII,ParagraphNC-3677.TheSTEHAMcomputerprogram(Appendix3A)isusedtocalculatefluidtransientforcesineachpipingsegment(straightpipepiecebetweentwoelbows,anelbowandatee,oranelbowandaterminalend)downstreamoftheSRVs.Aconservativelylowvalueofvalveopeningtimeisusedinthiscalculation.Waterslugsinpipesegmentsendinginthesuppressionpoolaretakenintoaccount.Dynamicstressesinthepipingarecomputedbytime-historyintegrationortheequivalentstaticmethodsusingoneofthepipinganalysiscomputerprogramsdescribedinAppendix3A.Thesestressesarecombinedwiththoseduetoothermechanicalloads,inaccordancewithloadcombinationsdescribedinSection3.9A.3.1.BothSRVsprotectingaheatexchangerareassumedtodischargeconcurrently.Theseloadsmeetdesignallowablesprovidedbythevendor.3.9A.3.4ComponentSupportsExpansionanchorbolts,usedinsupportingthemechanicalcomponentsfromconcretestructures,aredrilled-inwedge-typeuniformholeanchors.Drilled-in,bearing-type,flaredholeanchorsarealsousedinsupportingthemechanicalcomponentsfromconcretestructures.Drilled-in,wedge-type,uniformholedesignedforaminimumsafetyfactortheultimateloadtestsperformedbysettingtorqueisdeterminedfrominexpansionanchorsareoffour,asdeterminedbythemanufacturer.Thesitutests.Drilled-in,bearing-type,flaredholeanchorsaredesignedforaminimumsafetyfactorofthree,asdeterminedbyfieldtesting.Theloadsaretransferred=intoconcretebydirectbearingagainstconcrete.Theboltmaterialiscapableof'reachingfullUSARRevision83,.9A-29November1995 NineMilePointUnit2FSARductilitypriortofailure.Duetothesereasons,theanchorsaffordgreaterreliability,andalowersafetyfactorisjustified.Thedesign,procurement,andinstallationofbuildingsteelcomplywithrequirementsoftheAISCspecificationforthedesign,fabrication,anderectionofstructuralsteelforbuildings,asdescribedinSections3.8.4.2and3.8.4.6.3.TheexaminationandinspectionofbuildingsteelcomplywiththerequirementsofNRCRG1.94,asdescribedinTable1.8-1.3.9A.3.4.1PipeSupportsThepipesupportdesigns,usingbaseplatesandconcreteexpansionanchorbolts,areperformedusingtheflexibilitycriteriaofNRCIEBulletin79-02beforetheyarereleasedforfabrication.Verificationofas-builtconditionsinaccordancewithNRCIEBulletin79-14isdescribedinSection3.7A.3.8.1.ThebasesfordesignandconstructionofASMEandnon-ASMEpipingsupportsaregiveninTable3.9A-16.NonnucleaPiinNonnuclearpipingsupportssatisfytherequirementsoftheAmericanNationalStandardCodeforPressurePiping,ANSIB31.1-1973,uptoandincludingtheWinter1973Addenda,paragraph120and121.Anexceptionistakentoparagraph120.2.4ofthiseditionbyinvokingthesameparagraphofANSIB31.1-1980,permittingtheuseofthe8thEdition-1980EditionoftheAISCManualforSteelConstructionforthedesignofpartialpenetrationgrooveweldsinaccordancewithTable1.17.5.NuclearPiinPipesupportsfornuclearpipingaredesignedandfabricatedinaccordancewiththeASMEBoilerandPressureVesselCode,SectionIII,Division1,SubsectionNF,1974Edition,noAddendadatedJuly1,1974,subjecttotheexceptionsandadditionslistedbelow.Codestampingofpipesupportsisnotarequirementofthe1974Edition.AllpipesupportsapplicabletotheRCPBpipingorotherpipingareconsideredeitherlinearorcomponentstandard,withportionsofcomponentstandardsupportsdesignedtoplateandshellrules.ThepipesupportjurisdictionalboundariesareinaccordancewithNF-1000(seeexamplesonFigure3.9A-5).Portionsofsupportsthatareintegrallyattachedtopipingaredesigned,includinglocalpipestresses,inaccordancewithASMEIII,SubsectionNB,NC,orNDasapplicable.TheapplicabledimensionalstandardsofTableNB-3691-1apply.SeeAppendix3Eforadiscussionofthecriteriainthe1974EditionofASMESubsectionNFregardingstressesinsupportsdueUSARRevision83.9A-30November1995 Nine.MilePointUnit2FSARtothermalgrowthinpipingandseismicanchormotionasitcomparestosimilarcriteriainthe1983Edition.AspermittedbyNA-11'40':theportionsofthe1974EditionoftheASMECodeforwhichspecificprovisionsoflaterASMECodeaddendaoreditionsaresubstitutedarelistedbelow.NA-3256FilingofDesignSpecificationsTheSummer1978AddendadatedJune30,1978,isinvokedforthenewsubparagraphNCA-3256(b)topermitdesignspecificationsforcomponentstandardsupportstobeprovidedbythemanufacturerandtopermit/facilitatetheimplementationofASMEIIICodeCaseN-247.SeeTable5'-1.NA-3352StressReportsTheSummer1978AddendadatedJune30,1978,isinvokedforparagraphNCA-3351topermittheuseofthetermdesignreportinlieuofstressreportandtopermit/facilitatetheimplementationofASMEIIICodeCaseN-247.SeeTable5'-1~NF-1214ComponentStandardSupportsTheSummer1976AddendadatedJune20,1976,isinvokedtodeletethespecificreferencetohydraulicsnubbers.NF-2121PermittedMaterialSpecificationsTheSummer1974AddendadatedJune30,1974,isinvokedtopermittheuseofSA672material.NF-2121PermittedMaterialSpecificationsTheWinter1974AddendadatedDecember31,1974,isinvokedtopermittheuseofincreasedallowablestressforSA515G65.NF-2121PermittedMaterialSpecificationsTheSummer1976AddendadatedJune30,1976,isinvokedtoincludethenewsubparagraphNF-2121(c)topermittheexclusionofcertainshimstockfromtherequirementsofArticleNF-2120.NF-2121PermittedMaterialSpecificationsThe1977EditiondatedJuly1,1977,isinvokedtopermittheuseofSA36material.USARRevision8:3.9A-31November1995 Nine,MilePointUnit2FSARNF-2121PermittedMaterialSpecificationsThe1980EditiondatedJuly1,1980,isinvokedtopermittheuseofSA564,Type630material.NF-2121PermittedMaterialSpecificationsTheWinter1981AddendadatedDecember31,1981,isinvokedtopermittheuseofSA-194-2Hnuts.NF-2130CertificationbyMaterialManufacturerTheSummer1982AddendadatedJune30,1982,isinvokedformaterialcertification.NF-2610DocumentationandMaintenanceofQualitySystemsProgramsThe1977EditiondatedJuly1,1977,isinvokedtorevisethematerialmanufacturersandmaterialsuppliersresponsibilitiesformaterialsdefinedassmallproductsormaterialspermittedtobesuppliedwithCertificatesofCompliance.NF-3274SnubbersTheSummer1976AddendadatedJune30,1976,isinvokedforNF-3134.6topermittheuseofmechanicalsnubbers.NF-3226.5SpecialStressLimitsNF-3321.1DesignConditionsXVII-2211StressinTensionTheWinter1978AddendadatedDecember31,1978,isinvokedfortheseparagraphsectionswhichineffectdeletethecodemethodsforconsiderationofthroughthicknessstressesinplatesandelementsofrolledshapes.NF-3391.1NF-3392.1AllowableStressLimitsAllowableStressLimitsTheWinter1979AddendadatedDecember31,1979,isinvokedfortheseparagraphsectionswhichineffectdeletethecodemethodsforconsiderationofthroughthicknessstressesinplatesandelementsofrolledshapes.XVII-2454ButtandGrooveWeldsThe1980EditiondatedJuly1,1980,isinvokedtoredefinethethroatthicknessofpartialpenetrationgrooveweldsinaccordancewithTableXVII-2452.1-1.InthecasethatmaterialcannotbepurchasedtomeetthespecifiedASMEIIICode,thenmaterialthatmeetssubsequent'SME-USARRevision8,3.9A-32November1995 NineMilePoint'Unit2.FSARIIICodeEditions/Addendauptoandincludingthe1980Edition/Summer1982AddendamaybesubstitutedafterareviewandreconciliationofrelatedrequirementsoftheASMEIIICodeareperformedanddocumented.Table3.9A-14liststheloadconditions,loadcombinations,andallowablestresses.Loadsareappliedinwhatevermannerisnecessarytoattaintheworstpossiblestresslevelsforallsupportelements.Componentstandardsupportsarequalifiedeitherbyanalysisorbyacombinationofanalysisandloadrating.Allothersupportsarequalifiedbyanalysis.Nospecificdeformationlimitsarerequiredghowever,pipesupportdeformationsareconsistentwithpipestressanalysis.ThepipesupportbucklingcriteriaareconsistentwiththerequirementsofASMEIII,AppendixXVII.Thedesigncriteriaanddynamictestingrequirementsforcomponentandpipesupportslistedinthefollowingparagraphsareapplicableunderallplantoperatingconditions.InstrumentLinesTherequirementsforinstrumentlinesarelistedinTable3.9A-15.ComonentSuortsAllcomponentsupportsaredesigned,fabricated,andassembledsotheycannotbecomedisengagedbythemovementofthesupportedpipeorequipmentduringoperation.AllcomponentsupportsaredesignedinaccordancewiththerulesofASMESectionIII,SubsectionNF.SrinHanersVariableandConstantSuortThedesignloadonspringhangersistheloadcausedbydeadweightalone.Variablespringhangersarecalibratedtoensurethattheysupportthedeadweightatboththeirhotandcoldloadsettings.Forconstantsupportspringhangers,thedeadweightisalwayssupportedasaconstantload,notsubjecttoseparatehotandcoldloads.Springhangersalsoallowforadown-travelandup-travelinexcessofthespecifiedthermalmovementtoaccountfordynamicmovement.vthereisnopossibilityofcompression.StrutsThedesignloadsonstrutsincludethoseloadscausedbydeadweight,thermalexpansion,primaryseismic(OBEandSSE),systemanchordisplacements,andreactionforcescausedbyreliefvalvedischargeandturbinestopvalveclosure,etc.StrutsaredesignedinaccordancewithArticleNF-3000.SnubbersMechanicalThedesignloadsonsnubbers..includealldynamicloadssuchasseismicforces(OBEandSSE),systemdynamicanchormovements,andreactionforcescausedbyshortdurationreliefvalvedischargeandturbinestopvalveclosure,USARRevision83.9A-33November1995 NineMile.PointUnit.'FSARanddynamicloadsproducedbysuppressionpoolphenomena.Thesnubbersaredesignedandload-ratedinaccordancewithArticleNF-3000tobecapableofcarryingthedesignloadforalldynamicoperatingconditions.FaultedconditiondesignusesthecriteriaoutlinedinAppendixFoftheASMECode.Theprototypesnubbershavebeentesteddynamicallytoensurethattheycanperformasrequiredinthefollowingmanner:1.Thesnubberwassubjectedtoaforcethatvariedapproximatelyasthesinewave.2..Thefrequency(Hz)oftheinputforcewasvariedbysmallincrementswithinthespecifiedrange.3.Theresultingrelativedisplacementsandcorrespondingloadsacrosstheworkingcomponents,includingendattachments,wererecorded.4.Thetestwasconductedwiththesnubberatvarioustemperatures.5.Thepeakloadinbothstatictensionandcompressiontestswashigherthantheratedload.6.Thedurationofthetestsateachfrequencywasspecified.7~Snubbersweretestedforvariousabnormalenvironmentalconditions,includingsalt-fog,sandanddust,andhumidity,followedbyoperationaltests.Theenvironmentaltestresultsarefiledatthesnubbermanufacturer'slocation.Theothertestresultsareforwardedwiththeshipmentofeachsnubberandareincorporatedintothepermanentplantfile.AnchorsAnchorsaredesignedtorestrainallrotationsandtranslationsofpiping.Terminalanchorsarethosewhicharecommonto'twoindependentlyanalyzedpipingsubsystems,oneoneachsideoftheanchor.Foreachloadtype,loadsfrombothsidesoftheanchorarecombinedtoformatotalanchorload.Forvibratoryloadsthetotalanchorloadis2(theSRSSoftwoloadsfrombothsidesoftheanchor).Forstaticloadsthetotalanchorloadisthealgebraicsumofloadsfrombothsidesoftheanchor.Designtransientcyclicdataarenotapplicabletopipingsupports,sincenofatigueevaluationisnecessarytomeetthecoderequirements,unlessthedesignspecificationidentifiesmorethan20,000loadcycles.DesignofanchorsseparatingseismicallydesignedandnonseismicpipingisdiscussedinSection3.7A.3.1.3.1.3.9A.3.4.2PumpSupportsThepumppedestalandpedestalboltanalysisincludesconsiderationofloadsfromoperatingandseismicevents,USARRevision83.9A-34November1995 NineMilePointUnit2FSARconnectingpipes,temperature,anddeadweight.ThestresslimitsofASMESectionIIISubsectionNFaremet.Theanalysisincludesdeflectionofthepedestal.3.9A.3.4.3OtherComponentsSupportsIEquipmentsupportsand,theirconnectionstobuildingstructuresthataregovernedbyASMEareinaccordancewithASMESectionZII,SubsectionNF.ASMEclassifiesthesesupportsaseitherplateandshell-orlinear-typesupports.PlateandShell-TeSuortsThesesupports,e.g.,vesselskirtsandsaddles,arefabricatedfromplateandshellelementsandhavethesameASMECodeclassificationasthevessel.JurisdictionalBoundariesFigures3.9A-2and3.9A-3showtheboundariesfordifferentsubsectionsoftheASMECodeandbuildingstructures.Asshown,theNFjurisdictiontypicallyincludestheconnectionbetweenthecomponentsupportandthebuilding,withtheexceptionofconcreteanchorages.BasisforDesignandConstructionThesesupportsaredesigned,fabricated,andinstalledinaccordancewithASMESectionIII,SubsectionNF.Loads,LoadCombinations,andStressLimitsThecombinationofdesignloadingsforthesesupportsiscategorizedwithrespecttoplantoperatingconditions.TheseconditionsareidentifiedasservicelevelsAthroughD(Table3.9A-13).StresslimitsforthecorrespondingservicelevelsalsoaregiveninTable3.9A-13.DeformationLimitsDeformationsareconsideredsothereisnointerferencewithadjacentequipment,piping,orstructures.Ifsupportdeformationsaredeterminedtobecritical,theybecomeanintegralpartofthedesignandareheldwithintherequiredlimits;otherwise,deformationsareconsistentwithsupportstressanalysis.BucklingCriteriaAnalysisisperformedtodeterminecriticalbucklingstrength,includinglocalinstabilities.ActualloadsarecomparedtocriticalbucklingloadsinaccordancewithASMESectionIII,AppendixF.USARRevision83.9A-35November1995 NineMilePointUnit2FSARLinear-Te.SuortsThesesupports,e.g.,structuralelementssuchasbeams,columns,andframes,havethesameASMECodeclassificationasthecomponent.JurisdictionalBoundariesAtypicallinearequipmentsupportforaHVRunitcoolerisillustratedonFigure3.9A-4.Thejurisdictionalboundaryonthetypicalsupportistheconnectionbetweenthesupportingbeamsandtheframingstructure.TheboltedorweldedconnectionisNF-designed.BasicsforDesignandConstructionThesesupportsaredesigned,fabricated,andinstalledinaccordancewithASMESectionIII,SubsectionNF.Loads,LoadCombinations,andStressLimitsThecombinationofdesignloadingforthesesupportsiscategorizedwithrespecttoplantoperatingconditions.TheseconditionsareidentifiedasservicelevelsAthroughD(Table3.9A-13).StresslimitsarealsoinaccordancewithASMESectionIII,SubsectionNF.DeformationLimitsDeformationsareconsideredsotherearenointerferenceswithadjacentequipment,piping,orstructures.Ifsupportdeformationsaredeterminedtobecritical,theybecomeanintegralpartofthedesignandareheldwithintherequiredlimits;otherwise,deformationsareconsistentwithsupportstressanalysis.BucklingCriteriaSupportbucklingcriteriaisconsistentwiththerequirementsof'SMESectionIII,AppendixXVII.~BoltinTheallowablestresslimitsusedforboltsinequipmentanchorage,componentsupports,andflangedconnectionsaregivenbythefollowing:1~2~AnchorBoltsUsedinEquipmentAnchorage-AppendixBofACI349,CodeRequirementsforNuclearSafety-RelatedConcreteStructures.BoltsUsedinComponentSupports-ASMESectionIII,DivisionI,SubsectionNF,andAppendixXVII;paragraph2460.ForservicelevelsCandD,USARRevision83.9A-36November1995 NineMilePointUnit2FSARXVII-2460withfactorsindicatedunderXVII-2110isapplicabletothedesignrequirementsofbolting.Thecalculatedstressesunderthesecategoriesdonotexceedthespecifiedminimumyieldstressesattemperature.3.BoltsUsedinFlangedConnections-ASMEIII.Equipmentmountedwithhigh-strengthboltsincludevessels,unitcoolers,andheatexchangers.Thematerialforhigh-strengthboltsusedforthemountingofcomponentsupportstobuildingstructuresconformstotheassignedjurisdictionalboundary.Concretehigh-strengthanchorboltsusedatcomponentsupportsincludeA193,A325,andA490steel.ASMESectionIII,NFhigh-strengthboltsincludeSA-193andSA-325material.High-strengthboltsandlow-strengthboltsareusedinpipeandductsupportdesigns.3.9A.4ControlRodDriveSystemsSeeSection3.9B.4.3.9A.5ReactorPressureVesselInternalsSeeSection3.9B.5.3.9A.6In-serviceTestingofPumpsandValvesAnISTprogramwaspreparedinconformancewiththeapplicableportionsofGDC37,40,43,and46.Thisprogram,submittedinNovember1985,includedbaselinepreservicetestingandaperiodicISTprogramforpumpsandvalvesandisbasedontheASMEBoilerandPressureVesselCode,SectionXI,1980Edition,throughtheWinter1980Addenda.ThepurposeofthisprogramistoensurethatcertainSafetyClass1,2,and3pumpsprovidedwithanemergencypowersource,andSafetyClass1,2,and3valvesrequiredtoperformaspecificfunctioninbringingthereactortoacoldshutdownconditionorinmitigatingtheconsequencesofanaccident,areinastateofoperationalreadinessthroughoutthelifeoftheplant.ThistestprogramisbasedontheASMEBoilerandPressureVesselCode,SectionXI,andwillbeperiodicallyupdatedinaccordancewith10CFR50.55a(g).3.9A.6.1In-serviceTestingofPumpsTheISTprogramforcertainSafetyClass1,2,and3pumpsthathaveanemergencypowersourceisinaccordancewithSubsectionIWPofASMESectionXI.Thebasisofthetestprogramistodetectchangesinthehydraulicandmechanicalconditionofthepumprelativetoareferencesetofparameters.ReferencevalueswillbeestablishedinaccordancewithIWP-3000ofASMESectionUSARRevision83.9A-37November1995 Nine'MilePointUnit2FSARXIandlistedintheIWPpumptestingsectionoftheUnit2ISIprogram.Pumpsaretestedperiodicallyduringplantoperationandduringshutdownperiods,ifpractical,inaccordancewiththerequirementsofASMESectionXI,IWP-3100andIWP-3400(a).Ifapumpisnormallyoperatedmorefrequentlythanonceamonth,itneednotbespeciallytestedprovidedthattherequirementsofASMESectionXI,IWP-3400(b)aremet.Thepumpsaretoberunatleast5minunderconditionsasstableasthesystempermits.ThemethodsofmeasurementareinaccordancewithIWP-4100,-4200,-4300,-4400,-4500,and-4600ofASMESectionXIwithregardtoinstruments,pressuremeasurements,temperaturemeasurements,rotationalspeed,vibrationmeasurements,andflowmeasurement.ThespecificmethodsformeasuringpumptestparameterswillbedescribedinthetestproceduresfortheIWPpumpplan.ThepumptestplanandscheduleareprovidedintheIWPpumptestingsectionoftheUnit2ISIprogram.3.9A.6.2In-serviceTestingofValvesTheISTplanforallSafetyClass1,2,and3valvesthatarerequiredtoperformasafetyfunctionwillbeinaccordancewiththerequirementsofSubsectionIWVofASMESectionXI.InaccordancewiththeexemptionslistedinSubarticleIWV-1200ofASMESectionXI,valvesusedonlyformaintenanceorforoperatingconvenience,suchasmanualvent,drain,instrument,andtestvalves,willnotbeincludedintheplan.Allvalvesrequiringin-servicetestingwillbelistedintheIWVvalvetestingsectionoftheUnit2ISIplan.EachvalveintheplaniscategorizedinaccordancewiththerequirementsofSubarticleIWV-2100ofASMESectionXI.Valvetestswithregardtopreservicetests,valvereplacement,valverepairandmaintenance,indicationofvalveposition,andin-servicetestswillbeinaccordancewiththerequirementsofArticleIWV-3000ofASMESectionXI.TestmethodsforeachvalvetestedunderthevalveISTplanwillbedescribedinthevalvetestprocedures.ThevalveswhichseparatetheRCPB,identifiedinTable3.4.3.2-1oftheTechnicalSpecifications,frominterfacinglow-pressuresystemsshallbeleaktestedinaccordancewithTechnicalSpecification3.4.3.2.ThesevalvesareincludedintheUnit2PumpandValveISTProgramwhichwasdevelopedinaccordancewiththeASMEBoilerandPressureVesselCode,SectionXI,SubsectionIWV.TheUnit2leaktestingprogramforthesevalvesisdescribedasfollows:1~2~Theleakratetestwillbeperformed,asaminimum,atleasteveryrefuelingoutage(IWV-3422).TheleaktestmediumwillbewaterforthevalveswhicharenotTypeCper10CFR50AppendixJ,withatestacceptancecriteriaof0.5gpmleakagepernominalinUSARRevision83.9A-38November-1995 NineMilePointUnit2FSARofvalvesizeuptoamaximumof5gpmataRCSpressureof1,020+20psig.Forthosecheck,andglobevalveswhichrequirea10CFR50AppendixJTypeCtest,theairleakratedatamaybeconvertedtoawaterleakagerateat1,020+20psigandcomparedwiththeaboveacceptancecriteriaforcompliancetotheTechnicalSpecificationrequirement.3.Theperiodicleaktestwillbedoneduringrefuelingoutages.4.Aftermaintenancewhichcanaffectleak-tightnessofthevalve,leaktestingwillbeperformedinaccordancewithASMEXI,priortoreturningthevalvetoservice.P&IDshavebeensuppliedwiththeFSARandPreserviceandIn-ServiceInspectionPlanwhichdescribetheRCSpressureisolationvalves.ProcedurestosupportTechnicalSpecificationtestingshallbegeneratedinaccordancewiththestartupscheduleduring1985and1986.3.9A.6.3ReliefRequestsRequestsforrelieffromtherequirementsofArticleIWPofASMESectionXIforISTofpumpswillbedocumentedintheIWPpumptestingsectionoftheUnit2ISIprogram(TechnicalSpecifications).RequestsforrelieffromtherequirementsofArticleIWVofASMESectionXIforISTofvalveswillbedocumentedintheIWVvalvetestingsectionoftheUnit2ISIprogram.IffutureupdatingoftheUnit2ISIprogramrevealsadditionalcaseswheretestingofpumpsorvalvesisimpractical,withrespecttothecurrentorfuturerevisionsofArticlesIWPorIWV,additionalrequestsforrelieffromtestingrequirementswillbedocumentedandsubmittedinatimelymanner.3.9A.6.4PipeWeldsWithinBreakExclusionAreaA100-percentvolumetricpreserviceandin-serviceinspectionofhigh-energyfluidsystempipingweldswithinthebreakexclusionareawillbeconductedduringeachinspectioninterval,asdefinedinIWA-2400,ASMESectionXI.USARRevision83..9A-39November1995 fI'"-~<~,t NineMilePointUnit2FSARTABLE3.9A-1TRANSIENTSANDTHENUMBEROFASSOCIATEDCYCLESCONSIDEREDINTHEDESIGNANDFATIGUEANALYSESOFCLASS1PIPINGTransientsNormalUsetandTestinConditionsDynamicloadscausedbySRVdischargeevents@a.Pipingb.EquipmentOBEatratedoperatingconditions<4>No.of~ccles5,2006,000501.2~3~4~5.6.7~8(10~9.11.12~13.14~15.16.17.18.19.20.21.29'oltupDesignhydrotestStartup(100'F/hrheatuprate)+TurbinerollandincreasetoratedpowerDailypowerreductionto75~Weeklypowerreductionto504RodpatternchangeScram-turbinegeneratortrip,feedwateron,isolationvalvesstayopenPartialfeedwaterheaterbypassOtherscramsRatedpowernormaloperation-inadvertentactuationReductionto0>powerHotstandbyShutdownpriortovesselfloodingVesselfloodingShutdownVesselunboltRefuelingLossoffeedwaterpumps-isolationvalvesclosedSinglerelieforsafetyvalveblowdownInadvertent/accidentalvesseloverfilling+12313012012010,0002,00040050701401011111111111111112301084Emerenc22'3'4'5'627.Reactoroverpressurewithdelayedscram+Automaticblowdown+Improperstartofcoldrecircloop">Suddenstartofpumpincoldrecircloop+Hotstandby-drainshutoffpumprestart+DynamicloadscausedbysuppressionpooleventsduringSBA,IBA~'SARRevision81of2November1995 NineMilePointUnit2FSARTABLE3.9A-1(Cont'd.)TrsientsNo.of~Cclee~Fa1ted28.Piperuptureandblowdown(')SSEatratedoperatingconditions")DynamicloadscausedbysuppressionpooleventsduringDBA(')1101,500(4)(5)(6)Bulkaveragevesselcoolanttemperaturechangeinany1-hrperiod.Theprobabilityofeventtooccurin40-yrplantlife,P40,1s'mergencyconditions:10'P40>10'aultedconditions:10'P4,>10TheSRVdischargeeventsusedforanalysisaregiveninTable3.9A-2.Insomecases,consideredasanemergencyevent.Includes10maximumloadcyclesperevent.Fatigueanalysisisnotrequiredforemergencyandfaultedconditions.Numberofcyclesisbasedonmaximumtemperaturedifferential(hT)of141Fbetweenthemainsteampipewalltemperatureandtheincomingfluidtemperature,andit,includesonecycleforvesseloverfillingwhichoccurredinJanuary1988duringpowerascensiontesting.USARRevision82of2November1995 NineMilePointUnit2FSARTABLE3.9A-3PIPESTRESSANALYSISCLASSIFICATIONSFORASMECODECLASSES1g2/3PipingClassAnalsisClassificationClass1Class2,3NominalpipesizeTypeofanalysisNominalpipesizeortubingODTypeofanalysisDy1IIClass1D>6"ComputeranalysisDg]IIClass2"'<6~'oncomputeranalysis+SeeSection3.7.3.8.2Aforacceptancecriteria.Pipingorinstrumentationtubingisqualifiedbyplacingthesupportsinaccordancewithagenericprocedureorbyhandcalculationsofstressandsupportloads.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.9A-4BOPSEISMIC/DYNAMIC{}UALZFZCATIONRESULTS"MECHANICALEQUIPMENTEquipmentMethodsResultsMotor-operatedrotarygatesSpecialairfilterassembliesSpentfuelpoolcoolingwaterheatexchangersSelf-cleaningstrainersSimplexstrainersAstaticanalysisandtestwereperformed.TheapplicablestandardsandguidelinesareZEEE-323-1974andZEEE-344-1975andRG1.61,1.89,1.92,and1.100.Astaticanalysisandtestwereperformed.Theapplicablestandards,codes,andguidelinesareZEEE-344-1975,ASMESectionZZZ,andRG1.61,1.92,1.84,1.85,1.89,and1.100.Astaticanalysiswasperformed.Theapplicablestandards,codes,andguidelinesareZEEE-344-1975,ASMESectionZIZ,andRG1.61,1.92,1.89,and1.100.Thestrainersarequalifiedbystaticanalysisandtest.Theapplicablestandards,codes,andguidelinesareIEEE-323-1974,ZEEE-334-1974,ZEEE-344-1975,ASMESectionIZZ,andRG1.61,1.84,1.85,1.89,1.92,and1.100.Thestrainersaregualifiedbystaticanalysis.TheapplicablestandardsareASMECodeSectionZZZandRG1.61and1.92.Themotor-operatedrotarygatesareaffectedbyseismicloadsonly.Theanalysisindicatedthatthestresslevelsarewithintheallowablelimitsof3.9A.2.2.2.RefertoTable3.10A-1fozthegualificationoftheLimitorqueactuators.Thefilterassembliesareaffectedbyseismicloadsonly.Theresultsoftheanalysisofstructuralandfunctionalelementsoftheequipmentindicatethatthestressesarewithintheallowablelimitsof3.9A.2.2.2.RefertoTable3.10A-1forthegualificationoftheheater/flowswitches.Theheatexchangersareaffectedbyseismicloads.Theanalysisindicatesthatthestresslevelsarewithintheallowablelimitsof3.9A.2.2.2.Thestrainersaresubjectedtoseismicloads.Theanalysisindicatesthatthestressintensityforthestrainercomponentsiswithintheallowablestresslimitsof3.9A.2.2.2.Thedeflectionsdonotaffecttheoperabilityofthestrainer.RefertoTable3.10A-1forthegualificationofthemotors.Thestrainersaresubjectedtoseismicloads.Thestructuralintegrityofthestrainersisdemonstratedsincetheanalysisindicatesthestresslevelsarewithintheallowablelimitsof3.9A.2.2.2.ECCSandRCICsuppressionpoolstrainersThestrainezsaregualifiedbystaticanalysis.TheapplicablestandardsareASMECodeSectionIIIandRG1.61and1.92.Thestrainersaresubjectedtoseismic,hydrodynamic,andsuppressionpooldragloads.Theanalysisindicatesthatthestressintensityforthestrainercomponentsiswithintheallowablestresslimitsof3.9A.2.2.2.ActivepumpshorizontalcentrifugalDieselgeneratorfueloiltransferPumpsarequalifiedbydynamicandstaticanalysisandoperabilitytests.TheapplicablestandardsandguidelinesazeZEEE-344-1975,ZEEE-334-1974,RG1.48,1..61,1.89,).92,and1.100,andASMECodeSectionIZZ.Thepumpsareaffectedbyseismicloadsonly.Thestructuralintegrityandfunctionalcapabilityofthepumpshavebeendemonstratedbystaticanddynamicanalysis.Thecentrifugalpumpshavebeendeterminedtoberigid.Thefundamentalfrequencyofthefueloiltransferpumpswas6Hz.StressesaremaintainedwithintheallowablelimitsofTable3.9A-8.Allofthedeflectionsarewithinthenormalclearances.ThelowestmarginofsafetywithrespecttoboththestressesanddeflectionsisapproximatelyUSARRevision81of6November1995

NineMilePointUnit2FSARTABLE3.9A-4(Cont'd.)EquipmentMethodsResultsLocalinstrumentracksFlexiblemetalhosesMiscellaneousHVACAxialfansCentrifugalfansAirconditioningunitsBackdraftdampersBubbletightdampersButterflydamperTornadodamperFiredamperMultileafdamperSingle-bladeddampersTheinstrumentracksarequalifiedbyanalysis.TheapplicablestandardsandguidelinesareIEEE-323-1974,ZEEE-344-1975,andRG1.61and1.100.Flexiblemetalhosesarequalifiedbyanalysis.ApplicablestandardsandguidelinesareEJMA,ASMECode.SectionIIZ,ASMECodeCaseN-192-2,ZEEE-344-1975,andRG1.61,1.84,1.85,1.92,and1.100.TheHVACequipmentlistedwasqualifiedbyanalysisandtest.Applicablecodes,standards,andguidelinesincludeRG1.60,1.61,1.89,1.92,1.84,1.85,and1.100,ZEEE-323-1974,ZEEE-334-1974,ZEEE-334-1975,andASMESectionIII.1percent.Znadditiontotheseismicanalysis,theoperabilityofthepumpsisensuredthroughtheprogramdescribedinParagraph3.9A.3.2.1.ThequalificationofthemotorsconformstoIREE-334-1974.SeeTable3.10A-1forthequalificationresultsofthepumpmotorsandforthequalificationsummaryoftheelectricmotors.Theracksareaffectedbyseismicloadsonly.Theanalysiswasperformedusingafiniteelementmodel.Theequipmentwasdeterminedtoberigidand,therefore,staticanalysiswasutilized.Resultsoftheanalysisindicatethatthestressesarewithintheallowablestressesof3.9A.2.2.2.Flexiblehosesareaffectedbybothseismicandhydrodynamicloads.DesignadequacywasverifiedbyanalysisinaccordancewiththeE3MAStandard.Thisanalysistakesintoaccountdesigntemperature,pressure,dynamicloads.differentialdisplacements,andthenumberofcyclesofdisplacement.Inaddition,representativehosesarequalifiedbytwoseparatedynamictestprograms.Inthefirstdynamictest,hosesaresubjectedtoatotalof1millioncyclesofvibrationsinthefrequencyrangeof5to100Hz,ataccelerationsrangingfrom3gto51g.Inthesecondtest,thehosesaresubjectedtosixbiaxial,random,multifrequencyinputmotionsof30-secdurationseach.Thesixtestsarerepeatedintheotherhorizontalorientations.TheTRSenvelopstheapplicableportionofRRSwithatleasta10-percentmargin.Hoseswerepressurizedatthestartofeachtestseriestoatleastthedesignpressure.Duringandfollowingthedynamicteststhehosesmaintainedtheirpressureintegrity.Thisequipmentisaffectedbyseismicloadsonly.Theresultsoftheanalysisofstructuralandfunctionalelementsoftheequipmentindicatethatthestressesarewithintheallowablelimitsof3.9A.2.2.2.Thedeflectionofrotatingmemberswasdeterminedtobewithintheclearances.RefertoTable3.10A-1forthequalificationresultsofthefanmotorsandthepneumaticactuatorsusedonthedampers.USARRevision82of6November1995

NineMilePointUnit2FSARTABLE3.9A-4(Cont'd.)EquipmentMethodsResultsCentrifugalliquidchillersUnitspacecoolerSeismicqualificationisbystaticanalysisandtesting.ApplicablestandardsandguidelinesincludeASMECodeSectionZZZ,RG1.61,1.89,1.92,and1.100,ZEEE-323-1974,ZEEE-334-1974,andZEEE-334-1975.Theunitspacecoolersandairconditioningunitswerequalifiedbybothtestandanalysis.TheapplicablestandardsandguidelinesincludeIEEE-344-1975,ZEEE-323-1974,andZEEE-334-1974,ASMESectionIII,andRG1.61,1.89,1.92,and1.100.Thisequipmentisaffectedbyseismicloadsonly.Theanalysisofthechillerassemblyandstructuralcomponentsisperformedusingadetailedfiniteelementmodel.Resultsoftheanalysisindicatethatthestressesarewithintheallowablestressesof3.9A.2.2.2anddeflectionsofcriticalcomponentsarewithinlimitsrequiredtomaintainfunctionalcapability.TheelectroniccontrolpanelandtheSystemClass1Ecomponentswerequalifiedbydynamictesting.SeeTable3.10A-1fortestresults.'heunitspacecoolersandairconditioningunitsareaffectedbyseismicloadsonly.Theunitcoolersarecomposedofthreeparts:thefan-motorsection,coilsection,andfiltersection.Theunitshaveeitherapropeller-typefan(IndustrialAir)oravaneaxialfan(JoyManufacturing).Theyallhaveelectricmotors(Reliance)andmotorcontrolpanels.(Theairconditioningunitsareessentiallythesameastheunitcoolers,exceptthattheyhavenomotorcontrolpanels.)Allbuttwounitshaveairfilters(AmericanAirFilters)andeachhasoneortwoASMESectionZZZcoolingcoils.Apropellerfanspacecoolerandavaneaxialfanspacecoolerwerechosenfordynamictesting,sincetheywererepresentativeofthedimensionsandcharacteristicsoftheothercoolers.Thedynamictestingisperformedasfollows:Theunitsweremountedonthevibrationtesttablesothatthein-serviceconditionissimulated.Theunitswereinstrumentedtorecordaccelerations.Aresonancesearchwasperformedfrom1to35Hzforeachofthe3orthogonalaxes.Theseismicsimulationvibrationtestingconsistedofbiaxialrandommultifrequencytests,5OBEsand1SSEineachof2testorientations,90degapart.Theunitswerepressurizedandoperationalduringthetests.TheTRSenvelopedtheRRS.Thecoolingcoilsfortheunitcoolerswerequalifiedbyanalysis.Theresultsoftheanalysisindicatethatthestresslevelsarewithintheallowablelimitsof3.9A.2.2.2.Thefanandcoilsectionsoftheairconditioningunitwerequalifiedbydynamictesting.Theunitsweremountedonthevibrationtesttabletosimulateplantinstallation.Theywereinstrumentedtorecordaccelerations.Aresonancesearchwasperformedfrom1to33Hzforeachofthe3orthogonalaxes.Theseismicsimulationvibrationtestingconsistedofbiaxialrandommultifrequencytestof4SSEsineachofthetwotestorientations,90degapart.TheequipmentremainedoperationalduringthetestsandtheTRSenvelopedtheRRS.USARRevision83of6November1995

NineMilePointUnit2FSARTABLE3.9A-4(Cont'd.)EquipmentMethodsResultsNonactivevalvesHotor-operatedAir-operatedManualSolenoidNonactivevalvesarequalifiedbyanalysis.ApplicablestandardsandguidelinesareASMESectionIZZandRG1.61and1.92.Valvesaffectedbyseismicloadsonlyarequalifiedfor3ghorizontaland3gverticalloadings.Thosevalvesaffectedbyseismicandhydrodynamicloadingshavebeenqualifiedforupto20ghorizontaland20gverticalloadings.Pipingdesignacceptancecriteriaensureactualloadingstobewithinthequalifiedlevelsforeachvalve.Allvalvesweredeterminedtohaveanaturalfrequencythatisgenerallygreaterthan33Hz.Structuralandpressureintegrityofthevalveassemblieshasbeendemonstratedbystaticanalysisorthroughtheirsimilaritytoactivevalves.StressesaremaintainedwithinthelimitsofTables3.9A-7and3.9A-8.ForASMEClass1valves,designreportsarealsopreparedinaccordancewithASMESectionZIZ,SubsectionNB-3500.Forvalvesaffectedbyhydrodynamicloads,fatigueanalysesofthecriticalcomponentswerealsoperformed,andtheCUPsaremaintainedbelowone.ActivevalvesMotor-operatedAir-operatedSolenoidReliefvalvesElectrohydraulicActivevalvesarequalifiedbyanalysisandtest.ApplicablestandardsandguidelinesareASMESectionZIZ,RG1.48,1.61,1.89,1.92,and1.100,andZEEE-323-1974,ZEEE-344-1975andZEEE-382-1972.Valvesaffectedbyseismicloadsonlyaregenerallyqualifiedfor3ghorizontaland3gverticalloadings.Thevalvesaffectedbyseismicandhydrodynamicloadswerequalifiedforupto11ghorizontaland11gverticalloadings.Pipingdesignacceptancecriteriaensuresactualloadingstobewithinthequalifiedlevelsforeachvalve.Allvalvesweredeterminedtohavenaturalfrequenciesthataregenerallygreaterthan33Hz.Forvalveswithafundamentalnaturalfrequencybelow33Hz,theappropriatevalvemassandstiffnesspropertieswereincludedinpipingmodels,andthevalveaccelerationresponsesobtainedfromthepipinganalysesweremaintainedbelowthequalificationlevels.Structuralandpressureintegrityofthevalveassembliesaredemonstratedbyanalysis.StressesaremaintainedwithinthelimitsofTables3.9A-7and3.9A-8.Deflectionofcriticalcomponentsiswellwithintheallowablelimits.DesignstressanalyseswereperformedforASMEClass1valvesinaccordancewithASMESectionZII,SubsectionNB-3500.Forvalvesaffectedbyhydrodynamicloads,fatigueanalysesofthecriticalcomponentswerealsoperformed,andCUFsaremaintainedbelowone.ActuatorsforAOVsarequalifiedbydynamictesting.Eachtestedactuatorwasmountedontheshaketableasitnormallywouldbeinservice,andbiaxial,randommultifrequencytestsof30-secdurationwereperformedforeachofthefiveOBEandoneSSEconditions.Thetestswererepeatedinthesecondhorizontalandverticalorientation.TheactuatorwasoperatedthroughonecompletecycleforeachOBEandSSEtest.Theactuatorperformeditssafetyfunctionandsuccessfullycompletedthetest.TestspectraZPAhasaminimummarginof200percentoverthepeakaccelerationsobtainedfrompipinganalysesforvalvesaffectedbyseismicloadsonly.ForvalvesaffectedbycombinedseismicandhydrodynamicUSARRevision84of6November1995

NineMilePointUnit2FSARTABLE3.9A-4(Cont'd.)EquipmentMethodsResultsloads,theOBEandSSEtestspectraenvelopedtheupsetandfaultedRRS,respectively,byaminimummarginof10percent,exceptforonedirection,wherethemarginatonefrequencyisbelow10percent.However,theadjacent1/6octavepointsareabovethe10-percentmargin,andtheadjacent1/3octavepointsareabovea20-percentmargin.Additionally,testmarginsadequatelyenvelopethestresscyclesanddurationsrequiredforthehydrodynamicloads.FortheSOVs(TazgetRock)andtheelectriccomponentsofthevalves,suchassolenoidvalves,electrohydraulicoperators,motoroperators,limitswitches,etc.,qualificationisachievedthroughcomprehensiveenvironmentalanddynamictestprograms.DetailedresultsareprovidedinTable3.10A-1.FeedwatercheckvalvesThefeedwatercheckvalvesarequalifiedbyanalysis.TheClass1Ecomponentsoftheair-operatedcheckvalvesarequalifiedbytesting.ApplicablestandardsandguidelinesareASMESectionZZZ,NRCRG1.48,1.61,1.89,1.92,and1.100,andZEEE-323-1974andZEEE-344-1975.Operabilityofthevalveassembliesisdemonstratedbybothdynamicandstaticloadtests.Selectedvalvesweresubjectedtodynamicteststosimulatetheseismicandhydrodynamicloads.Othervalveswerequalifiedthroughstaticdeflectiontestsofparentvalveassemblies.ThetestprogramsconformtoParagraph3.9A.3.2.2.Functionaladequacywasverifiedduringandafterthesetests.Thefeedwatercheckvalvesareaffectedbybothseismicandhydrodynamicloads.Thevalvesarequalifiedbydynamicanalysisfortheworsttransientconditionfollowingapipebreak,togetherwiththeseismic/hydrodynamicloads.StressesaremaintainedwithinthelimitsofTable3.9A-7.DesignanalysisofthevalvesisalsopreparedinaccordancewithASMESectionZZZ,SubsectionNB-3500.Theelectricalappurtenancesoftheairoperators(limitswitch,solenoidvalves)arequalifiedbytesting.DetailedresultsareprovidedinTable3.10A-1.VacuumreliefvalvesThevacuumreliefvalvesarequalifiedbyanalysis.TheapplicablestandardsandguidelinesareASMESectionZZZandNRCRG1.48,1.61,and1.92.Thevacuumreliefvalvesareaffectedbybothseismicandhydrodynamicloads.Thevalvesarerigid(naturalfrequency>100Hz)andareanalyzedforupto16ghorizontaland14gverticalloadingstogetherwiththeoperatingloads(openingand/orclosingpressuretransients).ThedesignanalysismettheASMEZZZ,SubsectionNC-3500,requirements.ThestressesinallthecriticalvalvecomponentsaremaintainedwithinthelimitsofTable3.9A-8,andthecalculateddeflectionsdonotaffecttheoperabilityofthevalves.USARRevision8Sof6November1995

NineMilePointUnit2FSARTABLE3.9A-4(Cont'd.)BZuipmentMethodsResultsPolarcraneDynamicanalysisisperformedutilizingthetime-historytechnigue.ApplicablestandardsandguidelinesareCMAA-70,theAZSCCode,andNRCRG1.61and1.92.Thepolarcraneisaffectedbyseismicloads.Afiniteelementlumpedmassmathematicalmodelisdevelopedtosimulatethemassandstiffnesscharacteristicsofthecrane,includingthetrucks,trolleys,andhoistrope.Dynamicresponsesduetoseismicloadingsareevaluatedforseveraltrolleypositionsandloadliftheights,asappropriate,inordertodeterminethemaximumstresslevelsinallcriticalmembersandconnections.Theanalysisindicatesthatthestressesarewithintheallowablelimits.USARRevision86of6November1995

'J NineMilePointUnit2FSARTABLE3.9A-5LOADCOMBINATIONSFORASMESECTIONIIICLASS1VALVES(')ClassificationDesignCombinatioDesignpressureDesigntemperature(')Deadweight.PipingreactionsOBENormalUpsetEmergencyFaultedNormalconditionpressureNormalconditionmetaltemperatureDeadweightPipingreactionsUpsetconditionpressureUpsetconditionmetaltemperatureDeadweightDynamicload1"'ipingreactionsEmergencyconditionpressureEmergencyconditionmetaltemperatureDeadweightDynamicload3(')PipingreactionsFaultedconditionpressureFaultedconditionmetaltemperatureDeadweightDynamicload2+PipingreactionsTheonlyASMEClass1componentswithintheBOPscopearevalves.Temperatureisusedtodetermineallowablestressonly.Thedefinitionsoftheseloadsaregivenonpage2ofthistable.USARRevision81of3November1995 NineMilePoint'Unit2FSARTABLE3.9A-5(Cont'd.)LoadDefiitionsDnaicLoad1Locationa=[(OBE)+(SRV~)]'ocationb=OBEDnamicLoad2Locationa;theenvelopeof(i)(ii)(iii)and(iv)=[(SSE),'[(SSE)~+[(SSE)~+[(SSE)+(AP)2]in(SRVom)'(SRV/,~)+(SRV~~)+(CO1)2]1/2(CO2)2,]I/2(CHUG)~]~<Locationb=SSEDnamicLoad3Locationa;theenvelopeof(i)(ii)(iii)and(iv)Locationb=OBEWhere:[(OBE)+[(OBE)'[(OBE)+[(OBE)~+(AP)2]I/2(SRVom)'(SRV~gq)+(SRV~)~~(CO1)2]IQ(CO2)2]la(CHUG)]LocationaLocationbOBESSESRV~~SRV0gpADSC01C02APCHUGEquipmentinsidethereactorbuildingEquipmentoutsidethereactorbuildingOperatingbasisearthquakeSafeshutdownearthquakeEnvelopeofallsafetyreliefvalveactuationcases,includingsymmetric,asymmetric,ADS,andsinglesubsequentactuationsOnestuckopensafetyreliefvalveactuationcaseADSsafetyreliefvalvesactuationcaseBasiccondensationoscillationphaseofLOCACondensationoscillationphaseofLOCA,concurrentwithactuationofADSvalvesAnnuluspressurizationduetoLOCAEnvelopeofsymmetricandasymmetricchuggingphasesofLOCAUSARRevision82of3November1995 NineMile'PointUnit2FSARTABLE3.9A-5(Cont'd.)LOCA=EnvelopeofCOchuggingandannuluspressurizationduetoLOCANOTEForadetaileddiscussionoftheseloads,seetheDesignAssessmentReport(Appendix6A).USARRevision83of.3November1995 NineMilePointUnit2FSARTABLE3.9A-6LOADCOMBINATIONSFORASMESECTIONIIICLASS2AND3ANDNON-ASMECOMPONENTS1DesignConditionsIandIIaredefinedas:DesignConditionIDesignConditionIISpecifieddesignloads(temperature,pressure,etc.)+DynamicLoad1Specifieddesignloads(asabove)+DynamicLoad2piperuptureloads(ifapplicable)DnamicLoad1*Locationa=[(OBE)+(SRV~)]'ocationb=OBEDnamicLoad2*Locationagtheenvelopeof(i)(ii)(iii)and(iv)Locationb=SSE[(SSE)~+[(SSE)2(SSE)2P[(SSE)~+(AP)2]I/2(SRV)~/(CO1)]~(SRV~~q)+(CO2)](SRV)(CHUG)~]*SeeTable3.9A-5forhydrodynamicloadnomenclature.USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.9A-7STRESSLIMITSFORASMESECTIONZZZCLASS1(NB)SEISMICCATEGORYICOMPONENTS(ELASTICANALYSIS)PRESSUREBOUNDARY-DESZGNEDBYANALYSISConditionofDesign"'pset"'eferenceParagraphASMEIZZNB-3223PrimaStressLimitsPL(~)PL+PbExpansionStressLimitsPe3SPrimaryplusSecondaryStressLimitsPL+Pb+Pe+()3SSPeakStressLimitsPL+Pb+Pe+{}+FEmergency"'aulted""NB-3224NB-3225,NB-3221,App.FF1323.1Greaterof1.2Sor1.0SLesserof2.4Sor0~7SuGreaterof1.8Sor1.5SLesserof3.6Sor1.05SGreaterof1.8Sor1.5SLesserof3.6Sor1.05SNotrequiredNotrequiredNotrequiredNotrequiredsxncedesignloadsareusedintheactualanalysis,onlytheconditionsshownrequireevaluation.Usedesignloads.UseabovelimitsformaterialsofTableZ-l.2(ASMESectionZIZ).Use0.7SformaterialsofTableZ-l.l(ASMESectionZZZ)Primarystressesareevaluatedandcombinedwithsecondaryeffectsasappropriate.NOTE:Thenomenclature,conditions,andapplicationsoftheaboveallowablesareinaccordancewithASMESectionIII.Stresslimitsapplytodesignbyelasticanalysis.LimitandplasticanalysisisallowedinaccordancewithASMESectionIZIcriteria.SpecialstresslimitsofParagraphNB-3227applyasapplicable.USARRevision8lof1November1995 4

NineMilePointUnit2FSARTABLE3.9A-8STRESSLIMITSFORASMESECTIONIZICLASS2AND3COMPONENTS(ELASTICANALYSIS)DesignASMEZZICodeClassPrimarStressLimitsMembrane+MembraneBendingPressureVesselsIZZZP)ZIP)PumsNonactive<4"2(NC-3300)or3(ND-3300)2(NC-3200)1.1S2.0S1.1Sm2.0S1.65S2.40S1~65Sm2~40S~PumsActive<4"2(NC-3400)or3(ND-3400)2(NC-3400)or3(ND-3400)1.1S2.0S1.0S1.2S1~65S2.40S1.50S1.80SValvesActiveandNonactive<~~)IZI2(NC-3500)or3(ND-3500)1.1S2.0S1.65S240SIZI2(NC38-3900)or3(ND38-3900)1.1S2.0S1.65S2.40SKEY:S=AllowablestressvaluesatdesigntemperaturefromASMESectionIII,AppendixI,asallowedbyclassS=DesignstressintensityvaluesatdesigntemperaturefromASMESectionZII,AppendixI,asallowedbyclassRefertoTable3.9A-7forthedefinitionsofDesignConditionsIandII.Fatigueanalysismayberequiredwithoperatingconditions;seeParagraphNC-3219andAppendixXIVofASMESectionIII.USARRevision81of2November1995 NineMilePoint..Unit2FSARTABLE3.9A-8(Cont'd.)(4)WhenacompleteanalysisisperformedinaccordancewithSubparagraphNC-3211.1(c),thefaultedstresslimitsofAppendixFapply.InaccordancewithSubarticlesNC-3400andND-3400,anydesignmethodthathasbeendemonstratedtobesatisfactoryforthespecifieddesignconditionsmaybeused.StresslimitsofASMESectionIII,SubsectionNF,areusedforthedesignofsupportsasapplicable(Table3.9A-14).ThestandardoralternativedesignrulesofSubarticlesNC-3500andND-3500maybeusedinconjunctionwiththestresslimitsspecified.Valvenozzle(pipingload)stressanalysisisnotrequiredwhenboththefollowingconditionsaresatisfiedbycalculation:a~b.Sectionmodulusandareaattheplanenormaltotheflowpassagethroughtheregionatthevalvebodycrotchisatleast110percentofthatforthepipingconnected(orjoined)tothevalvebodyinletandoutletnozzles;and,Codeallowablestress,S,forvalvebodymaterial,isequaltoorgreaterthancodeallowablestress,S,ofconnectedpipingmaterial.Ifvalvebodymaterialallowablestressislessthanthatoftheconnectedpiping,thevalvesectionmodulusandareaascalculatedinItemaismultipliedbytheratiooftheallowablestressforthepipedividedbytheallowablestressofthevalve.ThedesignbyanalysisprocedureofSubparagraphNB-3545.2isanacceptablealternativemethodiftheserequirementscannotbemet.Acastingqualityfactorof1.0isused.Designrequirementslistedinthistablearenotapplicabletostems,castrings,orothernonpressure-retainingpartsofvalveswhicharecontainedwithintheconfinesofthebodyandbonnet.USARRevision82of2November1995 NineMilePointUnit2FSARTABLE3.9A-11THISTABLEHASBEENDELETEDUSARRevision81of1November1995 N,hI NineMilePointUnit2FSARTABLE3.9A-12ACTIVEVALVES(BOP)SystemNameReactorPlantComponentCooling(CCP)ContainmentAtmosphereMonitoring(CMS)MarkNumber2CCP*MOV14A,B2CCP*MOV15A,B2CCP*MOV16A,B2CCPAMOV17A,B2CCP*MOV18A,B2CCP*MOV1222CCPiMOV1242CCP~MOV2652CCPAMOV2732CCPiRV60A,B,C2CCPiRV64A,B2CCPARV1702CCP'RV1712CCP'MOV94A,B2CCP*AOV37A2CCP~AOV37B2CCP~AOV38A2CCP~AOV38B2CHS~SOV23A-F2CMS*SOV24A-D2CMS*SOV26A-D2CMS~SOV32A,B2CMS*SOV33A,B2CMS*SOV34A,B2CHS*SOV35A,B2CHS*SOV60A,B2CHS*SOV61A,B2CMS*SOV62A,B2CMS*SOV63A,B2CMS~SOV64A,B2CMS~SOV65A,B2CMS*EFVlA,B2CHS*EFV3A,B2CMS*EFVSA,B2CMS~EFV62CMS*EFVSA,B2CMS*EFV9A,B2CMS~EFV10Size1241288883/4x12x33/4x13/4x1411/2211/223/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/4ValveGateGateGateGateGateGateGateGateGateSRVSRVSRVSRVGatePlugPlugPlugPlugGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeCheckCheckCheckCheckCheckCheckCheckPressureRating(~)150150150150150150150150150150/150150/150150/150300/150150150150150150150015001500150015001500150015001500150015001500150045454545454545ASMEClassMfg.666666666666613131313131313ValveOperatorModel(Mfg.)SMB-0-25(1)SMB-000-5(1)SMB-000-5(1)SMB-000-5(1)SMB-0-25(1)SMB-00-15(1)SMB-00-15(1)SMB-00-15(1)SMB-00-15(1)NoneNoneNoneNoneSMB-000-5(1)NCB520-SR80(2)NCB725-SR80(2)NCB520-SR80(2)NCB725-SR80(2)76P-001(7)76P-001(7)76P-001(7)76P-002(7)76P-002(7)76P-002(7)76P-002(7)76P-001(7)76P-002(7)76P-002(7)76P-002(7)76P-001(7)76P-001(7)NoneNoneNoneNoneNoneNoneNoneActiveFunction6399963999944449646464641816,8316,8316,8316,8316,8316,8316161616626216161616161616USARRevision81of15November1995 III' NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNamePrimaryContainmentPurge(CPS)MarkNumber2CPS*AOV1042CPS~AOV1052CPS~AOV1062CPS~AOV1072CPS*AOV1082CPS*AOV1092CPS~AOV1102CPSAAOV1112CPSASOV1192CPS~SOV1202CPS+SOV1212CPS*SOV1222CPSSSOV1322CPSSSOV1331412141214121412222211SizeValveTypeButterflyButterflyButterflyButterflyButterflyButterflyButterflyButterflyGlobeGlobeGlobeGlobeGlobeGlobePressureRating(~)150150150150150150150150150015001500150015001500ASMEclassMfg.ValveOperatorModel(Mfg.)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)76P-020(7)76P-027(7)76P-020(7)76P-027(7)76P-035(7)76P-035(7)ActiveFunctionHighPressureCoreSpray(CSH)2CSHiAOV1082CSHARV1132CSHiRV1142CSHiV92CSH~RV1602CSHov172CSH~V552CSH+EFV12CSH~EFV22CSH~EFV3123/43/4163/433223/4x1x1x1CheckSRVSRVCheckSRVCheckCheckCheckCheckCheck900150/150150/150900150/15090090010010015753883811131313Series2A(6)NoneNoneNoneNoneNoneNoneNoneNoneNone9,164,9,16,564,9,16,56234,5630309,169.169,16LowPressureCoreSpray(CSL)2CSL~AOV1012CSL~FV1142CSL~MOV1042CSL*MOV1072CSLAMOV1122CSL4RV1052CSLSRV1232CSL~V42CSLiV142CSLiV172CSL~EFV12CSL'V92CSL+V212CSLiEFV3112101242011/2x23/4x116223/41223/4CheckGlobeGateGateButterflySRVSRVCheckCheckGateCheckCheckCheckCheck900300600300150300/150150/150300600600125015060012503511988111131113Series2A(6)SMB-00-5(1)SB-2-60(1)SMB-OOS-15(l)SMB"0"10/H4BC(1)NoneNoneNoneNoneNoneNoneNoneNoneNone9,16272831324,9,564,9,567430301622,312216USARRevision82of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameReactorBuildingEguipmentDrains(DER)ReactorBuildingFloorDrains(DFR)StandbyDieselGeneratorAirStartup(EGA)Feedwater(FWS)StandbyDieselGeneratorFuel(EGF)NitrogenTanks(GSN)StandbyGasTreatment(GTS)HydrogenRecombiner(HCS)MarkNumber2DER~MOV1192DER*MOV1202DER~MOV1302DER~MOV1312DER~EFV312DFRSMOV1202DFROMOV1212DFR~MOV1392DFRiMOV1402EGA~RV1252EGA~RV1262EGA~RV1272FWS~AOV23A,B2FWS~MOV21A,B2FWS~V12A,B2EGF"V122EGF*V132EGFOV322EGF*V332EGF~V522EGFAV532GSN~SOV1662GSN~V70A,B2GSN~V75A,B2GTS~MOV1A,B2GTS~MOV2A,B2GTSiMOV3A,B2GTS~MOV4A,B2GTS~MOV28A,B2GTS~PVSA,B2HCSAMOV1A,B2HCS~MOV2A,B2HCS"MOV3A,B2HCS~MOV4A,B2HCS~MOV5A,B2HCS~MOV6A,B2HCS~SOV10A,B2HCS~SOV11A,BSize4223/.430302224242420202088'4ValveTypeGateGateGlobeGlobeCheckGateGateGateGateSRVSRVSRVCheckGateCheckCheckCheckCheckCheckCheckCheckGlobeCheckCheckButterflyButterflyButterflyGateButterflyButterflyGateGlobeGateGateGlobeGateGlobeGlobePressureRating(*)150150150015001250150150150150150150150900900900600600600600600600150060060015015015015015015015015015015015015015001500ASMEClassMfg.111113101010151151511566ValveOperatorModel(Mfg.)SMB-000-5(1)SMB-000-5(1)SMB-000-5(1)SMB-000-5(1)NoneSMB-00-10(1)SMB-00-10(1)SMB-000-5(1)SMB-000-5(1)NoneNoneNoneSeries2A(6)SMB-4-200(1)NoneNoneNoneNoneNoneNoneNone76P-035(7)NoneNoneSMB-00-10/H3BC(1)85430(3)85430(3)SMB-00-15(1)86040(3)86060(3)SMB-00-10(1)SMB-000-5(1)SMB-00-10(1)SMB-000-5(1)SMB-000-5(1)SMB-000-5(1)76P-024(7)76P-024(7)ActiveFunction999916171717175656569179222222222222922,75761011ll111213USARRevision83of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameMarkNumberSizeValveTyPePressureRating(")ASMEClassMfg.ValveOPeratorModel(Mfg.)ActiveFunctionControlBuildingAirConditioner(HVC)2HVC~MOVIA,B18Butterfly150SMB-000-2/H1BC(1)ControlBuildingChilledWater(HVK)ZnstrumentAir(IAS)2HVKiRV14A,B2HVK*RV35A,B2HVK*RV37A,B2HVK~RV43A,B2HVK~SOV36A,B2HVK~TV21A,B2HVK~TV22A,B2IAS~V4482IAS~V4492ZASTAV3722IAS~V3712ZAS~SOV1642IASASOV1652IAS~SOV1662IAS~SOV1672IAS~SOV1682IAS~SOV1802IAS~SOV1842IAS~SOV18521AS~SV19A,B2IAS~SV20A,B2IAS~SOVY1812IAS~SOVY1862ZASiSOVX1812IAS~SOVX1862IAS"V5712IAS*V4712IAS'V4212IAS~V4312IAS'V5262IASiV5462ZAS~V5812IAS~EFV2002IASiEFV2012IAS~EFV2022IAS~EFV2032IAS~EFV2042ZAS*EFV2052ZAS~EFV2063/4x13/4x13/4x13/4x13411/211/21111/211/211/211/211/211/211/211/23/4x13/4xl3/43/411/211/211/411/411/411/411/411/411/43/43/43/43/43/43/43/4SRVSRVSRVSRVGlobeGlobeGlobeCheckCheckCheckCheckGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeSRVSRVGlobeGlobeGlobeGlobeCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheck150/150150/150150/150150/150150015015060060060060015001500150015001500150015001500600/150150/1501500150015001500600600600600600600600350350350350350350350111166666666886666111111113131313131313NoneNoneNoneNone76P-034(7)(3)(3)NoneNoneNoneNone76P-019(7)76P-019(7)76P-019(7)76P-019(7)76P-019(7)76P-019(7)76P-019(7)76P-019(7)NoneNone76P-03676P-03676P-03776P-037NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNone16,22,5916,22,59222216,5916,5916161616161656,5956,595959595922,5622,5622,5622,5622,5622,5622,5659,6059,6059,6059,6059,6059,6059,60USARRevision84of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameReactorCoreIsolationCooling(ICS)ReactorVesselInstrumentation(ZSC)MarkNumber2ZCSiAOV1092ZCS+AOV1102ICS*AOV1302ZCSiAOV1312ZCS~AOV1562ZCSSAOV1572ZCSAMOV1162ICSSMOV1202ICSAMOV1212ICSSMOV1222ICS~MOV1242ICSSMOV1262ZCSAMOV1282ICS'MOV1292ICSSMOV1362ICSiMOV1432ZCSiMOV1482ZCSSMOV1592ZCS&MOV1642ICSAMOV1702ICS0RV1122ICSSRV1142ICSAV272ICSiv282ICS~V292ICS+V382ICS'V392ICS*V402ZCS~PCV1152ICS~EFV12ICS~EFV22ICS*EFV32ICS~EFV42ISC~RV33A,B2ISC~RV34A,B2ZSCARV35A,B2ISC~RV36A,B2ZSC*EFV12ISCiEFV22ZSC~EFV32ISC~EFV42ISCiEFV52ZSCiEFV62ZSC~EFV7Sire22226624101261066211/2111/213/4x13/4x16612211/211/223/43/43/43/4242424243/43/43/43/43/43/43/4ValveTypeGlobeGlobeGlobeGlobeCheckCheckGlobeGlobeGateGateGateGateGateGateGateGlobeGlobeGlobeGlobeGlobeSRVSRVCheckCheckCheckCheckCheckCheckE/HCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckPressureRating(~)150150900900900900150090090015090090090015015015001500150015001500150/150150150150150150060060090012501250125012501501501501501250125012501250125012501250ASMEClassMfg.55553311111111111111881111115131313131010101013131313131313ValveOperatorModel(Mfg.)NoneNoneNoneNoneSeries2A(6)Series2A(6)SMB-00-5(1)SMB-00-10(1)SB-2-60(1)SMB-0-25(1)SMB-00-10(1)SMB-0-40(1)SB-2-60(1)SMB-00-10(1)SMB-00-10(1)SMB-00-5(1)SMB-000-5(1)SMB-000-2(1)SMB-000-5(1)SMB-000-2(1)NoneNoneNoneNoneNoneNoneNoneNone(3)NoneNoneNoneNone(4)(4)(4)(4)NoneNoneNoneNoneNoneNoneNoneActiveFunction38383838404042439444199464731484348944222222222222429999111160606060606060USARRevision85of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameReactorVesselZnstrumentation(ISC)(cont'd.)ContainmentLeakageMonitoring(LMS)MarkNumber2ZSC*EFV82ISC~EFV921SC+EFV102ZSC~EFV112ZSC*EFV122ISC~EFV1321SC~EFV142ISC*EFV152ISC~EFV162ISC~EFV172ISC~EFV182ISC~EFV192ISC~EFV202ISC*EFV212ISC~EFV222ISC~EFV232ISC*EFV242ISC*EFV252ISC~EFV262ISC~EFV272ISC*EFV282ISC~EFV292ISC*EFV302ISC~EFV312ZSC~EFV322ZSC~EFV332ZSC~EFV342ISC~EFV352ISC~EFV362ISC~EFV3721SC~EFV382ISC~EFV392ISC~EFV402ISC~EFV412ISC*EFV422LMS~SOV1522LMS~SOV1532LMS~SOV1572LMS~SOV156Size3/43/43/43/43/43/43/4.3/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/43/4ValveTypeCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckGlobeGlobeGlobeGlobePressureRating(*)125012501250125012501250125012501250125012501250125012501250125012501250125012501250125012501250125012501250125012501250125012501250125012501500150015001500ASMEClassMfg.1313131313131313131313131313131313131313131313131313131313131313131313ValveOperatorModel(Mfg.)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNone76P-001(7)76P-001(7)76P-001(7)76P-001(7)ActiveFunction60606060606060'060606060606060606060606060606060606060606060606060606016161616USARRevision86of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameMarkNumberSizeValveTypePressureRating(")ASMEClassMfg.ValveOperatorModel(Mfg.)ActiveFunctionMainSteamSystem(MSS)ReactorCoolantRecirculation(RCS)2MSS~MOVlll2MSS~MOV1122MSS~MOV2082MSS*PSV1202MSS~PSV1212MSS~PSV1222MSS~PSV1232MSS~PSV1242MSS*PSV1252MSS~PSV1262MSS~PSV1272MSS~PSV1282MSS~PSV1292MSS~PSV1302MSS"PSV1312MSS*PSV1322MSS*PSV1332MSS*PSV1342MSS~PSV1352MSS*PSV1362MSS"PSV1372MSS*EFV1A-D2MSS~EFV2A-D2MSS*EFV3A-D2MSS~EFV4A-D2RCS~SOV68A,B2RCS*SOV65A,B2RCS+SOV66A,B2RCS~SOV67A,B2RCS~SOV79A,B2RCS~SOV80A,B2RCS*SOV81A,B2RCS~SOV82A,B2RCSiSOV1042RSC~SOV1052RCSiV59A,B2RCS*V60A.B2RCS*V90A,B2RCS~EFV43A,B2RCS~EFV44A,B2RCS~EFV45A,B2RCS~EFV46A,B2RCS~EFV47A,B2RCS~EFV48A,B6628x108x108x108x108x108x108x108x108x108x108x108x108x108x108x108x108x108x103/43/43/43/43/42122123/43/43/43/43/43/43/43/43/43/43/43/4GlobeGlobeGlobeSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVCheckCheckCheckCheckGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeGlobeCheckCheckCheckCheckCheckCheckCheckCheckCheck60060015001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/3001500/30012501250125012502500150025001500150025001500250015001500150015001500125012501250125012501250111141414141414141414141414141414141414131313136666666666111131313131313SMB-2-25(1)SMB-2-25(1)SMB-000-5(1)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNone76P-040(7)76P-038(7)76P-039(7)76P-038(7)76P-038(7)76P-039(7)76P-038(7)76P-040(7)76P-049(7)76P-049(7)NoneNoneNoneNoneNoneNoneNoneNoneNone8,9,168,9,16,4516,8,9565656.5956565656,5956.595656,5956,5956565656,59565656,5960,1660,1660,1660,169999999999999161616161616USARRevision87of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameMarkNumberSireValveTypePressureRating(*)ASMEClassMfg.ValveOperatorModel(Mfg.)ActiveFunctionReactorCoolantRecirculation(RCS)(cont'd.)ResidualHeatRemoval(RHS)2RCS~EFV52A,B2RCS~EFV53A,B2RCS~EFV62A,B2RCS~EFV63A,B2RHS~MOV1A,B2RHSiMOV1C2RHS*MOV2A,B2RHS~MOV9A,B2RHS~V32RHS~AOV16A-C2RHSiAOV39A,B2RHS~AOV1502RHS~FV38A-C2RHS~MOV4A-C2RHS~MOV15A,B2RHS*MOV22A,B2RHS~MOV23A,B2RHS~MOV24A,B,C2RHS~MOV25A,B2RHS~MOV26A,B2RHS~MOV27A,B2RHSiMOV30A,B2RHS~MOV8A,B2RHS*V602RHS'V1432RHS~RV1172RHS~MOV32A,B2RHS*MOV33A,B2RHSiMOV37A,B2RHSiMOV40A,B2RHS~MOV67A,B2RHS~MOV80A,B2RHS*MOV1042RHS+MOV1122RHS'MOV1132RHS+MOV1152RHS*MOV1162RHS*MOV1422RHS~MOV1492RHS~RV20A-C2RHSiRV61A-C2RHS~RV1082RHSiRV1103/43/43/43/4242418181812121618616881216111818263/4x141221620201616333/4xl3/4x13x43/4x1CheckCheckCheckCheckButterflyButterflyButterflyButterflyCheckCheckCheckCheckGlobeGateGateGlobeGlobeGateGateGlobeGlobeButterflyButterflyCheckCheckSRVGateGlobeGlobeGlobeGlobeGlobeGlobeGateGateGateGateGlobeGateSRVSRVSRVSRV125012501250125030030030030030090090030030030030090090090030015001500300300600900185/18030030030090015001500900900900300150300300300/150300/150150/150300/15013131313NoneNoneNoneNoneSMB-2-60(1)SMB-0-25(1)SMB-0-25(1)SMB-00-10(1)NoneSeries2A(6)Series2A(6)4-A-FFX-8-3/4-Y(5)SMB-00-5(1)SMB-OOS-15(1)SMB-2-80(1)SMB-1-25(1)SMB-1-25(1)SMB-3-100(1)SMB-2-80(1)SMB-000-2(1)SMB-000-2(1)SMBO-25/H4BC(1)SMB-1-25/H5BC(1)NoneNoneNoneSMB-00-10(1)SMB-000-5(1)SMB-000-5(1)SMB-3-80(1)SMB-000-5(l)SMB-000-2(1)SMB-0-10(1)SB-3-150(11SB-3-150(1)SMB-0-25(1)SMB-0-25(1)SMB-000-5(1)SMB-000-5(1)NoneNoneNoneNone1616161649.52,5355,1650,5250,53,5549,50,53,554050,165152,5354,5252,55,16525249,52,1652,55,1652,1652,1653,54.1649,50,522250565252,55,165250,52,16165250,52,1650,1650,165151525256565656USARRevision88of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameResidualHeatRemoval(RHS)(cont'd.)SpentFuelPoolCoolingandCleanup(SFC)MarkNumber2RHS~RV1392RHSRV1522RHS*SOV35A,B2RHS*SOV36A,B2RHSiSOV70A,B2RHS~SOV71A,B2RHS~SOV1262RHS*SV34A,B2RHS~SV62A,B2RHS~RVV35A,B2RHS~RVV36A,B2RHS"MOV12A,B2RHS~V172RHS~V472RHS~V612RHS~V182RHS~V482RHS~V12RHS~V22RHS~EFVS2RHS*EFV62RHS~EFV72RHSiEFV82RHSiEFV92RHS*EFV102RHS~V192RHS~V202RHS'V1172RHS~V1182SFC~AOV1532SFC*AOV1542SFC"AOV19A,B2SFCiHV6A,B2SFC~HV17A,B2SFC~HV18A.B2SFCiHV37A,B2SFCivll2SFC*V20A,B2SFC'V9Size3/4x13/4x13/43/4113/44x66x81010182222218183/43/43/43/43/43/43/43/43/43/4888'10888888ValveTypeSRVSRVGlobeGlobeGlobeGlobeGlobeSRVSRVVacBrkrVacBrkrButterflyStopChkStopChkStopChkCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckButterflyButterflyButterflyButterflyButterflyButterflyButterflyCheckCheckCheckPressureRating(*)300/150900/15015001500150015001500600/300600/300150150300600600600600600300300125012501250125012501250600600600600300300300150300300300150300150ASMEClassMfg.886666688101021111111313131313131111ValveOperatorModel(Mfg.)NoneNone76P-032(7)76P-030(7)76P-025(7)76P-025(7)76P-023(7)NoneNoneNoneNoneSMB-00-10(1)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneN721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)N721C-SR80-M3HW(2)NoneNoneNoneActiveFunction565652,3452,34525251",5256.565757>>50,53,55222222222249,50,53,5549,50,53,551616161616165757575745454535353535782278USARRevision89of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameStandbyLiquidControlSystem(SLS)MainSteamSafety/ReliefValves,VentsandDrains(SW)MarkNumber2SLSiMOV1A,B2SLSAMOV5A,B2SLSiRV2A,B2SVV~RVV1012SW~RVV1022SW~RW1032SW~RW1042SW~RW1052SW+RW1062SW~RW1072SW~RW1082SW~RW1092SWiRW1102SVV'RW1112SWiRW1122SWiRW1132SWiRW1142SVViRW1152SW~RW1162SVViRW1172SW'RVV1182SW~RW2012SW~RW2022SW~RW2032SWiRW2042SW~RVV2052SW~RW2062SW~RW2072SW~RW2082SW~RW2092SW~RVV2102SW~RW2112SVV~RW2122SWiRW2132SW~RVV2142SWiRW2152SW~RVV2162SWiRW2172SVV~RVV2182SVV~RW3012SW~RW3022SW~RW3032SW~RW3042SVViRW305Size323/4xl10101010101010101010101010101010101010101010101010101010101010101010101021/221/221/221/221/2ValveTypeGlobeStopChkSRVCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckPressureRating(')15015001500/150600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600600150150150150150ASMEClassMfg.1010101010101010101010101010101010101010101010101010101010101010101010101010101010ValveOperatorModel(Mfg.)SB-00-5(1)SMB-00-10(1)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneActiveFunction6666,16562121212121212121212121212121212121212121212121212121212121212121212121212121212121USARRevision810of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameMainSteamSafety/ReliefValves,VentsandDrains(SVV)(cont'd.)ServiceWater(SWP)MarkNumber2SVV*RVV3062SVV~RVV3072SVV~RVV3082SVV*RVV3092SVV~RVV3102SVV~RW3112SVV~RVV3122SVV*RVV3132SVV"RVV3142SVV~RVV3152SVV~RVV3162SVV~RVV3172SVV~RVV3182SWPiAOV20A,22A2SWP~AOV20B,22B2SWPiAOV97A,B2SWPiAOV5722SWP+AOV78AB2SWPiFV54A,B2SWP~MOV1A-F2SWP~MOV3A,B2SWP~MOV19A,B2SWPiMOV33A.B2SWP~FV47A,B2SWP*MOVSOA,B2SWP~MOV74A-F2SWP~MOV90A,B2SWP~MOV15A,B2SWP~MOV17A,B2SWP*MOV18A,B2SWP~MOV21A,B2SWPiMOV66A,B2SWP~MOV67A,B2SWP~MOV94A,B2SWP*MOV95A,B2SWP~MOV5992SWP~MOV93A,B2SWP~MOV30A,B2SWP~MOV77A,B2SWPiRV9A,B2SWP~RV10A,B2SWP~RV11A,B2SWP~RV27A,B2SWP~RV34A,BSize21/221/221/221/221/221/221/221/221/221/221/2,21/221/211/22621/223043020183036181821/2121238488302448x7248x483/4x13/4x13/4xl3/4x14x6ValveTypeCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckPlugPlugPlugPlugPlugButterflyBallButterflyButterflyButterflyButterflyButterflyButterflyButterflyGateGateGateGateGateGateGateGateButterflyButterflyButterflyButterflySRVSRVSRVSRVSRVPressureRating(")150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150150/150150/150150/150150/150300/150ASMEClassMfg.1010101010101010101010101044491199999991111111199121288888ValveOperatorModel(Mfg.)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNCB520-SR80(2)NCB725-SR80(2)NTB12-SR3-M3HW(2)NCB725-SR80(2)NCB725-SR80(2)PD87265-500(7)SMB-000-2/H1BC(1)SMB-2-40/H6BC(1)SMB-1-15/H4BC(1)SMB-0-25/H4BC(1)PD89265-500-003&4(9)SMB-3-60/H6BC(1)SMB-0-40/H4BC(1)SMB-0-25/H4BC(1)SMB-000-5(1)SMB-0-25(1)SMB-0-25(1)SMB-000-5(1)SMB-00-15(1)SMB-000-5(1)SMB-00-15(1)SMB-00-15(1)SMB-1-25/H5BC(1)SMB-1-15/H4BC(1)SMB-0-15/H4BC(1)SMB-00-10/H3BC(1)NoneNoneNoneNoneNoneActiveFunction21212121212121212121212121646468686870245456770716967686363366568656545457273444456USARRevision811of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)SystemNameServiceWater(SWP)(cont'd.)MarkNumber2SWP~RV53A,B2SWP~RV58A,B2SWP~RV68A,B2SWP~RV72A,B2SWP*RV80A-F2SWPiRV82A-D2SWP~RV83A-E2SWP*RV84A-C2SWPiRV85A-C2SWP~RV87A,B2SWP~RV89A,B2SWP~RV155A,B2SWPiRV81A,B2SWP~RV202A,B2SWPiRV2032SWP~RV5152SWP"RV5182SWP~RV5562SWP*RV5582SWP"RV5642SWP*RV5752SWP*RV5762SWPiRVX46A,B2SWP~RVX157A,B2SWPiRVY46A,B2SWP~RVY157A,B2SWP~TV35A,B2SWP~VlA-F2SWP"V201A,B2SWP~V202A,B2SWP~V203A,B2SWP*V219A,B2SWP*V240A2SWP"V240B2SWP~V2592SWP~V2602SWPiV76A,B2SWP~V720A,B2SWPiV1002A,B2SWP'V10272SWP~V10282SWP'V10242SWP~V10252SWPiV10292SWP"RV566Size3/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x13/4x141811/430244488813303066303/4x1ValveTypeSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVSRVGlobeCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckCheckSRVPressureRating(~)150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150/150150150600150600150150150150150150600150150150150150150150/150ASMEClassMfg.888888888888888888888888885916911161611111991198ValveOperatorModel(Mfg.)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNone(3)NoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneNoneActiveFunction444444444444444444444468222222,4522222222222222222222222222224USARRevision812of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'.)SystemNameMarkNumberSizeValveTypePressureRating(~)ASMEClassMfg.ValveOperatorModel(Mfg.)ActiveFunctionServiceWater(SWP)(cont'd.)ReactorWaterCleanup(WCS)2SWP~AOV154A,B2SWP*AOV5712SWP*AOV5812SWP*AOV5732SWP~AOV5742WCSCMOV1022WCSiMOV1122WCSiMOV2002WCSiEFV2212WCS~EFV2222WCS*EFV2232WCS"EFV2242WCSiEFV30011/211/211/2228883/43/43/43/43/4PlugPlugPlugPlugPlugGlobeGlobeGlobeCheckCheckCheckCheckCheck150150150150150600600900125012501250125012501111313131313NCB520-SR80(2)NCB520-SR80(2)NCB520-SR80(2)NCB725-SR80(2)NCB725-SR80(2)SB-2-80(1)SB-2-80(1),SMB-1-25(1)NoneNoneNoneNoneNone68686868681616161616161616KetoManufacturerKetoValveerator/Manufacturer12345678910111213141516VelanCorp.Posi-SealAnchor-DarlingAtwoodaMorillCopes-VulcanTargetRockGulfaWesternCrosbyClowGPEControlsContromaticsHenryPrattCo.DragonDikkersWestinghouseEnertech123456789(")PressureRating-Inlet/OutletMotor/LimitorqueAir/BettisElectrohydraulic/Borg-WarnerPneumatic/Parker-Hannifin(cylinder)Air/Anchor-DarlingAir/Parker-Hannifin(piston)TargetRock(Deleted)Electrohydraulic/PaulMonroeKetoActiveFunctionsRelievepressurefromsuppressionchambertodrywell.Pressurecontrolforself-cleaningstrainersforservicewaterpumps.Hydrogenrecombinerisolation(activefunctionrequiredonlyafterapproximately2daysfollowingaLOCA)Pressurerelief.Computerroomisolation(safetyclasschange).Temperaturecontrolofcontrolroomair-conditioningunit.Temperaturecontrolofrelayroomair-conditioningunit.Highradiationisolationvalve.ContainmentisolationduringLOCA.USARRevision813of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)10ll1213141516171819202122232425262728293031323334353637383940414243444546474849505152535455valves.thevessel.Valveisopenedtoallowflowthevessel.Valveisopenedtoallowflowterminatedcondensatetank.RedundantsupplyflowpathtoGTSfromreactorbuildingventilationsystem.GTSfiltertrainoperation.GTSfiltertrainisolationuponhightemperatureofoneoftheGTStrains.Modulatetomaintaintherequiredreactorbuildingpressuredifferential.IsolationbetweenGTSandCPS.(Deleted)Primarycontainmentisolation.Isolationvalvesforpenetrationsthroughprimarycontainmentwall.Drywellsampleselectorvalves.(Deleted)ContainmentatmospheremonitoringandpostaccidentsamplingsystemisolationVacuumbreaker,waterhammermitigationformainsteamSRVdischargepiping.Preventreverseflow.HPCSsysteminjectionvalve.HPCSsuctionfrom2CNS-TK1B,isolatesonlowlevelintank.HPCSsuctionfromsuppressionpool,opensonlowlevelin2CNS-TK1B.HPCSsystemtestvalvetobeclosedtoensuremaximumflowisinjectedintotoreturntosuppressionpoolduringfullflow.LPCSsystemtestvalvetobeclosedtoensuremaximumflowisinjectedintotoreturntosuppressionpoolduringfullflow.LPCSsysteminjectionvalveandcontainmentisolationwhenLPCSserviceisLPCSsystemtestvalvetobeclosedtoensuremaximumflowisinjectedintoPreventreverseflowandprovidepressureboundary.Minimumflowbypasstoprotectpump.Containmentisolationonlowsuppressionpoollevel.Reactorvesseldrainlineisolationandclassbreak(ASMEIZItoANSZB31.1)Sampleisolationandclassbreak(ASMEZZItoANSIB31.1).SFCloopisolation.SFCmakeupfillisolation.Caskhandlingareaisolation.RCZCturbinedrainpotdrainisolation.Coolingloopshutoffvalve.Containmentisolation,openforinjection.IsolatesRCICtestreturn.Opentoallowlubeoilcooling.RCZCturbinesteamsupplyvalve.RCICturbineexhaust-containmentisolation.Safetyclasschange.IsolatesonlowCSTlevel.OpensonlowCSTlevel.Turbineexhaustvacuumrelief.LPCIinjection.Shutdowncooling.RHR/SNPcross-connectforpost-LOCAcontainmentflooding.Systemboundaryisolation.Suppressionpoolcooling.RHRpumpminiflow.Containmentspray.USARRevision814of15November1995

NineMilePointUnit2FSARTABLE3.9A-12(Cont'd.)enonlossofoffsitepower./chillers.56=Overpressureprotection.57=Vacuumbreaker/waterhammermitigation.58=(Deleted)59=Automaticdepressurizationsystem.60=Preventexcessflow.61=(Deleted)62=Hydrogen/oxygenanalyzerisolationvalvestoop63=SWP/CCPcrosstieforSFCheatexchanger.64=SWPICCPcrosstieforRHRpumpsealcoolers.65=SWPsupplyto/fromdieselgenerators.66=Standbyliguidcontrolinjection.67=SWPsupplyto/fromRHRheatexchangers.68=SWPsupplyto/fromsafety-relatedunitcoolers69=SWPpumpdischargevalves.70=SWPmakeuptoCWS.71=SWPdivisionalcross-connectisolation.72=Intakebaycross-connectisolation.73=Intakebaytravelingscreenbypass.74=LPCSinjection.75=AllowflowtoADSaccumulatortanks.76=Allowemergencynitrogenflow.78=Allowflowintheforwarddirection.83=CMSatmospheresamplevalves.USARRevision815of15November1995 I

NineMilePointUnit2FSARTABLE3.9A-13LOADCOMBINATIONSFORCOMPONENTSUPPORTSANDSTRESSLIMITSFORPLATEANDSHELL-TYPESUPPORTSA.LoadCombinationsforComponentSupportsoditooa'nCombatoev'cevelNormalUpsetEmergencyFaultedDL+S+D+R+A+EDL+S+Di+R+A+E+DNotApplicableDL+S+Dg+E+DKEYoLoadiCob't'osDLSD<<DzRAEDDeadloadSuperimposedloadsDynamicLoads1and2,respectively(fordefinitions,seeTable3.9A-6)RestrainedthermalexpansionAnchorandsupportmovementEnvironmentalloadsOtherexternaldynamicloadsNOTES:Foreachoperatingcondition,theloadingsasgiveninthetablearetobeconsideredsimultaneously.Symbolsusedaredefinedinthekey.Thespecificloadsofeachtypewhichareappliedduringtheapplicableoperatingconditionaredependentontheparticularsystemconditions.Thefollowinglistingidentifiessomeofthesespecificloadswhichareusedasageneralchecklistwhendeterminingloadingconditionsasrelatedtoplantoperatingconditions.VComponentmaximumoperatingweight(withappurtenances)HydrostatictestweightOperationaltestweightComponentsupportweightUSARRevision81of3November1995 NineMilePoint.Unit2FSARTABLE3.9A-13(Cont'd.)Sue'mosedPressureTemperaturePipingsystemreactionsLOCAbuildingdeflections~~~nicOBESSEPiperuptureHydrodynamicloadsJetimpingementMissileimpactVibrationsHandlingloads(construction,installation,servicing)ThermaltransientsWaterhammerSteamhammerValvetripscoaSoovemetOBE/SSEeffectsThermalgrowthLOCAvromentaRadiationMoistureChemicalsUSARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.9A-13(Cont'd.)B.StressLimitsfor.PlateandShell-TypeSupportsSe'ceLeveBD1.OS1.OS1.2Slesserof1.5Sor0.4su1.5S15S1.8Slesserof2.25Sor0.6Su0'S05S0.5S0ASSKEYoStess123SSuMembranestressBendingstressMaximumtensilestressatthecontactsurfaceofaweldproducingatensileloadinadirectionthroughthethicknessofaplateASMESectionIIIallowablestressASMESectionIIIminimumultimatetensilestrengthUSARRevision83of3November1995 p~

NineMilePointUnit2FSARTABLE3.9A-15REQUIREMENTSFORSAFETYCLASSES2AND3INSTRUMENTANDPNEUMATICTUBINGANDSUPPORTS(TUBINGSIZESUPTOANDINCLUDING1/2INO.D.)*1.DesignloadsandlimitsarecalculatedinaccordancewithASMEIII.2.ProcurementofmaterialisinaccordancewithASMEIIIexceptthatalternateQACategoryImaterialsmaybeusedforsupports.SeeFigure3.9A-1.3.FabricationandinstallationcontrolutilizesQACategoryImaterialmarkingofexclusivepurchaseofQACategoryImaterialswithcontroltopointof,use.4.AutomaticClass2weldingfollowstherequirementsofASMEIIICodeCaseN-127exceptthatCategoryIdocumentationisusedinlieuofN-127andtheAuthorizedNuclearInspector(ANI)involvementasnotedin5.abelow.5.Fabrication,installation,NDE,andhydrostaticinspectionsareasfollows:a~Pressureboundarywelds(1)WeldersandweldingproceduresarequalifiedtoASMESectionIX.(2)1004documentationofcompletionofallconstructionstepsbyContractor'sconstructionpriortoreleasetoContractor'sQAProgram.(3)100%liquidpenetrantcheckofClass2fieldwelds(automaticandmanual)andvisualinspectionofallClass3fieldweldsbyContractorFQCdocumentedbytheContractor'sQAProgram.(4)ContractorFQCin-processinspectiondocumentedbytheContractor'sQAProgram.*Thisprogramalsoappliestosafety-relatedinstrumenttubingforradiationprotectionprocessmonitoringupto1inwhentheprocesspiping,equipment,orcomponentisnotASMESectionIIIconstruction(e.g.,HVACduct).USARRevision81of3November1995 NineMilePointUnit2FSARTABLE3.9A-15(Cont'd.)(5)(6)(7)Pressuretest.tobeperformedinaccordancewithASMESectionZZZpressuretestrequirementsanddocumentviapressuretestreports.SurveillanceinspectionsbytheANIofapproximately10percentofin-processactivities(weldingandhydro)documentedbySISreport.Compressionfittingsareanacceptablesubstituteforweldedfittings.b.CompressionFittingsCompressionfittingswhichmeetASMEmaterialrequirementsandthefollowinginstallationrequirementsshallbeused.ThespecificdesigncriteriausedintheapplicationofcompressionfittingsatUnit2areASMESectionZII,SubsectionsNC/ND,Paragraphs3671.4and3673.2.(2)(3)(4)(5)(6)100-percentvisualinspectionofcompressionfittingmakeupisperformedbyconstructionpriortoreleasetoContractor'sQAProgram.Documentationofthecompletionofallconstructionisrequired.100-percentinspectionoffittingmakeupisperformedbyFQCusingvendor-suppliedtoolsandprocedures.DocumentationoftheFQCinspectionisrequired.PressuretesttobeperformedinaccordancewithASMESectionIZZpressuretestrequirementsanddocumentviapressuretestreports.coSupportsWeldersandweldingproceduresarequalifiedtoCategoryIspecificationrequirementsinvokingASMESectionZXorAWSstandardsasappropriatetothesupporttype.(2)100-percentdocumentationofcompletionofallconstructionstepsbyContractors'sconstructionpriortoreleasetoContractor'sQAProgram.USARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.9A-15(Cont'd.)(3)100-percentContractorFQCvisualinspectionofallfieldweldsusingASME,ANSI,orAWSacceptancecriteriaasrequiredinaccordancewiththeinstallationspecification(exceptundercutnotexceeding1/32-indeepisacceptableinlieuofAWSD1.1requirements).TheseinspectionsshallbedocumentedbytheContractor'sQAProgram.Foralternateweldinspection,refertoSection3.8.4.6.(4)ASTMA515,Gr65,maybeconsideredanAWSDl.lprequalifiedgroupno.1material.6.Visualexaminationacceptanceforpressure-retainingfieldwelds.Allweldsurfacesaresufficientlyfreefromcoarseripples,grooves,overlaps,abruptridges,andvalleystoallowexamination.Thefollowingindicationsareunacceptable:a.Cracks,externalsurface.b.FilletwelddimensionnotmeetingFigureNC/ND4427-1orbuttweldreinforcementgreaterthanspecifiedinFigureNC/ND4427-1.c.Lackoffusiononthesurface.7.UnsatisfactoryconditionsnotedbytheSWECFQConSISreportsareto.beaddressedandresolvedviaexistingEngineeringandQAprocedures.USARRevision83,of3November1995 t'qv NineMilePointUnit2FSAR3.9BMECHANICALSYSTEMSANDCOMPONENTS(GESCOPEOFSUPPLY)3.9B.1SpecialTopicsforMechanicalComponents3.9B.1.1DesignTransientsThissectiondescribesthetransientsthatareusedinthedesignofmajorNSSSASMESectionIII,SafetyClass1coresupport,reactorinternals,andCRDcomponents.Thenumberofcyclesoreventsforeachtransientisincluded.Thesetransientsareincludedinthedesignspecificationsand/orstressreportsforcomponents.TransientsorcombinationsoftransientsareclassifiedwithrespecttothecomponentoperatingconditioncategoriesidentifiedasNormal,Upset,Emergency,Faulted,orTestinginASMESectionIIIasapplicable.(ThefirstfourconditionscorrespondtoServiceLevelsA,B,C,andD,respectively.)3.9B.1.1.1ControlRodDriveTransientsThenormalandtestserviceloadcyclesusedforthedesignandfatigueanalysisforthe40-yrlifeoftheCRDareasfollows:Trs'ent1.Reactorstartup/shutdown2.Vesselpressuretests3.Vesseloverpressure4.ScramtestplusstartupscramsCate~opNormal/upsetNormal/upsetNormal/upsetNormal/upset~colee120130103005.Operationalscrams6.Jogcycles7.Shim/drivecyclesNormal/upsetNormal/upsetNormal/upset30030i0001I000Inadditiontotheabovecycles,thefollowinghavebeenconsideredinthedesignoftheCRD.ansietCatecaCorrCces8.ScramwithinoperativebufferNormal/upset109~ScramwithstuckcontrolbladeNormal/upsetUSARRevision83.9B-1November1995 NineMi'le.PointUnit2FSARrans'et10.Operatingbasisearthquake(OBE)*11.Safeshutdownearthquake(SSE)**12.ControlrodejectionaccidentCatecaCor'.Normal/upsetFaultedFaulted~Ccles10AllASMESectionIII,Class1componentsoftheCRDhavebeenevaluatedaccordingtotherequirementsoftheCode.ThecapacityoftheCRDsystemtowithstandemergencyandfaultedconditionsisverifiedbytestsratherthananalysis.3.9B.1.1.2ControlRodDriveHousingandIn-coreHousingTransientsThenumberoftransients,theircycles,andclassificationasconsideredinthedesignandfatigueanalysisoftheCRDhousingandin-corehousingareasfollows:ransient1.Normalstartupandshutdown~CateorNormal/upset~Ccles1202~3~4~VesselpressuretestsVesseloverpressuretestsInterruptionoffeedwaterflowNormal/upsetNormal/upsetNormal/upset13010805.Scrams6.OBE7.SSE8.Stuckrodscram9.ScramwithinoperativebufferNormal/upsetNormal/upsetFaultedNormal/upsetNormal/upset2001010Thefrequencyofoccurrenceofthistransientwouldindicateemergencycategory.However,forconservatismtheOBEconditionisanalyzedasanupsetcondition.TenpeakOBEcyclesarepostulated.SSEisafaultedcondition;however,inthestressanalysisitwastreatedasemergencywithlowerstresslimits.USARRevision83.9B-2November1995 NineMile,PointUnit,2FSAR3.9B.1'.3HydraulicControlUnitTransientsThetransientsusedinthedesignandanalysisoftheHCUanditscomponentsare:s'e1.Reactorstartup/shutdown2.Scramtests3.Operationalscrams4.Jogcycles5.Scramwithstuckscramdischargevalve6.OBE7.SSE~technoNormal/upsetNormal/upsetNormal/upsetNormal/upsetNormal/upsetNormal/upsetFaulted~Cue12030030030,000103.9B.1.1.4CoreSupportandReactorInternalsTransientsThecycleslistedinTable3.9B-1wereconsideredinthedesignandfatigueanalysisforthereactorinternals.3.9B.1.1.5MainSteamSystemTransientsSeeSection3.9A.1.3.9B.1.1.6RecirculationSystemTransientsThefollowingtransientsareconsideredinthestressanalysisoftherecirculationpiping:ransientcatecaoCrr.'~cclee1.Startup2.Turbinerollandincreasetopower3.Lossoffeedwaterheater4.Partialfeedwaterheaterbypass5.Scrams6.Shutdown7.LossoffeedwaterpumpsisolationvalvesclosedNormalNormalUpsetUpsetUpsetNormalUpset120120107018010USARRevision83.9B-3November1995 NineMilePoint,Unit.2FSARransient8.SingleSRVblowdown9.Hydrotest10.OBECa~ecaCo~rUpsetTestUpset~Ccles130503.9B.1.1.7ReactorAssemblyTransientsThereactorassemblyincludestheRPV,supportskirt,shroudsupport,andshroudplate.ThecycleslistedinTable3.9B-1werespecifiedinthereactorassemblydesignandfatigueanalysis.3.9B.1.1.8MainSteamIsolationValveTransientsThetransientsconsideredintheanalysisoftheMSIVsareasfollows:s'eC~teg~CYg'Lee1~2~Heatupfrom704Fto5524F(100'F/hr)Cooldownfrom5524Fto704F(100F/hr)Normal/upsetNormal/upset3003003~Smalltemperaturechangesof29'F(eitherincreaseordecrease)atanytemperaturebetween704Fand552'FNormal/upset6004~Temperaturechangesof504F(eitherincreaseordecrease)atanytemperaturebetween70Fand552'FNormal/upset2005~Lossoffeedwaterpumpsinwhichthetemperaturejumpsfrom5524Fto5734Fin3sec,dropsdownto5254Fin9min,risesto5734Fin6min,dropsdowntO4854Fin7min,risesto5734Fagainin8min,anddropsdownto4854Fin7min106.Turbinebypass,singlerelieforsafetyvalveblowdowninwhichtheUSARRevision83'B-4November1995 NineMilePointUnit2FSARransiet~cateor~cclestemperaturedropsfrom552'Fto375'Fin10min7~8~9~Reactoroverpressurewithdelayscraminwhichthetemperaturerisesfrom5524Fto5864Fin2sec,andthepressurerisesfrom1050to1375psigimmediatelyfollowedbycoolingtransientinwhichthetemperaturedropsfrom586Fto561'Fin30sec.Thepressuredropsdownto1125psig.Automaticblowdowninwhichthetemperaturechangesfrom552'Fto3754Fin3.3minimmediatelyfollowedbyachangefrom375Fto259Fin19min(3004F/hr)Piperuptureandblowdowninwhichthetemperaturechangesfrom552'Fto259'Fin15secEmergencyEmergencyFaulted10.Installedhydrotestsat1004Fa.1250psigb.1575psigTestingTesting13033.9B.1'.9Safety/ReliefValveTransientsThetransientsconsideredintheanalysisoftheSRVsareasfollows:1~TsietPreoperationalandin-servicetesting(100'F/hr)CatecaCorr.Normal/upset~Ccles1502~3~Startup(1004F/hr)andpressureincrease(0psigto1,000psig)Shutdown(1004F/hr,pressuredecreaseto0psig)Normal/upsetNormal/upset120120USARRevision83.9B-5November1995 NineMilePointUnit2FSAR4~5~s'etScramSystempressureandtemperaturedecayfrom1,000psigand5464Fto35psigand2814Fwithin15secCatecaCorrNormal/upsetEmergency/faulted~Cclee1806~Systemtemperaturechangefrom5464to3754Fwithin3.3minandfrom375to281Fat3004F/hr.Pressurechangefrom1,000to35psig.Emergency/faulted7~8~Systemtemperaturechangefrom546'o3754Fwithin10minandfrom3754to2814Fat1004F/hr.Pressurechangefrom1,000to35psig.Systemtemperaturechangefrom5464to583Fwithin2sec,from583'o538'Fwithin30sec,andfrom5384to4004Fandreturnto546'Fat100'F/hr.Pressurechangefrom1,000to1,350psig,thento240psigandreturnto1,000pslgeEmergency/faultedEmergency/faulted9~Systemtemperaturechanges,greaterthan30F,from561'o500'Fwithin7minandfrom500to4004Fandreturntonormaloperatingtemperatureof5464Fat1004F/hr.Pressurechangefrom1,000to1,180to240psigandreturntonormaloperatingof1,000psig.Emergency/faulted10ParagraphNB-3552ofASMESectionIIIexcludesvarioustransientsandprovidesameansforcombiningthosethatarenotexcluded.Reviewandapprovaloftheequipmentsupplier'scertifiedcalculationsprovidesassuranceofproperaccountingofthespecifiedtransients.USARRevision83.9B-6November1995 NineMilePointUnit2FSARTheSRVsusedforUnit2arethosenormallysuppliedforBWR6projects.Thestress(includingfatigue)analysisofthisSRVmodelisperformedonthebasisofBWR6plantconditions.TheseincludetransientsthatareanticipatedtobemorenumerousandmoreseverethanthetransientsshownaboveforUnit2.TheSRVis,therefore,qualifiedfortheabovetransients.3.9B.1.1.10RecirculationFlowControlValveTransientsThefollowingpressureandtemperaturetransientswereconsideredinthedesignoftherecirculationsystemflowcontrolvalve(FCV):rasient1.Startup(1004F/hrheatuprate704Ftodesigntemperature)ate<~oNormal/upset~cclee3002.Smalltemperaturestepchanges(29'Fstep)Normal/upset6003.50Fstepchanges4~5~SRVblowdowns(singlevalve)5224to3754Fin10min)Safetyvalvetransient(1104ofdesignpressure)Normal/upsetNormal/upsetNormal/upset2006.Installedhydrostatictestsa.1,300psigb.1,670psigTestingTesting13037~Automaticblowdown552'o375'Fin3.3min,followedbyachangefrom375'o281'Fin19minEmergency8.Improperstartofpumpincoldloopoveraperiodof15secEmergency3.9B.1.1.11RecirculationPumpTransientsThefollowingpressuretransientswereconsideredinthedesignoftherecirculationpumps:USARRevision83.9B-7November1995 NineMilePointUnit2FSAR1~2~3~4~5~6.7~8.9.sStartup(1004F/hrheatuprate70'Ftodesigntemperature)Smalltemperaturechanges(29'Fstep)50FstepchangesSRVblowdowns(singlevalve)(5524to3754Fin10min)Safetyvalvetransient(1104ofdesignpressure)Installedhydrotestsa.1,300psigb.1,670psigAutomaticblowdown(552'o,3754Fin3.3minand375'o281'Fin19min)Improperstartofpumpincoldloop(1004to5524Foveraperiodof15sec)Coolingtransient,5524to281'Fin15secggtecLooKNormal/upset,Normal/upsetNormal/upsetNormal/upsetNormal/upsetTestingTestingEmergencyEmergencyFaulted~Ccles30060020013033.9B.1.1.12RecirculationGateValveTransientsThefollowingtransientsareconsideredinthedesignoftherecirculationgatevalves:1~2~3~ansient504to575'o50'Fatarateof100F/hrX294Fbetweenlimitsof50'nd575'F,instantaneousf50'Fbetweenlimitsof50and5464F,instantaneous~ccles3006002004~5.6.552'o375'F,instantaneous546'o281'F,instantaneous130to546FIinstantaneousUSARRevision83.9B-8November1995 NineMilePointUnit2FSAR7~8.anset1104ofdesignpressureat5754F1,300psiat100'Finstalledhydrostatictest~Cclee1309.1,670psiat1004Finstalledhydrostatictest3.9B.1.2ComputerProgramsUsedinAnalysisThefollowingsectionsdiscusscomputerprogramsusedintheanalysisofspecificcomponents.(Computerprogramswerenotusedintheanalysisofallcomponents,thus,notallcomponentsarelisted.)TheNSSSprogramscanbedividedintotwocategories,GEprogramsandvendorprograms.EPrsVerificationofthefollowingGEprogramshasbeenperformedinaccordancewiththerequirementsof10CFR50AppendixB.Evidenceoftheverificationofinput,output,andmethodologyisdocumentedinGEDesignRecordFiles.SEISMMASSSNAP(MULTISHELL)HEATERANSI7PISYSPDAEZPYPSAP4GFTFLG01ANSYSPOSUMBILRDDYSEASPECACOSMOS/MVedooamsVerificationofthefollowingvendor(CB&I)programsisassuredbycontractualrequirementsbetweenGEandthevendor.In'ccordancewiththerequirements,theQAprocedureoftheseproprietaryprogramsusedinthedesignofN-stampedequipmentisinfullcompliancewith10CFR50AppendixB.711GENOZZ948NAPALM1027846781KALNINS979ASFAST7-66TEMAPR7-67PRINCESS9-28TGRV962E0962A984992GASP1037DUNHAMIS13351606&1657HAP163595316661684E1702A955MESHPLOT10281038USARRevision83.9B-9November1995 NineMilePointUnit2FSAR3.9B.1.2.1ReactorPressureVesselandInternalsectsseesseCB&oa7--GNOZTheGENOZZcomputerprogramisusedtoproportionbarrelanddoubletaper-typenozzlestocomplywiththespecificationsofASMESectionIIIandcontractdocuments.Theprogramwilleitherdesignsuchaconfigurationoranalyzetheconfigurationinputintoit.Iftheinputconfigurationdoesnotcomplywiththespecifications,theprogrammodifiesthedesignandredesignsittoyieldanacceptableresult.CB&P-48ThebasisfortheprogramNAPALM(NozzleAnalysisProgram-AllLoadsMechanical)istoanalyzenozzlesformechanicalloadsandfindthemaximumstressintensityandlocation.Theprogramanalyzesatspecifiedlocationsfromthepointofapplicationofthemechanicalloads.Ateachlocation,theprogramcalculatesthemaximumstressintensityforboththeinsideandoutsidesurfacesofthenozzle,anditsangularlocationaroundthecircumferenceofthenozzlefromthereferencelocation.Theprincipalstressesarealsoprinted.Thestressesresultingfromeachcomponentofloading(bending,axial,shear,andtorsion)areprinted,aswellastheloadsthatcausedthesestresses.CB&IPo027ThisprogramisacomputerizedversionoftheanalysismethodcontainedintheWeldingResearchCouncilBulletinNo.107,August1965.Partoftheprogramprovidesforthedeterminationoftheshellstressintensities(S)ateachoffourcardinalpointsatboththeupperandlowershellplatesurfaces(ordinarilyconsideredoutsideandinsidesurfaces)aroundtheperimeterofaloadedattachmentonacylindricalorsphericalvessel.WiththedeterminationofeachS,thecomponentsofthatS(twonormalstresses,oandcr,,andoneshearstressr)arealsodetermined.Thisprogramprovidesthesameinformationasthemanualcalculation,andtheinputdataareessentiallythegeometry.ofthevesselandattachment.CB&roram846ThisprogramcomputestherequiredthicknessofahemisphericalheadwithalargenumberofcircularparallelpenetrationsbymeansoftheareareplacementmethodinaccordancewiththeASMESectionIII.Incaseswherethepenetrationhasacounterbore,thethicknessisdeterminedsothatthecounterboredoesnotpenetratetheoutsidesurfaceofthehead.CB&Iora781-LSThisprogramisathinelasticshellprogramforshellsofrevolution.ThebasicmethodofanalysiswasdevelopedandpublishedbyDr.A.KalninsofLehighUniversity+.ExtensiverevisionsandimprovementshavebeenmadebyDr.J.EndicotttoyieldtheCB&Iversionofthisprogram.Theprogramisusedtoestablishtheshellinfluencecoefficientandtoperformdetailstressanalysisofthevessel.USARRevision83.9B-10November1995 NineMilePointUnit2FSARThestressesandthedeformationsofthevesselcanbecomputedforanycombinationofthefollowingaxisymmetricloading:1.Preloadcondition.2.Internalpressure.3.Thermalload.TheASFASTprogramperformsstressanalysisofaxisymmetric,boltedclosureflangesbetweenheadandcylindricalshell.C&oa7-66-EMAPThisprogramreducesanyarbitrarytemperaturegradientthroughthewallthicknesstoanequivalentlineargradient.Theresultingequivalentgradienthasthesameaveragetemperatureandthesametemperature-momentasthegiventemperaturedistribution.Inputconsistsofplatethicknessandactualtemperaturedistribution.Outputcontainsaveragetemperatureandtotalgradientthroughthewallthickness.TheprogramiswritteninFORTRANIVlanguage.&a7-6-CSSThePRINCESSprogramcalculatesthemaximumalternatingstressamplitudesfromaseriesofstressvaluesbythemethodinASMESectionIII.CB&oam9-28-TGRVTheTGRVprogramisusedtocalculatetemperaturedistributionsinstructuresorvessels.Althoughitisprimarilyaprogramforsolvingtheheatconductionequations,someprovisionshavebeenmadeforincludingradiationandconvectioneffectsatthesurfacesofthevessel.TheTGRVprogramisagreatlymodifiedversionoftheTIGERheattransferprogramwrittenabout1958atKnollsAtomicPowerLaboratorybyA.P.Bray.TherehavebeenmanyversionsofTIGERinexistence.includingTIGERII,TIGERIIB,TIGERIV,andTIGERV,inadditiontoTGRV.Theprogramusesanelectricalnetworkanalogytoobtainthetemperaturedistributionofanygivensystemasafunctionoftime.Thefinitedifferencerepresentationofthethree-dimensionalequationsofheattransferarerepeatedlysolvedforsmalltimeincrementsandcontinuallysummed.Linearmathematicsareusedtosolvethemeshnetworkforeverytimeinterval.Includedintheanalysisarethethreebasicformsofheattransfer,i.e.,conduction,radiation,andconvection,aswellasinternalheatgeneration.Givenanyodd-shapedstructure,whichisrepresentedbyathree-dimensionalfield,itsgeometryandphysicalproperties,boundaryconditions,andinternalheatgenerationrates,TGRVcalculatesandgivesasoutputthesteady-stateortransienttemperaturedistributionsinthestructureasafunctionoftime.USARRevision83.9B-11November1995 NineMilePointUnit2FSARB&ora6-E0962ProgramE0962Aisoneofagroupofprograms(E0953A,E1606A,E0962A,E0992N,E1037N,andE0984N)usedtogethertodeterminethetemperaturedistributionandstressesinpressurevesselcomponentsbythefiniteelementmethod.ProgramE0962Aisprimarilyaplottingprogram.UsingthenodaltemperaturescalculatedbyprogramE1606AorprogramE0928A,andthenodeandelementcardsforthefiniteelementmodel,itcalculatesandplotslinesofconstanttemperature(isotherms).Theseisothermplotsareusedaspartofthestressreporttopresenttheresultsofthethermalanalysis.Theyarealsoveryusefulindeterminingatwhichpointsintimethethermalstressesshouldbedetermined.Inadditiontoitsplottingcapability,theprogramcandeterminethetemperaturesofsomeofthenodalpointsbyinterpolation.ThisfeatureoftheprogramisintendedprimarilyforusewiththecompatibleTGRVandfiniteelementmodelsgeneratedbyprogramE0953A.CB&o84Program984isusedtocalculatethestressintensityofthestressdifferences,onacomponentlevel,betweentwodifferentstressconditions.Thecalculationofthestressintensityofstresscomponentdifferences(therangeofstressintensity)isrequiredbyASMESectionIII.CB&ora92-GASPTheGASPprogram,originatedbyProf.E.L.WilsonoftheUniversityofCaliforniaatBerkeley,usesthefiniteelementmethodtodeterminethestressesanddisplacementsofplaneoraxisymmetricstructuresofarbitrarygeometryandiswritteninFORTRANIV+.Thestructuresmayhavearbitrarygeometryandlinearornonlinearmaterialproperties.Theloadingsmaybethermal,mechanical,accelerational,oracombinationofthese.Thestructuretobeanalyzedisbrokenupintoafinitenumberofdiscreteelementsorfiniteelementswhichareinterconnectedatafinitenumberofnodalpointsornodes.Theactualloadsonthestructurearesimulatedbystaticallyequivalentloadsactingattheappropriatenodes.Thebasicinputtotheprogramconsistsofthegeometryofthestressmodelandtheboundaryconditions.Theprogramthengivesthestresscomponentsatthecenterofeachelementandthedisplacementsatthenodes,consistentwiththeprescribedboundaryconditions.CB&I03-D'SDUNHAM'Sprogramisafiniteringelementstressanalysisprogram.ItdeterminesthestressesanddisplacementsofaxisymmetricstructuresofarbitrarygeometrysubjectedtoeitheraxisymmetricloadsornonaxisymmetricloadsrepresentedbyFourierseries.ThisprogramissimilartotheGASPprogram(CB&I992).ThemajordifferencesarethatDUNHAM'Scanhandlenonaxisymmetricloads(whichrequiresthateachnodehave3degreesoffreedom)andthematerialpropertiesforUSARRevision83.9B-12November1995 NineMilePointUnit2FSARDUNHAM'Smustbeconstant.AsinGASP,theloadingsmaybethermal,mechanical,andaccelerational.CB&IProram1335Toobtainstressesintheshroudsupport,thebaffleplatemustbe-consideredasacontinuouscircularplate.ThisprogrammakesthismodificationandallowsthebaffleplatetobeincludedinCB&IProgram781astwoisotropicpartsandanorthotropicportionatthemiddle(wherethediffuserholesarelocated).C&1067-ATheHAPprogramisanaxisymmetricnonlinearheatanalysisprogram.Itisafiniteelementprogramandisusedtodeterminenodaltemperaturesinatwo-dimensionaloraxisymmetricbodysubjectedtotransientdisturbances.Programs1606and1657areidenticalexceptthat1606hasalargerstorageareaallocatedandcanthusbeusedtosolvelargerproblems.ThemodelforProgram1606iscompatiblewithCB&IstressPrograms992and1037.CB&Iora1635Program1635offersthreefeaturestoaidthestressanalystinpreparingastressreport:1.GeneratespunchedcardinputforProgram7-67(PRINCESS)fromthestressoutputofProgram781(KALNINS).2.Writesastresstableinaformatthatcanbeincorporatedintoafinalstressreport.3.Hastheoptiontoremovethrough-wallthermalbendingstressandreporttheseresultsinastresstablesimilartotheonementionedinItem2.CB&IProram953Theprogramisageneralpurposeprogramwhichdoesthefollowing:1.Preparesinputcardsforthethermalmodel.2.Preparesthenodeandelementcardsforthefiniteelementmodel.3~SetsupthemodelinsuchawaythatthenodalpointsintheTGRVmodelcorrespondtopointsinthefiniteelementmodel.Theyhavethesamenumbersothatthereisnopossibilityofconfusionintransferringtemperaturedatafromoneprogramtotheother.CB&IProram1666Thisprogramisprimarilywrittentocalculatethetemperaturedifferencesatselectedcriticalsectionsofthenuclearreactorvesselcomponentsatdifferenttimepointsofthermaltransientsduringitslifeofoperationandtolistthemallinatabularform.Sincethereisnoinvolvedcalculationapplicableparticularlytonuclearcomponents,thisprogramcanbeusedwithanyotherkindofmodelthatissubjectedtothermalUSARRevision83.9B-13November1995 NineMilePointUnit2FSARtransientsoveraperiodoftime.Thisprogramhelpsascertainthetimepointsinthermaltransientswhenthethermalstressesmaybecritical.CB&IProram1684Thisprogram,anexpansionofProgram984,iswrittentoexpeditethefatigueanalysisofnuclearreactorcomponentsasrequiredbyASMESectionIII.Thefeaturesofthisprogramallowtheusertoeasilyperformthecompletesecondarystressandfatigueevaluationincludingpartialfatigueusagecalculationofacomponentinonerun.Anadditionaloptionallowstheusertocompletelydocumenttheinputstressvaluesinaformatsuitableforastressanalysisreport.Theprogramiswrittentoallowforaminimumamountofdatahandlingbytheuseroncetheinitialdeckisestablished.CB&roraE102Thisprogramevaluatesthestress-intensityfactorK,duetopressure,temperature,andmechanicalloadstressesforanumberofdifferentstressconditions(times)andatanumberofdifferentlocations(elements).Itthencalculatesthemaximumreferencetemperaturenilductilitytransition(RT~~)theactualmaterialcanhavebasedona1/4TflawsizeandcomparesitwiththeorderedRT~~.IftheorderedRT~~islargerthanthemaximumRT~Y,themaximumallowableflawsizeiscalculated.TherulesofASMECodeAppendixGareusedexceptthatWeldingResearchCouncil(WRC)175canbeusedtocalculateK~cluetopressureinanozzle-to-shelljunction.Foramorethoroughdescriptionofthefractureproblem,seeWRCBulletinNo.175"'.CB&IProram955-MESHPLOTThisprogramplotsinputdatausedforfiniteelementanalysis.Theprogramplotsthefiniteelementmeshinoneofthreeways:withoutlabels,withnodelabels,orwithelementlabels.Theoutputconsistsofalistingandaplot.Thelistinggivesallnodepointswiththeircoordinatesandallelementswiththeirnodepoints.Theplotisafiniteelementmodelwiththerequestedlabels.C&0Thisprogramcalculatesthenecessaryformfactorsforthenodesofthemodelthatsimulatesheattransferbyradiation.Inputsareshapeanddimensionsofthehead-to-skirtknucklejunction.Theprogramislimitedtojunctionswithatoroidalknucklepart.&oa1038ThisprogramcalculatestheloadsrequiredtosatisfythecompatibilitybetweentheshroudbaffleplateandthejetpumpadaptorsforaGEBWRvessel.VesseIteralsuelSuotLoadsProam-SEISMSEISMcomputestheverticalfuelsupportloadsusingthecomponentelementmethodsindynamics<".USARRevision83.9B-14November1995 NineMilePointUnit2FSARtesThefollowingprogramsarealsousedintheanalysisofcoresupportstructuresandothersafety-relatedreactorinternals:MASS,SNAP(MULTISHELL),andHEATER.TheseprogramsaredescribedindetailinSection4.1.3.9B.1.2.2Pipinginalsisrora-PISYSPISYSisaspecializedcomputercodeforpipingloadcalculations.Itutilizesselectedstiffnessmatricesrepresentingstandardpipingcomponents,whichareassembledtoformafiniteelementmodelofapipingsystem.Thetechniquereliesondividingthepipemodelintoseveraldiscretesubstructures,calledpipeelements,whichareconnectedtoeachothervianodescalledpipejoints.Itisthroughthesejointsthatthemodelinteractswiththeenvironment,andloadingofthestructurebecomespossible.PISYSisbasedonlinearclassicalelasticityinwhichtheresultantdeformationandstressesareproportionaltotheloading,andthesuperpositionofloadingisvalid.PISYShasafullrangeofstaticanddynamicanalysisoptionsthatincludedistributedweight,thermalexpansion,differentialsupportmotionmodalextraction,responsespectra,andtime-historyanalysisbymodalordirectintegration.ThePISYSprogramhasbeenbenchmarkedagainstfiveNRCpipingmodelsfortheoption-of-response-spectrumanalysis,andtheresultsaredocumentedinareporttotheNRC,NEDO-24210+.ComonentAnalsis-ANSI7TheANSI7programdeterminesstressandaccumulativeusagefactorsinaccordancewithSubarticleNB-3600ofASMESectionIII.TheprogramwaswrittentoperformstressanalysisinaccordancewiththeASMEsampleproblem,andhasbeenverifiedbyreproducingtheresultsofthesampleproblemanalysis.SUPERIPEComuterProraTheSUPERPIPEcomputerprogramisdescribedinAppendix3B.iinaicAalsisProram-PDThepipewhipanalysiswasperformedusingthePDAprogramtodeterminetheresponseofapipesubjectedtothethrustforceoccurringafterapipebreak.Theprogramtreatsthesituationintermsofagenericpipebreakconfiguration,whichinvolvesastraight,uniformpipefixedatoneendandsubjectedtoatime-dependentthrustforceattheotherend.Atypicalrestraintusedtoreducetheresultingdeformationisalsoincludedatalocationbetweenthetwoends.Nonlinearandtime-dependentstress-strainrelationsareusedtomodelthepipeandtherestraint.Similartothepopularelastichingeconcept,bendingofthepipeisassumedtooccuronlyatthefixedendandatthelocationsupportedbytherestraint.Sheardeformationisneglected.Thepipebendingmoment-deflection(orrotation)relationusedfortheselocationsisobtainedfromastaticnonlinearcantileverbeamanalysis.USARRevision83.9B-15November1995 NineMilePointUnit2FSARUsingmoment-rotationrelations,nonlinearequationsofmotionareformulatedusingenergyconsiderationsandtheequationsarenumericallyintegratedinsmalltimestepstoyieldthetime-historyofthepipemotion.asisProra-EZYPEZPYPlinkstheANSI-7andSAPprograms.TheEZPYPprogramcanbeusedtorunseveralSAPcasesbymakinguser-specifiedchangestoabasicSAPpipemodel.BycontrollingfilesandSAPruns,theEZPYPprogramgivestheanalystthecapabilitytoperformacompletepipinganalysisinonecomputerrun.3.9B.1.2.3RecirculationPumpTheANSYScodeisusedintheanalysisoftherecirculationpumpcasingforvariousthermalandmechanicalloadsduringplantoperatingandpostulatedconditions.Ingeneral,thefiniteelementtechniquesareusedtosolvetemperaturedistributioninheattransfertransientproblems,andtoperformstressanalysisforvariousthermalandmechanicalloadingsbyusingthesamefiniteelementmodelrepresentingthepumpbody.Theoutputoftheseprogramsisintheformoftemperatureprofiles,deflections,andstressesatthenodalpointsofthefiniteelementidealizationofthepumpstructure.3.9B.1.2.4EmergencyCoreCoolingSystemPumpsandMotorsStructuraalsisPam-SAP4GSAP4GisusedtoanalyzethestructuralandfunctionalintegrityoftheECCSpumpandmotorsystems.Thisisageneralstructuralanalysisprogramforstaticanddynamicanalysisoflinearelasticcomplexstructures.Thefiniteelementdisplacementmethodisusedtosolvethedisplacementsandstressesofeachelementofthestructure.Thestructurecanbecomposedofanunlimitednumberofthree-dimensionaltruss,beam,plate,shell,solid,platestrain-planestressandspringelementsthatareaxisymmetric.Theprogramcantreatthermalandvariousformsofmechanicalloading.Thedynamic'nalysisincludesmodesuperposition,time-history,andresponsespectrumanalysis.Seismicloadingandtime-dependentpressurecanbetreated.Theprogramisversatileandefficientinanalyzinglargeandcomplexstructuralsystems.Theoutputcontainsdisplacementsofeachnodalpointaswellasstressesatthesurfaceofeachelement.etsaeectios-FLGOTheflangejointsconnectingthepumpbowlcastingsareanalyzedusingFTFLG01.ThisprogramusesthelocalforcesandmomentsdeterminedbySAP4GtoperformflatflangecalculationsinaccordancewiththerulessetforthinAppendixIIandASMEBoilerandPressureVesselCodeSectionIII.StructuralnalsisofDischareHead-ANSYSANSYSisusedtoanalyzethepumpdischargeheadflangeandboltingtakingintoUSARRevision83.9B-16November1995 NineMilePointUnit2FSARaccountthepryingactiondevelopedbytheflatfacecontactsurface.TheprogramisdescribedindetailinSection4.1.oess'0POSUMisacomputercodedesignedtoprocessSAP-generatedbeamelementdataforpumporheatexchangermodels.The.purposeistodeterminetheloadcombinationthatwouldproducethemaximumstressinaselectedbeamelement.ItisintendedtobeusedonRHRheatexchangerswithfournozzlesorECCSpumpswithtwonozzles.3.9B.1.2.5RHRHeatExchangerstutuas'soa-SSAP4GisusedtoevaluatethestructuralandfunctionalintegrityoftheRHRheatexchangers.AdescriptionofthisprogramisprovidedinSection3.9B.1.2.4.CcuatooSetachmentParametersadCoeficietsBILDBILRDisusedtocalculatetheshellattachmentparametersandcoefficientsusedinthestressanalysisofthesupport-to-shelljunction.Themethod,inaccordancewithWRCBulletinNo.107,isimplementedinBILRDtocalculatelocalmembranestressduetothesupportreactionloadsontheheatexchangershell.BeernetDatrocess'OSUMPOSUMisusedtoprocessSAP-generatedbeamelementdata.ThedescriptionofthisprogramisprovidedinSection3.9B.1.2.4.3.9B.1.2.6DynamicLoadAnalysisDamicAalsisProram-DSEADYSEAsimulatesabeammodelintheannuluspressurizationdynamicanalysis.AdescriptionofDYSEAisprovidedinSection4.1.DYSEAemploysapreprocessorprogramnamedGEAPL.GEAPLconvertspressuretime-historiesintotime-varyingloadsandforcingfunctionsforDYSEA.Theoverallresultantforcesandmomentstime-historiesatspecifiedpointsofresolutioncanalsobeobtainedfromGEAPL.ccelertoResoseSectrumProra-SPECSPECAgeneratesaccelerationresponsespectraforanarbitraryinputtime-historyofpiece-wiselinearaccelerations,i.e.,tocomputemaximumaccelerationresponsesforaseriesofsingledegree-of-freedomsystemssubjectedtothesameinput.Itcanacceptaccelerationtime-historiesfromarandomfile.Italsocangeneratethebroadened/envelopedspectrawhenthespectralpointsaregeneratedequallyspacedonalogarithmicscaleaxisofperiod/frequency.ThisprogramisalsousedinseismicandSRVtransientanalyses.3.9B.1.3ExperimentalStressAnalysisThefollowingsectionslistthoseNSSScomponentsforwhichexperimentalstressanalysiswasusedandprovideadiscussionoftheanalysis.USARRevision83'B-17November1995 NineMilePointUnit2FSAR3.9B.1.3.1ExperimentalStressAnalysisofPipingComponentsThefollowingcomponentshavebeentestedtoverifytheirdesignadequacy:1.Snubbers2.PipewhiprestraintsDescriptionsofthesnubbersandpipewhiprestrainttestsarecontainedinSections3.9B.3.4and3.6B.2.2.2,respectively.3.9B.1.3.2OrificedFuelSupport,VerticalandHorizontalLoadTestsAseriesofhorizontalandverticalloadtestswereperformedontheorificedfuelsupport(OFS)inordertoverifythedesign.ResultsfromthesetestsindicatethattheseismicandhydrodynamicloadingoftheOFSarebelowallowableloadlimits,withasafetymarginofatleast2.0fornormal,upsetandfaultedconditions.(Theallowableloadlimitswerearrivedatbyapplyinga0.75qualityfactortotheASMECodeallowablesof0.44xtestloadforupsetand0.80xtestloadforfaultedcondition.)3.9B.1.4ConsiderationsfortheEvaluationofFaultedConditionsEachitemofCategoryIequipmentisevaluatedforfaultedloadingconditions.Inallcases,calculatedstressesarewithintheallowablelimits.Thissectionprovidesexamplesofthetreatmentoffaultedconditionsforthemajorcomponentsonacomponent-by-componentbasis.AdditionaldiscussionoffaultedanalysisisfoundinSections3.9B.3and3.9B.5,andTable3.9B-2.Sections3.9B.2.2and3.7Bdiscussthetreatmentofdynamicloadsresultingfromthepostulatedfaultedcondition.Section3.9B.2.5discussesthedynamicanalysisofloadsonreactorinternalsresultingfromblowdown.Deformationsunderfaultedconditionshavebeenevaluatedincriticalareas,andnocaseshavebeenidentifiedwheredesignlimits,suchasclearancelimits,areexceeded.3.9B.1.4.1ControlRodDriveSystemComponentsContor'vesThemajorCRDcomponentsthathavebeenanalyzedforthefaultedconditionsaretheringflange,mainflange,andindicatortube.ThemaximumstressesforthesecomponentsandforvariousplantoperatingconditionsincludingthefaultedconditionaregiveninTable3.9B-2a.USARRevision83.9B-18November1995 NineMilePointUnit2FSARTheASMESectionIIICodecomponentsoftheCRDhavebeenanalyzedforconditionsinSection3.9B.1.1.1.Theloadsandstressesarewithintheelasticlimitsofthematerial.ThedesignadequacyofnoncodecomponentsoftheCRDhasbeenverifiedbyextensivetestingprogramsonboth(Codeandnon-Code)componentparts,speciallyinstrumentedprototypedrives,andproductiondrives.ThetestinghasincludedpostulatedabnormaleventsaswellastheservicelifecyclelistedinSection3.9B.1.1.1.HdraulicControlUnitTheseismicandhydrodynamicloadsadequacyoftheHCUisdemonstratedbytests.Section,3.9B.2.2.2discussesthedynamicqualificationoftheHCU.3.9B.1.4.2StandardReactorInternalComponentsCotroodGu'ubeThemaximumcalculatedstressonthecontrolrodguidetubeoccursinitsbaseduringthefaultedcondition.Thefaultedlimitisthelesserof2.4Sor0.7SatthedesigntemperatureinaccordancewithASMESectionIII,TableF1322-1;accordingtoASMESectionIII,TableI-1.2,S=57,500psiandS=16,000psiat575F.TheanalysisandlimitingstressesforvariousplantoperatingconditionsaregiveninTable3.9B-2b.coousiThemaximumcalculatedstressonthein-corehousingoccursattheoutersurfaceofthevesselpenetrationduringthefaultedcondition.Theallowablestressfortheelasticanalysisusedis2.4S=40,000psi.TheanalysisforvariousoperatingconditionsissummarizedinTable3.9B-2cwhichshowsthatthecalculatedstressesarewithintheallowables.~JetPumTheelasticanalysisforthejetpumpfaultedconditionsshowsthatthemaximumstressisduetoimpulseloadingofthediffuserduringapiperuptureandblowdown.Themaximumallowableforthiscondition,inaccordancewithASMESectionIIIAppendixFis3.6Sor60,000psi.Table3.9B-2dsummarizestheresultsofthestressanalysis.locationisboundedbytheallowablestresswhichis3.6S.Table3.9B-2esummarizesthecriteria,loadingconditions,thecalculatedandallowablestresses.USARRevision83'B-19November1995 NineMilePointUnit2FSAROrf'eSuorOFSisanalyzedforthefaultedcondition.TheanalysisandtestingaredescribedinSection3.9B.1.3.2.ResultsoftheanalysisareprovidedinTable3.9B-2f.CRDusTheCRDhousingisanalyzedforthefaultedcondition,consideringSSEandhydrodynamicloads.Table3.9B-2gshowsthatthecalculatedstressvaluesforthehighlystressedareasoftheCRDhousingarewithintheallowablelimits.3.9B.1.4.3ReactorPressureVesselAssemblyForthefaultedcondition,theRPVandtheshroudsupportwereevaluatedusingelasticanalysismethods.Forthesupportskirtandshroudsupport,anelasticanalysiswasperformed,andbucklingwasevaluatedforthecompressiveload.ThesupportskirtisdesignedincompliancewithASMEIIIrequirementsfortheClass1pressure-retainingportionofthevessel.AgenericBWR4/5studywasconductedontheLimerick1and2cylindricalsupportskirt,whichhasthesmallestratioofthicknesstoradius.Thestudyexaminedtheskirtbucklingunderaxialcompression,hoopstress,andtransverseshear(Section3.9.6-13)andshowedthat,ineachcase,thecriticalbucklingstresswasmuchgreaterthantheyieldstress.Sincethisstudyshowedthatinelasticstabilitylimitstheskirtintegrity,thepermissiblecompressiveloadislimitedto90percentoftheloadwhichproducesyieldstress,dividedbyasafetyfactorof1.125forfaultedconditionstoaccountfortheeffectsoffabricationoranyeccentricity.Forfaultedconditions,theRPVsupportskirtdesigncanmeettheallowablelimitoftwo-thirdsofthecriticalbucklingstressinaccordancewithASMEBoilerandPressureVesselCode,SectionIII,paragraphF-1370(c).AnanalysisoftheRPVsupportskirtshowsthatthedesignhasthecapabilitytomeetthisallowablestressattemperature.Table3.9B-2hliststhecalculatedandallowablestressesforthevariousloadcombinations.3.9B.1.4.4CoreSupportStructureThecoresupportstructureisevaluatedforthefaultedcondition.ThebasesfordeterminingthefaultedloadsduetoseismicandhydrodynamiceventsarediscussedinSections3.7BUSARRevision83.9B-20November1995 NineMilePointUnit2FSARand3.9B.5,respectively.ThecalculatedstressesandallowablesaresummarizedinTable3.9B-2i.3.9B.1.4.5RecirculationGate,Safety/ReliefValves,andMainSteamIsolationValves,tTables3.9B-2),3.9B-2k,and3.9B-2zprovideasummaryoftheanalysisoftheSRV,recirculationgatevalve,andMSIV,respectively.Standarddesignrules,asdefinedinASMESectionIII;areusedintheanalysisofpressureboundarycomponentsofCategoryIvalves.Conventional,elasticstressanalysisisusedtoevaluatecomponentsnotdefinedintheCode.TheCodeallowablestressesareappliedtodetermineacceptabilityofthestructureunderapplicableloadingconditionsincludingthefaultedcondition.3.9B.1.4.6RecirculationSystemFlowControlValveTherecirculationsystemFCVisanalyzedforfaultedconditionsusingtheelasticanalysismethodsfromASMESectionIII.TheanalysisissummarizedinTable3.9B-2l.3.9B.1.4.7RecirculationPipingForrecirculationsystempiping,elasticanalysismethodsareusedforevaluatingfaultedloadingconditions.TheequivalentallowablestressesusingelastictechniquesareobtainedfromtheASMESectionIII,AppendixF,andtheseareaboveelasticlimits.AdditionalinformationontherecirculationpipingisinTable3.9B-2m.3.9B.1.4.8NuclearSteamSupplySystemPumps,HeatExchanger,andTurbineTherecirculation,ECCS,RCIC,andSLCpumps,RHRheatexchangers,andRCICturbinehavebeenanalyzedforthefaultedloadingconditionsidentifiedinSection3.9B.1.1.Inallcases,stresseswerewithintheelasticlimits.Theanalyticalmethods,stresslimits,andallowablestressesaresummarizedinTable3.9B-2intherespectiveequipmenttable.3.9B.1.4.9ControlRodDriveHousingSupportsThecalculatedstressesandtheallowablestresslimitsforfaultedconditionsfortheCRDhousingsupportsareshowninTable3.9B-2y.3.9B.1.4.10FuelStorageRacksExamplesofthecalculatedstressesandstresslimitsforthefaultedconditionsforthenewfuelstorageracksareshowninTable3.9B-2n.USARRevision83.9B-21November1995 NineMilePointUnit2FSAR3.9B.1.4.11FuelAssembly(IncludingChannels)GEBWRfuelassemblydesignbases,analyticalmethods,andevaluationresults,includingthoseapplicabletothefaultedconditions,arecontainedinNEDE-24011<",NEDE-24011-US+,andNEDE-21175-3-P'@.TheaccelerationprofilesandfuelliftgaparesummarizedinTable3.9B-2o.3.9B.1.4.12RefuelingEquipmentRefuelingequipmentandservicingequipmentthatareimportanttosafetyareclassifiedasessentialcomponentsinaccordancewiththerequirementsof10CFR50AppendixA.ThisequipmentandotherequipmentwhosefailurewoulddegradeanessentialcomponentaredefinedinSection3.9B.1andareclassifiedasCategoryI.Thesecomponentsaresubjectedtoanelasticdynamicfiniteelementanalysistogenerateloadings.Thisanalysisutilizesappropriateseismicfloorresponsespectraandcombinesloadsatfrequenciesupto33Hzforseismicandupto80Hzforhydrodynamicloadsinthreedirections.Imposedstressesaregeneratedandcombinedfornormal,upset,andfaultedconditions.Stressesarecompared,dependingonthespecificsafetyclassoftheequipment,tothoseallowedbyIndustrialCodes,ASME,ANSI,AISC,orIndustrialStandardsallowables.Thecalculatedstressesandallowablelimitsforthefaultedconditionforthefuelstoragerack,fuelpreparationmachine,andrefuelingplatformaredocumentedinTable3.9B-2n.3.9B.2DynamicTestingandAnalysis3.9B.2.1PipingVibration,ThermalExpansion,andDynamicEffectsThetestprogramisdividedintothreephases:pipingvibration,thermalexpansion,anddynamiceffects.3.9B.2.1.lPipingVibrationPreperat'oalandStartu'brationTestnofecirculatio~Pi~inThepurposeofthepreoperationalvibrationtestphaseistoverifythatoperatingvibrationsintherecirculationpipingarewithinacceptablelimits.Thisphaseofthetestusesvisualobservationtosupplementremotemeasurements.If,duringsteady-stateoperation,visualobservationindicatesthatvibrationissignificant,measurementsaremadewithahand-heldvibrograph.Visualobservationsandmanualandremotemeasurementsaremadeduringthefollowingsteady-stateconditions:1.Recirculationpumpsatminimumflow.USARRevision83.9B-22November1995 NineMilePointUnit2FSAR2.Recirculationpumpsat50percentofratedflow.3.Recirculationpumpsat75percentofratedflow.4.Recirculationpumpsat100percentofratedflow.5.RHRsuctionpipingat100percentofratedflowintheshutdowncoolingmode.eoeatoalVibratioTestiofSmattcedPiinDuringvisualobservationoftestconditions1through5,specialattentionwillbegiventosmallattachedpipingandinstrumentconnectionstoensurethattheyarenotinresonancewiththerecirculationpumpmotorsorflow-inducedvibrations.Iftheoperatingvibrationsacceptancecriteriaarenotmet,correctiveactionsuchasmodificationofsupportswillbeundertaken.0eratiTransientLoadsonRecirculationPiinThepurposeoftheoperatingtransienttestphaseistoverifythatpipestressesarewithincodelimits.Theamplitudeofdisplacementsandnumberofcyclespertransientoftherecirculationpipingaremeasuredandthedisplacementscomparedwithacceptancecriteria.ThedeflectionsarecorrelatedwithstressestoverifythatthepipestressesremainwithinCodelimits.Remotevibrationanddeflectionmeasurementsaretakenduringthefollowingtransients:1.Recirculationpumpstarts.2.Recirculationpumptripat100percentofratedflow.3.Turbinestopvalveclosureat100percentpower.4.ManualdischargeofeachSRVat1,000psigandatplannedtransientteststhatresultinSRVdischarge.3.9B.2.1.2ThermalExpansionTestingofRecirculationPipingAthermalexpansion,preoperationalandstartuptestingprogram,performedthroughtheuseofpotentiometersensors,hasbeenestablishedtoverifythatnormalthermalmovementoccursinthepipingsystems.Themainpurposeofthisprogramistoensurethefollowing:1~2.Thepipingsystemduringsystemheatupandcooldownisfreetoexpand,contract,andmovewithoutunplannedobstructionorrestraintinthex,y,andzdirections.ThepipingsystemisworkinginamannerconsistentwiththeassumptionoftheNSSSstressanalysis.USARRevision83.9B-23November1995 NineMilePointUnit2FSAR3.Thereisadequateagreementbetweencalculatedvaluesofdisplacementsandmeasuredvalueofdisplacement.4.ThereisconsistencyandrepeatabilityinthermaldisplacementsduringheatupandcooldownoftheNSSSsystems.Limitsofthermalexpansiondisplacementsareestablishedpriortothestartofpipingtestingtowhichtheactualmeasureddisplacementsarecompared,todetermineacceptabilityoftheactualmotion.Ifthemeasureddisplacementdoesnot:varyfromtheacceptancelimitsvaluesbymorethanthespecifiedtolerances,thepipingsystemisrespondinginamannerconsistentwithpredictionsandis,therefore,acceptable.TwolevelsofdisplacementlimitsareestablishedtocheckthesystemsasexplainedinSection3.9B.2.1.4.3.9B.2.1.3DynamicEffectsTestingofRecirculationPipingToverifythatsnubbersareadequatelyperformingtheirintendedfunctionduringplantoperation,aprogramfordynamictesting,asapartofthenormalstartupoperationtesting,isplanned.Themainpurposeofthisprogramistoensurethefollowing:1.Thevibrationlevelsfromthevariousdynamicloadingsduringtransientandsteady-stateconditionsarebelowthepredeterminedacceptablelimits.2.Long-term.fatiguefailuredoesnotoccurduetounderestimatingthedynamiceffectscausedbycyclicloadingduringplanttransientoperations.ThisdynamictestingistoaccountfortheacousticwaveduetotheSRVlifts(RV1),SRVloadresultingfromairclearing(RV2),andturbinestopvalveclosure(TSVC)load.ThemaximumstressesdevelopedinthepipingbytheRV1,RV2,andTSVCtransientanalysesareusedasabasisforestablishingcriteriathatassureproperfunctioningofthesnubbers.Iffieldmeasurementsexceedcriterialimits,thesnubbersarenotoperatingproperly.Sampleproductionsnubbersofeachsize(i.e.,10,20,50kips)arequalifiedandtestedfordesignandfaultedconditionloadingspriortoshipmenttothefield.Snubbersaretestedtoallowfreepipingmovementsatlowvelocity.Duringplantstartup,thesnubbersarecheckedforpropersettings.Thecriteriaforvibrationdisplacementsarebasedonassumedlinearrelationshipbetweendisplacements,snubberloads,andthemagnitudeofappliedloadsforanyfunctionandresponseofsystem.Thus,themagnitudeoflimitsofdisplacements,snubberloads,andnozzleloadsareallproportional.Maximumdisplacements(Level1limits)areestablishedtopreventthemaximumstressinthepipingsystemsfromexceedingthenormalandupsetprimarystresslimitsand/orthemaximumsnubberloadUSARRevision83.9B-24November1995 NineMilePointUnit2FSARfromexceedingthemaximumloadtowhichthesnubberhasbeentested.Basedontheabovecriteria,Level1displacementlimitsareestablishedforallinstrumentedpointsinthepipingsystem.Theselimitsarecomparedwiththefieldmeasuredpipingdisplacements.Themethodofacceptanceisexplainedinthefollowingsection.3.9B.2.1.4TestEvaluationandAcceptanceCriteriaforRecirculationPipingThepipingresponsetotestconditionsisconsideredacceptableif'thetestresultsverifythatthepipingrespondedinamannerconsistentwiththepredictionsofthestressreportand/orthatpipingstressesarewithincodelimits(ASMESectionIII,SubarticleNB-3600).Acceptabledeflectionandaccelerationlimitsaredeterminedafterthecompletionofpipingsystemstressanalysisandareprovidedinthestartuptestspecifications.Toensuretestdataintegrityandtestsafety,criteriahavebeenestablishedtofacilitateassessmentofthetestwhileitisinprogress.Thesecriteria,designatedLevels1and2,aredescribedinthefollowingsections.3.9B.2.1.4.1Level1CriterionLevel1establishesthemaximumlimitsforthelevelofpipemotionwhich,ifexceeded,makesatestholdorterminationmandatory.IftheLevel1limitisexceeded,theplantwillbeplacedinasatisfactoryholdcondition,andtheresponsiblepipingdesignengineerwillbeadvised.Followingresolution,applicabletestsmustberepeatedtoverifythattherequirementsoftheLevel1limitsaresatisfied.3.9B.2.1.4.2Level2CriteriaIftheLevel2criteriaaresatisfiedforbothsteady-stateandoperatingtransientvibrations,therewillbenofatiguedamagetothepipingsystemduetosteady-statevibration,andalloperatingtransientvibrationsareboundedbythevaluesinthestressreport.ExceedingtheLevel2specifiedpipemotionrequiresthattheresponsiblepipingdesignengineerbeadvised.Plantoperatingandstartuptestingplanswouldnotnecessarilybealtered.Investigationsofthemeasurements,criteria,andcalculationsusedtogeneratethepipemotionlimitswouldbeinitiated.Anacceptableresolutionmustbereachedbyallappropriateandinvolvedparties,includingtheresponsiblepipingdesignengineer.Detailedevaluationisneededtodevelopcorrectiveactionorshowthatthemeasurementsareacceptable.Dependinguponthenatureofsuchresolution,theapplicabletestsmayormaynothavetoberepeated.USARRevision83.9B-25November1995 NineMilePointUnit2FSAR3.9B.2.1.4.3AcceptanceLimitsForsteady-statevibration,thepipingpeakstressduetovibrationonly(neglectingpressure)willnotexceed10,000psiforLevel1criteriaand5,000psiforLevel2criteria.TheselimitsarebelowthepipingmaterialfatigueendurancelimitsdefinedinDesignFatigueCurvesinAppendixIoftheASMECodefor10~cycles.Foroperatingtransientvibration,thepipingbendingstress(zerotopeak)willnotexceed1.2Sorpipesupport.loadswillnotexceedserviceLevelDratingsforLevel1criteria.The1.2Slimitensuresthatthetotalprimarystress,includingpressureanddeadweight,willnotexceed1.8S,theCodeserviceLevelBlimit.Level2criteriaarebasedonpipestressesandsupportloadsnotexceedingdesignbasispredictions.DesignbasiscriteriarequirethatoperatingtransientstressesandloadsnotexceedanyserviceLevelBlimits,includingprimarystresslimits,fatigueusagefactorlimits,andallowableloadsonsnubbers.3.9B.2.1.5CorrectiveActionsforRecirculationPipingDuringthecourseofthetests,theremotemeasurementsareregularlycheckedtodeterminecompliancewithLevel1criteria.IftrendsindicatethatLevel1criteriamaybeviolated,themeasurementsaremonitoredatmorefrequentintervals.ThetestisinterruptedassoonasLevel1criteriaareviolated.Assoonaspossibleafterthetestholdortermination,thefollowingcorrectiveactionsaretaken:2~stalat'osectioAwalkdownofthepipingandsuspensionismadetoidentifyanyobstructionorimproperlyoperatingsuspensioncomponents.Ifvibrationexceedscriteria,thesourceoftheexcitationmustbeidentifiedtodetermineifitisrelatedtoequipmentfailure.Actionistakentocorrectanydiscrepanciesbeforerepeatingthetest.stuetat'ect'oTheinstrumentationinstallationandcalibrationarechecked,andanydiscrepanciesarecorrected.Additionalinstrumentationisadded,ifnecessary.3~4~wthatcouldaccountforfailuretomeettheLevel1criteria,thetestwillberepeated.esolutooF'nd'nsIftheLevel1criteriaareviolatedontherepeattest,ornorelevantdiscrepanciesareidentifiedasdescribedinactions1and2,thetestresultsandcriteriaarereviewedtoensurethatthetestcanbesafelycontinued.USARRevision83.9B-26November1995 NineMilePointUnit2FSARIfthetestmeasurementsindicatefailuretomeettheLevel2criteria,thefollowingcorrectiveactionsaretakenaftercompletionofthetest:1.stallatiosectioAwalkdownofthepipingandsuspensionismadetoidentifyanyobstructionorimproperlyoperatingsuspensioncomponents.Snubbersareinstalledataboutthemidpointofthetotalrangeatoperatingtemperature.Hangersareinstalledintheiroperatingrangebetweenthehotandcoldsettings.Ifvibrationexceedslimits,thesourceofthevibrationisidentified.Actionistakentocorrectanydiscrepancies.2~stumetatosect'oTheinstrumentationinstallationandcalibrationarecheckedandanydiscrepanciesarecorrected.3~4~2aboveidentifyamalfunctionordiscrepancythatcouldaccountforfailuretocomplywithLevel2criteriaandappropriatecorrectiveactionhasbeentaken,thetestisrepeated.ocumentatiooD'sereanciesIfthetestisnotrepeated,thediscrepanciesfoundunderactions1and2aredocumentedinthetestevaluationreportandcorrelatedwiththetestcondition.Thetestisnotcompleteuntilthetestresultsarereconciledwiththeacceptancecriteria.3.9B.2.1.6MeasurementLocationsforRecirculationPipingRemoteshockandvibrationmeasurementsaremadeinthethreeorthogonaldirectionsonthepipingbetweentherecirculationpumpdischargeandthefirstdownstreamvalve.Duringpreoperationaltestingpriortofuelload,visualinspectionofthepipingismade,andanyvisiblevibrationismeasuredwithahand-heldinstrument.Foreachoftheselectedremotemeasurementlocations,Level1and2deflectionandaccelerationlimitsareprescribedinthestartuptestspecification.3.9B.2.2SeismicandHydrodynamicQualificationofSafety-RelatedMechanicalEquipmentThissectiondescribesthecriteriafordynamicqualificationofsafety-relatedmechanicalequipmentandthequalificationtestingand/oranalysisapplicabletothisplantforallthemajorcomponentsonacomponent-by-componentbasis.Insomecases,amoduleorassemblyconsistingofmechanicalandelectricalequipmentisqualifiedasaunit(e.g.,ECCSpumps).TheseUSARRevision83.9B-27November1995 NineMilePointUnit2FSARmodulesaregenerallydiscussedinthissectionratherthaninSections3.10Band3.11.DynamicloadqualificationtestingforpumpsandvalvesisalsodiscussedinSection3.9B.3.2.Electricalsupportingequipmentsuchascontrolconsoles,cabinets,andpanelsthatarepartoftheNSSSarediscussedinSection3.10B.3.9B.2.2.1TestsandAnalysisCriteriaandMethodsTheabilityofequipmenttoperformitssafety-relatedfunctionduringandaftertheapplicationofdynamicloads(earthquake)isdemonstratedbytestsand/oranalysis.Selectionoftesting,analysis,oracombinationofthetwoisdeterminedbythetype,size,shape,andcomplexityoftheequipmentbeingconsidered.Whenpractical,equipmentoperabilityisdemonstratedbytesting.Otherwise,operabilityisdemonstratedbymathematicalanalysis.Equipmentthatislarge,simple,and/orconsumeslargeamountsofpowerisusuallyqualifiedbyanalysisoxtesttoshowthattheloads,stresses,anddeflectionsarelessthantheallowablemaximum.Analysistestingisalsousedtoshowthattherearenonaturalfrequenciesbelow33Hzforseismicloadsand60Hzforhydrodynamicloads.Ifalowernaturalfrequencyisdiscovered,dynamictestsmaybeconductedand,inconjunctionwithmathematicalanalysis,usedtoverifyoperabilityandstructuralintegrityattherequireddynamicinputconditions.Asimilardynamictestand/oranalysisisperformedforhydrodynamicloadsoverafrequencyrangetoincludecontributionsfromallsignificantmodesinthetotalresponse.Whentheequipmentisqualifiedbydynamictest,theresponsespectrumortime-historyoftheattachmentpointisusedindetermininginputmotion.Naturalfrequencymaybedeterminedbyrunningacontinuoussweepfrequencysearchusingasinusoidalsteady-stateinputoflowmagnitude.Seismicconditionsaresimulatedbytestingusingrandomvibrationinputorsinglefrequencyinput(withinequipmentcapability)overthefrequencyrangeofinterest.Whichevermethodisused,theinputamplitudeduringtestingenvelopstheactualinputamplitudeexpectedduringhydrodynamicloadconditions.Equipmentbeingdynamicallytestedismountedonafixturethatsimulatestheintendedservicemountingandcausesnodynamiccouplingtotheequipment.Equipmenthavinganextendedstructure,suchasavalveoperator,isanalyzedbyapplyingstaticequivalentdynamicloadsatthecenterofgravityoftheextendedstructure.Incaseswheretheequipmentstructuralcomplexitymakesmathematicalanalysisimpractical,astaticbendtestisusedtodetermineoperationalcapabilityatmaximumequivalentdynamicloadconditions.Pipe-mountedequipmentisanalyzedinthepipingsystemdynamicanalysis.USARRevision83.9B-28November1995 NineMilePointUnit2FSARadoVibationutWhenrandomvzbratxoninputisused,theactualinputmotionenvelopstheappropriatefloorinputmotionattheindividualmodes.However,singlefrequencyinputsuchassinewavescanbeusedprovidedoneofthefollowingconditionsismet:1.Thecharacteristicsoftherequiredinputmotionaredominatedbyonefrequency.2.Theanticipatedresponseoftheequipmentisadequatelyrepresentedbyonemode.3~licTheinputhassufficientintensityanddurationtoexciteallmodestotherequiredmagnitude,insuchawaythatthetestingresponsespectraenvelopthecorrespondingresponsespectraoftheindividualmodes.futooWhendynamictestsareperformed,theinputmotionisappliedtooneverticalandonehorizontalaxissimultaneously.However,iftheequipmentresponsealongtheverticaldirectionisnotsensitivetothevibratorymotionalongthehorizontaldirection,andviceversa,thentheinputmotionisappliedtoonedirectionatatime.Inthecaseofsinglefrequencyinput,thetimephasingoftheinputsintheverticalandhorizontaldirectionsaresuchthatapurelyrectilinearresultantinputisavoided.itures'Thefixturedesignsimulatestheactualservicemountingandcausesnodynamiccouplingtotheequipment.PrototeestinEquipmenttestingisconductedonprototypesoftheequipmentinstalledinthisplant.3.9B.2.2.2SeismicandHydrodynamicLoadQualificationofSpecificNSSSMechanicalComponentsThefollowingsectionsdiscussthetestingoranalyticalqualificationofNSSSequipment.SeismicqualificationisalsodescribedinSections3.9B.1.4,3.9B.3.1,and3.9B.3.2.JetusAdynamicanalysisofthejetpumpsisperformedandstressesfromtheanalysisarebelowthedesignallowables.USARRevision83.9B-29November1995 NineMilePointUnit2FSARCRDandCRDHousinThedynamicqualificationoftheCRDhousing(withenclosedCRD)isdoneanalytically,andthestressresultsoftheiranalysisestablishedthestructuralintegrityofthesecomponents.PreliminarydynamictestshavebeenconductedtoverifytheoperabilityoftheCRDduringadynamicevent.Asimulatedtest,imposingastaticbowinthefuelchannels,isperformedwiththeCRDfunctioningsatisfactorily.CoreSuorFuelSuortandControlRoGuidubeAdetailedanalysisimposingdynamiceffectsduetoseismicandhydrodynamiceventsshowedthatthemaximumstressesdevelopedduringtheseeventsaremuchlowerthanthemaximumallowedforthecomponentmaterial.HdraulicControlUnitTheseismicandhydrodynamicloadadequacyoftheHCUhasbeendemonstratedbytests.AcompleteHCUassemblywasqualifiedbymultiaxis/multifrequencytestinginthefrequencyrangefrom1to100Hz.Therequiredsafetyfunctionofinitiatingreactorscramwasdemonstratedsuccessfully.essebnclud'aelsGEBWRfuelchanneldesignbases,analyticalmethods,andevaluationresults,includingseismicandhydrodynamicconsiderations,arecontainedinNEDE-24011"',NEDE-24011-US+,andNEDE-21175-3-P<'".Section3.9B.1.4.11.RecircuatioPumandMotossemblCalculationsweremadetoassurethattherecirculationpumpandmotorassemblyisdesignedtowithstandthespecificstaticequivalentseismicandhydrodynamicloads.Thefloodedassemblywasanalyzedasafreebodysupportedbyconstantsupporthangersfromthebracketsonthemotormountingmemberwithmechanicalsnubbersattachedtobracketslocatedonthepumpcaseandthetopofthemotorframe.Primarystressesduetohorizontalandverticalseismic(includinghydrodynamic)forcesareconsideredtoactsimultaneouslyandareconservativelyaddeddirectly.Horizontalandverticaldynamicforcesareappliedtomasscenters,andequilibriumreactionsaredeterminedformotorandpumpbrackets.CCStorAssembThequalificationoftheECCSpumpandmotorassembliesasaunitwhileoperatingunderfaultedconditionswasprovidedintheformofastaticearthquake-accelerationanalysis.ThemaximumspecifiedverticalandhorizontalaccelerationswereconstantlyUSARRevision83.9B-30November1995 NineMilePointUnit2FSARappliedsimultaneouslyintheworst-casecombinationandtheresultsoftheanalysisindicatethepumpiscapableofsustainingtheseloadingswithoutoverstressingthepumpcomponents.Analysisisusedforqualificationwhenmotorsaresimilarindesignfeaturesandinsulationtopreviouslyqualifiedmotors.Differencesindesignfeaturesandinsulationareidentifiedinacomparisonstudyorsimilarityanalysis.Alsoincludedinthiscomparisonstudyaredatashowingthatthedifferenceshavenoimpactonqualification.Inadditiontothecomparisonstudy,motoruniqueseismicanalysisisrequiredtoassurethatthemotorscanhandlethedesignloads.Amotorofsimilardesignhasbeenseismicallyqualifiedviaacombinationofstaticanalysisanddynamictesting.Thecompletemotorassemblyhasbeenseismicallyqualifiedviadynamictesting,inaccordancewithIEEE-344-1975.Thequalificationtestprogramincludeddemonstrationofstartupandshutdowncapabilities,aswellasno-loadoperabilityduringseismicandhydrodynamicloadingconditions.CICumssemblTheRCICpumpconstructionisabarrel-typeonalargecross-sectionpedestal.TheRCICpumpassemblyisanalyticallyqualifiedbystaticanalysisforseismicandhydrodynamicloadingaswellasthedesignoperatingloadsofpressure,temperature,andexternalpipingloads.Theresultsofthisanalysisconfirmthatthestressesaresubstantiallylessthantheallowables.Becauseoftheirlargesizeandweight,pumpsarenotincludedinthetestlist.Analysisisthemostviablequalificationmethod.CICurineAssemblTheRCICturbineisqualifiedforseismicandhydrodynamicloadsviaacombinationofstaticanalysisanddynamictesting.Theturbineassemblyconsistsofrigidmasses,whereinstaticanalysishasbeenutilized,interconnectedwithcontrolleversandelectroniccontrolsystems,necessitatingfinalqualificationbydynamictesting.Staticloadinganalysishasbeenemployedtoverifythestructuralintegrityoftheturbineassemblyandtheadequacyofboltingunderoperatingandseismicloadingconditions.TheRCICelectrohydraulicsystemintegratedwiththeturbinegoverningvalveisofasafety-gradedesign.TheentireturbineassemblyhasbeentestedforseismicqualificationinaccordancewithIEEE-344-1975.Theelectrohydraulicsystemwasinitsoperationalmodesduringthetestprogram.Thequalificationtestprogramincludeddemonstrationofstartupandshutdowncapabilities,aswellasno-loadoperabilityduringseismicloadingconditions.USARRevision83.9B-31November1995 NineMilePointUnit2FSARThespecificationforseismicqualificationoftheRCICturbineanditsaccessoriesstatesthattheyshallbecapableofwithstandingthespecifiedseismicaccelerationsatallfrequencieswithintherangeof0.25to33Hz.Properperformancemaybedemonstratedbytests,analysis,oracombinationofboth.Ifall.naturalfrequenciesoftheturbine,thecomponentparts,andtheaccessoriesaregreaterthan33Hz(asdefinedbytestand/oranalysis),astaticloadanalysismaybeperformed.Theseismicforcesofeachcomponentorassemblyareobtainedbyconcentratingitsmassatthecenterofmassandmultiplyingbytheseismicacceleration(earthquakecoefficient).Themagnitudeoftheearthquakecoefficientsis1.5gforbothhorizontalandvertical.Ifcomponentpartsand/oraccessorieshavenaturalfrequenciesbelow33Hz,thesepartsmustbedynamicallyanalyzedortested,demonstratingsatisfactionofthefloorresponsespectra.StandbLiuidControPumandMotorAssembEachofthetwoSLCpumpsisapositivedisplacementpumpandmotormountedonacommonbaseplatethatisqualifiedbystaticanalysis.TheSLCpumpandmotorassemblyisanalyticallyqualifiedbystaticanalysisforseismicandhydrodynamicloadsaswellasthedesignoperatingloadsofpressure,temperature,andexternalpipingloads.Theresultsofthisanalysisconfirmthatthestressesaresubstantiallylessthan90percentofallowable.RHRHeatEchaersAdynamicanalysisisperformedtoverifythattheRHRheatexchangercanwithstandseismicandhydrodynamicloads.Seismictestingisanimpracticalmethodtoverifytheseismicadequacyofpassiveequipment.tandbLiuidCotrolTanTheSLCstoragetankisacylindricaltank,9ftindiameterand12fthigh,boltedtotheconcretefloor.TheSLCtankisqualifiedforseismicandhydrodynamicloadsbyanalysisfor:1~2~Stressesinthetankbearingplate.Boltstresses.3~Sloshingloadsimposedatnaturalfrequencyofsloshing=0.58Hz.4~5.Minimumwallthickness.Buckling.USARRevision83.9B-32November1995 NineMilePointUnit2FSARTheresultsoftheanalysisconfirmthatstressesarelessthantheallowables.aiStasat-esTheMSIVsarequalifiedforseismicandhydrodynamicloadsbyanalysisandtest.ThefundamentalrequirementoftheMSIVfollowingaSSEorotherfaultedhydrodynamicloadingistocloseandremainclosedaftertheevent.ThisisdemonstratedbythetestandanalysisasoutlinedinSection3.9B.3.2.3.aiSteaSafetelieValvesDuetothecomplexityofthestructureandtheperformancerequirementsofthevalve,thetotalassemblyoftheSRV(includingelectrical,pneumaticdevices)isdynamicallytestedatseismicaccelerationequaltoorgreaterthanthecombinedSSEandhydrodynamicloadingdeterminedforthisplant.Satisfactoryoperationofthevalveswasdemonstratedduringandafterthetest.3.9B.2.3DynamicResponseofReactorInternalsUnderOperationalFlowTransientsandSteady-StateConditionsThemajorreactorinternalcomponentsaresubjectedtoextensivetestingcoupledwithdynamicsystemanalysestoproperlydescribetheresultingflow-inducedvibrationphenomenaincurredfromnormalreactoroperationandanticipatedoperationaltransients.Ingeneral,thevibrationforcingfunctionsforoperationalflowtransientsandsteady-stateconditionsarenotpredeterminedbydetailedanalysis.Specialanalysisoftheresponsesignalsmeasuredforreactorinternalsofmanysimilardesignsareperformedtoobtaintheparameters-thatdeterminetheamplitudesandmodalcontributionsinthevibrationresponses.Thesestudiesprovideusefulpredictiveinformationforextrapolatingtheresultsfromtestsofcomponentswithsimilardesignstocomponentsofdifferentdesigns.Thisvibrationpredictionmethodisappropriatewherestandardhydrodynamictheorycannotbeappliedduetothecomplexityofthestructureandflowconditions.Elementsofthevibrationpredictionmethodareoutlinedasfollows:1~Dynamicanalysisofmajorcomponentsandsubassembliesisperformedtoidentifyvibrationmodesandfrequencies.TheanalysismodelsusedforCategoryIstructuresaresimilartothoseoutlinedinSection3.7B.2~2~Datafrompreviousplantvibrationmeasurementsareassembledandexaminedtoidentifypredominantvibrationresponsemodesofmajorcomponents.InUSARRevision83.9B-33November1995 NineMilePointUnit2FSAR3~4~5.general,responsemodesaresimilar,butresponseamplitudesvaryamongBWRsofdifferingsizeanddesign.Parametersareidentifiedthatareexpectedtoinfluencevibrationresponseamplitudesamongtheseveralreferenceplants.Theseincludehydraulicparameterssuchasvelocityandsteamflowratesandstructuralparameterssuchasnaturalfrequencyandsignificantdimensions.Correlationfunctionsofthevariableparametersaredevelopedwhich,multipliedbyresponseamplitudes,tendtominimizethestatisticalvariabilitybetweenplants.Acorrelationfunctionisobtainedforeachmajorcomponentandresponsemode.Predictedvibrationamplitudesforcomponentsoftheprototypeplantareobtainedfromthesecorrelationfunctions,basedonapplicablevaluesoftheparametersfortheprototypeplant.Thepredictedamplitudeforeachdominantresponsemode'isstatedintermsofarange,takingintoaccountthedegreeofstatisticalvariabilityineachofthecorrelations.ThepredictedmodeandfrequencyareobtainedfromthedynamicanalysesofItem1above.Thedynamicmodalanalysisalsoformsthebasisforinterpretationofthepreoperationalandinitialstartuptestresults(Section3.9B.2.4).Modalstressesarecalculated,andrelationshipsareobtainedbetweensensorresponseamplitudesandpeakcomponentstressesforeachofthelowernormalmodes.Theallowableamplitudeineachmodeisthatwhichproducesapeakstressamplitudeof+10,000psi.3.9B.2.4PreoperationalFlow-InducedVibrationTestingofReactorInternalsVibrationtestingofreactorinternalsisperformedonallGEBWRplants.AtthetimeoftheoriginalissueofAECRG1.20,testprogramsforcompliancewereinstituted.ThefirstBWR5plantofeachsizeisconsideredaprototypeandisinstrumentedandsubjectedtopreoperationalandstartupflowtestingtodemonstratethatflow-inducedvibrationssimilartothoseexpectedduringoperationcausenodamage.SubsequentplantsthathaveinternalssimilartothoseoftheprototypesarealsotestedincompliancewiththerequirementsofRG1.20.Unit2reactorinternalswillbetestedinaccordancewithRG1.20,Revision2,fornonprototype,CategoryIVplantsusingTokai-2asthelimitedvalidprototype.Thetestprocedurewillrequirevibrationmeasurementstodeterminethevibrationcharacteristicsofvesselinternalsduringtheinitialpowerascension.VibratoryresponsesatvariouspowerlevelsandUSARRevision83.9B-34November1995 NineMilePointUnit2FSARrecirculationflowratesarerecordedusingaccelerometersontheshroudheadassemblyandstraingaugesontwoselectedjetpumpriserpipebraces.ReactorinternalsforUnit2aresubstantiallythesameastheinternalsdesignconfigurationsthathavebeentestedinprototypeBWR4plants.Exceptionsarethejetpumps,whichareoftheBWR5design.AvibrationmeasurementandinspectionprogramhasbeenconductedatTokai-2toverifythedesignofthejetpumpswithrespecttovibration.ResultsoftheprototypetestsarepresentedinNEDE-24057-P(ClassIII)andNEDO-24057(ClassI)"~.3.9B.2.5DynamicSystemAnalysisofReactorInternalsUnderFaultedConditionsToensurethatnosignificantdynamicamplificationofloadoccursasaresultoftheoscillatorynatureoftheblowdownforces,acomparisonismadeoftheperiodsoftheappliedforcesandthenaturalperiodsofthecoresupportstructuresbeingacteduponbytheappliedforces.Theseperiodsaredeterminedfroma12-nodeverticaldynamicmodeloftheRPVandinternals.InadditiontotherealmassesoftheRPVandcoresupportstructures,hydrodynamicmassesincludingfluid-structureinteractioneffectsareaccountedfor.Time-varyingpressuresareappliedtothedynamicmodelofthereactorinternalsdescribedabove.Exceptforthenatureandlocationsoftheforcingfunctionsandthedynamicmodel,thedynamicanalysismethodisidenticaltothatdescribedforseismicanalysisandisdetailedinSection3.7B.2.1.Thedynamiccomponentsofforcesfromtheseloadsarecombinedwithdynamicforcecomponentsfromotherdynamicloads(includingseismicandhydrodynamic),allactinginthesamedirection,bytheSRSSmethod.Thisresultantforceisthencombinedwithothersteady-stateandstaticloadsonanabsolutesumbasistodeterminethedesignloadinagivendirection.ResultsofthedynamicanalysisaresummarizedinTable3.9B-2i.3.9B.2.6CorrelationsofReactorInternalsVibrationTestsWithAnalyticalResultsPriortoinitiationoftheinstrumentedvibrationtestprogramfortheprototypeplant,extensivedynamicanalysesofthereactorandinternalswereperformed.Theresultsoftheseanalyseswereusedtogeneratetheallowablevibrationlevelsduringthevibrationtest.Thevibrationdataobtainedduringthetestwereanalyzedindetail.Theresultsofthedataanalysis,vibrationamplitudes,naturalfrequencies,andmodeshapeswerethencomparedtothoseobtainedfromthetheoreticalanalysis.Suchcomparisonsprovidedinsightintothedynamicbehaviorofthereactorinternals.TheadditionalknowledgegainedwasUSARRevision83.9B-35November1995 NineMilePointUnit2FSARutilizedinthegenerationofthedynamicmodelsforseismicandLOCAanalysesforthisplant.Themodelsusedforthisplantaresimilartothoseusedforthevibrationanalysisoftheprototypeplant,Tokai-2.3.9B.3ASMESectionIII,SafetyClass1,2,and3Components,ComponentSupports,andCoreSupportStructures3.9B.3.1LoadCombinations,DesignTransients,andStressLimitsThissectiondelineatescriteriaforselectionanddefinitionofdesignlimitsandloadcombinationsassociatedwithnormaloperation,postulatedaccidents,andspecifiedseismicandhydrodynamiceventsforthedesignofsafety-relatedASMECodeNSSScomponents.ThissectionalsoliststhemajorASMESectionIII,SafetyClass1,2,and3,NSSSpressurepartsandassociatedequipmentonacomponent-by-componentbasisandidentifiestheapplicableloadings,calculationmethods,calculatedstresses,andallowablestresses.DesigntransientsforASMESectionIII,SafetyClass1equipmentareaddressedinSection3.9B.1.1.Seismic-relatedloadsarediscussedinSection3.7B.ThehydrodynamicloadsaredescribedintheMarkIIContainmentDynamicForcingFunctionsInformationReport(DFFR)+.Table3.9B-2isthemajorpartofthissection;itpresentstheloadcombinations,analyticalmethods(byreferenceorexample),andcalculatedstressorotherdesignvaluesforthemostcriticalareasinthedesignofeachcomponent.ThesevaluesarealsocomparedtoapplicableCodeallowables.Table3.9B-2presentsthegenericloadcombinationsrequiredtobeconsideredforthedesignandanalysisofaplant,andisapplicabletoallASMESafetyClass1,2,and3componentsupportsandcoresupportstructures.3.9B.3.1.1PlantConditionsAlleventsthattheplantmightcrediblyexperienceduringareactoryearareevaluatedtoestablishadesignbasisforplantequipment.Theseeventsaredividedintofourplantconditions.Theplantconditionsdescribedinthefollowingsectionsarebasedoneventprobability(i.e.,frequencyofoccurrence)andcorrelateddesignconditionsdefinedintheASMESectionIII.NormalConditioNormalconditionsareanyconditionsinthecourseofsystemstartup,operationinthedesignpowerrange,normalhotstandby(withcondenseravailable),andsystemshutdownotherthanupset,emergency,faulted,ortesting.USARRevision83.9B-36November1995 NineMilePointUnit2FSARUsetCondit'oUpsetconditionsareanydeviationsfromnormalconditionsanticipatedtooccuroftenenoughthatdesignshouldincludeacapabilitytowithstandtheconditionswithoutoperationalimpairment.TheupsetconditionsincludetransientsthatresultfromanysingleOperatorerrororcontrolmalfunction,transientscausedbyafaultinasystemcomponentrequiringitsisolationfromthesystem,andtransientsduetolossofloadorpower.VibrationsduetoOBEareconservativelytreatedasupset.Hotstandbywiththemaincondenserisolatedisanupsetcondition.eecd'tEmergencyconditionsaredeviationsfromnormalconditionsthatrequireshutdownforcorrectionoftheconditionsorrepairofdamageintheRCPB.Theseconditionshavealowprobabilityofoccurrence,butareincludedtoprovideassurancethatnogrosslossofstructuralintegrityresultsasaconcomitanteffectofanydamagedevelopedinthesystem.Emergencyconditioneventsinclude,butarenotlimitedto,transientscausedbyoneofthefollowing:amultiplevalvesafety/reliefblowdownofthereactorvessel;lossofreactorcoolantfromasmallbreakorcrackthatdoesnotdepressurizethereactorsystemorresultinleakagebeyondnormalmakeupsystemcapacity,butwhichrequiresthesafetyfunctionsofisolationofcontainmentandreactorshutdown;improperassemblyofthecoreduringrefueling;andvibrationofanOBEincombinationwithassociatedsystemtransients.ltedCotioThesearecombinationsofconditionsassociatedwithextremelylowprobability,postulatedeventswhoseconsequencesaresuchthattheintegrityandoperabilityofthesystemmaybeimpairedtotheextentthatconsiderationsofpublichealthandsafetyareinvolved.Faultedconditionsencompasseventsthatarepostulatedbecausetheirconsequenceswouldincludethepotentialforthereleaseofsignificantamountsofradioactivematerial.Thesepostulatedeventsarethemostdrasticthatmustbedesignedagainstandthusrepresentlimitingdesignbases.Faultedconditioneventsinclude,butarenotlimitedto,oneofthefollowing:acontrolroddropaccident(CRDA),afuelhandlingaccident,aMSLbreak,arecirculationloopbreak,thecombinationofanypipebreakplustheseismicmotionassociatedwithaSSEandhydrodynamicloadsplusaLOOP,ortheSSE.CorreltiootCdit'onswitEvetobabilitTheprobabilityofaneventoccurringperreactoryearassociatedwiththeplantconditionsislistedbelow.Thiscorrelationcanbeusedtoidentifytheappropriateplantconditionforanyhypothesizedeventorsequenceofevents.USARRevision83.9B-37November1995 NineMilePointUnit2FSARtCoNormal(planned)Upset(moderateprobability)Emergency(lowprobability)Faulted(extremelylowprobability)SafetCassFunct'oaCr'teriaEventEncounterProbabilityPeretre1.01.0>P>1010'P>10~10>P>10Foranynormalorupsetdesignconditionevent,SafetyClass1,2,and3equipmentiscapableofaccomplishingitssafetyfunctionsasrequiredbytheeventandincursnopermanentchangesthatadverselyaffectitsabilitytoaccomplishitssafetyfunctionsasrequiredbyanysubsequentdesignconditionevent.Foranyemergencyorfaulteddesignconditionevent,SafetyClass1,2,and3equipmentiscapableofaccomplishingitssafetyfunctionsasrequiredbytheevent,butrepairscouldberequiredtoensureitsabilitytoaccomplishitssafetyfunctionsasrequiredbyanysubsequentdesignconditionevent.octeuloGide1.48RG1.48wasissuedafterthedesignofthisplantwasestablishedandwasthereforenotusedasadesignbasisrequirement.However,GEdesignbasiswasrepresentativeofgoodindustrypracticesatthetimeofdesign,procurement,andmanufactureandisshowntobeingeneralagreementwiththerequirementofRG1.48throughtheuseofthealternateapproachcitedinTable3.9B-3.RG1.48delineatesacceptabledesignlimitsandappropriatecombinationsofloadingsassociatedwithnormaloperation,postulatedaccidents,andspecifiedseismiceventsforthedesignoftheCategoryIfluidsystemcomponents.ForacomparisonofNSSScompliancewithRG1.48refertoTable3.9B-3.ThiscomparisonreflectsgeneralGEpracticeonBWR5plantsandthereforeisapplicabletothisplant.3.9B.3.1.2ReactorPressureVesselAssemblyTheRPVassemblyconsistsoftheRPVsupportstructureandshroudsupport.TheRPVsupportstructureandshroudsupportareconstructedinaccordancewithASMESectionIII.Theshroudsupportconsistsoftheshroudsupportplateandtheshroudsupportcylinderanditslegs.TheRPVassemblycomponentsareclassifiedasASMESafetyClass1.CompletestressreportsonthesecomponentshavebeenpreparedinaccordancewithASMEUSARRevision83.9B-38November1995 NineMilePointUnit2FSARrequirements.Table3.9B-2hsummarizestheloadingconditions,calculatedstresses,andallowables.Thestressanalysesperformedforthereactorvesselassembly,includingthefaultedconditions,werecompletedusingelasticmethods.ExceptasnotedinSection3.9B.1.4.3,theloadcombinationsandstressanalysesforthecoresupportstructureandotherreactorinternalsarediscussedinSection3.9B.5.3.9B.3.1.3MainSteamPipingThemainsteampipingisdiscussedinSection3.9A.3.9B.3.1.4RecirculationLoopPipingTherecirculationsystempipingboundedbytheRPVnozzlesisdesignedinaccordancewithASMESectionIII,SubarticleNB-3600.Theloadconditions,stresscriteria,calculatedstresses,andallowablesareshowninTable3.9B-2m.TherulescontainedinAppendixFofASMESectionIIIareusedinevaluatingfaultedloadingconditionsindependentlyofallotherdesignandoperatingconditions.StressescalculatedonanelasticbasisareevaluatedinaccordancewithAppendixF.3.9B.3.1.5RecirculationSystemValvesTherecirculationsystemflowcontrolandsuctionanddischargegatevalvesaredesignedinaccordancewithASMESectionIII,SafetyClass1,SubarticleNB-3500.ThesevalvesarenotrequiredtooperateundertheSSE.LoadcombinationsandotherstressanalysisinformationarepresentedinTables3.9B-21(FCVs)and3.9B-2k(gatevalves).3.9B.3.1.6RecirculationPumpInthedesignoftherecirculationpumps,theASMEBoilerandPressureVesselCode,SectionVIII,Division1,1971Editionwithlatestaddendawasusedasaguideincalculationsmadefordeterminingthethicknessofpressure-retainingpartsandinsizingthepressure-r'etainingbolting.Thepumpvendormadecalculationsforthedesignofthepressure-containingcomponentstoincludethedeterminationofminimumwallthickness,allowablestress,andpressures.TheloadingconditionsandotherstressanalysisinformationarepresentedinTable3.9B-2p.Load,shear,andmomentdiagramswereconstructedtoscale,usingliveloads,deadloads,andcalculatedsnubberreactions.Combinedbending,tension,andshearstressesweredeterminedforeachmajorcomponentoftheassembly,includingthepumpdrivermount,motorflangebolting,andpumpcase.Themaximumcombinedtensilestressinthecoverboltingwascalculatedusingtensilestressfromdesignpressure.Combinedprimarystressesdidnotexceed150percentoftheCodeallowablestressshowninSectionUSARRevision83.9B-39November1995 NineMilePointUnit2FSARVIIIoftheASMEBoilerandPressureVesselCode,1971Edition.Thesemethodsandcalculationsdemonstratethatthepumpwillmaintainpressureintegrityatalltimes.3.9B.3.1.7StandbyLiquidControlTankTheSLCtankisdesignedinaccordancewithASMEBoilerandPressureVesselCode,SectionIII.Theloadingconditions,stresscriteria,calculatedstresses,andallowablesaresummarizedinTable3.9B-2q.3.9B.3.1.8ResidualHeatRemovalHeatExchangersTheRHRheatexchangersaredesignedinaccordancewiththeASMEBoilerandPressureVesselCodeSectionIII.ThecalculatedstressesandallowablesareshowninTable3.9B-2r.3.9B.3.1.9RCICTurbineAlthoughnotunderthejurisdictionoftheASMECode,theRCICturbineisdesignedandfabricatedfollowingthebasicguidelinesforanASMESectionIII,SafetyClass2component.DesignoperatingconditionsfortheRCICturbineinclude:1~2~veaceestMonthlyoperationwithreactorpressureat1,000psia,nominal,andsaturatedtemperature,turbineexhaustpressureat25psia,peak,andsaturatedtemperature.utomaticStartu30cycles/yrwithreactorpressureat1,150psia,nominal,andsaturatedtemperature,turbineexhaustpressureat25psia,peak,andsaturatedtemperature.DesignconditionsfortheRCICturbineinclude:1.Turbineinlet-1,250psigatsaturatedtemperature.2.Turbineexhaust-165psigatsaturatedtemperature.Table3.9B-2ssummarizesthecriteria,calculatedstresses,andallowablesfortheRCICturbinecomponents.3.9B.3.1.10RCICPumpTheRCICpumpisdesignedandfabricatedtotherequirementsforanASMESectionIIISafetyClass2component.OperatingconditionsfortheRCICpumparetestedundersurveillancetogetherwiththeRCICturbine.AmonthlyoperationtestisperformedwheretheRCICpumptakescondensatefromtheCSTandatdesignflowdischargescondensatebacktotheCSTviaaclosedtestloop.USARRevision83.9B-40November1995 NineMilePointUnit2FSARDesignconditionsfortheRCICpumpinclude:1.AvailableNPSHminimum2.Totalhead21ftHighspeedLowspeed3.Constantflowrate4.Normalambientoperatingtemperature2,895ft610ftat165psiareactorpressure625gpm60~to1004F5.Normalplusupsetconditionswhichcontrolthepumpdesigninclude:DesignpressureDesigntemperatureOBE1,525psig40'in-1404Fmax2/3ofSSETable3.9B-2tcontainsasummaryofthedesigncalculationsfortheRCICpumpcomponents.3.9B.3.1.11ECCSPumpsTheRHR,LPCS,andHPCSpumpsaredesignedandfabricatedtotherequirementsofASMESectionIII.Table3.9B-2usummarizesthedesigncalculationsfortheECCSpumps.3.9B.3.1.12StandbyLiquidControlPumpTheSLCpumpisdesignedandfabricatedfollowingtherequirementsforanASMESectionIII,SafetyClass2component.OperatingconditionsfortheSLCpumpandmotorarefunctionallytestedbypumpingdemineralizedwaterthroughaclosedtestloop.TheSLCpumpiscapableofinjectingthenetcontentsofthestoragetankintothereactorin50to125min.Thepumpiscapableofinjectingflowintothereactoragainstzeropsiguptotheinitialsetpointofthereactorreliefvalves.DesignconditionsfortheSLCpumpinclude:1~2~3.FlowrateAvailableNPSH,maximumMaximumoperatingdischargepressure43gpm12.9psi1,220psigUSARRevision83.9B-41November1995 NineMilePointUnit2FSAR4.Ambientconditions:TemperatureRelativehumidity70-104F20-954'.Normalplusupsetconditionsthatcontrolthepumpdesigninclude:DesignpressureDesigntemperatureOBE1,400psig150~F2/3ofSSEAsummaryofthedesigncalculationsfortheSLCpumpcomponentsisprovidedinTable3.9B-2v.3.9B.3.1.13MainSteamIsolationandSafety/ReliefValvesTheMSIVsandSRVsaredesignedinaccordancewiththerequirementsofASMEBoilerandPressureVesselCode,SectionIII,SubarticleNB-3500,SafetyClass1components.Loadcombination,analyticalmethods,calculatedstresses,andallowablelimitsfortheSRVsandMSIVsareshowninTables3.9B-2jand3.9B-2z.3.9B.3.1.14ReactorWaterCleanupSystemPumpandHeatExchangersTheRWCUpumpandregenerativeandnonregenerativeheatexchangersarenotpartofasafetysystemandarenotdesignedtoCategoryIrequirements.TherequirementsofASMEBoilerandPressureVesselCode,SectionIII,SafetyClass3componentsareusedasguidelinesinevaluatingtheRWCUsystempumpandheatexchangercomponents.Theloadingconditions,stresscriteria,andcalculatedandallowablestressesaresummarizedinTables3.9B-2wand3.9B-2x.3.9B.3.2PumpandValveOperabilityAssuranceTheactivepumpsandvalvesarelistedinTable3.9B-4.ActivemechanicalequipmentclassifiedasCategoryIisdesignedtoperformitsfunctionsduringthelifeoftheplantunderpostulatedplantconditions.EquipmentwithfaultedconditionfunctionalrequirementsincludesactivepumpsandvalvesinfluidsystemssuchastheECCSandMSSsystem.(Activeequipmentmustperformamechanicalmotionduringthecourseofaccomplishingasafetyfunction.)Safety-relatedvalvesarequalifiedbytestingandanalysis,andsatisfystressanddeformationcriteriaatcriticallocations.Operabilityisassuredbysatisfyingtherequirementsoftheprogramsdetailedinthefollowingsections.USARRevision83.9B-42November1995 NineMilePointUnit2FSAR3.9B.3.2.1ECCSPumpsandMotorsAllactivepumpsandmotorsarequalifiedforoperabilitybyfirstbeingsubjectedtorigoroustestsbeforeandafterinstallationintheplant.Thein-shoptestsinclude1)hydrostatictestsofpressure-retainingpartsto125percentofthedesignpressure(multipliedbytheratioofmaterialallowablestressatroomtemperaturetotheallowablestressvalueatthedesigntemperature),2)sealleakagetests,and3)performancetests,whilethepumpisoperatedwithflow,todeterminetotaldevelopedhead,minimumandmaximumhead,andNPSHrequirements.Alsomonitoredduringtheseoperatingtestsarebearingtemperatures(exceptwater-cooledbearings)andvibrationlevels.Bothareshowntobebelowspecifiedlimits.Afterthepumpisinstalledintheplant,itundergoescoldhydrotests,functionaltests,andtherequiredperiodicISIandoperation.Thesetestsdemonstratereliabilityofthepumpforthedesignlifeoftheplant.Inadditiontothesetests,thesafety-relatedactivepumpsareanalyzedforoperabilityduringafaultedconditionbyimposingthefollowingcriteria:1)thepumpisnotdamagedduringthefaultedevent,and2)thepumpcontinuesoperatingdespitethefaultedloads.nalsisofLoadiStressandAcceleratioCod'tionsToavoiddamageduringthefaultedplantcondition,thestressescausedbythecombinationofnormaloperatingloads,SSE,hydrodynamic,anddynamicsystemloadsarelimitedtothematerialelasticlimit,asindicatedinSection3.9B.3.1andTable3.9B-2.Athree-dimensionalfiniteelementmodelofthepump/motoranditssupportwasdevelopedanddynamicallyanalyzedusingtheresponsespectrumanalysismethod.Thesamemodelwasanalyzedforstaticnozzleloads,pumpthrustloads,anddeadweight.Criticallocationstresseswereevaluatedandcomparedwiththeallowablestresscriteria.Criticallocationdeflectionandaccelerationwereevaluatedtoassureoperability.Themaximumseismicnozzleloadsfromtheattachedpipingsystemarealsoconsideredinananalysisofthepumpsupporttoassurethattherewillbenogeometric/dimensionaldeformationofthepumpcomponents.Sincethepumpsandmotorsarestructurallycoupled,thedynamicaccelerationvaluesatthemotorwereobtainedbyperformingapump/motorresponsespectrumdynamicanalysistotransferthefloorRRStothemotoranddeterminethepeakvibrationaccelerationamplitudeatthepointofhighestaccelerationinthemotor.Thisanalysisshowedthatthemaximumaccelerationwaslessthanthevalvesusedinthedetailedmotoranalyses.USARRevision83.9B-43November1995 NineMilePointUnit2FSARumo'SActivepump/motorrotorcombinationsaredesignedtorotateataconstantspeedunderallconditions.Motorsaredesignedtowithstandshortperiodsofsevereoverload.Thehighrotaryinertiaintheoperatingpumprotorandthenatureoftherandom,shortdurationloadingcharacteristicsoftheseismiceventpreventtherotorfrombecomingseized.Inactuality,theseismicandhydrodynamicloadingscauseonlyaslightincrease,ifany,inthetorque(i.e.,motorcurrent)necessarytodrivethepumpattheconstantdesignspeed.Therefore,thepumpdoesnotshutdownduringthefaultedloadandcontinuestooperateatthedesignspeed.Thefunctionalabilityoftheactivepumpsafterafaultedconditionisassuredsinceonlynormaloperatingloadsandsteady-statenozzleloadsexist.Fortheactivepumps,thefaultedconditionisgreaterthanthenormalconditiononlyduetoseismicSSEandhydrodynamicloadsontheequipment.Theseeventsareinfrequentandofrelativelyshortdurationcomparedtothedesignlifeoftheequipment.Sinceitisdemonstratedthatthepumpsarenotdamagedduringthefaultedevent,thepostfaultedconditionoperatingloadsarenoworsethanthenormalplantoperatinglimits.Thisisensuredbyrequiringthattheimposednozzleloads(steady-stateloads)fornormalconditionsandpostfaultedconditionsarelimitedbythemagnitudesofthenormalconditionnozzleloads.Thepostfaultedconditionabilityofthepumpstofunctionundertheseappliedloadsisprovenduringthenormaloperatingplantconditionsforactivepumps.CCSotorsTheanalysisoftheECCSmotorsisperformedbyacomputerprogramthatconsistsofthemechanicalanalysisofthemotorrotorassemblywhenacteduponbyexternalforcesincludingmagneticandcentrifugalforcesatanypointalongtheshaft.Thecalculationfortheseismicandhydrodynamicconditionassumesthatthemotorisoperatingandtheseismic,hydrodynamic,magnetic,andcentrifugalforcesallactsimultaneouslyandinphaseontherotorshaftassembly.Othercomponentsofthemotor,suchasstatorframe,lower-endshield,statorsupports,basefasteners,topcap,andconduitbox,arecheckedforthecombinedeffectsofseismic,self-weight,hydrodynamic,andoperationalloads,includingconsiderationofbending,shear,torsion,anddirectbearingloads.TheanalysisandteststhatareusedforqualificationsofECCSpumpmotorswereperformedonanECCStestmotorofverysimilarmechanicalconstruction.Thetypetesthasbeenperformedona1,250-hpverticalmotorinaccordancewithIEEE-323-1974,byfirstsimulatingnormalUSARRevision83.9B-44November1995 NineMilePointUnit2FSARoperationduringthedesignlife,thenwiththemotorbeingsubjectedtoanumberofseismicandhydrodynamicevents,andtotheabnormalenvironmentalconditionspossibleduringandafteraLOCA.Thetestplanforthe'ypetestwasasfollows:1~Thermalagingofthemotorelectricalinsulationsystem(whichisapartofthestatoronly)wasbasedonextrapolationinaccordancewiththetemperaturelifecharacteristiccurvetosatisfytherequirementsofIEEE-275-1966andfromtestdatafortheinsulationtypeusedontheECCSmotors.Theamountofagingwasequivalenttothetotalestimateddaysatmaximuminsulationtemperature.2.Radiationagingofthemotorelectricalinsulationequalsthemaximumestimatedintegrateddoseofgammaduringnormalandabnormalconditions.3~4~5.Thedynamicdeflectionanalysisontherotorshaft,performedtoensureadequaterotationclearance,hasbeenverifiedbystaticloadinganddeflectionoftherotorforthetypetestmotor.DynamicloadagingandtestinghasbeenperformedonabiaxialtesttableinaccordancewithIEEE-344-1975.DuringthistypetesttheshaketableinputsimulatedthemaximumdesignlimitoftheSSEandhydrodynamicloads,combinedwithmotorstartsandoperationalcombinationsthatmaypossiblyoccurduringplantlife.Theaccelerationvaluesofthemotorinthetypetestweresignificantlyhigherthanthosefoundinthestructurally-coupledmotorandpumpdynamicanalyses.AnenvironmentaltestsimulatingaLOCAconditionwith100-daysdurationtimehasbeenperformedwiththetestmotorfullyloaded,simulatingpumpoperation.Thetestconsistedofstartupand6-hroperationat212Fambienttemperatureand100-percentsteamenvironment.Anotherstartupandoperationofthetestmotorafter1-hrstandstillinthesameenvironmentwasfollowedbysufficientoperationathighhumidityandtemperature,basedonextrapolationinaccordancewiththetemperaturelifecharacteristiccurvetosatisfytherequirementsofIEEE-275-1966fortheinsulationtypeusedontheECCSmotors.3.9B.3.2.2SLCPumpandMotorAssemblyandRCICPumpAssemblyTheseequipmentassembliesaresmall,compact,rigidassemblies,withnaturalfrequencieswellabove33Hz.Withthisfactverified,eachequipmentassemblyhasbeenseismicallyqualifiedbystaticanalysis.ThisstaticqualificationverifiesUSARRevision83.9B-45November1995 NineMilePointUnit2FSARoperabilityunderseismicconditions,andassuresstructuralloadingstresseswithinCodelimitations.3.9B.3.2.3NSSSValves3.9B.3.2.3.1SafetyClass1ActiveValvesTheSafetyClass1activevalvesaretheMSIVs,SRVs,SLCvalves,andHPCSinjectionvalves.EachofthesevalvesisdesignedtoperformitsmechanicalfunctioninconjunctionwithaDBAincludinghydrodynamicloads.Qualificationforoperabilityisuniqueforeachvalvetype.Themethodofqualificationisdescribedbelow.esotoesTheMSIVsareevaluatedforoperabilityduringseismicandhydrodynamicloadeventsbybothanalysisandtest.1~2~ThevalvebodyisdesignedinaccordancewithASMECodeSectionIII,SubsectionNB(Table3.9B-2z),whichlimitsdeformationtowithintheelasticlimitofthematerialbylimitingpressureandpipereactioninputloads(includingseismicandhydrodynamicloads).Thisensuresthatonlysmalldeformationsareallowedintheoperatingareaofthevalvebody,hence,nointerferencewithvalveoperability.Theentiretopworksassemblywasdynamicallyqualifiedbyabidirectional,random-frequencyshaketest.TheloadingsincludeSRVaging,OBEandSSEmotions,andchuggingmotions.The'SRVaginglasted15minforeachpairofverticalaxesandoneofthetwomajorhorizontalaxes.Themotionsimulationinvolved5intervalsof30seceachforthe2bidirectionalcombinations.TheSSEsimulationinvolved1intervalof30seceachforthetwobidirectionalcombinations.Thechuggingmotioninvolved15minofbidirectionalloadingslasting15minforeachpairofmajororthogonalaxes.Thetestingcoveredseismicandhydrodynamicloads.TheTRSexceededtheRRSby10percent.Duringeachtestinterval,theMSIVtopworkswascycledfromfullopentofullclosedtodemonstrateoperability.Afterthecompletedynamictestprogram,theMSIVtopworkswasagaincycledtoensureoperability.PipeanchorsandrestraintsareprovidedinsuchawayastolimitthedynamicresponseandamplifiedaccelerationstowithindesignlimitsfortheMSIVs.Themathematicalmodelingoftheassemblyaccountsforthenaturalfrequenciesoftheassemblyasdeterminedbytheanalysisandconfirmedbyagenerictest.USARRevision83.9B-46November1995 NineMilePointUnit2FSAR3~MSIVoperabilityfollowingadownstreamlinebreakwasdemonstratedbythe"statelinetest,"asdefinedinthereportAPED-5750(March1969)">.Thetestspecimenwasa20-invalveofadesignrepresentativeoftheMSIVs.ainSteamSafetelieVavesSRVsarequalifiedbytestforoperabilityduringaseismicandhydrodynamicloadingevent.Eachvalveisdesignedformaximummomentsthatmaybeimposedwheninstalledinservice;Thesemomentsareresultantsduetodeadweightplusseismicandhydrodynamicloadingofboththevalveandtheconnectingpipe,thethermalexpansionoftheconnectingpipe,andthereactionforcesfromvalvedischarge.TheSRVswerequalifiedbytestingforseismicandhydrodynamicloads.Thenaturalfrequenciesweredeterminedtobegreaterthan33Hzforseismicand60Hzforhydrodynamicloading.TheSRVdesignhasbeenupgradedtoNUREG-0588Category1requirements.TheSRVqualificationprogramconsistsof:1.Radiationagingofelectropneumaticactuatorassemblyfora5-yr(minimum)period.2.ThermalagingoftheSRVassemblyfora5-yr(minimum)periodat300F.3.ThermalcyclingoftheSRVfrom135oFto220'Fbackto135'F80timesandsimultaneouslyactuatingtheSRVassemblyapproximately130timesduringtheenvironmentaltransientcondition.4~MechanicalcyclingoftheSRVassembly1,250timesina150'Fambientenvironmentbeforesubjectingtheactuatorassemblytoaseriesofexternalpressurizationtests.ThedynamictestsforSRVassemblyenvelopetheUnit2RRSandhydrodynamicloadingcondition.Thedynamictestingconsistsof'vibrationaginginaccordancewithIEEE-382-1980,40-yrequivalenthydrodynamicaging,andupsetandfaultedloadingconditions.SRVoperabilitywasdemonstratedbyperiodicallyactuating(openingandclosing)thevalvesuccessfullywithoutmalfunction.StndbLiu'dCotrolExosiveValveTheSLCvalvehasbeenqualifiedbytestincompliancewithNUREG-0588,Category1requirements.ThequalificationincludescompliancewithIEEE-323-1974,IEEE-344-1975,andIEEE-382-1980.Priortoseismicandhydrodynamictesting,theexplosivevalvewassubjectedtoradiationandthermalaging.NomechanicalUSARRevision83.9B-47November1995 NineMilePointUnit2FSARcyclingwasperformedsincethisvalveisdesignedforone-timeuseand,therefore,notsubjectedtooperationalcycles.Fatiguetestingduetopipe-inducedvibration,however,wasperformedbysimulatingSRV,OBE,andSSEloadstodemonstratefunctionaloperability.PCSGteveThereisoneClass1HPCSvalve.Thisvalveisamotor-operatedgatevalve.Thevalvebodydesign,analysis,andtestingisinaccordancewiththeASMEBoilerandPressureVesselCode,SectionIII,Class1requirements.Theenvironmentaltesting(radiation,thermal,andmechanicalaging)inaccordancewithIEEE-382-1980anddynamictestingperIEEE-344-1975ofaspecimenmotoractuatorwillbeperformedfortheequivalentof40-yrnormalenvironmentand100-daypost-LOCAenvironmenttodemonstratefunctionaloperability.3.9B.3.2.3.2SafetyClass2and3ActiveValvesTherearesixHPCSgatevalvesandfourCRDglobevalvesinthiscategory.ThereisnoClass3activevalveintheNSSSscopeofsupply.CSGateValvesTheseMOVsarequalifiedbytestingvalvesthataregenerallytypicalofthevalvessuppliedbyGE.Operabilityisensuredbytestingatthestaticdesignbasisload.TheactuatorsarequalifiedtoIEEE-382-1980tolevelsthatexceedthedesignloadings.CRDGloeVvesThesefourCRDSDVventanddrainvalvesareair-operatedglobevalves.Theyweredynamicallyqualifiedbytest,inaccordancewithIEEE-344-1975,todemonstrateoperationalandstructuralintegrityunderseismicandhydrodynamicloadconditions.3.9B.3.3DesignandInstallationofPressureReliefDevices3.9B.3.3.1MainSteamSafety/ReliefValvesSRVvalveopeningresultsinatransientthatproducesmomentaryunbalancedforcesactingonthedischargepipingsystemfortheperiodfromopeningoftheSRVuntilasteadydischargeflowfromtheRPVtothesuppressionpoolisestablished.Thisperiodincludesclearingofthewaterslugfromtheendofthedischargepipingsubmergedinthesuppressionpool.PressurewavestravelingthroughthedischargepipingfollowingtherelativelyrapidopeningoftheSRVcausetheSRVdischargepipingtovibrate.Thisinturnproducesforcesthatactonthemainsteampiping.USARRevision83.9B-48November1995 NineMilePointUnit2FSARTheanalysisofthereliefvalvedischargetransientconsistsofastepwisetime-historysolutionofthefluidflowequationtogenerateatime-historyofthefluidpropertiesatnumerouslocationsalongthepipe.ThefluidtransientpropertiesarecalculatedbasedonthemaximumSRVsetpressurespecifiedinthesteamsystemspecification,andthevalueoftheASMEflowratingincreasedbyafactortoaccountfortheconservativemethodofestablishingtherating.Simultaneousdischargeofallvalvesisassumedintheanalysisasthisis'consideredtoinducemaximumstressinthepiping.Reactionloadsonthepipearedeterminedateachelbowlocation.Theseloadsarecomposedofpressuretimesarea,momentumchange,andfluidfrictionterms.Themethodofanalysistodeterminepipingsystemresponsetoreliefvalveoperationistime-historyintegration.Theforcesareappliedatlocationsonthepipingsystemwherefluidflowchangesdirection,thuscausingmomentaryreactions.TheresultingloadsontheSRV,theMSL,andthedischargepipingarecombinedwithloadsduetoothereffectsasspecifiedinSection3.9B.3.1.TheCodestresslimitscorrespondingtoloadcombinationclassificationsofnormal,upset,emergency,andfaultedareappliedtothesteamanddischargepipe.3.9B.3.4ComponentSupports3.9B.3.4.1PipingPipingsupportsaredesignedinaccordancewithSubsectionNFofASMESectionIII.SupportsareeitherdesignedbyloadratinginaccordancewithSubsubarticleNF-3260ortothestresslimitsforlinearsupportsinaccordancewithSubsubarticleNF-3231.Toavoidbucklinginthecomponentsupports,AppendixesFandXVIIofASMESectionIIIrequirethattheallowableloadsbelimitedtotwo-thirdsofthecriticalbucklingloads.ThecriticalbucklingloadsforASMESafetyClass1componentsupportsintheNSSSscopesubjectedtofaultedloadsthataremoreseverethannormal,upset,andemergencyloads,aredeterminedbythevendorusingthemethodsdiscussedinAppendixFoftheASMECode.Ingeneral,theloadcombinationsfortheconditionscorrespondtothoseusedtodesignthesupportedpipe.DesigntransientcyclicdataarenotapplicabletopipingsupportsasnofatigueevaluationisnecessarytomeettheCoderequirements.SeeAppendix3Eforadiscussionofstressesinsupportsduetothermalgrowthofpipingandseismicanchormotion.Thedesigncriteriaanddynamictestingrequirementsforcomponentsupportsareasfollows:StiffPieClamsStiffpipeclampsareusedontherecirculationpipingsystem.Thereare3E-systempipeclampsoneachrecirculationloop.Thisistheonlyuseofstiffpipeclamps.USARRevision83.9B-49November1995 NineMilePointUnit2FSARTheclampswerenotusedtomeetstiffnesscriteria;theyweredesignedtomeettherequirementsforstrengthandloaddistributionusingaminimumofspace.Theclampdesignutilizesadoublenutarrangementtopreventthenutsfrombackingoff.The,lowtemperature((600)andstressesintheboltfrompreloadswillnotcausearelaxationofthematerial;consequently,nolift-offfromthepipingwilloccur.AlthoughboltpreloadsarenotaddressableunderASMEIIIrulesforpiping,preloadcouldresultindamagetothepipeifaclampispoorlydesigned.Calculationshavebeenmadetoensurethatboltpreloadwillnotresultinplasticdeformationofrecirculationpipewalls.Equation9(ofASMEIII,SubsectionNB)isaimedatpreventingcollapseofthepipingsystemduetoloadsthatproduceprimarystresses.Collapseispreventedbykeepingthestressesduetopressure,deadweight,andinertiaeffectsofdynamicloadslessthanprescribedvalues.Theexistenceofclampsonpipingsystemsdoesnotadverselyaffectthemomentcarryingcapabilityorreducetheabilityofthepipingsystemtoresistcollapseundercombinedloadingsthatproduceprimarystresses.Theonlyconcernistheloadingtransmittedfromthesnubberthroughtheclamppadstothepipe.Thisbearingloadwillresultinlocalstressinthepipewall.ThesestressesareconservativelycalculatedusingtheindicesmethodandaddedtothemembraneandoverallbendingstressescomputedbyEquation9oftheCode.Clamp-inducedstressescausedbytheconstraintofpipeexpansionduetointernalpressurehavebeenaddedtootheroperatingsecondaryandpeakstressesbycalculatingeffectiveincreasesinlocalbendingstresses.Clamp-inducedstressesduetodifferentialtemperaturesandmaterialexpansioncoefficientshavebeenaccountedforbycomputingeffectiveincreasesinlocalbendingstresses.Thesestresseshavebeenaddedtootheroperatingsecondaryandpeakstresses.Thefatigueusageateachclamplocationhasbeenconservativelycomputed,takingintoconsiderationclamp-inducedstressesfrominternalpressure,differentialthermalexpansion,andsnubberloads.Theclamp-inducedstresseswereaddedtothestressescomputedforeachloadsetusingEquations10and11ofNB-3650.CumulativefatigueusagewascomputedbytherulesoftheCode.ThestressesinducedateachclamplocationwerecalculatedandcomparedtoCodeacceptancecriteria.TheprimarystressescomputedbyEquation9wereshowntobenongoverning.TheUSARRevision83.9B-50November1995 NineMilePointUnit2FSARthermalexpansionstressescomputedbyEquation12werealsoshowntobenongoverning.ThestressratchetcriteriaofEquation13andthefatigueusagecriteriaofEquation14meetCodecriteria,withsignificantmargins.omoeSuortsAllcomponentsupports,whichincludepipingclamps,hangers,snubbers,struts,andattachments(e.g.,clevis)tothebuildingstructurearedesigned,fabricated,andassembledsotheycannotbecomedisengagedbythemovementofthesupportedpipeorequipmentaftertheyhavebeeninstalled.AllcomponentsupportsaredesignedinaccordancewiththerulesofSubsectionNFoftheCode.FortheNSSSscopeofsupply,valveoperatorsmountedonSafetyClass1pipingarenotusedascomponentsupports.Table3.9B-2includesloadsandloadcombinationswhichareusedalsofortheNSSSpipingsupports.ThestresslimitsareinaccordancewithASMEIII,SubsectionNF.Nospecificdeformationlimitisrequired.Deformationislimitedbyrequiringproperstresslimits.Qan~~erThedesignloadonhangersistheloadcausedbydeadweight.Thehangersarecalibratedtoensurethattheysupportthedesignloadatboththeirhotandcoldloadsettings.Hangersprovideaspecifieddowntravelanduptravelinexcessofthespecifiedthermalmovement.~i~ub~~~eu'oaCaac'tadSubeocat'oTheentirepipingsystem,includingvalvesandsuspensionsystembetweenanchorpoints,ismathematicallymodeledforcompletestructuralanalysis.Inthemathematicalmodel,thesnubbersaremodeledasspringswithagivenspringstiffnessdependingonthesnubbersize.Theanalysisdeterminestheforcesandmomentsactingoneachcomponentandtheforcesactingonthesnubbersduetoalldynamicloadingconditionsdefinedinthepipingdesignspecification.Thedesignloadonsnubbersincludesthoseloadscausedbyseismicforces(OBEandSSE),hydrodynamicforces,systemanchormovements,andreactionforcescausedbyreliefvalvedischarge,turbinestopvalveclosure,andothers.Thesnubberlocationandloadingdirectionarefirstdecidedbyestimationtoconfinethestressesinthepipingsystemtoacceptablevalues.Thesnubberlocationsanddirectionarerefinedbyperformingthecomputeranalysisonthepipingsystemasdescribedabove.ThespringconstantrequiredbythesuspensiondesignspecificationforagivenloadcapacitysnubberiscomparedUSARRevision83.9B-51November1995 NineMilePointUnit2FSARagainstthespringconstantusedinthepipingsystemmodel.Ifthespringconstantsarethesame,thenthesnubberlocationandloaddirectionhavebeenconfirmed.Ifthespringconstantsarenotinagreement,theyarebroughtintoagreement,andthesystemanalysisisredonetoconfirmthesnubberloads.Thisiterationiscontinueduntilallsnubberloadcapacitiesandspringconstantsarecompatible.es'ecicateeetsToassurethattherequiredstructuralandmechanicalperformancecharacteristicsandproductqualityareachieved,thefollowingrequirementsfordesignandtestingareimposedonthemanufacturer:1~ThesnubbersarerequiredbythesuspensiondesignspecificationtobedesignedinaccordancewithallrulesandregulationsofASMESectionIII,SubsectionNF.Thisdesignrequirementincludesanalysiswhereinthestressesinthesnubbercomponentpartsarecalculatedundernormal,upset,emergency,andfaultedloads.ThesecalculatedstressesarethencomparedagainsttheallowablestressesofthematerialasgiveninASMESectionIIItoensurethattheyarebelowtheallowablelimit.2~ThesnubbersaretestedtoensurethattheycanperformasrequiredduringtheOBE,theSSE,andhydrodynamiceventsunderanticipatedoperationaltransientloadsorothermechanicalloadsassociatedwiththedesignrequirementsfortheplant.Thetestrequirementsinclude:a.Snubbersaresubjectedtoforceordisplacementversustimeloadingatfrequencieswithintherangeofsignificantmodesofthepipingsystem.b.Displacementsaremeasuredtodeterminetheperformancecharacteristicsspecified.c.Testsareconductedatvarioustemperaturestoensureoperabilityoverthespecifiedrange.d.Peaktestloadsinbothtensionandcompressionareequaltoorhigherthantheratedloadrequirements.e.Testsareconductedforvariousabnormalenvironmentalconditions.Uponcompletionoftheaboveabnormalenvironmentaltransienttest,thesnubberistesteddynamicallyatafrequencywithaspecifiedfrequencyrange.Thesnubbermustoperateasdesignedduringthedynamictest.SnubberIstallationReuirementsAninstallationinstructionmanualisrequiredbythesuspensiondesignspecification.ThisUSARRevision83.9B-52November1995 NineMilePoint,Unit2FSARmanualisrequiredtocontaininstructionsforstorage,handling,erection,andadjustments(ifnecessary)ofsnubbers.Eachsnubberhasaninstallationlocationdrawing,whichcontainstheinstallationlocationofthesnubberonthepipeandstructure,thehotandcoldsettings,andadditionalinformationneededtoinstalltheparticularsnubber.Thesuspensiondesignspecificationrequiresthatsnubbersbeprovidedwithpositionindicatorstoidentifytherodposition.Thisindicatorfacilitatesthecheckingofhotandcoldsettingsofthesnubber,asspecifiedintheinstallationmanual,duringplantpreoperationalandstartuptesting.IsectioestiReairandoreacementSnubbersThesuspensiondesignspecificationrequiresthatthesnubbersupplierprepareaninstallationinstructionmanual.Thismanualisrequiredtocontaincompleteinstructionsforthetesting,maintenance,andrepairofthesnubber.Italsocontainsinspectionpointsandtheperiodforinspection.Thedesignloadonstrutsincludesthoseloadscausedbydeadweight,thermalexpansion,primaryseismicforces(OBEandSSE),hydrodynamicloads,systemanchordisplacements,andreactionforcescausedbyreliefvalvedischarge,turbinestopvalveclosure,etc.StrutsaredesignedinaccordancewithASMESectionIII,ArticleNF-3000tobecapableofcarryingthedesignloadforalloperatingconditions.3.9B.3.4.2ReactorPressureVesselStabilizerTheRPVstabilizer,whichismassiveandwellsupported,isdesignedasaSafetyClass1linear-typecomponentsupportinaccordancewiththerequirementsofASMEBoilerandPressureVesselCodeSectionIII,SubsectionNF.TheRPVstabilizersattachtotheringgirder/startrussstructure.Theringgirder/startrussstructure,whichisthetopextensionoftheshieldwall,isconsideredbuildingsteelandisdesignedtoAISCcriteria(seeSection3.8.3.2).ThestabilizerprovidesareactionpointneartheupperendoftheRPVtoresisthorizontalloadsduetoeffectssuchasearthquakeandpiperupture.Thedesignloadsandloadcombinations,stresscriteria,calculatedstresses,andallowablestressesinthecriticalareasaresummarizedinTable3.9B-2f.Deformationislimitedbyrequiringproperstresslimits.3.9B.3.4.3NSSSFloor-MountedEquipment(Pumps,HeatExchanger,andRCICTurbine)TheNSSSfloor-mountedequipmentisanalyzedtoverifytheadequacyofitssupportstructuresundervariousplantoperatingconditions.InallcasesthestressloadsinthecriticalUSARRevision83.9B-53November1995 NineMilePointUnit2FSARsupportareasarewithintheASMECodeallowables.Theloadingconditions,stresscriteria,andtheallowablestressesinthecriticalsupportareasaregiveninTable3.9B-2intherespectiveequipmenttable.3.9B.3.4.4SupportsforASMESafetyClass1,2,and3ActiveComponentsASMESafetyClass1,2,and3activecomponentsareeitherpumpsorvalves.Sincevalvesaresupportedbypipingandnottiedtobuildingstructures,pipedesigncriteriagovern.CategoryIactivepumpsupportsarequalifiedforseismicandhydrodynamicloadsbytestingwhenthepumpsupportsandthepumpsfulfillthefollowingconditions:1.Simulateactualmountingconditions.2.Simulateallstaticanddynamicloadingsonthepump.3.Monitorpumpoperabilityduringtesting.4~5.Normaloperationofthepumpduringandafterthetestindicatesthatthesupportsareadequate.Anydeflectionordeformationofthepumpsupportsthatprecludestheoperabilityofthepumpisnotaccepted.Supportsareinspectedforstructuralintegrityafterthetest..Anycrackingorpermanentdeformationisnotaccepted.Seismicandhydrodynamicqualificationofcomponentsupportsbyanalysisisgenerallyaccomplishedasfollows:Stressesatallsupportelementsandpartssuchaspumpholddowns,andbaseplateholddownbolts,pumpsupportpads,pumppedestal,andfoundationarecheckedtobewithintheallowablelimitsasspecifiedinASMESubsectionNF.2~3~Fornormalandupsetplantconditions,thedeflectionsanddeformationsofthesupportareassuredtobewithintheelasticlimitsandmustnotexceedthevaluespermittedbythedesignerbasedonhisdesignverificationteststoensuretheoperabilityofthepumps.Foremergencyandfaultedplantconditions,thedeformationsmustnotexceedthevaluespermittedbythedesignertoensuretheoperabilityofthepumps.USARRevision83.9B-54November1995 NineMilePointUnit2FSAR3.9B.3.4.5BoltingSupportComotuooltThesupportboltingoftheRWCUpumpisdesignedfortheeffectsofpipeandSSEloadstothe.requirementsofASMESectionIII,AppendixXVII.Thestresslimitsof0.25Syfortensionand0.20Syforshearareused.Theequipment-to-baseplateboltingofRCIC/SLCpumpsandRCICturbinesatisfiesthefollowingdesigncriteria:Fornormalandupsetconditions,1.0Sisusedforprimarymembraneand1.5Sforprimarymembraneplusbending,whereSistheallowablestresslimitfromASMESectionIII,AppendixI,TableI-7.3.Foremergencyandfaultedconditions,stressesshallbelessthan1.2timestheallowablelimitsfornormalandupsetconditions.PiinSuortsandPie-MountedEuimentSuortsTheallowablestressesforboltsmeetthecriteriaofASMESectionIII,SubsectionNF.ForservicelevelsAandB,theboltsmeetthecriteriaofNF-3280.ForservicelevelsCandD,XVII-2460withfactorsindicatedunderXVII-2110isapplicabletothedesignrequirementsofbolting.Thecalculatedstressesunderthesecategoriesdonotexceedthespecifiedminimumyieldstressesattemperature.Hih-StetBotsBoltsSA-193,GrB7,andASTMA-490-76aareusedonBergen-PattersonriserclampsforhangerattachmentsandE-systemsclampsforsnubberattachments,respectively.TheRWCUpumpanddrivermotorholddownboltsareSA-193,GrB7,andSAEGr8,respectively.TheRCICpumpandholddownboltsareSA-449.TheSLCpumpanddrivermotorholddownboltsareSA-193,GrB7,andSAEGr8,respectively.3.9B.4ControlRodDriveSystemUnit2isequippedwithahydraulicCRDsystemthatincludestheCRDmechanism,theHCU,thecondensatesupplysystem,andtheSDV,andextendstothecouplinginterfacewiththecontrolrods.3.9B.4.1DescriptiveInformationonCRDSystemDescriptiveinformationontheCRDsandtheentiredriveandcontrolsystemiscontainedinSection4.6.USARRevision83.9B-55November1995 NineMilePointUnit2FSAR3.9B.4.2ApplicableCRDSystemDesignSpecificationsTheCRDsystemisdesignedtomeetthefunctionaldesigncriteriaoutlinedinSection4.6andconsistsofthefollowing:1.LockingpistonCRD.2.Hydrauliccontrolunit.3.Hydraulicpowersupply(pumps).4.Interconnectingpiping.5.Flow,andpressureandisolationvalves.6.Instrumentationandelectricalcontrols.QualitygroupclassificationisnotapplicabletotheCRD.ThosecomponentsoftheCRDformingpartoftheprimarypressureboundaryaredesignedaccordingtoASMESectionIII.ThequalitygroupclassificationoftheCRDhydraulicsystemisoutlinedinTable3.2-1,andthecomponentsaredesignedaccordingtothecodesandstandardsgoverningtheindividualqualitygroups.PertinentaspectsofthedesignandqualificationoftheCRDsystemcomponentsarediscussedinthefollowingsections:transientsinSection3.9B.1.1,faultedconditionsinSection3.9B.1.4,seismictestinginSection3.9B.2.2,loadcombinationsandstresslimitsinTable3.9B-2a.Tables3.9B-2gand3.9B-2sshowtheloadcombinations,analyticalmethods,andallowableandcalculatedstressvaluesforthehighlystressedareasoftheCRDhousingandsupports.3.9B.4.3DesignLoads,StressLimits,andAllowableDeformationTheASMECodecomponentsoftheCRDsystemhavebeenevaluatedanalytically,andthedesignloadcombinationsandstresslimitsarelistedinTable3.9B-2a.Forthenon-Codecomponents,experimentaltestingwasusedtodeterminetheCRDperformanceunderallpossibleconditionsasdescribedinSection3.9B.4.4.DeformationhasbeencomparedwiththeallowablesandisnotalimitingfactorintheanalysisoftheCRDcomponents.3.9B.4.4CRDPerformanceAssuranceProgramTheCRDtestprogramconsistsofthefollowingtests:1.Developmenttests.2.Factoryqualitycontroltests.USARRevision83.9B-56November1995 NineMilePointUnit2FSAR3.5-yrmaintenancelifetests.4.1.5xdesignlifetests.5.Operationaltests.6.Acceptancetests.7.Surveillancetests.Alltheabovetestsexcept3and4arediscussedinSections4.6.3through4.6.3.1.1.5.Tests3and4arediscussedasfollows:Test3-5-MaintenanceLifeTestsFourCRDsarenormallypickedatrandomfromtheproductionstockeachyearandsubjectedtovarioustestsundersimulatedreactorconditionsandmorethanone-eighthofthecyclesspecifiedinSection3.9B.1.1.Uponcompletionofthetestprogram,CRDsmustmeetorsurpasstheminimumspecifiedperformancerequirements.ThissamplesizeisbasedonthelargeproductionvolumeduringthemanufacturingofCRDsthroughandincludingModel7RDB144C.ThepracticeoftestingtheCRDscontinuesforModel7RDB144EG001.However,duetothelowerproductionvolumeexpectedforthismodel,fewerdrivesperyeararetested.Test-.5Desi'feTestsWhenasignificantdesignchangeismadetothecomponentsofthedrive,thedriveissubjectedtoaseriesoftestsequivalentto1.5timesthelifetestcyclesspecifiedinSection3.9B.1.1.TwoCRDsunderwentsuchtestingin1976.Uponcompletionofthetestprogram,theseCRDsmetorexceededtheminimumspecifiedperformancerequirements.3.9B.5ReactorCoreSupportStructuresandPressureVesselInternals3.9B.5.1DesignArrangementsThecoresupportstructuresandreactorvesselinternals(exclusiveoffuel,controlrods,CRDs,andin-corenuclearinstrumentation)areidentifiedbelow:1~Coresupportstructures:a0b.Co'd~Shroud.Shroudsupport.Coreplateandholddownbolts.Topguide.USARRevision83.9B-57November1995 NineMilePointUnit2FSARe.Fuelsupports.f.CRDhousing.g.Controlrodguidetubes.2.Reactorinternals:a.Jetpumpassembliesandinstrumentationpenetrationseal,instrumentationlines.*b.Feedwaterspargers.*c.Vesselheadspraynozzle.d.Differentialpressureandliquidcontrollines.e.In-corefluxmonitorguidetubes.f.Initialstartupneutronsources.*g.Surveillancesampleholders.*h.Corespraylinesandspargers.i.In-coreinstrumenthousings.LPCIcoupling.k.Steamdryer.*l.Shroudheadandsteamseparatorassembly.*m.Guiderods.*n.CRDthermalsleeves.*AgeneralassemblydrawingoftheimportantreactorcomponentsisshownonFigure5.3-4.ThefloodableinnervolumeoftheRPVinsidethecoreshrouduptothelevelofthe)etpumpsuctioninletandinternalflowpathfollowingapostulatedrecirculationlinebreakaredepictedinFigure3.9B-2.Thedesignarrangementofthereactorinternalssuchasthejetpumps,steamseparators,andguidetube,issuchthatoneendisunrestrictedandthusfreetoexpand.*Nonsafety-classequipment.USARRevision83.9B-58November1995 NineMilePointUnit2FSAR3.9B.5.1.1CoreSupportStructuresThesestructuresformpartitionswithinthereactorvesseltosustainpressuredifferentialsacrossthepartitions,directtheflowofthecoolantwater,andlaterallylocateandsupportthefuelassemblies.ghhoudTheshroudsupport,shroud,andtopguidemakeupastainlesssteelcylindricalassembly.Thefirsttwostructuresprovideapartitiontoseparatetheupwardflowofcoolantthroughthecorefromthedownwardrecirculationflow.Thispartitionseparatesthecoreregionfromthedowncomerannulus,providingafloodableregionfollowingarecirculationlinebreak.Thevolumeenclosedbythisassemblyischaracterizedbythreeregions.Theupperportionsurroundsthecoredischargeplenum,whichisboundedbytheshroudheadontopandthetopguidegridplatebelow.Thecentralportionoftheshroudsurroundstheactivefuelandformsthelongestsectionoftheassembly.Thissectionisboundedatthetopbythegridplateandatthebottombythecoreplate.Thelowerportion,surroundingpartofthelowerplenum,isweldedtotheRPVshroudsupport.u0Theshroudsupportisdesignedtosupporttheshroudandto.supportandlocatethejetpumps.TheshroudsupportprovidesanannularbafflebetweentheRPVandtheshroud.Thejetpumpdischargediffuserspenetratetheshroudsupporttointroducethecoolanttotheinletplenumbelowthecore.ShroudHeadandSteamSearatorssemblThiscomponentisnotacoresupportstructureorsafetyclasscomponent.ItisdiscussedheretodescribethecoolantflowpathsintheRPV.Theshroudheadandsteamseparatorassemblyisboltedtothetopofthetopguidetoformthetopofthecoredischargeplenum.Thisplenumprovidesamixingchamberforthesteam-watermixturebeforeitentersthesteamseparators.Individualstainlesssteelaxialflowsteamseparatorsareattachedtothetopofstandpipesthatareweldedintotheshroudhead.Thesteamseparatorshavenomovingparts.Ineachseparator,thesteam-watermixturerisingthroughthestandpipepassesvanesthatimpartaspintoestablishavortex,separatingthewaterfromthesteam.Theseparatedwaterflowsfromthelowerportionofthesteamseparatorintothedowncomerannulus.CreatThecoreplateconsistsofacircularstainlesssteelplatewithboredholesstiffenedwitharim-and-beamstructure.Theplateprovideslateralsupportandguidanceforthecontrolrodguidetubes,in-corefluxmonitorguidetubes,peripheralfuelUSARRevision83.9B-59November1995 NineMilePointUnit2FSARsupports,andstartupneutronsources.Thelasttwoitemsarealsosupportedverticallybythecoresupportplate.Theentireassemblyisboltedtoasupportledgeonthelowerportionsoftheshroud.ToGidThetopguideisformedbyaseriesofstainlesssteelbeamsjoinedatrightanglestoformsquareopeningsandfastenedtoaperipheralrim.Eachopeningprovideslateralsupportandguidanceforfourfuelassembliesor,inthecaseofperipheralfuel,lessthanfourfuelassemblies.Socketsareprovidedinthebottomofthebeamintersectionstoanchorthein-corefluxmonitorsandstartupneutronsources.Therimofthetopguiderestsonaledgebetweentheupperandcentralportionsoftheshroud.Thetopguidehasalignmentpinsthatengageandbearagainstslotsintheshroudthatareusedtopositiontheassemblycorrectlybeforeitissecured.Lateralrestraintisprovidedbywedgeblocksbetweenthetopguideandtheshroudwall.uelSuortThefuelsupportsshownonFigure3.9B-3areoftwobasic.types:peripheralsupportsandfour-lobedorificedfuelsupports.Theperipheralfuelsupportislocatedattheouteredgeoftheactivecoreandisnotadjacenttocontrolrods.Eachperipheralfuelsupportsupportsonefuelassemblyandcontainsasingleorificeassemblydesignedtoensurepropercoolantflowtotheperipheralfuelassembly.Eachfour-lobedorificedfuelsupportsupportsfourfuelassembliesandhasfourorificeplatestoensurepropercoolantflowdistributiontoeachrod-controlledfuelassembly.Thefour-lobedorificedfuelsupportsrestinthetopofthecontrolrodguidetubeswhicharesupportedlaterallybythecoreplate.Thecontrolrodspassthroughslotsinthecenterofthefour-lobedorificedfuelsupport.Acontrolrodandthefouradjacentfuel.assembliesrepresentacorecelldescribedinSection4.4.2.CotroodGuideubesThecontrolrodguidetubes,locatedinsidethevessel,extendfromthetopoftheCRDhousingsupthroughholesinthecoreplate.Eachtubeisdesignedastheguideforacontrolrodandastheverticalsupportforafour-lobedorificedfuelsupportpieceandthefourfuelassembliessurroundingthecontrolrod.ThebottomoftheguidetubeissupportedbytheCRDhousing,whichinturntransmitstheweightoftheguidetube,fuelsupport,andfuelassembliestothereactorvesselbottomhead.AthermalsleeveisinsertedintotheCRDhousingfrombelowandisrotatedtolockthecontrolrodguidetubeinplace.AkeyisinsertedintoalockingslotinthebottomoftheCRDhousingtoholdthethermalsleeveinposition.USARRevision83.9B-60November1995 NineMilePointUnit2FSAR3.9B.5.1.2ReactorVesselInternalsJetussembl'estThejetpumpassembliesarenotcoresupportstructuresbutarediscussedheretodescribecoolantflowpathsintheRPV.ThejetpumpassembliesarelocatedintwosemicirculargroupsinthedowncomerannulusbetweenthecoreshroudandtheRPVwall.ThedesignandperformanceofthejetpumparecoveredindetailinAPED-5460""andNEDO-10602"".Eachstainlesssteeljetpumpconsistsofdrivingnozzles,suctioninlet,throatormixingsection,anddiffuser(Figure3.9B-4).Thedrivingnozzle,suctioninlet,andthroatarejoinedtogetherasaremovableunit,andthediffuserispermanentlyinstalled.High-pressurewaterfromtherecirculationpumpsissuppliedtoeachpairofjetpumpsthroughariserpipeweldedtotherecirculationinletnozzlethermalsleeve.AriserbraceconsistsofcantileverbeamsweldedtoariserpipeandtopadsontheRPVwall.Thenozzleentrysectionisconnectedtotheriserbyametal-to-metal,spherical-to-conicalsealjoint.Firmcontactismaintainedbyaholddownclamp.Thethroatsectionissupportedlaterallybyabracketattachedtotheriser.Thereisaslip-fitjointbetweenthethroatanddiffuser.Thediffuserisagradualconicalsectionchangingtoastraightcylindricalsectionatthelowerend.NMPCwillreducethepreloadonthebeamsfrom30to25kipsinaccordancewithGE'srecommendations.Theexpectedlifeofthesebeamswithoutcrackingis19to40yr.ISIofthejetpumpholddownbeamwillbeperformedtodetectcracking.InspectionfrequencieswillbebasedonaleadplantexperienceandGEtesting.SteamresThesteamdryerassemblyisneitheracoresupportstructurenorasafetyclasscomponent.Itisdiscussedheretodescribecoolantflowpathsinthevessel.Thesteamdryersremovemoisturefromthewetsteamleavingthesteamseparators.Theextractedmoistureflowsdownthedryervanestothecollectingtroughs,thenflowsthroughtubesintothedowncomerannulus.Askirtextendsfromthebottomofthedryervanehousingtothesteamseparatorstandpipebelowthewaterlevel.Thisskirtformsasealbetweenthewetsteamplenumandthedrysteamflowingfromthetopofthedryerstothesteamoutletnozzles.Thesteamdryerandshroudheadarepositionedinthevesselduringinstallationwiththeaidofverticalguiderods.ThedryerassemblyrestsonsteamdryersupportbracketsattachedtotheRPVwall.Upwardmovementofthedryerassembly,whichmayoccurunderaccidentconditions,isrestrictedbysteamdryerholddownbracketsattachedtotheRPVtophead.USARRevision83.9B-61November1995 NineMilePointUnit2FSAReedwateSrersThesecomponentsarenotcoresupportstructuresnorsafetyclasscomponents.Theyarediscussedheretodescribeflowpathsinthevessel.Thefeedwaterspargersarestainlesssteelheaderslocatedinthemixingplenum.abovethedowncomerannulus.Aseparatespargerisfittedtoeachfeedwaternozzleandisshapedtoconformtothecurveofthevesselwall..Spargerendbracketsarepinnedtovesselbracketstosupportthespargers.Feedwaterflowentersthecenterofthespargersandisdischargedradiallyinwardtomixthecoolerfeedwaterwiththedowncomerflowfromthesteamseparatorsandsteamdryerbeforeitcontactsthevesselwall.Thefeedwateralsoservestocondensethesteamintheregionabovethedowncomerannulusandtosubcoolthewaterflowingtothejetpumpsandrecirculationpumps.esThiscomponentisnotacoresupportstructure.ItisdiscussedheretodescribeasafetyclassfeatureinsidetheRPV.Thecorespraylinesarethemeansfordirectingflowtothecorespraynozzles,whichdistributecoolantduringaccidentconditions.TwocorespraylinesentertheRPVthroughthetwocorespraynozzles(Section5.4).ThelinesdivideimmediatelyinsidetheRPV.ThetwohalvesareroutedtooppositesidesoftheRPVandaresupportedbyclampsattachedtothevesselwall.Thelinesarethenrouteddownwardintothedowncomerannulusandpassthroughthetopguidecylinderimmediatelybelowtheflange.Theflowdividesagainasitentersthecenterofthesemicircularsparger,whichisroutedhalfwayaroundtheinsideofthetopguidecylinder.Thetwospargersaresupportedbybracketsdesignedtoaccommodatethermalexpansion.Thelineroutingandsupportsaredesignedtoaccommodatedifferentialmovementbetweenthetopguideandvessel.Theothercorespraylineisidenticalexceptthatitenterstheoppositesideofthevesselandthespargersareataslightlydifferentelevationinsidethetopguidecylinder.Thecorrectspraydistributionpatternisprovidedbyacombinationofdistributionnozzlespointedradiallyinwardanddownwardfromthespargers(Section6.3).VesseleaSaoleThiscomponentisnotacoresupportstructure.ItisincludedheretodescribeasafetyclassfeatureintheRPV.WhenreactorcoolantisreturnedtotheRPV,partoftheflowcanbedivertedtoaspraynozzleinthereactorhead.ThisspraymaintainssaturatedconditionsintheRPVheadvolumebycondensingsteambeinggeneratedbythehotRPVwallsandinternals.ThesprayalsodecreasesthermalstratificationintheRPVcoolant.ThisensuresthatthewaterlevelintheRPVcanrise.ThehigherwaterlevelprovidesconductioncoolingtomoreofthemassofmetaloftheRPVand,therefore,helpstomaintainthecooldownrate.ThevesselheadspraynozzleismountedtoashortlengthUSARRevision83.9B-62November1995 INineMilePointUnit2FSARofpipeandaflange,whichisboltedtoamatingflangeontheRPVheadnozzle(Section5.4.7).DifferntialPressureadLiuidControlieThiscomponentisnotacoresupportstructure.ItisincludedheretodescribeasafetyclasscomponentintheRPV.Thedifferentialpressureandliquidcontrollinesenterthevesselthroughtwobottomheadpenetrationsandserveadualfunctionwithinthereactorvessel:tosensethedifferentialpressureacrossthecoresupportplate(Section5.4),andtoprovideapathfortheinjectionoftheSLCsolutionintothecoolantstream.Onelineterminatesnearthelowershroudwithaperforatedlengthbelowthecoresupportplate.Itisusedtosensethepressurebelowthecoresupportplateduringnormaloperationandtoinjectliquidcontrolsolutionifrequired.Thislocationfacilitatesgoodmixinganddispersion.Theotherlineterminatesimmediatelyabovethecoresupportplateandsensesthepressureintheregionoutsidethefuelassemblies.-ceuebesThesecomponentsarenotcoresupportstructures.Theyareasafetyclassfeatureandprovideameansofpositioningfixeddetectorsinthecoreaswellasprovideapathforcalibrationmonitors(TIPsystem).Thein-corefluxmonitorguidetubesextendfromthetopofthein-corefluxmonitorhousing(Section5.4)inthelowerplenumtothetopofthecoresupportplate.ThepowerrangedetectorsforthepowerrangemonitoringunitsandthedrytubesfortheSRMandIRMdetectorsareinsertedthroughtheguidetubes.Alatticeworkofclamps,tiebars,andspacersgivelateralsupportandrigiditytotheguidetubes.Theboltsandclampsarewelded,afterassembly,topreventlooseningduringreactoroperation.SeceSaeodesThiscomponentisnotacoresupportstructureorasafetyclasscomponent.Thesurveillancesampleholdersareweldedbasketscontainingimpactandtensilespecimencapsules(Section5.4).Thebasketshangfromthebracketsthat,areattachedtotheinsidewalloftheRPVandextendtomid-heightoftheactivecore.TheradialpositionsarechosentoexposethespecimenstothesameenvironmentandmaximumneutronfluxesexperiencedbytheRPVitselfwhileavoidingjetpumpremovalinterferenceordamage.esseootcL'eetatosThiscomponentisasafetyclassfeature,notacoresupportstructure,butisdiscussedheretodescribethecoolantflowpathsintheRPV.ThreeLPCIlinespenetratethecoreshroudUSARRevision83.9B-63November1995 NineMilePointUnit2FSARthroughseparateLPCInozzles.CoolantisdischargedinsidethecoreshroudimmediatelybelowthetopguidetorestoreandmaintainthewaterlevelinthevesselrequiredafteraLOCA.3.9B.5.2DesignLoadingConditions3.9B.5.2.1EventstoBeEvaluatedExaminationofthespectrumofconditionsforwhichthesafetydesignbasismustbesatisfiedbycoresupportstructuresandESFcomponentsrevealsthefollowingsignificantfaultedevents:1~ec'rcut'neBreaAbreakinarecirculationlinebetweentheRPVandtherecirculationpumpsuction.2~SteamineBreakAccidentAbreakinoneMSLbetweentheRPVandtheflowrestrictor.Theaccidentresultsinsignificantpressuredifferentialsacrosssomeofthestructureswithinthereactor.reactorinternalstosignificantforcesasaresultofgroundmotion.4.SRVdischargeincombinationwithaSSE.Analysisofotherconditionsexistingduringnormaloperation,abnormaloperationaltransients,andaccidentsshowsthattheloadsaffectingthecoresupportstructuresandotherESFreactorinternalsarelessseverethanthesefourpostulatedevents.ThefaultedconditionsfortheRPVinternalsarediscussedinSection3.9B.1.4.LoadcombinationsandanalysisfortheRPVinternalsarediscussedinSection3.9B.3.1andTables3.9B-2hand3.9B-2i.ThestressdeformationandfatiguelimitsarediscussedinSections3.9B.5.3.5and3.9B.5.3.6.3.9B.5.2.2PressureDifferentialDuringRapidDepressurizationAdigitalcomputercodeisusedtoanalyzethetransientconditionswithintheRPVfollowingtherecirculationlinebreakaccidentandthesteamlinebreakaccident.Theanalyticalmodelofthevesselconsistsofninenodesthatareconnectedtothenecessaryadjoiningnodesbyflowpathshavingtherequiredresistanceandinertialcharacteristics.Theprogramsolvestheenergyandmassconservationequationsforeachnodetogivethedepressurizationratesandpressureinthevariousregionsofthereactor.Figure3.9B-5showstheninereactornodes.ThecomputercodeusedistheGEShort-TermThermal-HydraulicModel"".ThismodelhasbeenapprovedforuseinECCSconformanceevaluationunder10CFR50AppendixK.Inordertoadequatelydescribetheblowdownpressureeffectontheindividualassemblycomponents,threefeaturesareincludedinUSARRevision83.9B-64November1995 NineMilePointUnit2FSARthemodelthatarenotapplicabletotheECCSanalysisandarethereforenotdescribedinNEDE-20566"".Theseadditionalfeaturesarediscussedasfollows:I1.Theliquidlevelinthesteamseparatorregionandintheannulusbetweenthedryerskirtandthepressurevesselistrackedtomoreaccuratelydeterminetheflowandmixturequalityinthesteamdryerandinthesteamline.2~TheflowpathbetweenthebypassregionandtheshroudheadismoreaccuratelymodeledsincethefuelassemblypressuredifferentialPisinfluencedbyflashingintheguidetubesandbypassregionforasteamlinebreak.IntheECCSanalysis,themomentumequationissolvedinthisflowpath,butitsirreversiblelosscoefficientisconservativelysetatanarbitrarylowvalue.3~Theenthalpiesintheguidetubesandthebypassarecalculatedseparately,sincethefuelassemblyPisinfluencedbyflashingintheseregions.IntheECCSanalysis,theseregionsarelumped.3.9B.5.2.3RecirculationLineandSteamLineBreakAccidentDefinitioBotharecirculationlinebreak(thelargestliquidbreak)andasteamlinebreakinsidecontainment(thelargeststeambreak)areconsideredindeterminingtheDBAfortheESFreactorinternals.TherecirculationlinebreakisthesameasthedesignbasisLOCA(Section6.3).Asudden,completecircumferentialbreakisassumedtooccurinonerecirculationloop.ThepressuredifferentialsonthereactorinternalsandcoresupportstructuresareinallcaseslowerthanthosefortheMSLbreak.Theanalysisofthesteamlinebreakassumesasudden,completecircumferentialbreakofoneMSLbetweentheRPVandtheMSLrestrictor.Asteamlinebreakupstreamoftheflowrestrictorsproducesalargerblowdownareaandthusafasterdepressurizationratethanabreakdownstreamoftherestrictors.Thelargerblowdownarearesultsingreaterpressuredifferentialsacrossthereactorinternalstructures.Thesteamlinebreakaccidentproducessignificantlyhigherpressuredifferentialsacrossthereactorinternalstructuresthandoestherecirculationlinebreak.Thisresultsfromthehigherreactordepressurizationrateassociatedwiththesteamlinebreak.Therefore,thesteamlinebreakistheDBAforinternalpressuredifferentials.USARRevision83.9B-65November1995 NineMilePointUnit2FSARffectso't'aleactorPowerandCoreoThemaximuminternalpressureloadscanbeconsideredtobecomposedoftwoparts:steady-stateandtransientpressuredifferentials.Foragivenplant,thecoreflowandpowerarethetwomajorfactorsthatinfluencethereactorinternalpressuredifferentials.Thecoreflowessentiallyaffectsonlythesteady-statedifferentialpressure.Forafixedpower,thegreaterthecoreflow,thelargerwillbethesteady-statepressuredifferentials.Thecorepoweraffectsboththesteady-stateandthetransientdifferentialpressure.Asthepowerisdecreased,thereislessvoidinginthecoreand,consequently,thesteady-statecorepressuredifferentialisless.However,lessvoidinginthecorealsomeansthatlesssteamisgeneratedintheRPVandthusthedepressurizationrateandthetransientpartofthemaximumpressureloadisincreased.Asaresult,thetotalloadsonsomecomponentsarehigheratlowpower.Toensurethatthecalculatedpressuredifferencesboundthosethatcouldbeexpectedifasteamlinebreakshouldoccur,ananalysisisconductedatalowpower,highrecirculationflowconditioninadditiontothestandardsafetyanalysisconditionathighpower,ratedrecirculationflow.Thepowerchosenforanalysisistheminimumvaluepermittedbytherecirculationsystemcontrolsatratedrecirculationdriveflow(ratedrecirculationdriveflowisthedriveflowusedtoachieveratedcoreflow.Thisconditionmaximizesthoseloadsthatareinverselyproportionaltopower.ecetsTheseismicandhydrodynamicloadsactingonthestructureswithintheRPVarebasedonadynamicanalysisasdescribedinSections3.9Band3.9B.2.5.Dynamicanalysisisperformedbycouplingthelumpedmassmodelof.theRPVandinternalswiththebuildingmodeltodeterminetheforces,acceleration,andmomenttime-historyinthereactorvesselandinternals.Thisisdoneusingthemodalsuperpositionmethod.ARSarealsogeneratedforsubsystemanalysesofselectedcomponents.3.9B.5.3DesignBases3.9B.5.3.1SafetyDesignBasesThereactorcoresupportstructuresandinternalsmeetthefollowingsafetydesignbases:TheyarearrangedtoprovideafloodablevolumeinwhichthecorecanbeadequatelycooledintheeventofabreachinthenuclearsystemprocessbarrierexternaltotheRPV.USARRevision83.9B-66November1995 NineMilePointUnit2FSAR2.Deformationislimitedtoassurethatthecontrolrodsandcorestandbycoolingsystemscanperformtheirsafetyfunctions.3~Mechanicaldesignofapplicablestructuresassuresthatsafetydesignbases1and2aresatisfiedsothatthesafeshutdownoftheplantandremovalofdecayheatarenotimpaired.3.9B.5.3.2PowerGenerationDesignBasesThereactorcoresupportstructuresandinternalsaredesignedtothefollowingpowergenerationdesignbases:1.Theyprovidethepropercoolantdistributionduringallanticipatednormaloperatingconditionsuptofullpoweroperationofthecorewithoutfueldamage.2.Theyarearrangedtofacilitaterefuelingoperations.3.Theyaredesignedtofacilitateinspection.3.9B.5.3.3DesignLoadingCategoriesThebasisfordeterminingfaultedloadsonthereactorinternalsisshownforseismicandhydrodynamicloadsinSections3.7B,3.8B,and3.9B.2.5,andforpiperuptureloadsinSections3.9B.5.2.3and3.9B.5.3.4.Loadingconditionsforshroudsupport,coresupportstructures,CRDhousing(jetpumps,LPCIcoupling,andcontrolrodguidetubesaregiveninTable3.9B-2undertherespectiveequipmenttable.CoresupportstructureandsafetyclassinternalsstresslimitsareconsistentwithASMESectionIII,ParagraphNA-2140,andassociatedstresslimitscontainedinAddendadatedthroughSummer1976..LevelA,B,C,andDservicelimitsdefinedinWinter1976Addendawhichreplacenormal,upset,emergency,andfaultedconditionlimitsarenotreflectedindesigndocumentsforcoresupportstructuresandothersafetyclassinternalsforthisreactor.However,forthesecomponents,LevelA,B,C,andDservicelimitsarejudgedtobeequivalenttothenormal,upset,emergency,andfaultedloadingconditionlimitsand,therefore,forclarity,bothsetsofnomenclatureareretainedherein.StressintensityandotherdesignlimitsarediscussedinSection3.9B.5.3.5.ThecoresupportstructuresthatarefabricatedaspartoftheRPVassemblyarediscussedinSection3.9B.1.3.Thedesignrequirementsforequipmentclassifiedas"otherinternals"(e.g.,steamdryersandshroudheads)werespecifiedbythedesignerwithappropriateconsiderationoftheintendedserviceoftheequipmentandexpectedplantandenvironmentalconditionsunderwhichitistooperate.Wherepossible,designUSARRevision83.9B-67November1995 NineMilePointUnit2FSARrequirementsarebasedonapplicableindustrycodesandstandards.Ifthesearenotavailable,thedesignerreliesonacceptedindustryorengineeringpractices.3.9B.5.3.4ResponseofInternalsDuetoInsideSteamBreakAccidentThemaximumpressureloadsactingonthereactorinternalcomponentsresultfromaninsidesteamlinebreak,andonsomecomponentstheloadsaremaximumwhenoperatingattheminimumpowerassociatedwiththemaximumcoreflow.Thishasbeensubstantiatedbytheanalyticalcomparisonofliquidversussteambreaksandbytheinvestigationoftheeffectsofcorepowerandcoreflow.Ithasalsobeenpointedoutthatitispossiblebutnotprobablethatthereactorwouldbeoperatingattheratherabnormalconditionofminimumpowerandmaximumcoreflow.Morerealistically,thereactorwouldbeatornearafullpowerconditionandthusthemaximumpressureloadswouldactontheinternalcomponents.3.9B.5.3.5Stress,Deformation,andFatigueLimitsforEngineeredSafetyFeatureReactorInternals(ExceptCoreSupportStructure)ThestressdeformationandfatiguecriterialistedinTables3.9B-5through3.9B-8areused,orthecriteriaarebasedonthecriteriaestablishedinapplicablecodesandstandardsforsimilarequipment,bymanufacturers'tandards,orbyempiricalmethodsbasedonfieldexperienceandtesting.ForthequantitySF(minimumsafetyfactor)appearinginthosetables,thefollowingvalueswereused.Service~eveDesignCoditioSFDNormalUpsetEmergencyFaulted2.252.251.51~125ComponentsinsidetheRPV,suchascontrolrodsthatmustmoveduringaccidentconditions,havebeenexaminedforadequateclearancesduringemergencyandfaultedconditions.Nomechanicalclearanceproblemshavebeenidentified.TheforcingfunctionsapplicabletothereactorinternalsarediscussedinSection3.9B.2.5.USARRevision83.9B-68November1995 NineMilePointUnit2FSAR3.9B.5.3.6Stress,Deformation,andFatigueLimitsforCoreSupportStructuresThestress,deformation,andfatiguecriteriapresentedinTables3.9B-9through3.9B-11areused.Thesecriteriaaresupplemented,whereapplicable,bythecriteriaforthereactorinternalsintheprevioussection.USARRevision83.9B-69November1995 NineMilePointUnit2FSAR3.9B.6References1~2~3~4~5.6.7~8~9.10.12.13~Kalnins,A.AnalysisofShellsofRevolutionsubjectedtoSymmetricalandNon-SymmetricalLoads,inJournalofAppliedMechanics,Vol.31,September1964,pp467-476.Wilson,E.L.ADigitalComputerProgramfortheFiniteElementAnalysisofSolidswithNon-LinearMaterialProperties.AerojetGeneralCorporation,Sacramento,CA,TechnicalMemorandumNo.23,July1965.PVRCRecommendationsonToughnessRequirementsforFerriticMaterials.WeldingResearchCouncilBulletinNo.175,(datelater).Levy,S.andWilkinson,J.D.P.TheComponentElementMethodsinDynamics,McGrawHillCo.,NewYork,NY,1976.PISYSAnalysisofNRCProblem,NED0-24210,August1979.GeneralElectricStandardApplicationforReactorFuel,NEDE-24011-P-A(latestapprovedrevision).GeneralElectricStandardApplicationforReactorFuel-UnitedStatesSupplement,NEDE-24011-P-A-US,(latestapprovedrevision).NEDE-24057-P(ClassIII)andNEDO-24057(ClassI).AssessmentofReactorInternalsVibrationinBWR/4andBWR/5Plants,November1977.AlsoNEDO-24075-1-P(AmendmentNo.1datedDecember1978)andNEDE-2-P-24075(AmendmentNo.2datedJune1979).MarkIIContainmentDynamicForcingFunctionsInformationReport,NED0-21061,Revision3,June1978.DesignandPerformanceofG.E.BWRJetPumps.GeneralElectricCompany,AtomicPowerEquipmentDepartment,APED-5460,July1968.Moen,H.H.TestingofImprovedJetPumpsfortheBWR/6NuclearSystem.GeneralElectricCompany,AtomicPowerEquipmentDepartment,NED0-10602,June1972.AnalyticalModelforLoss-of-CoolantAnalysisinAccordancewith10CFR50,AppendixK.ProprietaryDocument,GeneralElectricCompany,NEDE-20566.BWRFuelAssemblyEvaluationofCombinedSafeShutdownEarthquake(SSE)andLoss-of-CoolantAccident(LOCA)Loadings,NEDE-21175-3-P,GeneralElectricCompany,July1982.USARRevision83-9B-70November1995 NineMilePointUnit2FSAR14.DesignandPerformanceofGeneralElectricBoilingWaterReactorMainSteamIsolationValves,APED-5750,GeneralElectricCompany,March1969.USARRevision83'B-71November1995

NineMilePointUnit2FSARTABLE3.9B-1PLANTEVENTSormalUsetandTestinCoditionBoltup<'>2.Designhydrostatictest3.Startup(100'F/hrheatuprate)+4.Dailyreductionto754power<'>5.Weeklyreduction504power">6.Controlrodpatternchange+No.of~Ccles12313012010,0002,0004007.Lossoffeedwaterheaters(80cyclestotal)8.504SSEeventatratedoperatingconditions(OBE)8010/50+9.Scram:a.Turbinegeneratortrip,feedwateron,isolationvalvesstayopen40b.Otherscrams140c.Lossoffeedwaterpumps,isolationvalvesclosed10d.Singlesafetyorreliefvalveblowdown10.Reductionto04power,hotstandby,shutdown(1004F/hrcooldownrate)+11.UnboltEmerencCondition12312.Scram:a.Reactoroverpressurewithdelayedscram,feedwaterstayson,isolationvalvesstayopen1(4)USARRevision81of2November1995 NineMilePointUnit2FSARTABLE3.9B-1(Cont'd.)eretioNo.of~Ccleeb.Automaticblowdown13.Improperstartofcoldrecirculationloop14.Suddenstartofpumpincoldrecirculationloop15.Hotstandby,RPVdrainshutoff,recirculationpumpsrestartquiteCodito1(4)1(4)1(4)1(4)16.Piperuptureandblowdown1(4)17.Safeshutdownearthquakeat.ratedoperatingconditions1(4)(4)Appliestoreactorpressurevesselonly.Bulkaveragevesselcoolanttemperaturechangeinany1-hrperiod.50peakOBEcyclesforNSSSpiping;10peakOBEcyclesforotherNSSSequipmentandcomponents.Annualencounterprobabilityoftheone-cycleeventsis<10~foremergencyand<10~forfaultedevents.USARRevision82of2November1995 NineMilePointUnit2FSARTABLE3.9B-2LOADCOMBINATIONSiSTRESSLIMITSiANDALLOWABLESTRESSESLoadCombinationsforASMESafetyClass1,2,and3NSSSComponentsINTRODUCTIONThistableliststhemajorsafety-relatedcomponentsintheplant,andbothcalculatedandallowablestresses.VariouspartsofthetablearereferencedinSection3.9B.Theformatsinvariouspartsofthetablearenotconsistentsincevariationinanalyticalmethodanddepthofdetail,necessarytodemonstratethesafetyaspectsofvariouscomponents,differs.INDEXa.ControlRodDriveb.ControlRodGuideTubec.In-coreHousingd.JetPumpse.HighestStressedRegionontheLPCICoupling(AttachmentRing)f.ReactorVesselSupportEquipmentg.ControlRodDriveHousingh.ReactorPressureVesselandShroudSupportAssemblyi.ReactorVesselInternalsandAssociatedEquipmentj.ActingTypeSafety/ReliefValvesSpring-LoadedDirectk.ReactorRecirculationSystemGateValvesl.RecirculationFlowControlValvem.ASMESafetyClass1RecirculationLoopPipingandPipe-MountedEquipment(Class1)n.ReactorRefuelingandServicingEquipmento.FuelAssembly(includingChannel)USARRevision81of4November1995 NineMilePointUnit2FSARTABLE3.9B-2(Cont'd.)p.RecirculationPumpq.StandbyLiquidControlTankr.ResidualHeatRemovalHeatExchangers.RCICTurbinet.RCICPumpu.ECCSPumpsv.StandbyLiquidControlPumpw.ReactorWaterCleanupSystemPumpx.ReactorWaterCleanupHeatExchangersy.ControlRodDriveHousingSupportsz.MainSteamIsolationValveUSARRevision82of4November1995 NineMilePointUnit2FSARTABLE3.9B-2(Cont'd.)LOADCOMBINATIONSANDACCEPTANCECRITERIAFORASMESAFETYCLASS1i2iAND3NSSSPIPINGANDEQUIPMENToao't'esignBasisEvaluationassServiceLevelN+SRV~~N+OBEN+OBE+SRV~~N+SSE+SRV~~N+SBA+SRVN+IBA+SRVN+SBA+SRV~pgN+SBA+OBE+SRV~pqN+IBA+OBE+SRV~pgN+SBA/IBA+SSE+SRVpggN+LOCA++SSEUpsetUpsetUpsetUpsetEmergencyUpsetFaultedFaulted<'>FaultedFaulted+EmergencyEmergency+FaultedFaultedFaultedFaultedFaulted<'>Faulted"'aulted"'aulted<'~EmergencyEmergency<"LOADDEFINITIONKEY:NOBESSESRVSRV~~SR'gNormaland/orabnormalloadsdependingonacceptancecriteriaOperatingbasisearthquakeloadsSafeshutdownearthquakeloadsSafety/reliefvalvedischarge-inducedloadsfromtwoadjacentvalves(onevalveactuatedwhenadjacentvalveiscycling)Loadsinducedbyactuationofallsafety/reliefvalvesthatactivatewithinmillisecondsofeachother(e.g.,turbinetripoperationaltransient)Loadsinducedbyactuationofsafety/reliefvalvesassociatedwiththeautomaticdepressurizationsystemthatactuatewithinmillisecondsofeachotherduringthepostulatedsmallorintermediatesizepiperuptureUSARRevision83of4November1995 NineMilePointUnit2FSARTABLE3.9B-2(Cont'd.)LOCALOCA)LOCQLOCALLOCA4LOCAsLOCA6LOCA7SBAIBALoss-of-coolantaccidentassociatedwiththepostulated'iperuptureoflargepipes(e.g.,mainsteam,feedwater,recirculationpiping)Poolswelldrag/falloutloadsonpipingandcomponentslocatedbetweenthemainventdischargeoutletandthesuppressionpoolwateruppersurfacePoolswellimpactloadsonpipingandcomponentslocatedabovethesuppressionpoolwateruppersurfaceOscillatingpressure-inducedloadsonsubmergedpipingandcomponentsduringcondensationoscillationsBuildingmotion-inducedloadsfromchuggingBuildingmotion-inducedloadsfrommainventairclearingVerticalandhorizontalloadsonmainventpipingAnnuluspressurizationloadsAbnormaltransientsassociatedwithsmallbreakaccidentAbnormaltransientsassociatedwithintermediatebreakaccidentAllASMESafetyClass1,2,and3pipingsystemsthatarerequiredtofunctionforsafeshutdownunderthepostulatedeventsaredesignedtomeetthefunctionalcapabilitycriteriainaccordancewithNED0-21985.ThemostlimitingcaseofloadcombinationamongLOCA,throughLOCA7.USARRevision84of4November1995 NineMilePointUnit2FSARTABLE3.9B-2dJETPUMPSCriteriaPrimarymembraneplusbendingstressbasedonASMESectionIIIForServiceLevelsAandB(normalandupset)condition:ForType30485504FS16,900psiSi<<<<=1.5Sps'orServiceLevelC(emergency)condition:ForType3048550FSa16,900psiS,<<=1.8Sps>ForServiceLevelD(faulted)condition:ForType304()550~FS~16,900psiS><~<<=36S~psiLoadCombinations1.Deadweight2.Pressure3.OBE4.SRV1.Deadweight2.Pressure3.OBE4.SRV1.Deadweight2.Pressure3.Chugging4.SRV5.SSEStressTypePrimarymembraneplusbendingPrimarymembraneplusbendingPrimarymembraneplusbendingAllowableStress(psi)25,35030,42060,840Calculated*Stress(psi)19,34619,34634,417TheNewLoadsAdequacyEvaluationhasconcludedthatthelistedlimitingdesignbasisloadsenvelopenewloads.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.9B-2eHIGHESTSTRESSEDREGIONONTHELPCICOUPLING(ATTACHMENTRING)(Bellow-TypeDesign)CriteriaLoadCombinationsStressTypeAllowableStress(psi)Calculated~Stress(psi)PrimarymembraneplusbendingstressbasedonASMESectionIIIforType304LForServiceLevelsA&B(normalandupset)condition:S-1.5S=20,925ps'orServiceLevelC(emergency)condition:Sute=2.25S=31,400psiForServiceLevelD(faulted)condition:Snse-3.6Sa=50,220ps@1.Normalloads2.Pressure3.OBE4.SRV1.Normalloads2.Pressure3.OBE4.SRV1.NormalLoads2.Pressure3.Annuluspressurization4.SSEPrimarymembraneplusbendingPrimarymembraneplusbendingPrimarymembraneplusbending20,92531,40050,22018,90018,90035,700TheNewLoadsAdequacyEvaluationhasconcludedthatthelisteddesignbasisloadsenvelopenewloads.USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.9B-2fREACTORPRESSUREVESSELSUPPORTEQUIPMENTRPVSupport(BearingPlate)CriteriaLoadingLocationAllowableStress(psi)Calculated"'tress(psi)PrimaryStressLimit:AISCspecificationforthedesign,~fabrication,anderectionofstructuralsteelforbuildingsFornormalandupsetcondition:AZSCallowablestresses,butwithouttheusualincreasesforearthquakeloadsForemergencycondition:1.5xAISCallowablestressesForfaultedcondition:1.67xAZSCallowablestressesforstructuralsteelmembers.Normalandupsetcondition:1.Deadweight2.OBE3.ScramEmergencycondition:1.Deadweight2.OBE3.ScramFaultedcondition:1.Deadweight2.SSE3.JetreactionloadBearingplateBearingplateBearingplateFl,(bearing)22,000Fb(bearing)33,000Fl,(bearing)36,000fl,=3,680fb=7,360fl,=9,080USARRevision8lof4November1995

NineMilePointUnit2FSARTABLE3.9B-2f(Cont'd.)RPVStabilizerCriteriaLoadingLocation"'llowableStress(psi)Calculated"'tress(psi)PrimaryStressLimit:ASMESectionIII,SubsectionNF-LineartypesupportMaterial:Bracketandyoke:SA-516,Gr.70Rod:SA-540,B24,C1.2Fornormalandupsetconditions:SubsectionNFallowablesForemergencyconditions:1.33xnormal/upsetallowablesForfaultedconditions:(0.7S/ft)xnormal/upsetallowablesUpsetcondition:1.Springpreload2.OBEEmergencycondition:1.Springpreload2.SSEFaultedcondition:1.Springpreload2.SSE3.JetreactionloadBracketYokeRodBracketBracketYokeYokeRodFb=29,000Fv=19i300Fb=34,600F,=27,610F~=104,490(2)f~=16,430f=4,390fb=26,550fg19~000fc=84'20USARRevision82of4November1995

NineMilePointUnit2FSARTABLE3.9B-2f(Cont'd.)StabilizerBracket-AdjacentShellCriteriaLoadingLocationAllowableStress(psi)Calculated"'tress{psi)ASMESectionIZZprimarylocalmembraneplusprimarybendinglimitforSA533GradeB,ClassI:Fornormalandupsetcondition:Si~~=1.5xS~Normalandupsetconditionloads:1.OBE2.PressureLocalmembraneplusbending40,05038,895Foremergencycondition:Su~i~=1.5xSForfaultedcondition:Sn~g15xS>Emergencyconditionloads:1.SSE2.PressureFaultedconditionloads:1.SSE2.Jetreaction3.PressureLocalmembraneplusbendingLocalmembraneplusbending63,45056,604USARRevision83of4November1995

NineMilePointUnit2PSARTABLE3.9B-2f(Cont'd.)OrificedPuelSupportsCriteriaLoadingDirectionAllowableLoads(LBF)CalculatedLoads(LBP)BasedonASMESubsectionNG-3228.4Fornormal,upset,andemergencyconditions:Lna<<=0.44LNormal,upset,andemergencyloads:Horizontal:Normaloperatingloads:OBE"SRVHorizontal4,4952,109Forfaultedcondition:L~<<=0.80L'~'ertical:Normaloperatingloads:SRVSCRAMPaultedloads:Horizontal:NormaloperatingloadsJetReactionAPSSEVertical:Normaloperatingloads:SRVSSESCRAMVerticalHorizontalVertical49,6328,17290,2404,0283,0758,044CumulativeusagefactorLimit=0.047ul0)<<)($)Bracketandyokehaveleaststressmargininemergencycondition,androdinfaultedcondition.Porthethreelocations,normalandupsetconditionhashigherstressmarginsascomparedtootherconditions.Faultedcategoryloadsareevaluatedwithemergencyallowablestresses;hence,emergencyconditionisnotevaluated.TheNewLoadsAdequacyEvaluationhasconcludedthatthelisteddesignbasisloadsenvelopethenewloads.Ultimatetestload.USARRevision84of4November1995

NineMilePointUnit2FSARTABLE3.9B-2hREACTORPRESSUREVESSELANDSHROUDSUPPORTASSEMBLYZ.VesselSupportSkirtASMESectionZZZPrimaryStressLimitCriteriaLoadingPrimaryStressTypeAllowableStress(psi)CalculatedStress~(psi)Material:SA-533Gr.BClassZA.NormalandUpsetConditions:P<SS=26700B575oFP~+Po<1.5S~S=26,700B575FB.EmergencyCondition:P<1.2SS=26,700B575FP+Pb<18SSo-26700B575oFC.FaultedCondition:P<0.7SSz=80,000B575oFP+Pb<105SS<-80000B5$5oFD.MaximumCumulativeUsageFactor:1.Deadweight2.Pressureloads3.OBE4.SRV1.Deadweight2.Pressureloads3.OBE4.SRV1.Deadweight2.Pressure3.Jetreaction4.AnnuluspressurizationS.SSE0.248atknucklePrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbending26,70040,05032,04048,06056,00084,00021,90030,91026,93047,96026,93047,960USARRevision81of4November1995

NineMilePointUnit2FSARTABLE3.9B-2h(Cont'd.)II.ShroudSupportASMESectionIIIPrimaryStressLimitCriteriaLoadingPrimaryStressTypeAllowableStress(psi)CalculatedStress>>(psi)Material:SB-168A.NormalandUpsetConditions:P<SS~=23,300psi8575FP~+Pb<SS=28,124psi8575oFB.EmergencyCondition:P<SS=28,5488528oFPg.+Pb<1.5SyS,=28,548ps'528oFC.FaultedCondition:1.Deadweight2.Pressure3.OBE4.SRV1.Deadweight2.Pressure3.Chugging4.SRVPrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbending23,30028,12528,54842,82211,82028,03017,99040,040P~<SyS=28,548psi8528oFP+Pb<1.5SS>-285488$28oF1.2.3.4.5.DeadweightPressureChuggingSRVSSEPrimarymembranePrimarymembraneplusbending28,54842,82221,42040,040D.MaximumCumulativeUsageFactor:0.047atInconelsection0.053atlowalloysteelsectionUSARRevision82of4November1995

NineMilePointUnit2FSARTABLE3.9B-2h(Cont'd.)ZZZ.RPVFeedwaterNozzleASMESectionZZIPrimaryStressLimitCriteriaLoadingPrimaryStressTypeAllowableStress(psi)CalculatedStress*(psi)Material:SA-508ClassIsafeendSRSSvaluesonlyA.NormalandUpsetConditions:P<17,700psiS=17,700B575oFP+P~<26,550psi1.5S=26550B575oFB.EmergencyCondition:P<25,900psiS>-25900B594oFP+P~<38,850psi15S~-38850B594oFC.FaultedCondition:P<53,100psi3S~=53,100B575FP+Pb<38,850psi1.5S=38850B594oFD.MaximumCumulativeUsageFactor:1.Deadweight2.Pressureloads3.OBE4.SRV1.Deadweight2.Pressureloads3.SRV4.SBA1.Deadweight2.Pressureloads3.SSE4.SRV5.ZBA0.965atsafeendPrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbending17,70026,55025,90038,85053,10038,85016,22022,93021,42022,40028,30033,740USARRevision83of4November1995

NineMilePointUnit2FSARTABLE3.9B-2h(Cont'd.)ZV.CRDPenetrationASMESectionZIIPrimaryStressLimitCriteriaMaterial:SB167(Znconelstubtube)A.NormalandUpsetConditions:P<SS=20,0008575FP+Pb<1.5S~S=20,0008575oFB.EmergencyCondition:P~<SS>=241008575oFP+Pb<15SSz=241008$75oFC.FaultedCondition:P<2.4SS=20,0008575oFP+Pb<3.6SS=20,0008575oFD.MaximumCumulativeUsageFactor:Loading1.Normalloads2.Pressure3.OBE4.SRV1.Normalloads2.Pressure3.OBE4.SRV1.Normalloads2.Pressure3.Jetreaction4.Ventclearing5.SSE6.Scram0.645atstubtubePrimaryStressTypePrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbendingPrimarymembranePrimarymembraneplusbendingAllowableStress(psi)20,00030,00024,10036,15048,00072,000CalculatedStress*(psi)8.25027,0518,25027,0519,76031,900TheNewLoadsAdequacyEvaluationhasconcludedthatthelisteddesignbasisloadsenvelopenewloads.USARRevision84of4November1995

NineMilePointUnit2FSARTABLE3.9B-2jSAFETY/RELIEFVALVESSPRING-LOADEDDIRECT-ACTINGTYPETopicMethodofAnalysisDikkersAnalysisAllowableValueCalculatedValue1.Bodyinletandoutletflangestresses'"WhereS>>=S>>=S>>=longitudinalhubwallstress,psiRadialflange"(bodybase,inlet)stress,psiTangentialflangestress,psifNoS>>>>L+-<1.5S2PBLgB4g(4te/3+1)MoS>>2<1.SS~LtBYHoSr=2-ZS>><1.5S>>tB(Usessamenotationascodes)Bodymaterial:ASMESA352LCBInlet:Sat585~F=17,540psiOutlet:Sat500~F=18,900psi1.5S=26,310psi(inlet)and28,350psi(outlet)Inlet:S>>=1.15S~(allowable)S>>=0~23S>>(allowable)S>>=0.98S>>(allowable)Outlet:S=1.21S(allowable)SR=0.79S(allowable)S>>=0.49S(allowable)=0.77=0.16=0.66=0.81=0.53=0.332.Inletandoutletstudarearequirements"'otalcross-sectionalareashallexceedthegreaterof:Rn,SborAn~-A)n,Sa(Usessamenotationascodes)Inlet:~,(>Am,)=12.45in'utlet:Am,()Am,)=4.65in~Inlet:Ab(actualarea)=1.52Am(requiredmin)Outlet:Am(actualarea)=1.84Am(requiredmin)USARRevision81of5November1995

NineMilePointUnit2FSARTABLE3.9B-2j(Cont'd.)TopicMethodofAnalysisDikkersAnalysisAllowableValueCalculatedValue3.NozzlewallthicknessWhere:Am,=Totalrequiredbolt(stud)areaforconditionAm,=Totalrequiredbolt(stud)areaforgasketseating1.Minimumwallthicknesscriterion:0)Where:Minimumcalculatedthicknessrequirement,including,corrosionallowanceActualnozzlewallthicknessBoltingmaterial:ASMESA193Gr.B7Sectionnearnozzlebase:c<r(actual)Nozzlemidsection:c<t(actual)Thinsectionnearvalveseat:t,<t~(actual)Thinnestsectionatnozzletip-justbelowvalveseat:r<t(actual)t~0.84inchc~0.81incht~0.79incht0.206inchr(actual)~1.58rt'actual)1.54rt(actual)1.012r,t(actual)~1.68tNozzleMaterial:ASMESA350LF2ActualthicknessgreaterthantatthesectionunderconsiderationUSARRevision82of5November1995

NineMilePointUnit2FSARTable3.9B-2j(Cont'd.)TopicMethodofAnalysisDikkersAnalysisAllowableValueCalculatedValue(RefertoSection3.9B.1.1.9forthermaltransientsinformation.)2.CyclicRating:Thermal:pNriNiEtZ-.(i~1,2,3,4,5)NiIt(max)<1.0It=0.0014(=0.0014xIt(max])Faticaue:N>2,000cycles,asbasedonSa,whereSaisdefinedasthelargerof:N~>2,000cycles,asbasedonSa,whereSa=Sp,(>Sp,)N>2,000cyclesN,(basedonSa=Sp,)400,000cycles,thereforesatisfiescriterionSpi~(2/3)gp+-+gr+1.3g,orSp~~0.4g~+-(P~+2gr)K21(Usessamenotationascodes)Where:Sp,=Sp~Fatiguestressintensityatinsidesurfaceofcrotch,psiFatiguestressintensityatinsidesurfaceofcrotch,psiUSARRevision83of5November1995

NineMilePointUnit2FSARTable3.9B-2j(Cont'd.)TopicMethodofAnalysisDikkersAnalysisAllowableValueCalculatedValue4.BonnetflangestrengthFlangetreatedasaloosetypeflangewithouthub:6',St~(3.14C-nD)5.46M'r~a[0.3181(Vsessamenotationascodes)1.5S(formaxS,S,andS~),=28,350psiSR=1.35S=0.9(allowable)ST=0.53S=0.35(allowable)(max+atbackfaceofflange)Where:SaRadialflange"stress,psiTangentialflangestress,psiBonnetMaterial:ASMESA-352LCBSat5000F=18,900psi5.BonnetboltingarearequirementsTotalcross-sectionalareashallexceedthegreaterof:Am,(>Am,)=7.399inA,(actualarea)=1.34Am(requiredmin)AyMn,SbWm,An~-SborAn~-SaAn,--RnSaWhere:Am,=Totalrequiredbolt(stud)areaforoperatingconditionAm,=Totalrequiredbolt(stud)areaforgasketseatingWhere:Am(requiredminimum)isthegreaterofAm,andAM,;andAb(actualboltarea)mustexceedAm.Bodytobonnetboltingmaterial:ASMESA-193Gr.B7USARRevision84of5November1995

NineMilePointUnit2FSARTable3.9B-2j(Cont'd.)TopicMethodofAnalysisDikkersAnalysisAllowableValueCalculatedValue6.DiscThediscstressiscalculatedbytreatingthediscasaflatcircularplate,edgessupported,uniformloadoverareawithradiusr.referenceBach'sFormulas,Machinery'sHandbook,15thEd.,p414.Fromthereference:w=27,430lbr,=0.785inR=2.48int(minallowable)=1.067inActualt=1068in=1.0009(requiredmin)Discmaterial:ASMESA351CF3AWisbasedonp=1,375psiunderthediscTemperature:585~FS(585oF)=18,235psi.Allowablestressis1.5S.ThisisthevalueSintheaboveformula.(1.5S=27,353psi)7.SeismiccapabilityStressanalysisusesF.ggg(massofvalve)x(4.5g),andF~,,=(massofvalve)x(6.5g),with800,000in-lband300,000in-lbappliedattheinletandoutlet,respectively.Actualcapabilityverifiablebytest(withthemomentsconcurrentlyapplied)andexceedsthesevalues.ASMESectionZZI,July1974,includingaddendathroughsummer1976.Designpressures:Pb=1,375psig(inlet)P~=625psig(outlet)Thesearethemaximumanticipatedpressuresunderalloperatingconditions.Analysesincludeappliedmomentsof:M=800,000in-lb(inlet)andM=300,000in-lb(outlet).Theanalysesalsoincludeconsiderationofseismic,operational,andflowreactionforces.SincetheseSRVsarepipe-mountedequipment,refertothepipinganalysisforverificationthatthemomentsarenotexceeded.This~istinaccordancewithnotationofthecodes.USARRevision85of5November1995

NineMilePointUnit2FSARTABLE3.9B-2kREACTORRECIRCULATIONSZSTEMGATEVALVESSuctionValvesItemNo.Component/Load/StressTypeDesignProcedureAllowableLimitDesign/CalculatedValueRatioCalculated/Allowed1.01.21.31.51.61.71.81.91.10BodandBonnetLoads:DesignpressureDesigntemperaturePressureratingMinimumwallthicknessPrimarymembranestressSecondarystressduetopipereactionPrimaryplussecondarystressduetointernalpressureThermalsecondarystressRangeofprimaryplussecondarystressatcrotchregionCyclerequirementsforfatigueanalysisUsagefactorrequirementsforfatigueanalysisSystemrequirementSystemrequirementASMESectionZZI"',FigureNB-3545.1>>2ASMESectionZZI"',ParagraphNB-3542ASMESectionZIZ'",ParagraphNB-3545.1ASMESectionIZZ"',ParagraphNB-3545.2(b)(i)ASMESectionZZZ'n,ParagraphNB-3545.2(a)(1)ASMESectionIIZ"',ParagraphNB-3545.2(c)ASMESectionZZI'",ParagraphNB-3545.2ASMESectionZII'",ParagraphNB-3545.3ASMESectionZIZ"',ParagraphNB-35501,250psi575'PFP,=734.96psit,=1.931inP<S(5000F)=19,600psiP=greatestvalueofpP,~andP.,<1.5S(500~F)(1.5)(19.600)=29,400psiSeeParagraph1.8SeeParagraph1.8S,<3S~(500oF)=58,800PS1N,>2,000cyclesZ,<1.01,250psi5750FP,"-734.96psit,=1.931minP=8,087psiP~=6,300psiP~=13,894psiP=13,894psiQp=20,632psiQ~=998psi1SpQp+Pp+2Q,=28~928psiN5=1x10~cyclesZc=0.0025N/AN/AN/AN/A0.540.210.470.470.49N/AUSARRevision81of8November1995

NineMilePointUnit2FSARTABLE3.9B-2k(Cont'd.)SuctionValves(Cont'd.)ItemNo.2.02.12.22.3Component/Load/StressTypeBodtoBonnetBoltinLoads:designpressureandtemperature,gasketloads,stemoperationalload,seismicload(SSE)BoltareaBodFlaneStressesDesignProcedureASMESectionIZI'",ParagraphNB-3647.1ASMESectionZII'",ParagraphNB-3647.1AllowableLimitA>28.96in'=28.675psiDesign/CalculatedValueA=29.70in'b=28.675psiRatioCalculated/AllowedN/AN/A2.3.12.3.2OperatingconditionGasketseatingconditionBonnetFlaneStressesASMESectionIII"',ParagraphNB-3647.1ASMESection1ZI"',ParagraphNB-3647.1ASMESectionIZI"',ParagraphNB-3647.1Sh<1.5PSlS,<1.5PS1S~<1.5PS1S<1.5PS1.S,<1.5PS1S,<1.5PS1.S(5750F)=28,832S(575oF)=28,837S(575oF)=28837S(100F)=30,000S(1000F)=30,000S(100oF)=30000Sh-S,=SCSc=14,293psi11,568psi3,914psi18,437psi16,242psi5,498psi0.500.400.140.610.540.182.4.1OperatingconditionASMESectionIIZ"',ParagraphNB-3647.115S~(575oF)-28837PSl.S,<1.5S(5750F)=28,837PS1S,<1.5S~(575F)=28,837PSl.S=18,783psiS,=14,968psiS,=4,691psi0.650.520.16USARRevision82of8November1995

NineMilePointUnit2FSAR.TABLE3.98-2k(Cont'd.)SuctionValves(Cont'd.)ItemNo.2.4.23.0Component/Load/StressTypeGasketseatingconditionStressesinStemDesignProcedureASMESectionIII"',ParagraphNB-3647.1AllowableLimitS<1.5S~(100F)=30,000PS1S<1.5S(1004F)=30000PS1S,<1.5S(1004F)=30,000ps1Design/CalculatedValueS=18,214psiS,=14,391psiS,=4,507psiRatioCalculated/Allowed0.610.480.153.13.23.3Loads:operatorthrustandtorqueStemthruststressStemshearstressBucklingonstemCalculatestressduetooperatorthrustincriticalcrosssectionCalculateshearstressduetooperatortorqueincriticalcrosssectionCalculateslendernessratio.Ifgreaterthan30calculateallowableloadfromRankine'sformulausingsafetyfactorof4S,<S=42,275psiS,<0.6S=25,365psiMax.allowableload=34,284lbS,=3,347psiS,=2,288psiSlendernessratio=115Actualloadonstem=15,115lb(therefore,nobuckling)0.080.09N/A4.0DiscAnalsis4.2Loads:maximumdifferentialpressure"'aximumstressindiscASMESectionIII"',ParagraphsNB-3215andNB-3221.3S<1.5S(5754F)27,487psiMaxstress=20,225psi0.74USARRevision83of8November1995

NineMilePointUnit2FSARTABLE3.9B-2k(Cont'd.)SuctionValves(Cont'd.)ItemNo.Component/Load/StressTypeDesignProcedureAllowableLimitDesign/CalculatedValueRatioCalculated/Allowed5.05.15.25.3YokeandYokeConnectionsLoads:stemoperationalloadsTensilestressinyokelegboltsBendingstressofyokelegsCalculatestressesintheyokeandyokeconnectionstoacceptablestructuralanalysismethodsS<S(100oF)=35,000psiS~(1.5S(1850F)=33,165psrS=8,718psiSb=14,011psi0.250.42USARRevision84of8November1995

NineMilePointUnit2FSARTABLE3.9B-2k(Cont'd.)DischargeValvesItemNo.Component/Load/StressTypeDesignProcedureAllowableLimitDesign/CalculatedValueRatioCalculated/Allowed1.01.21.31.41.51.6BodandBonnetLoads:DesignpressureDesigntemperaturePipereactionThermaleffectsPressureratingMinimumwallthicknessPrimarymembranestressSecondarystressduetopipereactionPrimaryplussecondarystressduetointernalpressureSystemrequirementSystemrequirementNotspecifiedNotspecifiedASMESectionIZI"',FigureNB-3545.1-2ASMESectionZII"',ParagraphNB-3542ASMESectionIII"',ParagraphNB-3545.1ASMESectionZII"',ParagraphNB-3545.2ASMESectionZZZ'",ParagraphNB-3545.2(a)(1)1,650psi5754FN/AN/AP,=969.68psit(nominal)=2.432inP<S(5004F)=19,600PSiP=greatestvalueofP.,andP.,<1.5S(5004F)1.5(19,600)=29,400psiSh<3Sa(5004F)=58800PS1,N/AN/AN/AN/AP,"-969.68psit=2.432min,inP=9,831psi5,917psi13,834psiP=13,834psiP,=P=13,834psiQ~=23,264psiN/AN/AN/AN/AN/AN/A0.500.200.470.471.7ThermalsecondarystressASMESectionIII'",ParagraphNB-3545.2(c)S<3S(500F)=58,000PSl.Q,=1,020psi1.81.91.10SumofprimaryplussecondarystressFatiguerequirementsCyclicratingASMESectionIII"',ParagraphNB-3545.2ASMESectionIIZ"',ParagraphNB-3545.3ASMESectionIZI"',ParagraphNB-3550S,<3S~(500F)=58,500PS1N,>2,000cyclesZ,<1.0Sb=Q+P,+2Q,=31,221PS1N5=4x10'ycles10=0.00320.53N/AN/AUSARRevision85of8November1995

NineMilePointUnit2FSARTABLE3.9B-2k(Cont'd.)DischargeValves(Cont'd.)ItemNo.2.02.12.22.3Component/Load/StressTypeBodtoBonnetBoltinLoads:designpressureandtemperature,gasketloads,stemoperationalload,seismicload(designbasisearthquake)BoltareaBodFlaneStressesDesignProcedureASMESectionZIZ"',ParagraphNB-3647.1ASMESectionIZZ"',ParagraphNB-3647.1ASMESectionZII"',ParagraphNB-3647.1AllowableLimitA<41.23incS,<28.675psiDesign/CalculatedValueA>47.52in'b=28,675psiRatioCalculated/AllowedN/AN/A2.3.12.3.2OperatingconditionsGasketseatingconditionASMESectionZZZ"',ParagraphNB-3647.1ASMESectionZZZ'".ParagraphNB-3647.1S<PS1SPS1s,PS1Sb~<PS1Sc<PS1SPS11.5S(575~F)=28,837S=14,682psi1.5S(5750F)=28,837S,=18,889psi1.5S~(5750F)=28,837Sc=4,815psi1.5S(100F)=30,000Sh-"19,884psi1.5S~(100F)=30,000S,=28,378psi1.5S~(100oF)=30,000Sc=7,235ps10.510.650.170.660.940.242.4.1BonnetFlaneStressesOperatingconditionASMESectionIII'",ParagraphNB-3647.1Sc,<1.5S~(575F)-28,837PS1S,<1.5S~(575F)=28,837PS1Sc1.5S(575oF)-28837PS1S=18,352psiS,=24,546psiS,=6,400psi0.640.850.22USARRevision86of8November1995

NineMilePointUnit2FSARTABLE3.9B-2k(Cont'd.)DischargeValves(Cont'd.)ItemNo.2.4.23.0Component/Load/StressTypeGasketseatingconditionStressesinStemDesignProcedureASMESectionIII'",ParagraphNB-3647.1AllowableLimit1.5S(100oF)=30,000psst.Sc1.5S(100oF)-30000pslS~<15S(100oF)-30000ps1Design/CalculatedValueS=18,540psiS,=24,875psiS,=6,485psiRatioCalculated/Allowed0.620.830.223.13.23.33.44.0Load:operatorthrustandtorqueStemthruststressStemtorquestressBucklingonstemDiscAnalsisCalculatestressduetooperatorthrustincriticalcrosssectionCalculateshearstressduetooperatortorqueincriticalcrosssectionCalculateslendernessratio.Ifgreaterthan30,calculateallowableloadfromRankine'sformulausingsafetyfactorof4.S,<S=42,275psiS,<0.6S=25,365psiMaxallowableload=44,322lbS,=7,295psiS,=4,986psiSlendernessratio=96.5Actualloadonstem=32,9441b(therefore,nobuckling)0.170.20N/A0.74Loads:maximumdifferentialpressure"'aximumstressindiscASMESectionIII"',ParagraphsNB-3215andNB-3221.3S<15S(575oF27,487psiMaxstress=26,179psi0.95USARRevision87of8November1995

NineMilePointUnit2FSARTABLE3.9B-2k(Cont'd.)DischargeValves(Cont'd.)ItemNo.Component/Load/StressTypeDesignProcedureAllowableLimitDesign/CalculatedValueRatioCalculated/Allowed5.05.15.25.3YokeandYokeConnectionsLoads:stemoperationalloadTensilestressinyokelegboltsBendingstressofyokelegsCalculatestressesinyokeandyokeconnectionstoacceptablestructuralanalysismethodsS~<S(100oF)-35000psis~<1.5S(185F)=33,165psstS=14,654psiSb=19,988psi0.420.60ASMESectionEIZ,1971Edition."'alvedifferentialpressureis50psig."'alvedifferentialpressureis450psig.USARRevision88of8November1995

NineMilePointUnit2FSARTABLE3.9B-2mASMESAFETYCLASS1RECIRCULATIONPIPINGANDPIPEMOUNTEDEQUIPMENTHIGHESTSTRESSSUMMARYAcceptanceCriteriaLimitingStressTypeCalculatedStress'"orUsageFactorAllowableIimitsRatioActual/AllowableLoadingIdentification'"ofLocationsofHighestStxessPointsASMESectionZIZ,NB-3600DesignCondition:Eq.9<1.5SServiceLevelsAandB(normal&upset)condition:Eq.12<3.0SServiceLevelsAandB(normal&upset)condition:Eq.13<3.0SPrimarySecondaryPrimaryplussecondary(exceptthermalexpansion)15,846psi30,015psi40,978psi25,875psi51,750psi51,750psi0.610.580.791.Pressure2.Weight1.Thermal1.Pressure2.Weight3.OBE4.Operatingtransients5.SRVHangerlug(LoopB)Headersweepolet(LoopB)RHSreturnsweepolet(LoopB)ServiceLevelsAandB(normalandupset)condition:CumulativeusagefactorServiceLevelB(upset)condition:Eq.9<1.8S&1.5SServiceLevelC(emergency)condition:Eg.9<225S&18SServiceLevelD(faulted)condition:Eq.9<3.0S+2.0S'/APrimaryPrimaryPrimary0.5629,239psi18,540psi34,058psi1.029,388psi35,266psi39,184psi0.560.990.530.871.Pressure2.Weight3.OBE4.SRV1.Pressure2.Weight3.Chugging4.SRV1.Pressure2.Weight3.SSE4.APHeadersweepolet(LoopB)RHSreturnsweepolet(LoopB)Hangerlug(LoopB)RHSreturnsweepolet(LoopB)USARRevision81of2November1995

NineMilePointUnit2FSARTABLE3.9B-2m(Cont'd.)Component/LoadTypeHighestCalculatedLoadAllowableLoadRatioCalculated/AllowableLoadingidentificationofEquipmentwithHighestLoadsSnubberLoad(lb)ServiceLevelBServiceLevelCServiceLevelD53,92420,77472.271100,000133,000150,0000.540.160.481.OBE2.SRV1.Chugging2.SRV1.SSE2.APSnubberSB10SnubberSB10SnubberSB10FlangeMoment(in-lb)LevelBLevelCLevelDAcceleration(g)Horizontal1,164,538471,3821,374,2321.581,527,1401,527,1401,527,1409.00.760.310.900.181.Weight2.Thermal3.OBE4.SRV1.Weight2.Thermal3.chugging4.SRV1.Weight2.Thermal3.SSE4.AP1.SSE2.Chugging3.SRVDischargevalve(LoopB)Dischargevalve(LoopB)Dischargevalve(LoopB)Flowcontrolvalve(LoopA)Vertical6.00.231.SSE2.APFlowcontrolvalve(LoopB)USARRevision82of2November1995

NineMilePointUnit2FSARTABLE3.9B-2pRECIRCULATIONPUMPSummaryofLoadClassificationHighStressLocationsandLimitCriteriaPumpCaseLoadCombinationLoadingConditionASMESectionIIIDesign(NB-3112)Normal(NB-3113.1)andupset(NB-3113.2)Emergency(NB-3113.3)Faulted(NB-3113.4)Pressure(psig)Designpressure=1,650Mostseverenormal/upsetpressure=1,313Mostsevereemergencypressure1,796Mostseverefaultedpressure=1,313MechanicalLoads1.OBE2.Pumpthrust3.Deadweight4.Nozzleloads5.Gasketseating1.Deadweight2.Nozzleloads3.Thermaltransient4.OBE5.Upset1.Deadweight2.Nozzleloads3.Pumpthrust4.Gasketseating5.OBE1.Deadweight2.Nozzleloads3.SSE4.Pumpthrust5.GasketseatingCriteria(ASMESectionIIINB-3220)FigureNB-3221-1P<10SPg,+Pb<1.5SFigureNB-3222-1P+Pb+P.+Q<3.0SP<3.0SFigureNB-3224-1P<(1.2SorS)P<(1.8Sor1.5Sy)Pi+P~<(1.8Sor1.5S)TableF-1322.2-1P<2.4Sor0.7S+P<1.5(2.4Sor0.7S)P+Pb<1.5(2.4Sor0.75S)LocationPumpcaseDischargetransitionBoltsCrotchDischargetransitionHighestCalc.Stress(psi)/UsageFactor28,449psi48,449psiu=0.2932,317psi52,563psiAllowableValue28,838psi58,020psi1.034,812psi66845psiRatioAct./All.0.990.840.290.930.79USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3.9B-4GE-SUPPLIEDSEISMICACTIVEPUMPSANDVALVESComonentMainsteamisolationvalveMainsteamSRVStandbyliquidcontrol(explosive)valveCRDsolenoidvalveMasterPartsListNo.B22-F022B22-F028B22-F013C41-F004C12-F009C12-F110C12-F160C12-F162C12-F163C12-F182Standards<'>IEEE-323-1974IEEE-344-1975IEEE-382-1980NUREG-0588,Cat.1ASMESectionIII,1977Edition,S77AddendaIEEE-323-1974IEEE-344-1975IEEE-382-1980NUREG-0588,Cat.1ASMESectionIII,1974Edition,S76AddendaIEEE-323-1974IEEE-344-1975NUREG-0588,Cat.1ASMESectionIII,1977Edition,S77AddendaIEEE-323-1974IEEE-344-1975IEEE-382-1980NUREG-0588,Cat.1CRDglobevalveHPCSgatevalvesC12-F010C12-F011C12-F180C12-F181E22-F001E22-F004E22-F010E22-F011IEEE-344-1975ASMESectionIII,1971Edition,S73AddendaIEEE-344-1975IEEE-382-1980ASMESectionIII,1977Edition,S77AddendaIEEE-323-1974IEEE-344-1975IEEE-382-1980NUREG-0588,Cat.1USARRevision81of2November1995 NineMilePointUnit2FSARTABLE3.9B-4(Cont'd.)ComoetMasterPartsStadads'"RCICturbineRCICpumpSLCpumpandmotorE22-F012E22-F015E22-F023E51-C002E51-C001C41-C001Pump:Motor:d,e,f,h,ia,b,c,d,e,ftgshtie3ASMESectionIII,1971Edition,W73Addendaa,bd,e,f,h,jRHRpumpandmotorLPCSpumpandmotorHPCSpumpandmotorE12-C002E21-C001E22-C001Pump:Motor:Pump:Motor:Pump:Motor:d,e,f,h,ia,b,c,d,e,figiht>i3d,e,f,h,ia,b,c,d,e,figi~i>i3d,e,f,h,ia,b,c,d,e,f,g,h,i,jc'0e:foIEEE-323-74IEEE-344-75IEEE-334-74RG1.48RG1.60RG1.61RG1.89RG1.92RG1.100RG1.122USARRevision82of2November1995 NineMilePointUnit2FSARTABLE3.9B-5DEFORMATIONLIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)Eitheroneof(notboth):eissideot'oPAnalyzeddeformationcausinglossoffunction,DLeeSF~2.PermissibledeformationDPExperimentdeformationcausinglossoffunction,DEWhere:DPDLPermissibledeformationunderstatedconditionsofServiceLevelsA,B,C,orD(normal,upset,emergency,orfaulted)Analyzeddeformationthatcouldcauseasystemlossoffunction+DEExperimentallydetermineddeformationthatcouldcauseasystemlossoffunctionEquation2isnotusedunlesssupportingdataisprovidedtotheNRCbyGE."Lossoffunction"canonlybedefinedquitegenerallyuntilattentionisfocusedonthecomponentofinterest.Incasesofinterest,wheredeformationlimitscanaffectthefunctionofequipmentandcomponents,theyarespecificallydelineated.Fromapracticalviewpoint,itisconvenienttointerchangesomedeformationconditionatwhichfunctionisassuredwiththelossoffunctionconditioniftherequiredsafetymarginsfromthefunctioningconditionscanbeachieved.Therefore,itisoftenunnecessarytodeterminetheactuallossoffunctionconditionbecausethisinterchangeprocedureproducesconservativeandsafedesigns.Exampleswheredeformationlimitsapplyare:CRDalignmentandclearancesforproperinsertion,coresupportdeformationcausingfueldisarrangementorexcessleakageofanycomponent.USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.9B-6PRIMARYSTRESSLIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)Anyoneof(nomorethanonerequired):1.Elast'valuatedr'marstressesPEPermissibleprimarystresses,PN2~PeissoadLPLargestlowerboundlimitload,CLGeneralLimit2.25SF~~5SF~3.lasticevaluatedrimarstressPEConventionalultimatestrengthattemperature,US0.75SF~4~Elastic-plasticevaluatedomialrimarstressEPConventionalultimatestrengthattemperature,US0.9SF~5~*erissibleloadPPlasticinstabilityload,PL0.9SF~6'PeissibleoadPUltimateloadfromfractureanalysis,UF7~*PermissibleloadLPUltimateloadorlossoffunctionloadfromtest,LP1.0SF~Where:PEPrimarystressesevaluatedonanelasticbasis.Theeffectivemembranestressesaretobeaveragedthroughtheload-carryingsectionofinterest.Thesimplestaveragebending,shear,ortorsionstressdistributionthatsupportstheexternalloadingisaddedtothemembranestressesatthesectionofinterest.PNPermissibleprimarystresslevelsunderServiceLevelsAorB(normalorupset)conditionsunderASMESectionIII.*LPPermissibleloadunderstatedconditionsofServiceLevelsA,B,C,orD(normal,upset,emergency,orfaulted).USARRevision81of3November1995 NineMilePointUnit2FSARTABLE3.9B-6(Cont'd.)CLUSEPPLUFLowerboundlimitloadwithyieldpointequalto1.5SwhereSisthetabulatedvalueofallowablestressattemperatureofASMESectionIIIoritsequivalent.The"lowerboundlimitload"isheredefinedasthatproducedfromtheanalysisofanideallyplastic(nonstrainhardening)materialwheredeformationsincreasewithnofurtherincreaseinappliedload.Thelowerboundloadisoneinwhichthematerialeverywheresatisfiesequilibriumandnowhereexceedsthedefinedmaterialyieldstrengthusingeitherasheartheoryorastrainenergyofdistortiontheorytorelatemultiaxialyieldtotheuniaxialcase.Conventionalultimatestrengthattemperatureorloadingthatwouldcauseasystemmalfunction,whicheverismorelimiting.Elastic-plasticevaluatednominalprimarystress.Strainhardeningofthematerialmaybeusedfortheactualmonotonicstressstraincurveatthetemperatureofloadingoranyapproximationtotheactualstressstraincurvethateverywherehasalowerstressforthesamestrainastheactualmonotoniccurvemaybeused.Eithertheshearorstrainenergyofdistortionflowrulemaybeused.Plasticinstabilityloaddefinedhereastheloadatwhichanyload-bearingsectionbeginstodiminishitscross-sectionalareaatafasterratethanthestrainhardeningcanaccommodatetheloss.inarea.Thistypeanalysisrequiresatruestress-truestraincurveoracloseapproximationbasedonmonotonicloadingatthetemperatureofloading.IUltimateloadfromfractureanalyses.Forcomponentsthatinvolvesharpdiscontinuities(localtheoreticalstressconcentration<3),theuseofafracturemechanicsanalysiswhereapplicableutilizingmeasurementsofplanestrainfracturetoughnessmaybeappliedtocomputefractureloads.Correctionforfiniteplasticzonesandthicknesseffectsaswellasgrossyieldingmaybenecessary.Themethodsoflinearelasticstressanalysismaybeusedinthefractureanalysiswhereitsuseisclearlyconservativeorsupportedbyexperimentalevidence.ExampleswhereUSARRevision82of3November1995 NineMilePointUnit2FSARTABLE3.9B-6(Cont'd.)fracturemechanicsmaybeappliedareforfilletweldsorend-of-fatigue-lifecrackpropagation.LE=Ultimateloadorlossoffunctionloadasdeterminedfromexperiment.Inusingthismethod,accountwillbetakenofthedimensionaltolerancesthatmayexistbetweentheactualpartandthetestedpartorpartsaswellasdifferencesthatmayexistintheultimatetensilestrengthoftheactualpartandthetestedparts.Theguidetobeusedineachoftheseareasisthattheexperimentallydeterminedloadisadjustedtoaccountformaterialpropertyanddimensionvariations,eachofwhichhasnogreaterprobabilitythan0.1ofbeingexceededintheactualpart.*Notusedunlesssupportingdataareprovided.USARRevision83of3November1995 NineMilePointUnit2FSARTABLE3.9B-7BUCKLINGSTABILITYLIMIT(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)Anyoneof(nomorethanonerequired):General1.lServiceLevelA(normal)permissibleload,PNJ<SF~2~ssStabilityanalysisload,SL<SF~3~*PermissibleoLP~X0Ultimatebucklingcollapseloadfromtest,SEJ<SF.Where:PNPermissibleloadunderstatedconditionsofServiceLevelsA,B,C,orD(normal,upset,emergency,orfaulted).ApplicableServiceLevelA(normal)permissibleload.SLStabilityanalysisload.Theidealbucklinganalysisisoftensensitivetootherwiseminordeviationsfromidealgeometryandboundaryconditions.Theseeffectswillbeaccountedforintheanalysisofthebucklingstabilityloads.Examplesofthisareovalityinexternallypressurizedshellsoreccentricityoncolumnmembers.SEUltimatebucklingcollapseloadasdeterminedfromexperiment.Inusingthismethod,accountwillbetakenofthedimensionaltolerancesthatmayexistbetweentheactualpartandthetestedpart.Theguidetobeusedineachoftheseareasisthattheexperimentallydeterminedloadwillbeadjustedtoaccountformaterialpropertyanddimensionvariations,eachofwhichhasnogreaterprobabilitythan0.1ofbeingexceededintheactualpart.*Notusedunlesssupportingdataareprovided.USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3.9B-8FATIGUELIMIT*(FORSAFETYCLASSREACTORINTERNALSTRUCTURESONLY)CumulatveamaeinatiueDesignfatiguecycleusagefromanalysisusingthemethodofASMECodeLimitforServiceLevelsAandB(normalandupset)esinConditions(1.0*SummationoffatiguedamageusagewithdesignandoperationloadsfollowingMinerhypotheses.SOURCE:Miner,M.A.CumulativeDamageinFatigue,JournalofAppliedMechanics,Vol.12,ASMEVol.67,ppA159-A164,September1945.USARRevision81of1November1995 PDTEDFETYNLYIREPRNINEMILEPOINTNUCLEARSTATION-UNIT27NIAGARAUMOHAWKVOL.12

NineMilePointUnit2FSARTABLEOFCONTENTSSectionCHAPTER1~TiteINTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANTVolume1.11.2131.41.51.61~71.S1.91'0F111'2113CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2.12.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,445678CHAPTER33.13.23.33.4DESIGNOFSTRUCTURESICOMPONENTSgEQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)~Sectic3.53.6A3.6B3'A3.7B3'3.9A3.9B3.10A3.10B3'1Appendixes3ACHAPTER44.14.24.34'4.54.6Appendix4ACHAPTER55'5'5.35~4Appendixes5A,g1'.t'LeMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociated-WithPostulatedRuptureofPiping{GEScopeofSupply)SeismicDesignSeismicDesign(GEScopeofSupply)DesignofSeismicCategoryIStructuresMechanicalSystemsandComponents{SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTORSummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5BVolume9,10101010101212121212121212121212131313131313USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER66.16'6'6'6.56.6AppendixesCHAPTER77'7'7~3747'7.6F7Appendixes,CHAPTER88'828.3Appendix8ACHAPTER96A7A,TitleENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsIn-serviceInspectionofSafetyClass2andClass3Componentsthrough6DINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)SystemInstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSVolume131314151515151515151616161616161616,171717F19.29.39'9.5Appendixes9A,CHAPTER1010.110.210.3FuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEMSummaryDescriptionTurbineGeneratorMainSteamSupplySystem17181920,2121,222323232324USARRevisionNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)~Sectic10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume242411.111'11.311'11.5Appendix11ACHAPTER1212F112.212.312~412'CHAPTER1313F113213~313'13'13.6CHAPTER1414.1I14214~3CHAPTER1515.0SourceTermsLic{uid-WasteManagement-SystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystemsRADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresSecurityINITIALTESTPROGRAMSpecificInformationToBeIncludedinPSARSpecificInformationToBeIncludedinFSAR-InitialTestProgramInitialTestProgramforOperationatPowerUprateConditions(3,467MWt)ACCIDENTANALYSISGeneral24242525252525252525262626262626262626262626,27272727USARRevisionivNovember1995 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15~115.215e315'15.515.615.715.8AppendicesCHAPTER16CHAPTER1717.017~117'CHAPTER1818.118.2APPENDIXAAPPENDIXB15ATitleDecreas'einReactorCoolantTemperatureIncreaseinReactorPressureDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientsWithoutScramthrough15HTECHNICALSPECXFICATXONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETY'ARAMETERDXSPLAYSYSTEMDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNXAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPXCALREPORT(NMPC-QATR-l),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATXONSPHASEVolume27272727272727272828282828282828282828USARRevisionNovember1995

NineMilePointUnit2FSAR3.10SEISMICQUALIFICATIONOFCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENTTwoinputsareprovidedforSection3.10:Section3.10AappliestotheSWECscopeofsupply,andSection3.10BappliestotheGEscopeofsupply.3.10ASEISMICQUALIFICATIONOFCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENT(SWECSCOPEOFSUPPLY)Thissectionprovidesthequalificationmethodsforequipmentaffectedbyseismicloads.ThemethodsforthequalificationofequipmentaffectedbyhydrodynamicloadsassociatedwithSRVdischargeandthepostulatedLOCAareprovidedintheDAR,Appendix6A,Subsection6A.9.3.10A.1SeismicQualificationCriteriaTable3.10A-1providesalistingofCategoryIinstrumentationandelectricalequipmentrequiringseismicqualification.ParametersusedtodevelopseismicloadingsandcriteriaforCategoryIstructures,systems,andcomponentsaredescribedinSection3.7A.Fromthegroundinputdata,aseriesofresponsespectrumcurvesatvariousbuildingelevationswasdeveloped.ThemagnitudeandfrequencyoftheSSEloadingsforwhicheachcomponentisqualifiedvary,dependingontheirlocationswithintheplant.TheseseismicdatawereincludedinthepurchasespecificationsforCategoryIequipmentandsystems.Forequipmentlocatedatvariousareasthroughouttheplant,thepurchasespecificationincludesresponsespectrumcurvesthatenveloptheresponsespectraatalllocationswheretheequipmentisused.Forequipmentsubjecttohydrodynamicloads,seetheDARforHydrodynamicLoads(Appendix6A)fordetails.SeismicqualificationanddocumentationproceduresusedforClass1Eequipmentand/orsystemsmeettheprovisionsofIEEE-344-1975,assupplementedbyRG1.100.CategoryIequipmentisdividedintotwoclassifications:1)equipmentdesignedtomaintainitsfunctionalcapabilityduringandafteranSSE,and2)equipmentthat,althoughnotrequiredtomaintainitsfunctionalcapability,isdesignedtomaintainthepressureboundaryintegrityofthesystemofwhichitisapart,duringandafteranSSE.Therequirementsforinstrumentation,equipment,andsystemsrequiredtomaintainpressureboundaryintegrityareinaccordancewithASMESectionIII,1974orlater,dependingontimeofpurchaseofequipment.TheperformancerequirementsofCategoryIelectricalandinstrumentationitemsandtheirrespectivesupportsmaybestructuralaswellasfunctional.Thestructuraldesignisinaccordancewithapplicablecodes,aslistedintheequipmentspecification.USARRevision83.10A-1November1995 NineMilePointUnit2FSARItshouldbenotedthatcertainnon-CategoryIequipmentisreviewedformaintenanceofstructuralintegritytoensurethatfailureoftheseitemsortheirsupportswillnotjeopardizeadjacentCategoryIequipment.Ifnocodesareapplicable,thestresslevelfortheOBEcombinedwithoperatingloadsislimitedto75percentoftheminimumyieldforthematerialinaccordancewiththeASTMspecification.FortheSSEcombinedwithoperatingloads,thestressleveldoesnotexceedthesmallerof:1.100percentoftheminimumyieldstrength,or2.70percentoftheminimumultimatetensilestrengthofthematerial(atdesigntemperature),inaccordancewiththeASTMspecification.Seismicanalysis,withouttesting,isperformedonequipmentwhosefunctionaloperabilityisassuredbyitsstructuralintegrityalone.Whencompleteseismictestingisimpractical,acombinationoftestsandanalysesisperformed.SeeTable3.10A-1fortheseismicqualificationmethodsapplicabletospecificequipment.3.10A.2MethodsandProceduresforQualifyingElectricalEquipmentandInstrumentationThemethodsbywhichthesuppliercanqualifyequipmentforcompliancewithseismicrequirementsareasfollows:1.Testing.2.Type-testing(prototype).3.Analysis.4.Combinationof1or2and3.Thesemethods,includingthefactorsforselectionofananalyticalortestoption,testobjectives,andacceptabilitycriteria,aredescribedinSection3.7A.3.1.1.QualificationanddocumentationproceduresusedforCategoryIequipmentand/orsystemsmeettheprovisionsofIEEE-344-1975,assupplementedbytherequirementsofRG1.100.3.10A.2.1TestingSeismictestsareperformedbysubjectingequipmenttovibratorymotionthatconservativelysimulatestheseismicloadingattheequipmentmounting.Suchtestsareconductedovertherangeof1to33Hz.Forcomponentssusceptibletoenvironmentalaging(temperature,humidity,radiation,etc.),seismictestingisperformedonenvironmentallypreagedcomponents,followingtherequirementsofIEEE-323-1974.USARRevision83.10A-2November1995 NineMilePointUnit2FSARForequipmentsubjecttohydrodynamicloads,seetheDARforHydrodynamicLoads(Appendix6A)fordetails.Wheneverfeasible,seismicqualificationtestsonequipmentareperformedwhiletheequipmentissubjectedtonormaloperatingloads.However,occasionallyanoperationalconfigurationisdifficulttosimulatecorrectly,andwhereitcanbedemonstratedthatoperatingloadssuchaspressure,torque,flow,voltage,current,ortemperaturedonotcausesignificantstressloadswithintheequipment,orwheresuchoperatingloadsarenotsignificanttoadeterminationofequipmentoperability,operationunderloadisnotspecified.Theequipmentismonitoredandevaluatedduringandafterthetestformalfunctionorfailureand,uponcompletionofthetest,istestedforproperoperation.Inseismicqualificationtesting,equipmentauxiliarycomponents,suchasrelays,switches,andinstrumentsnecessaryforproperoperation,aremountedsimilarlytothemannerinwhichtheyaretobeinstalled,andthentestedandqualifiedalongwiththeequipment.Formulticabinetassemblies,thetestedprototypeunitoccasionallyconsistsofasmallernumberofframesthantheframesintheassemblybeingprovided.Insuchcases,anevaluationoftheresponsesduetothefront-to-back,side-to-side,vertical,andtorsionalmodesofthemulticabinetassemblies,withrespecttothoseofthetestedunit,aremade.Thisevaluationensurestheadequacyofthequalificationofthemulticabinetassembliesandoftheelectricalcomponentslocatedwithinthem.Theinputmotionisappliedtotheverticalaxis,combinedwitheachoneoftheprincipalhorizontalaxes,unlessitcanbedemonstratedthattheequipmentresponsealongtheverticaldirectionisnotsensitive(coupled)tothevibrationmotionalongthehorizontaldirectionandviceversa.RefertoSection3.7A.3.1.1forcompletedetailsoftesting.Themaximuminputmotionaccelerationisequalto,orisinexcessof,themaximumseismicaccelerationexpectedattheequipmentmountinglocation.FollowingtherequirementsofRG1.100,itisspecifiedthatthetestresponsespectrumcloselyenvelopapplicableportionsoftherequiredresponsespectruminverifyingtheadequacyoftestinputmotion.3.10A.2.2PrototypeTestingInsomecases,wheregroupsofequipmenthavesimilarcharacteristics,thetestprogramisbasedupontestingofaprototypeitemofequipment.Thetestreports,furnishedbytheequipmentsupplier,arereviewedforassurancethatthegroupofcomponentsqualifiedbytheprototypeisdynamicallysimilar.Ifanyextrapolationastodimensionormassisused,thevendorisrequiredtojustifysimilarityofthedynamiccharacteristics.USARRevision83.10A-3November1995 NineMilePointUnit2FSAR3.10A.2.3AnalysisAnalysiswithouttestingisacceptableonlyifstructuralintegrityalonecouldassurethedesign-intendedfunction.Responsesarecalculatedforthethree-directionalseismicloadingsindividuallyandcombinedbytheSRSSmethod.Theseismicresponseisaddedtotheoperatingloadresponseonanabsolutebasistoestablishthecombinedeffects,andcomparedwithallowablestress,strain,ordeflections,asthebasisforacceptablequalification.3.10A.2.4CombinedAnalysisandTestingWhentheequipmentcannotbepracticallyqualifiedbyanalysisortestingalonebecauseofitscomplexityorsize,combinedanalysisandtestingisused.Whenthisprocedureisemployed,themajorcomponentisqualifiedbyanalysis,andthemotors,operators,andappurtenancesnecessaryforoperationarequalifiedbytesting.Theauxiliaryequipmentistestedandqualifiedtotheaccelerationlevelatitsmountedlocation,anditsequivalentseismicloadingisappliedtothemajorcomponentbeinganalyzed.3.10A.3MethodsandProceduresofAnalysisorTestingofSupportsofElectricalEquipmentandInstrumentationAdesignobjective,whenfeasible,istoprovidesupportsforelectricalequipment,instrumentation,andcontrolsystemswithfundamentalnaturalfrequenciesabovethecutofffrequencyoftherelevantamplifiedresponsespectracurves.Thisensuresthatamplificationofflooraccelerationsthroughsupportingmemberstomountedequipmentisminimized.Theresponseofracks,panels,cabinets,andconsolesisconsideredinassessingthecapabilityofinstrumentationandelectricalequipment.Itemsofelectricalequipmentandinstrumentationaretested,whereverfeasible,withtheirsupportingstructuresintheirinstalledconfigurations.Intermediatesupportstructuresaredesignedtoberigidtoprecludedynamicinteraction.Whenitisimpracticaltodesignrigidstructures,qualificationanalysiswillincludethemassandstiffnesscharacteristicsofthesupport.Mountedcomponentsarethereforequalifiedtoaccelerationlevelsconsistentwiththosetransmittedbytheirsupportingstructures.DeterminationofamplificationandseismicadequacyofinstrumentationandelectricalequipmentisimplementedbytheanalysisandtestingmethodsoutlinedinSection3.7A.3.TheCategoryIcabletraysupportsystemsareanalyzedusingamodalanalysis/responsespectramethod.Mathematicalmodelsincludebothtwo-andthree-dimensionallumpedmassmodelsthataresubjectedtoasupportexcitationgeneratedbyapplyingtheamplifiedresponsespectraforthatstructurefortheseismicUSARRevision83.10A-4November1995 NineMilePointUnit2FSARand/orthehydrodynamicloadsevents.TheseconditionswereconsideredindesigningthecabletraysupportsysteminaccordancewiththeapplicableloadingcombinationsdescribedinSection3.8.4.Theboundaryconditionsusedintheanalysisassumethat.thesystemisfixed(i.e.,rigidlyattached)orpinneddependingonthe,connectiontothemainstructuralsteelandconcretemembersatitssupportpoints.TheprocurementandtestingrequirementsforstructuralsteeltraysupportsarediscussedinSection3.8.4.6.3.10A.4OperatingLicenseReviewTheresultsofallseismictestsandanalysesperformedbyoutsidevendorsarereviewedandapproved.Theseresultsbecomeapermanentonsiterecord.Asummaryofseismictestand/oranalysisresultsisgiveninTable3.10A-1.USARRevision83.10A-5November1995

NineMilePointUnit2FSAR3.10BSEISMICANDHYDRODYNAMICQUALIFICATIONSOFSEISMICCATEGORYIINSTRUMENTATIONANDELECTRICALEQUIPMENT(GESCOPEOFSUPPLY)3.10B.1DynamicQualificationCriteria3.10B.1.1SeismicCategoryIEquipmentIdentificationSeismicCategoryIinstrumentationandelectricalequipmentislistedinTable3.2-1.<<Active<<NSSSpumps,motors,valves,andvalve-mountedequipmentarelistedinTable3.9B-3.SeismicCategoryIinstrumentationandelectricalequipmentaredesignedtowithstandthefaultedeventwithoutfunctionalimpairment.TheClass1EinstrumentationelectricalequipmentandsupportstructuressuppliedbyGErequiringseismicqualificationareidentifiedinTable3.10B-1.Theseismicqualificationoftheseinstrumentation,equipment,andsupportsisdescribedinthefollowingsubsections.Section3.9B.2.2ofthisFSARaddressesthedynamicqualificationtestingandanalysisoftheCategoryImechanicalcomponents,equipment,andtheirsupports,includingtheintegralorassociatedelectricalcomponentssuchasvalve-mountedcomponentsandpumpmotors.3.10B.1.2DynamicDesignCriteria3.10B.1.2.1NSSSEquipmentTheseismiccriterionusedinthedesignandsubsequentqualificationofallClass1EinstrumentationandelectricalequipmentsuppliedbyGEisdescribedinthefollowingparagraph.TheClass1Eequipmentiscapableofperformingitssafety-relatedfunctionsduring1)normalplantoperation,2)anticipatedtransients,3)designbasisaccidents,and4)postaccidentoperationwhilebeingsubjectedto,andafterthecessationof,theaccelerationsresultingfromtheseismicandhydrodynamicloadsatthepointofattachmentoftheequipmenttothebuildingorsupportingstructure.ThecriteriaforeachofthedevicesusedintheClass1Esystemsdependontheuseinagivensystem,e.g.,arelayinonesystemmayhaveasitssafetyfunctiontodeenergizeandopenitscontactswithinacertaintime,whileinanothersystemitmustenergizeandcloseitscontacts.SinceGEsuppliesmanydevicesformanyapplications,theapproachtakenwastotestthedeviceintheworstcaseconfiguration.Inthisway,thecapabilityofprotectiveactioninitiationandtheproperoperationoffail-safecircuitsisensured.USARRevision83.10B-1November1995 NineMilePointUnit.2FSARFromthebasicinputgroundmotiondata,aseriesofresponsecurvesatvariousbuildingelevationsisdevelopedafterthebuildinglayoutiscompleted.StandardrequirementlevelsthatmeetorexceedthemaximumexpecteduniqueplantinformationareincludedinthedesignspecificationsforSeismicCategoryIequipment.EquipmentisqualifieddynamicallyeitherbyGEorbythesupplier;ineithercase,testdata,operatingexperience,and/orcalculationssubstantiatethatthecomponents,systems,etc.,donotsufferlossoffunctionduringoraftexexposuretoseismicandhydrodynamicloads.ThemagnitudeandfrequencyoftheSSEloadingswhicheachcomponentmayexperiencearedeterminedbyitsspecificlocationwithintheplant.3.10B.2MethodsandProceduresforQualifyingElectricalEquipmentandInstrumentation3.10B.2.1MethodsofShowingNSSSEquipmentCompliancewithIEEE-344-1975andRegulatoryGuide1.100RG1.100isnottheUnit2licensingbasisfortheGEscopeofsupply.However,GEdynamicallyreevaluatestheequipmenttotherequirementsofIEEE-344-1975.ThisisaccomplishedthroughtheGESeismicQualificationReviewTeam(SQRT)program.UndertheGESQRTprogram,thequalificationofrecentlyqualifiedequipmentorequipment,yettobequalifiedcomplieswithRG1.100andIEEE-344-1975.ForequipmentoriginallyqualifiedtoIEEE-344-1971,theSQRTmethodologyisappliedtotheoriginaltestdatatodemonstratethatrequirementsofIEEE-344-1975aresatisfiedalso.IftheSQRTrequirementsarenotsatisfiedforaspecificpieceofequipment,theequipmentisrequalifiedtoIEEE-344-1975orreplacedwithacomponentthatisqualifiedtoIEEE-344-1975.GE-suppliedClass1Eequipmentmeetstherequirementthatthedynamicqualificationshoulddemonstratethecapabilitytoperformtherequiredsafetyfunctionduringandaftertheseismicandhydrodynamicloads.Bothanalysisandtestingwereused,butmostequipmentwastested.Analysiswasprimarilyusedtodeterminetheadequacyofmechanicalstrength,suchasmountingboltsandpressureboundaries.-GE-suppliedClasslEequipmentperformingprimarilyamechanicalsafetyfunction(pressureboundarydevices,etc.)wasanalyzedsincethepassivenatureoftheircriticalsafetyroleusuallymadetestingunnecessary.AnalyticalmethodsoutlinedinIEEE-344-1975wereutilizedinsuchcases.(SeeTable3.10B-1forindicationofwhichitemswerequalifiedbyanalysis.)USARRevision83.10B-2November1995 NineMilePointUnit2FSAR~~-GE-suppliedClass1EequipmenthavinganactiveelectricalsafetyfunctionwastestedincompliancewithIEEE-344-1975'vailabledocumentationverifiestheseismicqualificationofGE-suppliedClasslEequipment.3.10B.2.2TestingProceduresfor{}ualifyingElectricalEquipmentandInstrumentationThetestprocedurerequiredthatthedevicebemountedonthetableofthevibrationmachineinamannersimilartoitsnormal,installedconfiguration.ThedevicewastestedintheoperatingstatesasifitwereperformingitsClass1Efunctions;thesestatesweremonitoredbefore,during,andafterthetesttoensureproperfunctionandabsenceofspuriousfunction.Inthecaseoftherelayexample,bothenergizedanddeenergizedstatesandnormallyopenandnormallyclosedcontactconfigurationsweretestediftherelayisusedinthoseconfigurationsinitsClass1Efunctions.Thedynamicexcitationwasarandommultiplefrequencytestinwhichtheappliedvibrationwasasinusoidaltablemotionatafixedpeakaccelerationandadiscretefrequencyatanygiventime.Thevibratoryexcitationwasappliedintwoorthogonalaxes,horizontalandverticalsimultaneously,withtheaxeschosenasthosecoincidentwiththemostprobablemountingconfiguration.Thedevicewasthenrotated90deginthehorizontalplane,andthetestwasrepeated.Eachdevice,therefore,hasbeentestedinthethreemajororthogonalaxes.Thefirststepwasusuallyasearchforresonancesineachaxissinceresonancescauseamplificationoftheinputvibrationandarethemostlikelycauseofmalfunction.Theresonancesearchwasusuallyrunatlowaccelerationlevelstoavoiddamagingthetestsampleifasevereresonancewasencountered.TheresonancesearchwasperformedfortheapplicablefrequencyrangeinaccordancewithIEEE-344;ifthedevicewaslargeenough,thevibrationsweremonitoredbyaccelerometersplacedatcriticallocationsfromwhichresonancesweredeterminedbycomparingtheaccelerationlevelwiththatatthetableofthevibrationmachine.Sometimesthedeviceseitherweretoosmallforanaccelerometer,withtheircriticalpartsinaninaccessiblelocation,orhadcriticalpartsthatwillbeadverselyaffectedbythemountingofanaccelerometer.Thevibrationsweremonitoredattheclosestlocation.Followingthefrequencyscanandresonancedetermination,thedevicesweretestedtodeterminetheirdynamiccapabilitylimit.Formultifrequencytesting,fiveOBEandoneSSEtestswererunattheappropriateTRS.Insomecases,theTRSwasincreasedgraduallyuntildevicemalfunctionoccurredortheshaketableUSARRevision83.10B-3November1995 NineMilePointUnit2FSARlimitwasreached.Forsinglefrequencytesting,amalfunctionlimittest.wasrunateachresonantfrequencyasdeterminedbythefrequencyscan.Inthistest,theaccelerationlevelwasgraduallyincreaseduntileitherthedevicemalfunctionedorthelimitofthevibrationmachinewasreached.Ifnoresonancesweredetected(aswasusuallythecase),thedevicewasconsideredtoberigid(allpartsmoveinunison)andthemalfunctionlimitwasthereforeindependentoffrequency.Toachievemaximumaccelerationfromthevibrationmachine,rigiddevicesweremalfunctiontestedattheuppertestfrequencysincethatallowedthemaximumaccelerationtobeobtainedfromdeflection-limitedmachines.ThesummaryofthetestsonthedevicesusedinClass1EapplicationsgiveninTable3.10B-1.TheaboveprocedureswererequiredofpurchaseddevicesaswellasthosemadebyGE.Vendortestresultswerereviewedandifunacceptable,thetestswererepeatedeitherbyGEorthevendor.Ifthevendortestswereadequate,thedevicewasconsideredqualifiedtothelimitsofthetest.3.10B.2.3QualificationofValveOperatorsThequalificationofvalveoperatorsisdiscussedinSection3.9B.2.10B.2.4QualificationofNSSSMotorsSeismicqualificationofNSSSmotorsisdiscussedinSection3.9B.2.2inconjunctionwiththeECCSpumpandmotorassembly.Seismicqualificationofthestandbyliquidcontrol(SLC)pumpmotorisdiscussedinSection3.9B.2.2.2.10inconjunctionwiththeSLCpumpmotorassembly.3.10B.3MethodsandProcedureofAnalysisorTestingofSupportsofElectricalEquipmentandInstrumentation.3.10B.3.1DynamicAnalysisandTestingProcedures3.10B.3.1.1Panel-MountedEquipmentTheClass1EequipmentsuppliedbyGEisusedinmanysystemsonmanydifferentplantsandissubjectedtowidelyvaryingdynamicloads.Thequalificationtestswereperformedtoenveloptheapplicablefrequencyrange.Forsupportssubjectedtoseismicloadsonly,thetestedfrequenciesrangefrom1to33Hz.Wheretestingbelow5Hzwaslimitedbycapabilityofthetestfacility,acombinationoftestandanalysiswasusedtoensurethattherewerenountestedresonances.Formulticabinetassembliesthataretoolargeforthetesttable,oneortwobaysoftheassemblyaretested,givingrepresentativeresultsinthefront-to-backandverticalUSARRevision83.10B-4November1995 NineMilePointUnit2FSARdirections.Theside-to-sideresultsareevaluatedandgenerallyfoundtobeconservativeduetotheincreasedflexibilityofthenarrowersection.Ifconservatismcannotbeestablished,thepanelismodeledaccuratelyandacomputeranalysisofitsstructuralresponseisperformed.SomeGE-suppliedClass1Edeviceswerequalifiedbyanalysisonly.AnalysiswasusedforpassivemechanicaldevicesandwassometimesusedincombinationwithtestingforlargerassembliescontainingClass1Edevices.Forexample,atestmighthavebeenruntodeterminenaturalfrequenciesintheequipmentwithinthecriticalfrequencyrange.Iftheequipmentwasdeterminedtobefreeofnaturalfrequencies,itwasassumedtoberigid.Ifithadnaturalfrequenciesinthecriticalfrequencyrange,thencalculationsoftransmissibilityandresponsestovaryinginputaccelerationsweredeterminedtoseeifClass1Edevicesmountedintheassemblywouldoperatewithoutmalfunctioning.Generally,thetestingofClass1Eequipmentwasaccomplishedusingthefollowingprocedure.Assemblies(i.e.,controlpanelsandlocalracks)containingdeviceswithestablishedseismicandhydrodynamicmalfunctionlimitsweremountedonthetableofavibrationmachineinthemanneritwastobemountedwheninuse.AllcontrolpanelandlocalracktestshavebeenperformedaccordingtotherequirementsofIEEE-344.Theinitialvibrationtestineachcasewasalow-levelresonancesearch.Aswiththedevices,theassembliesweretestedinthethreemajororthogonalaxes.Theresonancesearchwasruninthesamemannerasdescribedfordevices.Ifresonanceswerepresent,thetransmissibilitybetweentheinputandthelocationofeachClass1Edevicewasdeterminedbymeasuringtheaccelerationsateachdevicelocationandcalculatingthemagnificationbetweenitandtheinput.Onceknown,thetransmissibilitiescouldbeusedanalyticallytodetermineconservativelytheinputmotionatanyClass1Edevicelocationforanygiveninputtothebaseoftheassembly.Thedescribedfullaccelerationleveltestsshowedthatthepaneltypeshadmorethanadequatemechanicalstrengthandthatacceptabilitywasgustafunctionofitsamplificationfactorandthemalfunctionlevelsofthedevicesmountedinit.Manydevicesweremountedinthetestpanelorrackandqualifiedasanassembly.Otherdevicesweretestedindividuallyaspreviouslydescribed.Sometimespanelsweretestedatloweraccelerationlevelsandthetransmissibilitiesmeasuredtothevariousdevices.Bydividingthedevice'smalfunctionlevelsbythepaneltransmissibilitybetweenthedeviceandthepanelinput,thepanelseismicqualificationlevelcouldbedetermined.Severalhigh-leveltestshavebeenrunonselectedgenericpaneldesignstoensuretheconservatisminusingthetransmissibilityanalysisdescribed.USARRevision83.10B-5November1995 NineMilePointUnit2FSAR3.10B.4OperatingLicenseReviewThedynamictestresultsforsafety-relatedpanelsandcontrolequipmentwithintheNSSSscopearemaintainedinapermanentfilebyGEandcanbereadilyauditedinallcases.TheequipmentusedinClass1EapplicationsatUnit2passedtheprescribedtests.AsummaryofthetestresultsforthedevicesusedinClass1EapplicationsisgiveninTable3.10B-1.USARRevision83.10B-6November1995 NineMilePointUnit2FSAR3~11ENVIRONMENTALQUALIFICATIONOFMECHANICALANDELECTRICALEQUIPMENTSafety-relatedequipmentandcomponentsarequalifiedtomeetperformancerequirementsundernormal,abnormal,accident,andpost-accidentenvironmentalconditionsforthelengthoftimetheyarerequiredtofunctionandtoremaininasafemodeaftertheirsafetyfunctionisperformed.Theenvironmentalconditionsforthoseportionsoftheplantcontainingsafety-relatedequipmentaregivenintheEquipmentQualificationEnvironmentalDesignCriteria(EQEDC),whichissuppliedseparatelyfromtheFSAR.Themethodologyusedtoenvironmentallyqualifyequipmentlocatedinharshenvironments,equipmentlocatedinmildenvironments,andsafety-relatedmechanicalequipmentisdescribedintheEquipmentQualificationDocument(EQD).Section6oftheEQDdescribestheenvironmental-qualification-relatedmaintenance/surveillanceprogram.Equipmentqualificationdocumentationdescribedherein,includingtheEQEDC,EQD,SystemComponentEvaluationWork(SCEW)sheets,andapplicableportionsoftheUnit2MasterEquipmentList,aremaintainedaspartoftheUnit2EquipmentQualificationProgram.ThesedocumentsaremaintainedseparatelyfromtheFSARandarenotconsideredpartoftheFSAR.3.11.1EquipmentIdentificationandEnvironmentalConditionsEnvironmentallyqualifiedelectricalequipmentincludesallthreecategoriesof10CFR50.49(b)+.Safety-relatedmechanicalequipmentincludespumps,MOVs,SRVs,andcheckvalves.AlistofallenvironmentallyqualifiedelectricalandmechanicalequipmentthatislocatedinaharshenvironmentareaisprovidedintheUnit2MEL.Environmentalconditionsforthezoneswheretheequipmentislocatedhavebeencalculatedfornormal,abnormal,andaccidentconditionsandarereportedintheEQEDC.Environmentalconditionsarelistedbyzones,eachzonedefiningaspecificareaintheplant.Environmentalparametersincludetemperature,pressure,relativehumidity,betaandgammaradiationdose,doserateandneutrondose.Whereapplicable,theseparametersaregivenintermsofatime-basedprofile.AsummarypresentationofenvironmentalconditionsandqualifiedconditionsfortheenvironmentallyqualifiedequipmentlocatedinaharshenvironmentzoneiscontainedintheSCEWsheets.USARRevision83.11-1November1995 NineMilePointUnit2FSAR3.11.2QualificationTestsandAnalyses3.11.2.1QualificationEnvironmentallyqualifiedelectricalequipmentthatislocatedinaharshenvironmenthasbeenqualifiedbytestorothermethodsasdescribedinIEEE-323andpermittedby10CFR50.49(f)<'>.Equipmenttypetestisthepreferredmethodofqualification.Environmentallyqualifiedmechanicalequipmentthatislocatedinaharshenvironmenthasbeenqualifiedbyanalysisofmaterialsdatawhicharegenerallybasedontestsandoperatingexperience.ThequalificationmethodologyisdescribedindetailinSection4oftheEQD.TherequirementsofGDC1,4,23,and50ofAppendixAto10CFR50andCriterionIIIofAppendixBto10CFR50aremetasoutlinedbelow:GDC1of10CFR50,AppendixA,requirementsareachievedbyincorporatingperformance,design,construction,andtestingrequirementsintoequipmentspecificationsandbytheestablishmentofasystemofreviewstoensureconformancewiththesespecifiedrequirements.Appropriateauditablerecordsaremaintainedinapermanentfile.RefertoChapter17forafurtherdefinitionofhowCriterionIIIofAppendixBto10CFR50ismet.GDC4requirementsaremetforharshenvironmentequipmentbydesigningandqualifyingtheequipmentforsatisfactoryoperationandpropersafetyfunctionperformanceduringnormal,abnormal,test,andDBAenvironments.TheprotectionsystemmeetsGDC23.Failuremodesandeffectsanalyseshavebeenperformedtoprovethatnosinglefailureresultsinalossofthecapabilityofasystemtoperformitssafetyfunction.Bothelectricalandmechanicalfailureshavebeenconsideredfromcausessuchaslossofpowersupply,lossofcontrolsignal,andfailuresinducedbynormal,abnormal,accident,andseismicevents.Harshenvironmentequipmenthasbeenenvironmentallyqualifiedtoprecludecommonmodefailures.GDC50requirementsareachievedbyanalysisandtestingofpressureboundarycomponentstoensurecontainmentintegrity.AdiscussionofcompliancewithRegulatoryGuidesisprovidedinSection1.8.DesignCriteria1,4,23,and50ofAppendixA,10CFR50,andCriterionIIIofAppendixB,10CFR50.USARRevision83'1-2November1995 NineMilePointUnit2FSARGDC1requirementsareachievedbyincorporationofperformance,design,construction,andtestingrequirementsintoequipmentspecificationsandbyestablishmentofasystemofreviewstoensureconformancewiththesespecifiedrequirements.Appropriateauditablerecordsaremaintainedinapermanentfile.RefertoChapter17forafurtherdefinitionofhowCriterionIIIofAppendixBto10CFR50ismet.Theenvironmentalconditionsinareascontainingsafety-relatedequipmentaregivenintheEQEDC.GDC4requirementsaremetforClass1Eharshenvironmentequipmentbydesigningandqualifyingtheequipmentforsatisfactoryoperationandpropersafetyfunctionperformanceduringnormal,abnormal,test,andDBAenvironments.TheprotectionsystemmeetsGDC23.Failuremodesandeffectsanalyseshavebeenperformedtoprovethatnosinglefailureresultsinalossofthecapabilityofasafety-relatedsystemtoperformitssafetyfunction.Bothelectricalandmechanicalfailureshavebeenconsideredfromcausessuchaslossofpowersupply,lossofcontrolsignal,andfailuresinducedbynormal,abnormal,accident,andseismicevents.Class1Eharshenvironmentequipmenthasbeenenvironmentallyqualifiedtoprecludecommonmodefailures.TherecommendationsprovidedinRGs1.9,1.30,1.40,1.63,1.73,1.89,and1.131havebeenutilizedbyincludingtheserecommendationsinappropriateequipmentspecifications.AdiscussionofcompliancewiththeseregulatoryguidesisprovidedinSection1.8.3.11.2.2MethodofQualificationofClass1EEquipmentandComponentsThedateoftheconstructionpermitSafetyEvaluationReportforUnit2ispriortoJulyI,1974;therefore,Unit2isaCategoryIIplantundertheguidanceofNUREG-0588,July1981,InterimStaffPositiononEnvironmentalQualificationofSafety-RelatedElectricalEquipment.TheenvironmentalqualificationofClass1EequipmentlocatedinharshenvironmentsmeetsorexceedstherequirementsforCategoryIIqualificationinaccordancewithNUREG-0588,includingtheguidanceprovidedforincorporationofIEEE-323.TheenvironmentsforwhichClass1Eequipmentmustperformitssafetyfunctionhavebeenspecifiedandusedasthebasisforenvironmentalqualification.DetailswithrespecttothequalificationmethodologyandacceptancecriteriaareprovidedintheEQD.USARRevision83~113November1995 NineMilePointUnit2FSAR3.11.3QualificationTestResultsTheresultsofqualificationtestsforenvironmentallyqualifiedequipmentaremaintainedinanauditablefile.Asummarypresentationofqualificationtestresultsforenvironmentally-qualifiedelectricequipmentthat,islocatedinaharshenvironmentiscontainedintheSCEWsheets.3.11.4LossofHeating,Ventilating,andAirConditioningToensurethatHVACsystemsdoesnotadverselyaffecttheoperabilityofsafety-relatedcontrolsandelectricalequipmentinbuildingsandareasservedbysafety-relatedHVACsystems,theHVACsystemsservingtheseareasmeetthesingle-failurecriterion.TheHVACsystemsandtherespectivesectionswherespecificsafetyevaluationdetailsmaybefoundareasfollows:1.Maincontrolroom,relayroom,standbyswitchgearrooms,andelectricaltunnels(Section9.4.1).2.Reactorbuildingandstandbygastreatmentfilterrooms(Section9.4.2).3.Dieselgeneratorbuilding(Section9.4.6).4.Servicewaterpumpbays(Section9.4.7.2.2).3.11.5EstimatedChemicalandRadiationEnvironment3.11.5.1ChemicalEnvironmentThechemicalcompositionandresultingpHtowhichsafety-relatedequipmentisexposedduringnormaloperationanddesignbasisaccidentconditionsisreportedinSection2.3oftheEQD.Samplingstationsareprovidedforperiodicanalysisofreactorwater,refuelingandfuelstoragepoolwater,andsuppressionpoolwatertoassurecompliancewithoperationlimitsoftheplanttechnicalspecifications.3.11.5.2RadiationEnvironmentSafety-relatedsystemsandcomponentsaredesignedtoperformtheirsafety-relatedfunctionwhenexposedtonormaloperationalradiationlevelsandaccidentradiationlevels.ThenormaloperationalexposureisbasedontheradiationsourcesprovidedinChapters11and12.RadiationsourcesassociatedwiththeDBAanddevelopedinaccordancewithNUREG-0588,Revision1areprovidedinChapter15.USARRevision83~11-4November1995 NineMilePointUnit2FSARIntegrateddosesassociatedwithnormalplantoperationandtheDBAconditionforvariousplantcompartmentsaredescribedintheEQEDC.Safety-relatedequipmentisqualifiedinaccordancewiththemethodologydescribedintheEQDfortheapplicablebeta,gamma,andneutrondoses.3.11.6SubmergenceAnysafety-relatedequipmentwhichmaybesubmergedduetoaLOCAisidentifiedinSection2.4oftheEQD.ThisequipmentisqualifiedforsubmergenceasshownontheEQDSCEWsheets.USARRevision83.11-5November1995 NineMilePointUnit2FSAR3.11.7References1~2~3.4~5.6.Title10,CodeofFederalRegulations,Paragraph50.49,EnvironmentalQualificationofElectricEquipmentImportanttoSafetyforNuclearPowerPlants.FederalRegisterVol.48,No.15,January21,1983.A.J.Szukiewicz,etal.InterimStaffPositiononEnvironmentalQualificationofSafety-RelatedElectricalEquipment,NUREG-0588,Revision1,July1981.NRCRegulatoryGuide1.89,EnvironmentalQualificationofElectricalEquipmentInformationtoSafetyforNuclearPowerPlants.ProposedRevision1,November1983.NRCRegulatoryGuide1.7,ControlofCombustibleGasConcentrationsinContainmentFollowingaLoss-of-CoolantAccident,Revision2,November1978.NRCRegulatoryGuide1.97,Revision3,InstrumentationforLight-Water-CooledNuclearPowerPlantstoAssessPlantandEnvironsConditionsDuringandFollowinganAccident.IEEE-323-724,QualifyingClassIElectricEquipmentforNuclearPowerGeneratingStations.USARRevision83.11-6November1995 NineMilePointUnit2FSARAPPENDIX3ALISTOFTABLESTableNumberTitle3A.1-13A.3-13A.7-13A.10-13A.12-13A.13-13A~13-23A.14-13A.15-13A.15-23A.15-3EXACTANDCOMPUTERSTRESSESFORTHIN-WALLCYIINDERSHELL1COMPUTERPROGRAMINPUTTHERMALPARAMETERFUNCTIONSFORTAC2DSAMPLEPROBLEMDELETEDCOMPARISONOFEXPERIMENTALDATAANDANALYTICALDATAUSINGLIMITA3SSLAMPROGRAMOUTPUTDATAVERIFICATIONSSLOADPROGRAMOUTPUTDATAVERIFICATIONCOMPUTERVALUESSSLOADPROGRAMOUTPUTDATAVERIFICATIONHANDCALCULATEDVALUESMISSILEPROGRAMVERIFICATIONCOMPARISONOFSUPPORTREACTIONDUETOTHERMAL,ANCHORMOVEMENT,ANDEXTERNALFORCELOADINGCOMPARISONOFDEFLECTIONSANDROTATIONSDUETOTHERMAL,ANCHORMOVEMENT,ANDEXTERNALFORCELOADINGCOMPARISONOFSTRESSDUETOTHERMAL,ANCHORMOVEMENT,ANDEXTERNALFORCE'OADING273A.15-43A.15"53A.15-63A.15-73A.15-8Amendment273A-vJuly1986COMPARISONOFINTERNALFORCESDUETODEADWEIGHTANALYSISCOMPARISONOFDEFLECTIONSANDROTATIONDUETODEADWEIGHTANALYSISCOMPARISONOFSTRESSESDUETODEADWEIGHTANALYSISCOMPARISONOFNATURALFREQUENCIESCOMPARISONOFNATURALFREQUENCIES NineMilePointUnit2FSARAPPENDIX3ALISTOFTABLES(Cont'd.)TableNumber3A.15-93A.15-103A.17-13A.17-23A.17-33A.17-43A.17-53A.18-1TitleNUPIPEVERSUSHANDCALCULATIONINDIVIDUALPAIRUSAGEFACTORFORPOINTNO.30PIPEMATERIALPROPERTIESFLUIDMATERIAL/THERMALPROPERTIESCOMPARISONOFHTLOADWITHHANDCALCULATIONCOMPARISONOFHTLOADWITHCHARTSOFBROCKANDMCNEILLCOMPARISONOFHTLOADWITHTRHEATCOMPARISONOFGHOSH-WILSONRESULTSVERSUSTHEORETICALSOLUTIONSFORACYLINDERUNDERSTATICINTERNALPRESSURE3A.20-13A.21-13A.21-23A.22-13A.22-2NODALFORCECOMPARISONINPUTDATAFORWATHAMCOMPARISONOFNODALFORCECALCULATIONATTIME2.34SECCOMPARISONOFPITRUSTWITHFRANKLININSTITUTEPROGRAM,CYLNOZ,ANDHANDCALCULATIONCOMPARISONOFPITRUSTWITHREFERENCE2RESULTSUSARRevision83A-viNovember1995 NineMilePointUnit2FSARTABLE3A.1-1EXACTANDCOMPUTERSTRESSESFORTHIN-WALLCYLINDERSHELL1COMPUTERPROGRAM~Vi~abe@~a~t3.348x10'n3,750psi!jgEE~13.342x10'n3,750psiUSARRevision81of1November1995

NineMilePointUnit2FSARTABLE3A.17-3COMPARISONOFHTLOADWITHHANDCALCULATIONReynoldsnumberHeattransfercoefficientHTLOAD186,700946'Btu/'F-hr-ft~HandCalculation186,700946.8Btu/F-hr-ft~

NineMilePointUnit2FSARTABLE3A.17-4COMPARISONOFHTLOADWITHCHARTSOFBROCKANDMCNEILLaraeteMaximumhT,('F)MaximumhT~('F)/~a.ts43.318.50~~OD45.148.36USARRevision81of1November1995 NineMilePointUnit2FSARTABLE3A.17-5COMPARISONOFHTLOADWITHTRHEATParaeterMaximumhT,(4F)MaximumET~(4F)MaximumT,-T,('F)TRH~E44.708'919.03HTLOAD45.148.3619.08USARRevision81of1November1995

NineMilePointUnit2FSARTABLE3A.18-1COMPARISONOFGHOSH-WILSONRESULTSVERSUSTHEORETICALSOLUTIONSFORACYLINDERUNDERSTATICINTERNALPRESSURERadiusTheoreticalI!ILSThin-Shell~TheorShellglementRectangularleetTriangularlementGOS-ILSONesultsR=39.519.748ogR=4020F00KsfR=40.519.249arR39507357KsfR=40.5-0.23620.2719.7419.24-0.7365-0.236919.75519.255-0.683-0.188R=39R=40ftR=411.82x10'.812x101.804x101.87x10'.8197x1031.8111x10'.8039x101.8192x10'.8110x101.8039x10',=hoopstress0,=radialstress=displacementinradialdirectionUSARRevision81of1November1995

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NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESGENERALTABLEOFCONTENTSPageT=TableF=FicFurePageAmendmentT=TableNumberF=FicFurePageAmendmentT=TableAmendmentNumberF=FicFureNumberiii1ii1VvR06R07R07R06R06USARRevision7EPiOctober1994

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PDTKDFKTYLININEMILEPOINTNUCLEARSTATION-UNIT27NIAGARAuMOHAWKVOL.1

NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANT1.11.21~31.41.51.61.71.81.91.101.111.121.13CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2222.12.22.32.42.5GeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,4Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QCHAPTER33.13.23.33.4DESIGNOFSTRUCTURES,COMPONENTS,EQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsHindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume3.5)3.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3.11Appendixes3Athrough3EMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulated.RuptureofPiping(SWECScopeof-.Supply)ProtectionAgainstDynamicEffectsAssociatedWithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesignDesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipment9,101010101012121212CHAPTER4REACTOR124.14.24.34.44.54.6Appendix4ACHAPTER55.15.25.35.4Appendixes5A,SummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSSummaryDescriptionIntegrity.ofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B12121212121212131313131313USARRevision7October1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolumeCHAPTER6ENGINEEREDSAFETYFEATURES136.16.26.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER7INSTRUMENTATIONANDCONTROLSYSTEMS7.17.27.37.47.57.67.7Appendixes7AgCHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5Appendixes9A,CHAPTER10IntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,CoolingfandVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEM151515161616161616161616,17171717181920,2121,22232310.110'10.3SummaryDescriptionTurbineGeneratorMainSteamSupplySystem232324USARRevision7October1994 NineMilePointUnit2FSARSectionTABLEOFCONTENTS(Cont'd.)TitleVolume010.4CHAPTER11OtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENT242411.,111.211.311.411.5Appendix11ACHAPTER1212.112.212.312.412.5CHAPTER1313.113.213:313.413.513.6CHAPTER1414.114.2CHAPTER15RADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALA%%)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurityINITIALTESTPROGRAMSpecificIncludedAnalysisSpecificIncludedAnalysisInformationToBeinPreliminarySafetyReport,(PSAR)InformationToBeinFinalSafetyReport,(FSAR)ACCIDENTANALYSISSourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems24242525252525252525262626262626262626262626,272715.015.115.2GeneralDecreaseinReactorCoolantTemperatureIncreaseinReactorPressure272727USARRevisionivApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section15.315.415.515.615.715.8AppendicesCHAPTER16CHAPTER1717.017.117.2CHAPTER18TitleDecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientswithoutScram(ATWS)15Athrough15HTECHNICALSPECIFICATZONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMVolume2727272727272828282828282818.118.2APPENDIXAAPPENDIXBDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1),NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE28282828USARRevision6April1994

NineMilePointUnit2FSARCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANTTABLEOFCONTENTSSectionTitleINTRODUCTIONPacae1~111.21.2.11.2.1.11.2.1.21.2.1.2.11.2.1.31;2.1.3.1.1.2.1.3.21.2.1.3.31.2.1.3.41.2.1.3.51.2.1.3.61.2.1.3.71.2.1.3.81.2.21.2.2.11.2.2.21.2.2.31.2.31.2.41.2.4.11.2.4.21.2.4.31.2.4.41.2.4.51.2.4.61.2.51.2.5.11.2.5.21.2.5.31.2.61'.7GENERALPLANTDESCRIPTIONPrincipalDesignCriteriaGeneralCriteriaPowerGenerationDesignCriteriaSafetyDesignCriteriaSystem-by-SystemApproachNuclearSystemCriteriaPowerConversionSystemsCriteriaElectricalPowerSystemsDesignCriteriaRadwasteSystemDesignCriteriaAuxiliarySystemsDesignCriteriaShieldingandAccessControlDesignCriteriaNuclearSafetySystemsandEngineeredSafeguardsDesignCriteriaProcessControlSystemDesignCriteriaSiteDescriptionSiteCharacteristics:SiteLocationandSizeAccesstotheSiteDescriptionoftheSiteandEnvironsStructuresandEquipmentNuclearSteamSupplySystemReactorCoreandControlRodsReactorVesselandInternalsReactorRecirculationSystemResidualHeatRemovalSystemReactorWaterCleanupSystemNuclearLeakDetectionSystemElectrical,Instrumentation,andControlSystemsElectricalPowerSystemNuclearSystemProcessControlandInstrumentationPowerConversionSystemsProcessControlandInstrumentationRadioactiveWasteSystemFuelHandlingandStorageSystems1.2-11.2-11.2-11~2210231.2-61.2-61027102-71~271.2-81.2-81.2-81.2-91.2-101.2-101~2111~2111~211102-131~2131~2131.2-141.2-141.2-151.2-151.2-151.2-151.2-171.2-181.2-191.2-20USARRevisionApril1994 NineMilePointUnit2FSARCHAPTER1TABLEOFCONTENTS(Cont'd.)Section1.2.7.11.2.7.21.2.7.31.2.7.41.2.81.2.8.11.2.8.21.2.8.31.2.8.41.2'.8.51.2.8.61.2.8.71.2.8.81.2.8.91.2.91.2.9.11.2.9.21.2.9.31.2.9.41.2.9.51.2.9.61.2.9.71.2.9.81.2.9.91.2.9.101.2.9.111.2.9.121.2.9.131.2.9.141.2.9.151.2.9.161.2.9.171.2.9.181.2.9.191.2.9.20TitleNewFuelStorageSpentFuelStorageFuelHandlingSystemSpentFuelPoolCoolingandCleanupSystemPowerConversionSystemTurbineGeneratorMainSteamSystemMainCondenserMainCondenserAirRemovalSystemTurbineGlandSealingSystemSteamBypassSystemandPressureControlSystemCirculatingWaterSystemCondensateandFeedwaterSystemsCondensateDemineralizerSystemNuclearSafetySystemsandEngineeredSafetyFeaturesReactorProtectionSystemNeutronMonitoringSystemControlRodDriveSystemControlRodDriveHousingSupportsControlRodVelocityLimiterNuclearSystemPressureReliefSystemReactorCoreIsolationCoolingSystemEmergencyCoreCoolingSystemsContainmentSystemsContainmentandReactorVesselIsolationControlSystemMainSteamIsolationValves(MSIV)MainSteamFlowRestrictorsMainSteamRadiationMonitoringSystemResidualHeatRemovalSystemVentilationExhaustRadiationMonitoringSystemStandbyGasTreatmentSystemSafety-RelatedElectricalPowerSystemsStandbyLiquidControlSystemSafeShutdownfromOutsidetheControlRoomMainControlRoomHeating,VentilatingandAirConditioningSystemPacae1.2-201.2-201.2-201.2-201.2-21,1.2-211.2-211.2-211.2-211.2-221.2-221.2-221.2-221~2231~2231~2231~2231~2231.2-241.2-241.2-241.2-241.2-241.2-251.2-261.2-261.2-261~2271~2271A2271~2271~2271.2-281.2-281.2-29USARRevision1-iiApril1994 NineMilePointUnit2FSARCHAPTER1LISTOFTABLESTable,NumberTitle1%311.3-210331.3-4COMPARISONOFNUCLEARSTEAMSUPPLYSYSTEMDESIGNCHARACTERISTICSCOMPARISONOFENGINEEREDSAFETYFEATURESDESIGNCHARACTERISTICSCOMPARISONOFCONTAINMENTDESIGNCHARACTERISTICSCOMPARISONOFELECTRICALPOWERSYSTEMDESIGNCHARACTERISTICS1.3-5COMPARISONOFRADIOACTIVEWASTEMANAGEMENTDESZGNCHARACTERISTICS1.3-61~371.3-81.3-91.6-11~711.721.8-11.8-1a1.8-21.9-1F10-11.11-1COMPARISONOFPOWERCONVERSIONSYSTEMDESIGNCHARACTERISTICSCOMPARISONOFSTRUCTURALDES1GNCHARACTERISTICSCOMPARISONOFFINALANDPRELIMINARYDESIGNINFORMATIONFORTHENSSSSCOPEOFSUPPLYCOMPARISONOFFINALANDPRELIMINARYDESIGNINFORMATIONFORTHEBALANCEOFPLANTREFERENCEDREPORTSFORTHENSSSSCOPEOFSUPPLY'ELECTRXGAL~INSTRUMENTATION~ANDCONTROLDRAWINGSPIPXNGANDXNSTRUMENTATIONDIAGRAMSCONFORMANCEWITHDIVISION1NRCREGULATORYGUIDESCOMPLIANCEWXTHREGULATORYGUIDE1.150CONFORMANCETODIVISION8NRCREGULATORYGUIDESTANDARDREVIEWPLANCONFORMANCETOACCEPTANCECRITERIANUREG-0737TMI-2ITEMSABBREVIATXONSANDACRONYMSUSEDINFSARUSARRevision6April1994 NineMilePointUnit2FSARCHAPTER1LISTOFFIGURESFigureNumberTitle10111.2-11~221~231.2-41.2-5HEATBALANCEATRATEDPOWERPLOTPLANSTATIONAEUVQlGEMENTDELETEDDELETEDDELETED1.2-6Sjl.1GENERALAEGVQTGEMENTiREACTORBUILDINGPLAN175~-P"AND188~-6"1.2-6Sjl.2GENERALAEGVQlGEMENT~REACTORBUILDINGPLANEL196'0"1427Sjl.1GENERALAREVQlGEMENT,REACTORBUILDINGPLANEL215~-0"1~27S11.2GENERALARE~GEMENT~REACTORBUILDINGPLANEL240/-Pn1.2-8Sh.11.2-8Sh.2GENERALARP~GEMENT,REACTORBUILDINGPLANEL261'-0"ANDMISCELLANEOUSGENERALARRANGEMENT,REACTORBUILDINGPLANEL215'-0"ANDMISCELLANEOUS1.2-9S11.1GENERALAREV&7GEMENT,REACTORBUILDINGPLANEL289'-0"1.2-9Sjl.21.2-10S11.11.2-10SIL.2GENERALARRANGEMENT~REACTORBUILDINGPLANEL306r0'sGENERALARR2WGEMENTiREACTORBUILDINGPLANEL328'-10"GENERALARRt&lGEMENT,REACTORBUILDINGPLANEL353'-10"1.2-111.2-12'GENERALAEGVQIGEMENT,REACTORBUILDINGSECTIONS(SHEETS1THROUGH4)GENERALARRANGEMENT,REACTORBUILDINGSECTION2-2USARRevision61V3.April1994 NineMilePointUnit2FSARCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANT

1.1INTRODUCTION

ThisFinalSafetyAnalysisReport(FSAR)issubmittedbytheNiagaraMohawkPowerCorporation(Applicant)anditsco-owners(CentralHudsonGasandElectricCorporation,LongIslandLightingCompany,NewYorkStateElectricandGasCorporation,andRochesterGasandElectricCorporation)insupportoftheapplicationforaClass103operatinglicenseforthenuclearpowerstationdesignatedNineMilePointNuclearStation-Unit2(Unit2).Unit2islocatedona364-ha(900-acre)siteownedbyNiagaraMohawkPowerCorporation(NMPC),andissituatedonthesoutheastshoreofLakeOntario,OswegoCounty)NYtapproximately10km(6.2mi)northeastofthecityofOswego.Unit2andsupportfacilitiesoccupyabout18.2ha(45acres),andsharethesitewiththeexistingNineMilePointNuclearStation-Unit1(Unit1)(DocketNo.50-220)whichhasbeenincommercialoperationsince1969.TheNineMilePointsiteisadjacenttotheJamesA.FitzPatrickNuclearPowerPlantownedbytheNewYorkPowerAuthority(NYPA);Unit2islocated274m(900ft)eastofUnit1andabout716m(2,350ft)westoftheJamesA.FitzPatrickplant.Unit2employsanuclearsteamsupplysystem(NSSS)consistingofasingle-cycle,forcedcirculatingboilingwaterreactor(BWR).Theplant-ratedcorethermalpowerlevel(Figure1.1-1)is3,323MWtcorrespondingtoanetelectricaloutputof1,080MWe,anddesignthermalpowerof3,463MWtcorrespondingtoagrosselectricaloutputof1,202MWe.Thethermalpowerusedfortheplanttransientandloss-of-coolantaccident(LOCA)analysesis3,463MWt.Allsafetysystemshavebeendesignedforathermalpowerof3,489MWt.TheNSSSsupplierisGeneralElectricCompany-NuclearEnergyOperations(GE-NEO).ThebalanceoftheplantisdesignedandconstructedbyStone&WebsterEngineeringCorporation(SWEC).OtherplantsdesignedbySWECthataresimilarinconceptarecurrentlyunderreviewbytheNuclearRegulatoryCommission(NRC).ThesearetheShorehamNuclearPowerStation,Brookhaven,LongIslandiNYgandtheRiverBendStation,St.Francisville,LA.ThecontainmentdesignemploystheBWRMarkIIconceptofover-underpressuresuppressionwithmultipledowncomersconnectingthereactordrywelltothewater"-filledpressuresuppressionchamber.Theprimarycontainmentisasteel-lined,reinforcedconcreteenclosurehousingthereactorandthesuppressionpool.USARRevision61.1-1April1994 NineMilePointUnit2FSARThereactorbuildingcompletelyenclosestheprimarycontainment.Thestructureprovidessecondarycontainmentwhentheprimarycontainmentisclosedandinservice,andprovidesprimarycontainmentwhentheprimarycontainmentisopen,asduringrefueling.Thereactorbuildinghousestherefuelingandreactorservicingequipment,newandspentfuelstoragefacilities,andotherreactorauxiliaryandserviceequipment.Theprimarypurposeofthereactorbuildingistominimizeground-level'releaseof'airborneradioactivematerial.Theouterwallofthereactorbuildingisreinforcedconcreteuptothecraneraillevelabovetherefueling.floor.Abovethecraneraillevel,thesuperstructureisasteelframeusingmetalwallpanelswithsealedjoints.Accesstothebuildingisthroughairlocks.Thepowergenerationcomplexincludesseveralcontiguousbuildings:'hereactorbuildingwithtwoauxiliarybays,thecontrolbuilding,theturbinebuilding,andtheradwastebuilding.Otherbuildings,suchasthesecurityfacility,arealsolocatedinthegeneralplantarea.Ascreenwellforthecirculatingandservicewatersystemsislocatedapproximately107m(350ft)northwestofthecenterlineofthereactorbuilding.CondensercoolingforUnit2isprovidedfromacounterflow,natural-draft,hyperbolic,concretecoolingtowerlocatedapproximately330m(1,000ft)southofthecenterlineofthereactorbuilding.TheultimateheatsinkforemergencycorecoolingisLakeOntario.Belowgradeandnorthofthescreenwellbuilding,therearetwoconcretetunnelsthatconveytheservicewaterintake,servicewaterdischarge,andcoolingtowerblowdown.Asafety-relatedintakepipeisenclosedineachtunnel.Theintakepipesextendfromtheintakeshaftapproximately396m(1,300ft)northwardunderLakeOntariotothesubmergedintakestructures.Onetunnelalsocontainsthedischargepipewhichextendsapproximately550m(1,800ft)tothedischargediffuser.RadionuclidesareemittedtotheatmospherefromtwolocationsatUnit2.Thesearethestackandthecombinedventfortheradwasteandreactorbuildings.Liquidradwasteisstoredfordecayorconcentratedtoasolidwasteforcontrolleddisposalatregulatedstoragesites.TheshieldingdesignandplantlayoutarebasedonextensiveexperienceofNMPCandSWECincontrollingradiologicalexposurestoaslowasreasonablyachievable(ALARA)levels.Estimatedradiologicaldosesfornormaloperationsandpostulatedaccidentsareallfractionalpartsofthedoseslistedinfederalradiologicalguidelinesforsitingandoperationofnuclearpowerplants.EnvironmentalimpactsaredescribedintheseparateEnvironmentalReport-OperatingLicenseStage(ER-OLS)beingsubmittedforUnit2.USARRevision61~12April1994 NineMilePointUnit2FSARl.llABBREVIATIONSANDACRONYMSTablel.ll-lisalistofabbreviationsusedinthisFSAR.

NineMilePointUnit2FSARTABLE1.11-1ABBREVIATIONSANDACRONYMSUSEDINFSARADSALARAAOVAPAPRMARIARMSATWSAutomaticdepressurizationsystemAslowasreasonablyachievableAir-operatedvalveAnnuluspressurizationAveragepowerrangemonitorAlternaterodinsertionArearadiationmonitoringsystemAnticipatedtransientwithoutscramBCPBOCBSWBTPBWRBottomcenterpressureBeginningofcycleBiologicalshieldwallBranchtechnicalpositionBoilingwaterreactorCADCAMCCWCGCSCHFCIVCIVMCMFACNDCOCPRCRDCRDACRPICRVICSCUFCWSContainmentatmospheredilution(device')ContinuousairmonitorClosedcoolingwaterCombustiblegascontrolsystemCriticalheatfluxCombinedintermediatevalveCollision-imported-velocitymethodCommonmodefailureanalysisCondensatedemineralizerCondensationoscillationCriticalpowerratioControlroddriveContxolroddropaccidentControlrodpositionindicationContainmentandreactorvesselisolationcontrolsystemCumulativeusagefactorCirculatingwatersystemDARDBDBADBEDBFLDCDTDERDGDRMSDesignAssessmentReport,forHydrodynamicLoadsDesignbasisDesignbasisaccidentDesignbasisearthquakeDesignbasisfloodlevelDirectcurrentdifferentialtransducerDouble-endedruptureDieselgeneratorDigitalradiationmonitoringsystemEABExclusionareaboundary1of6 0

NineMilePointUnit2FSARTABLE1'1-1(Cont)ECAECCSECNEFCVEHCEICEOCEOFEPAEPZEQDERFESFETSEngineeringchangeauthorizationEmergencycorecoolingsystemEngineeringchangenoticeExcessflowcheckvalveElectrohydrauliccontrolEnergyInformationCenterEndofcycleEquivalentoccurrencefactorElectricprotectiveassemblyEmergencyplanningzoneEnvironmentalqualificationdocumentEmergencyresponsefacilityEngineeredsafetyfeatureEmergencytripsystemFAFASFATTFCDFDDRFLECHTFMEAFMHFPCCFPSFSARFullarc(modeofTCVoperation)FluidactuatorsystemFractureappearancetransitiontemperatureFunctionalcontroldiagramFielddeviationdispositionrequestFull-lengthemergencycoolingheat,transferFailuremodesandeffectsanalysisFixturemountingheightFuelpoolcoolingandcleanupFireprotectionsystemFinalsafetyanalysisreportGDCGEGETABGeneraldesigncriterionGeneralElectricCompanyGEthermalanalysisbasisHAZHCUHDFMHELBHEMHEPAHEPCOHPCIHPCSHPUHXHVACHVRSHeataffectedzoneHydrauliccontrolunitHeavydensityfillmaterialHighenergylinebreakHomogeneousequilibriummodelHigh-efficiencyparticulateair/absolute(filter)Hydro-ElectricPowerCommissionofOntarioHighpressurecoolantinjectionHighpressurecoresprayHydraulicpowerunit,HeatexchangerHeating,ventilating,andairconditioningReactorbuildingventilationsystemIACIASInterimacceptancecriteria(NRC)Instrumentairservice2of6

NineMilePointUnit2FSARTABLE1.11-1(Cont)IBAICCIDCIDSIEDIGSCCILRTIPCEAIRMLCOLCSLDSLFMGLHGRLOCALOFWLOOP(LOP)LPAPLPCILPCSLPDSLPRMLPSPLPZLSALSDLSSSLTCLWSMAPLHGR~MBAMCCM/CCMCPRMGMLDMLHGRMMIMOIMOVMPCMSIVMSIV-LCSIntermediatebreakaccidentInadequatecorecoolingIncidentdetectioncircuitryInstrumentdatasheetInstrumentandelectricaldrawingIntergranularstresscorrosioncrackingIntegratedleakageratetestInsulatedPowerCablesEngineersAssociationIntermediaterangemonitorLimitingconditionofoperationLeakagecontrolsystemLeak-detectionsystemLowfrequencymotorgeneratorLinearheatgenerationrateLoss-of-coolantaccidentLossoffeedwaterLossofoffsitepowerLowpoweralarmpointLowpressurecoolantinjectionLowpressurecoresprayLoosepartsdetectionsystemLocalpowerrangemonitorLowpowersetpointLowpopulationzoneLowspecificactivityLakesurveydatum(of1935)LimitingsafetysystemsettingLoadtapchanging(mechanism)LiquidradwastesystemMaximumaverageplanarlinearheatgenerationrateMisplacedbundleaccidentMotorcontrolcenterMaintenanceandcalibrationcommunication(system)MinimumcriticalpowerratioMotorgeneratorsetMeanlowwaterdatumMaximumlinearheatgenerationrateModifiedMercalliintensityMethodofimagesMotoroperatedvalveMaximumpermissibleconcentrationMainsteamisolationvalveMainsteamisolationvalveleakagecontrolsystemUSARRevision13of6October1989

NineMilePointUnit2FSARTABLE1.11-1(Cont'd)mslMSLMSLBMTVMeansealevelMainsteamlineMainsteamlinebreakMechanicaltripvalve.NBNBRNBSNDLNDTNDTTNEDNIOSHNMSNPRDSNPSHNRVNSSNSOANSSSNUMACRWMNuclearboilerNuclearboilerrated(power)NationalBureauofStandardsNucleardatalinkNilductilitytransitionNilductilitytransitiontemperatureNuclearenergydivision(GE)NationalInstituteforOccupationalSafetyandHealthNeutronmonitoringsystemNuclearplantreliabilitydatasystemNetpositivesuctionheadNonreturnvalveNonnuclearsafetyNuclearsafetyoperationalanalysisNuclearsteamsupplysystemNuclearmeasurementanalysisandcontrolrodworthminimizerOBEOFSOREOTOperatingbasisearthquakeOrificedfuelsupportOccupationalradiationexposuresOperationaltransientPAPAMPASNYPCIPCIOMRPCRVICSPCSPCTp.f.PGCCPE(IDPLUPMFPMSPMWSPP/PAPQLPRMPublicaddress(system)Post-accidentmonitoringPowerAuthorityoftheStateofNewYorkPellet-claddinginteractionPreconditioningcladdinginterimoperatingmanagementrecommendationPrimarycontainmentandreactorvesselisolationcontrolsystemProcesscomputersystemPeakcladdingtemperaturePowerfactorPowergeneratingcontrolcenterPipingandinstrumentationdiagramPowerloadunbalanceProbablemaximumfloodProbablemaximumsurgeProbablemaximumwindstormPageparty/publicaddress(system)ProductqualitychecklistPowerrangemonitorUSARRevision34of'6October1991

NineMilePointUnit2FSARTABLE1.11-1(Cont'd)PSARPSDPTPDPVSPWRPreliminarysafetyanalysisreportPowerspectrumdensityProjecttestprogramobjectivesPlantventstackPressurizedwaterreactorQAQCQualityassuranceQualitycontrolRABRBCLCWRBMRBPCRCICRCPBRCSRCSCMRDCSRHRHRRMCSRMSRMSRPCRPISRPSRPTRPVRRCSRSCMRSCSRSORSPCMRSSRWCURWPRestrictedareaboundaryReactorbuildingclosedloopcoolingwater(system)RodblockmonitorReactorbuildingpolarcraneReactorcoreisolationcoolingReactorcoolantpressureboundaryReactorcoolantsystemRHRcontainmentspraycoolingmodeRoddrivecontrolsystemRelativehumidityResidualheatremovalReactormanualcontrolsystemRadiationmonitoringsystemRootmeansquareRodpatterncontrollerRodpositioninformationsystemReactorprotection(trip)systemRecirculationpumptripReactorpressurevesselRedundantreactivitycontrolsystemRHRreactorshutdowncoolingmodeRodsequencecontrolsystemReactorsystemoutlineRHRsuppressionpoolcoolingmodeRemoteshutdownsystemReactorwatercleanupRadiationworkpermitSACFSARSBASCASCBASDIVSDVSEFSingleactivecomponentfailureSafetyanalysisreportSmallbreakaccidentSingle-channelanalyzerSelf-containedbreathingapparatusScramdischargeinstrumentvolumeScramdischargevolumeSingleequipmentfailureUSARRevision35of6October1991

NineMilePointUnit2FSARTABLE1.11-1(Cont'd)SFCSGTSSLCSMSASOESOFSORCSPCSPDSSPGSRABSRDISRMSRMSRPSRSSSRVSRVDLSSSSESWPSpentfuelpoolcoolingandcleanupsystemStandbygastreatmentsystemStandbyliquidcontrolStandardmetropolitanstatisticalareaSingleoperatorerrorSingleoperator.failureStationOperationsReviewCommitteeSound~oweredcommunication(system)SafetyparameterdisplaysystemSubstitutepositiongeneratorSafetyReviewandAuditBoardSafety-relateddisplayinstrumentationSourcerangemonitorSecurity-relatedmaterialsStandardReviewPlanSquarerootofthesumofthesquaresSafety/reliefvalveSafety/reliefvalvedischargelineSafeshutdownSafeshutdownearthquakeServicewatersystemTBCLCWTCVTGTIPTLDTSSTSVCTurbinebuildingclosedloopcoolingwaterTurbinecontrolvalveTurbinegeneratorTraversingincoreprobeThermoluminescentdosimeterTemperaturesensor/switchTurbinestopvalveclosureUHSUPSUltimateheatsinkUninterruptiblepowersupplyZPAZeroperiodasymptoteUSARRevision36of6October1991

(CONSISTENTWITH1967ASMESTEAMTABLES)LEGEND~FLOW,Ib/hrF~TEMPERATURE,FH,h~ENTHALPY,Btu/IbM~%MOISTUREP~PRESSURE,psiaM~ISOLATIONVALVES1020PASSUMEDSYSTEMLOSSESTHERMAL1.1MWMAINSTEAMFLOW14,267,000¹1191.6H0.3M985P32,500,000¹534F,528.5h3323MwtMAINFEEDFLOW14,575,000¹420F,398.0h14,235,000¹420.0F,397.6h2RECIRCULATIONLOOPS20INTERNALJETPUMPSTOTALCOREFLOW105.5x105¹4h~1.2,CORETHERMALPOWERPUMPHEATINGCLEANUPDEMINSYSTEMLOSSESOTHERSYSTEMLOSSESTURBINECYCLEUSE3323.0MWt+12.411.21.13323.1MWtMtttDh.Q527.5in436F415.1hCLEANUPDEMINERALIZERSYSTEMRODDRIVEFEEDFLOW32,000IIBOF4Bh340,000¹533F,527.3hFROMCONDENSATESTORAGETANKFIGURE1.1-1HEATBALANCEATRATEDPOWERNIAGARAMOHAWKPOWERCORPORATIONNINEMILEPOINT-UNIT2FINALSAFETYANALYSISREPORTAMENDMENT21SEPTEMBER1985 00 NineMilePointUnit2FSAR16.accidentsthatreleaseradioactivematerialintotheprimarycontainmentvolume.'Itispossibletotestprimarycontainmentintegrityandleak-tightnessatperiodicintervals.17.Areactorbuildingisprovidedthatcompletelyenclosesboththeprimarycontainmentandthefuelstorageareas.Thesecondarycontainmentincludesamethodforcontrollingreleaseofradioactivematerialsfromthebarrierandincludesacapabilityforfilteringradioactivematerialswithinthebarrier.18.Thereactorbuildingisdesignedtoactasaradioactivematerialbarrier,ifrequired,whentheprimarycontainmentisopenforexpectedoperationalpurposes.19.Theprimarycontainmentandreactorbuilding,inconjunctionwithotherengineeredsafeguards,limitsradiologicaleffectsofaccidentsresultinginthereleaseofradioactivematerialtotheprimarycontainmentvolumetosignificantlylessthantherequirementsof10CFR100.20.Provisionsaremadeforremovingenergyfromwithintheprimarycontainment,tomaintaintheintegrityoftheprimarycontainmentsystemfollowingaccidentsthatreleaseenergytotheprimarycontainment.21.Pipingthatpenetratestheprimarycontainment.structureandservesasapathfortheuncontrolledreleaseofradioactivematerialtotheenvironsisautomaticallyisolatedwheneversuchpotentialforradioactivematerialreleaseexists.Suchisolationiseffectedintimetolimitradiologicaleffectstosignificantlylessthantherequirementsof10CFR100.22.Theemergencycorecoolingsystem(ECCS)isprovidedtolimitfuelcladdingtemperatureto2,200'FasaresultofaLOCA.23.TheECCSprovidesforcontinuityofcorecoolingoverthecompleterangeofpostulatedbreaksizesintheRCPB.24.TheECCSisdiverse,reliable,andredundant.25.OperationoftheECCSisinitiatedautomaticallywhenrequired,regardlessoftheavailabilityofoffsitepower.26.Themaincontrolroomisshieldedagainstradiationtopermitcontinuedoccupancyunderaccidentconditions.USARRevision61.2-5April1994 NineMilePointUnit,2FSAR27.Intheeventthatthemaincontrolroombecomesuninhabitable,itispossibletobringthereactorfrompowerrangeoperationtoacoldshutdownconditionbymanipulatinglocalcontrolsandequipmentavailableoutsidethemaincontrolroom.28.Backupreactorshutdowncapabilityisprovidedindependentofnormalreactivitycontrolprovisions.Thisbackupsystemshutsdownthereactorfromanynormaloperatingconditionandmaintainstheshutdowncondition.1.2.1.3System-by-SystemApproachTheprincipalarchitecturalandengineeringcriteriafordesignaresummarizedbelowonasystem-by-systemorsystemgroupbasis.'hesystem-by-systempresentationfacilitatesunderstandingoftheactualdesignofanyonesystem.Onlythemostrestrictiveofanyrelatedcriteriaarestatedforasystem.Wherethemostrestrictivecriterionisclassifiedasapowergenerationconsideration,lessrestrictivesafetycriteriamaynotbestatedinthesystem-by-systempresentation.However,theactualdesignofasystemmustreflectallcriteriathatpertaintoit.1.2.1.3.1NuclearSystemCriteriaPrincipaldesigncriteriaforthereactorsECCSgRCPBgandreactivitycontrolsystemsareasfollows:ThenuclearsystemisdesignedtosupportaGEBWRratedat3,323MWt.2.Fuelcladdingisdesignedtoretainintegrityasaradioactivematerialbarrierthroughoutthedesignpowerrange.Fuelcladdingisdesignedtoaccommodate,withoutlossofintegrity,thepressuresgeneratedbythefissiongasesreleasedfromfuelmaterialthroughoutthedesignlifeofthefuel.3.Fuelcladding,inconjunctionwithotherunitsystems,isdesignedtoretainintegritythroughoutanyabnormaloperationaltransient.ThoseportionsofthenuclearsystemthatformpartoftheRCPBaredesignedtoretainintegrity,asaradioactivematerialbarrierfollowingabnormaloperationaltransientsandaccidents.5.HeatremovalsystemsincludingtheECCSandmakeupwatersuppliesareprovidedinsufficientcapacity,redundancy,andoperationaladequacytoremoveheatgeneratedinthereactorcoreforthefullrangeofnormaloperationalconditionsfromunitshutdowntodesignpowerandforanyabnormaloperationaltransientUSARRevision61.2-6April1994 NineMilePointUnit2FSARTheauxiliaryboilerbuilding(Figure1.2-34),locatednorthofthescreenwellbuilding,housestheelectricboilersandaccessoriestosupplysteamtotheplantduringshutdown.Thestandby'astreatmentbuildingandrailroadaccessarea(Figures1.2-35and1.2-36)housethestandbygastreatmentfiltersandassociatedequipmentandallowaccessforspentfuelshipping.Thecondensatestoragetankbuilding(Figure1.2-37)housesthecondensatestoragetanksandassociatedequipment.Thenatural-draftcoolingtower(Figures1.2-38and1.2-39)providesthenormalheatsinkforheattransferredtothecirculatingwatersystemfromthemaincondensers.Theauxiliaryservicebuilding(Figures1.2-7and1.2-8),adjacenttothereactorbuilding,housestheheating,ventilatingandairconditioning(HVAC)roomanddecontaminationandshowerfacilitiesforpersonnel.Thedecontaminationarea(Figures1.2-19through1.2-21,1.2-23,and1.2-24),immediatelysouthoftheradwastebuilding,providesthefacilityfordecontaminationoflargetoolsandequipment,andasimpleroom.Italsohousescleansteamreboilersandrelatedequipment.Thehydrogenstoragearea(forhydrogencoolingoftheturbinegenerator,Figure1.2-40)islocatedwestoftheoffgasarea.Thehydrogenstoragebottlesaremountedonconcretepadsandareinafencedarea.1.2.4NuclearSteamSupplySystemThenuclearsystemincludesadirect-cycle,forcedcirculation,GEBWRthatproducessteamfordirectuseinthesteamturbine.AheatbalanceshowingthemajorparametersofthenuclearsystemforthewarrantedpowerconditionisshownonFigure1.1-1.TheNSSSisfurtherdiscussedinChapters4and5.1.2.4.1ReactorCoreandControlRodsThereactorfuelandcoredesignaredescribedinSection2ofReference5andSection1ofReference6.Experiencehasshownthatthecontrolrodsarenotsusceptibletodistortionandhaveanaveragelifeexpectancymanytimestheresidencetimeofafuelloading.1.2.4.2ReactorVesselandInternalsThereactorvesselcontainsthecoreandsupportingstructures;thesteamseparatorsanddryers;thejetpumps;thecontrolrodUSARRevision61.2-13April1994 NineMilePointUnit2FSARguidetubes;thedistributionlinesforthefeedwater,coresprays,andstandbyliquidcontrol;thein-coreinstrumentation;~andothercomponents.Themainconnectionstothevesselincludethesteamlines,coolantrecirculationlines,feedwaterlines,CRDandin-corenuclearinstrumenthousings,corespraylines,residualheatremoval(RHR)lines,standbyliquidcontrolline,coredifferentialpressureline,jetpumppressure-sensinglines,andwaterlevelinstrumentation.fThereactorvesselisdesignedandfabricatedinaccordancewithapplicablecodesforapressureof1,250psig.Thenominaloperatingpressureinthesteamspaceabovetheseparatorsis1,020psia.Thevesselisfabricatedoflow-alloysteelandiscladinternallywithstainlesssteel(exceptforthetopheadnozzlesandnozzleweldzoneswhichareunclad).Thereactorcoreiscooledbydemineralizedwaterthatentersthelowerportionofthecoreandboilsasitflowsupwardaroundthefuelrods.ThesteamleavingthecoreisdriedbysteamseparatorsanddryerslocatedintheupperportionoftheRPV.Thesteamisthendirectedtotheturbinethroughthemainsteamlines.Eachsteamlinehastwoisolationvalvesinseries,oneoneithersideoftheprimarycontainmentbarrier.1.2.4.3ReactorRecirculationSystemThereactorrecirculationsystemconsistsoftworecirculationpumploopsexternaltotheRPV.TheseloopsprovidethepipingpathforthedrivingflowofwatertotheRPVjetpumps.Eachexternalloopcontainsonehigh-capacitymotor-drivenrecirculationpump,twomotor-operatedmaintenancevalves,andonehydraulically-operatedflowcontrolvalve.Thevariablepositionhydraulicflowcontrolvalveoperatesinconjunctionwithalow-frequencymotorgenerator(MG)settocontrolreactorpowerlevelthroughtheeffectsofcoolantflowrateonmoderatorvoidcontent.ThejetpumpsareRPVinternals.Theyprovideacontinuousinternalcirculationpathforthemajorportionofthecorecoolantflow.Thejetpumpsarelocatedintheannularregionbetweenthecoreshroudandthevesselinnerwall.Anyrecirculationlinebreakstillallowscorefloodingtoapproximatelytwo-thirdsofthecoreheight,theleveloftheinletofthejetpumps.1.2.4.4ResidualHeatRemovalSystemTheRHRsystemisasystemofpumps,heatexchangers,andpipingthatfulfillsthefollowingfunctions:1.Removesdecayandsensibleheatduringandafterplantshutdown.USARRevision61.2-14April1994 NineMilePointUnit2FSARwatertemperature,purity,clarity,andlevel.Thisprocesspreventsthespentfuelfromoverheatingandthebuildupofexcessiveradioactivematerialsinthecoolingwater,therebyminimizingradiationlevels.Thesystemincludestwoheatexchangers,eachofwhichiscapableofremovingthefulldecayheatfromanormalrefuelingoffloadofspentfuel.Across-connectiontotheRHRsystemprovidesadditionalemergencybackupcoolingandcoolingduringafullcoreoffload.Chapter9givesfurtherdetailsofthefuelhandlingandstoragesystem.1.2.8PowerConversionSystemChapter10providesadetaileddiscussionofthefollowingequipmentsystems.1.2.8.1TurbineGeneratorTheturbineisa1,800-rpmtandem-compound,six-flow,single-stagereheatunitwithanelectrohydraulicgovernorcontrol.Theturbinegeneratorhasanemergencytripsystemforturbineoverspeed.Theoutputoftheturbinegeneratoris1,165,663kWeatturbineguaranteeconditionswith2.0inHgabsbackpressureand0percentmakeup.Thegeneratorisadirect-driven,three-phase,60-Hz,25,000-V,1,800-rpmhydrogeninner-cooled,synchronousgeneratorratedat1,348,400kVAat0.90powerfactor,0.58short-circuitratioatmaximumhydrogenpressureof75psig.1.2.8.2MainSteamSystemThemainsteamsystemdeliverssteamfromthenuclearboilersystemthroughfour26-/28-inODsteamlinestotheturbinegenerator,turbinebypassvalves,SJAEs,offgaspreheaters,steamsealevaporator,andradwastesteamreboiler.1.2.8.3MainCondenserThemaincondensermaintains2.0inHgabswhenoperatingatturbineguaranteeconditionswith67.97'Fcirculatingwaterinlettemperature.Thecondenserincludesprovisionsforacceptingsteambypassedaroundtheturbinegenerator.Deaerationofcondensateisaccomplishedinthecondenser.1.2.8.4MainCondenserAirRemovalSystemThemaincondenserairremovalsystem,usingairejectorsfornormaloperationandvacuumhoggingpumpsforstartup,evacuatesgasesfromthemainturbineandcondenserduringplantstartupandmaintainsthecondenseressentiallyfreeofgasesduringUSARRevision61.2-21April1994 NineMilePointUnit2FSARoperation.Thissystemhandlesallin-leakageofnoncondensablegasesthroughtheturbineseals,condensate,feedwater,andsteamsystems,andnoncondensablesthataregeneratedinthereactorbydisassociationofwater.1.2.8.5TurbineGlandSealingSystemTheturbineglandsealingsystemprovidesmildlyradioactive~steamtothesealsoftheturbinethrottlevalvestemglandsandtheturbineshaftglands.Thesealingsteamissuppliedbyacleansteamreboilerusingcondensate.Theunitauxiliaryboilerprovidesanauxiliarysteamsupplyforstartupandwhenreactorheatingsteamisnotavailable.Thesteampackingexhaustercollectsandcondensestheairandsteammixtureanddischargestheairandothernoncondensablestotheplantexhaustducttotheatmosphere,usingamotor-drivenexhauster.1.2.8.6SteamBypassSystemandPressureControlSystemAturbinebypasssystemisprovidedwhichpassessteamdirectlytothemaincondenserundercontrolofthepressureregulator.Steamisbypassedtothecondenserwheneverthereactorsteamingrateexceedstheloadpassedtotheturbinegenerator.Thecapacityoftheturbinebypasssystemis25percentoftheturbineratedsteamflow.Thepressureregulationsystemprovidesmainturbinecontrolvalveandbypassvalveflowdemandstomaintainanearly'onstantreactorpressureduringnormalplantoperation.Italsoprovidesdemandstotherecirculationsystemtoadjustpowerlevelsbychangingreactorrecirculationflowrates.1.2.8.7CirculatingWaterSystemThecirculatingwatersystem(CWS)providesthecondenserwithacontinuoussupplyofcoolingwater.TheCWSisapumpedclosedloopsystemutilizinganair-coolednatural-draftcoolingtowerasaheatsink.Sixone-sixthcapacitycirculatingwaterpumpsareprovidedtopumpcoolingwaterfromthecoolingtowerbasinthroughthemaincondenserandbacktothetopofthecoolingtower.MakeupwaterisprovidedfromLakeOntariobytheservicewatersystem.1.2.8.8CondensateandFeedwaterSystemsThecondensateandfeedwatersystemssupplycondensatefromthecondenserhotwelltotheRPV.Thecondensateispumpedbytwoofthethreecondensatepumpsthroughthefullflowcondensatedemineralizersystem,theintercoolerofthe.airejectors,andthesteampackingexhaustertothecondensateboosterpumps.Thecondensateboosterpumpspumptheflowthroughthreestringsconsistingoftwodraincoolersandfivestagesoflow-pressureheaterseach.Inaddition,threeheaterdrainpumpsprovideapproximatelyone-thirdofthefeedwaterflowrequirements.Thelastlow-pressureheatersdischargetothesuctionofthreeUSARRevision61.2-22April1994 TEDFLIE'INEMILEPOINTNUCLEARSTATION-gNIT2j,(((gl'A~'I~7NIAGARAUMOHAWK I1, NineMilePointUnit2FSARTABLEOFCONTENTSSectionTitleVolumeCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANT1.11.21.31.41.51.61.71.81.91.101.111.121'3CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesZdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedZnformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMZ)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2.12.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,45678CHAPTER33.13.23.33.4DESIGNOFSTRUCTURESiCOMPONENTSiEQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume3.53.6A.3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3.11Appendixes3ACHAPTER4MissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociatedWithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesignDesignofSeismicCategoryIStructuresMechanicalSystemsandComponents{SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTOR9,101010101012121212124.14.24.34.44.54.6Appendix4ACHAPTER5SummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMS121212121212125.15.25.35.4Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevisionOctober1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolumeCHAPTER6ENGINEEREDSAFETYFEATURES136.16.26.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER77.17.27.37.47.57.67.7Appendixes7A,CHAPTER88.1'.28.3.,Appendix8ACHAPTER9INSTRUMENTATZONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafety.FeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS151515161616161616161616,17179.19.29.39.49.5AppendixesCHAPTER109A,FuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEM17181920,212lg22232310.110'10.3SummaryDescriptionTurbineGeneratorMainSteamSupplySystem232324USARRevision7October1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume2411.111.211.311.411.5Appendix11ACHAPTER1212.112.212.312.412.5CHAPTER1313.113.213.313.413.513.6CHAPTER1414.114.2CHAPTER15RADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALtQQ)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurityXNITXALTESTPROGRAMSpeci.fi.cIncludedAnalysisSpecificIncludedAnalysisInformationToBeinPreliminarySafetyReport,(PSAR)InformationToBeinFinalSafetyReport.(FSAR)ACCIDENTANALXSISSourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems24242525252525252525262626262626262626262626~272715.015.115.2GeneralDecreaseinReactorCoolantTemperatureIncreaseinReactorPressure272727USARRevisioni.vApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume15.3~DecreaseinReactorCoolantSystemFlowRate15.4ReactivityandPowerDistributionAnomalies15.5IncreaseinReactorCoolantInventory15.6DecreaseinReactorCoolantInventory15.7RadioactiveReleaseFromSubsystemsorComponents15.8AnticipatedTransientswithoutScram(ATNS)Appendices15Athrough15HCHAPTER16TECHNICALSPECIFICATIONS2727272727272828CHAPTER1717.017.117.2CHAPTER18QUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEM282828282818.118.2APPENDIXAAPPENDIXBDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPCQATR1)ININEMILEPOZNTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE28282828USARRevision6April1994 0

NineMilePointUnit2FSARCHAPTER5REACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMSTABLEOFCONTENTSSection5.15.1.15.1.25.1.35.25.2.15.2.1.15.2.15.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.25.2.3.2.1.1.1.1.2.1.3.1.4.2.2.1.2.2.2.3.3.4.4.1.4'.4.3.5.6.7.8.9.105.2.3.2.45.2.3.15.2.3.25.2.3.2.15.2.3.2.25.2.3.2.3TitleSUMMARYDESCRIPTIONSchematicFlowDiagramPipingandInstrumentationDiagramElevationDrawingINTEGRITYOFREACTORCOOLANTPRESSUREBOUNDARYCompliancewithCodesandCodeCasesCompliancewith10CFR50,Section50.55aApplicableCode.CasesOverpressureProtectionDesignBasisSafetyDesignBasesPowerGenerationDesignBasesDiscussionSafety/ReliefValveCapacityDesignEvaluationMethodofAnalysisSystemDesignEvaluationofResultsPipingandInstrumentDiagramsEquipmentandComponentDescriptionDescriptionDesignParametersSafety/ReliefValveMountingofPressureReliefDevicesApplicableCodesandClassificationMaterialSpecificationProcessInstrumentationSystemReliabilityInspectionandTestingReactorCoolantPressureBoundaryMaterialsMaterialSpecificationsCompatibilitywithReactorCoolantPWRChemistryofReactorCoolantBWRChemistryofReactorCoolantCompatibilityofConstructionMaterialswithReactorCoolantCompatibilityofConstructionMaterialswithExternalInsulationandReactorCoolantPacae5.1-15.1-35.1-35.1-35.2-15.2-15.2-15.2-1'5.2-15.2-15.2-15.2-25.2-25.2-25.2-45.2-45.2-45.2-65.2-65.2-75.2-75'-105.2-105.2-115.2-125.2-125.2-125.2-125.2-125.2-155.2-155.2-165.2-165.2-165.2-205.2-21USARRevision65-iApril1994 NineMilePointUnit2FSAR*CHAPTER5TABLEOFCONTENTS(Contd.)Section5.2.3.35.2.3.3.15.2.3.3.25.2.3.3.35.2.3.3.45.2.3.45.2.3.4.15.2.3.4.25.2.45.2.4.15.2.4.25.2.4'.15.2.4.2.25.2.4.35.2.4.3.15.2.4.3.25.2.4.3.35.2.4.45.2.4.55.2.4.65.2.4.75.2.4.85.2.55.2.5.15.2.5.1.15.2.5.1.25.2.5.1.35.2.5.1.4TitleFabricationandProcessingofFerriticMaterialsFractureToughnessControlofWeldingNondestructiveExaminationofFerriticTubularProductsMoistureControlForLowHydrogenCoveredArcWeldingElectrodesFabricationandProcessingofAusteniticStainlessSteelsAvoidanceofStressCorrosionCrackingControlofWeldingIn-serviceInspectionandTestingofReactorCoolantPressureBoundarySystemBoundarySubjecttoInspectionProvisionsforAccesstotheReactorCoolantPressureBoundaryReactorPressureVesselPipe,Pumps,andValvesExaminationTechniquesandProceduresEquipmentfor1n-serviceInspectionCoordinationofInspectionEquipmentwithAccessProvisionsRecordingandComparingDataInspectionIntervalsIn-serviceInspectionProgramCategoriesandRequirementsEvaluationofExaminationResultsSystemLeakageandHydrostaticPressureTestsIn-serviceInspectionCommitmentRCPBandECCSLeakageDetectionSystemLeakageDetectionMethodsDetectionofLeakageWithinthePrimaryContainmentDetectionofLeakageExternaltothePrimaryContainment(WithinReactorBuilding)DetectionofLeakageExternaltothePrimaryContainmentIntersystemLeakageMonitoringPacae5.2-215.2-215.2-225.2-235.2-235.2-235.2-235.2-255.2-275.2-275.2-285.2-285.2-295.2-295.2-295.2-305.2-305.2-305.2-305.2-305.2-305.2-305.2-315.2-315.2-325.2-335.2-335.2-34USARRevisionApril1994 NineMilePointUnit2FSARCHAPTER5TABLEOFCONTENTS(Cont'd.)Section5.2.5.25.2.5.2.15.2.5.2.25.2.5.2.35.2.5.35.2.5.45.2.5.4.15.2.5.4.25.2.5.55.2.5.5.15.2.5.5.25.2.5.5.35.2.5.5.45.2;5.5.55.2.5.65.2.5.75.2.5.85.2.5.95.2.6TitleLeakDetectionInstrumentationandMonitoringLeakDetectionInstrumentationandMonitoringInsidePrimaryContainmentLeakDetectionInstrumentationandMonitoringExternaltoPrimaryContainmentSummaryIndicationinMainControlRoomLimitsforReactorCoolantLeakageLeakageRateLimitsIdentifiedLeakageInsidethePrimaryContainmentUnidentifiedLeakageInsidethePrimaryContainment.UnidentifiedLeakageRateSensitivityandResponseTimeLengthofThrough-WallFlawMarginsofSafetyCriteriatoEvaluatetheAdequacyandMarginoftheLeakDetectionSystemDifferentiationBetweenIdentifiedandUnidentifiedLeaksSafetyInterfacesTestingandCalibrationRegulatoryGuideComplianceReferencesPacae5.2-355.2-355.2-37-5.2-405.2-405.2-405.2-405.2-415.2-415.2-415.2-415.2-415.2-445.2-455.2-455.2-455.2-455.2-455.2-485'5.3.15.3.1.15.3.1.25.3.1.45.3.15.3.15.3.15.3.15.3.1.4.1.5.5.1.6.6.15.3.1.3REACTORVESSELReactorVesselMaterialsMaterialsSpecificationsSpecialProcessesUsedforManufacturingandFabricationSpecialMethodsforNondestructiveExaminationSpecialControlsforFerriticandAusteniticStainlessSteelsComplianceWithRegulatoryGuidesFractureToughnessCompliancewith10CFR50AppendixGMaterialSurveillanceCompliancewithReactorVesselMaterialSurveillanceProgramRequirements5.3-15.3-15.3-15.3-15.3-25.3-25.3-25.3-25.3-25.3-55'-5USARRevision65111April1994 NineMilePointUnit2FSARCHAPTER5TABLEOFCONTENTS(Cont'd.)Section5.3.1.6.25.3.1.6.35.3.1.6.45.3.1.6.55.3.2.1.35.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.5.3.2.1.42.1.52.233.13.1.13.1.23.1.33.1.43.23.33.43.53.63.745.45.4.15.4.1.15.4.1.25.4.1.35.4.1.45.4.1.55.4.25.4.35.4.45.4.4.15.4.4.25.3.1.75.3.25.3.2.15.3.2.1.15.3.2.1.2TitleNeutronFluxandFluenceCalculationsPredictedIrradiationEffectsonVesselBeltlineMaterialsPositioningofSurveillanceCapsulesandMethodsofAttachmentTimeandNumberofDosimetryMeasurementsReactorVesselFastenersPressure-TemperatureLimitsLimitCurvesTemperatureLimitsforBoltupTemperatureLimitsforPreoperationalSystemHydrostaticTestsandISIHydrostaticorLeakPressureTestsOperatingLimitsDuringHeatup,Cooldown,andCoreOperationReactorVesselAnnealingPredictedShiftinRT~~OperatingProceduresReactorVesselIntegrityDesignDescriptionSafetyDesi.gnBasi.sPowerGenerationDesignBasisReactorVesselDesignDataMaterialsofConstructionFabricationMethodsInspectionRequirementsShipmentandInstallationOperatingConditionsIn-serviceSurveillanceReferencesCOMPONENTANDSUBSYSTEMDESIGNReactorRecirculationSystemSafetyDesignBasesPowerGenerationDesignBasesDescriptionSafetyEvaluationInspectionandTestingSteamGenerators(PNR)ReactorCoolantPipingMainSteamLineFlowRestrictorsSafetyDesignBasesDescriptionPacae5.3-65.3-65.3-65.3-75.3-75.3-95.3-95.3-105.3-105.3-105.3-115.3-115.3-115.3-125.3-135.3-135.3-145.3-155.3-155.3-175.3-175.3-175.3-185.3-185.3-195.3-205.4-15.4-15.4-15.4-15.4-15.4-45.4-55.4-55.4-65.4-65.4-65.4-6USARRevisi.on5-ivApril1994 NineMilePointUnit2FSARCHAPTER5LISTOFFIGURESFigureNumberTitle5.3-2d5.3-2e5.3-35.3-45.3-55.4-1MINIMUMBELTLINEDOWNCOMERWATERTEMPERATUREFORPRESSURIZATIONDURINGCOREOPERATION(CORECRITICAL)HEATUPMINIMUMBELTLINEDOWNCOMERWATERTEMPERATUREFOR~PRESSURIZATIONDURXNGCOREOPERATION(CORECRITICAL)COOLDOWNCALCULATEDADJUSTMENTOFRT~qFORNINEMILEPOINTUNIT2LIMITINGBELTLZNEPLATEC3147REACTORVESSELNOMINALREACTORVESSELWATERLEVELTRIPANDALARMELEVATIONSETTINGSRECIRCULATZONSYSTEMELEVATZONANDISOMETRIC5.4-2athru5.4.2dREACTORRECZRCULATIONSYSTEMP&ID5.4-35.4-45.4-55.4-,65.4-75.4-8RECIRCULATIONPUMPHEAD,NPSH~FLOWANDEFFICIENCYCURVESOPERATINGPRINCIPLEOFJETPUMPCOREFLOODINGCAPABILITYOFRECIRCULATIONSYSTEMMAINSTEAMLINEFLOWRESTRICTORMAINSTEAMZSOLATIONVALVECUTAWAYVIEWDELETED5.4-9athruRCICSY'TEM5.4-9d5.4-10REACTORCOREISOLATIONCOOLANTSYSTEMPROCESSDIAGRAM5.4-10aRCICTURBINECHARACTERISTICCURVES-STEAMFLOWVS.POWER5.4-10bRCZCTURBINECHARACTERISTICCURVES-STEAMFLOWVS.PRESSUREUSARRevision65-ixApril1994 NineMilePointUnit2FSARCHAPTER5LISTOFFIGURES(Cont'd.)FigureNumberTitle5.4-115.4-125.4-13athru5.4-13g5.4-145.4-15VESSELCOOLANTTEMPERATUREVERSUSTIME(TWOHEATEXCHANGERSAVAILABLE)VESSELCOOLANTTEMPERATUREVERSUSTIME(ONEHEATEXCHANGERAVAILABLE)RESIDUALHEATREMOVALSYSTEMRESIDUALHEATREMOVALSYSTEMPROCESSDIAGRAMANDDATA(SHEETS1THROUGH3)RHRPUMPCHARACTERISTICCURVES5.4-16athzuREACTORWATERCLEANUPSYSTEMP&ID5.4-16f5.4-175.4-185.4-19REACTORWATERCLEANUPSYSTEM(SHEETS1THROUGH3)DELETEDFILTERDEMINERALIZERSYSTEMUSARRevision65-xApril1994 STEAMDRYERSe303)Q)MAINSTEAMFLOWTOTURBINEn<STEAMSEPARATORS04DRIVINGFLDFI~Q5MAINFEEDFLOW0oCOREJETPUMPFCVFCVRECIRCULATIONPUMPQ6Q7'I.COREINLET2.COREOUTLET3,SFPARATOROUTLET(STEAMDOME)4.STEAMLINE(2NDISOLATIONVALVE)5.FEEOWATERINLET(INCLUDESRWCURETURNFLOW)6.'RECIRCULATINGPUMPSUCTION7.RECIRCULATINGPUMPDISCHARGE'CHANNELBYPASS-NOMINALLY101(FPRESSURE(psial105610311020985104510251303FLOWI(b/hr)108.5x10108.5x1014.3x)014.3x1014.6xl035.7x'I035.7x10TEMPERATURE(oF)533548547543420533ENTHALPY(Btu/lb)527.5632.01191.61191.6398.0527.3528.5FIGURE5.1-1aRATEDOPERATINGCONDITIONSOFTHEBOILINGWATERREACTORNIAGARAMOHAWKPOWERCORPORATIONNINEMILEPOINT-UNIT2FINALSAFETYANALYSISREPORTAMENDMENT24FEBRUARY1986

NineMilePointUnit2FSAREditionuptoandincludingWinter1972Addenda.TheessentialASMErequirementswhichareallmetbythisanalysisarediscussedasfollows.Itisrecognizedthattheprotectionofvesselsinanuclearpowerplantisdependentuponmanyprotectivesystemstorelieveorterminatepressuretransients.Installationofpressure-relievingdevicesmaynotindependentlyprovidecompleteprotection.Thesafetyvalvesizingevaluationassumescreditforoperationofthescramprotectivesystemwhichmaybetrippedbyeitheroneoftwosources,i.e.,adirectorfluxtripsignal.ThedirectscramtripsignalisderivedfrompositionswitchesmountedontheMSIVs,ortheturbinestopvalves,orfrompressureswitchesmountedonthedumpvalveoftheturbinecontrolvalve(TCV)hydraulicactuationsystem.Thepositionswitchsettingsarelessthanorequalto85percent.fullyopenforMSIVsandlesstQanorequalto90percentfullyopenfortheturbinestopvalves.ThepressureswitchesareactuatedwhenafastclosureoftheTCVsisinitiated.Further,nocreditistakenforpoweroperationoftheSRVsinthereliefmode.Creditistakenforthedual-purposeSRVsinthesafetymode.TheratedcapacityoftheSRVsissufficienttopreventariseinpressurewithintheprotectedvesselofmorethan110percentofthedesignpressure(1.10x1,250psig=1,375psig)foreventsdefinedinChapter15andAppendixA.Fullaccountistakenofthepressuredroponboththeinletanddischargesidesofthevalves.AllSRVsdischargeintothesuppressionpoolthroughadischargepipefromeachvalvewhichisdesignedtoachievesonicflowconditionsthroughthevalve,thusprovidingflowindependencetodischargepipinglosses.AdditionalmeasurestocounteracttheeffectsofbackpressureintheSRVdischa'rgelinesarediscussedinSections5.2.2.2.3and5.2.2.4.1.ThemethoddescribedinReference5showsthatsonicflowisachievedthroughaSRVwiththefollowingdimensions:NozzleBoreValveDischargeDiameter(atoutletflange)ValveInletDiameter4.84in(d)-10in(d,)8in(basedonsweepolet)TheSRVsteamflowsfromthesteamline,alargereservoir,throughthesweepolet(samediameterasinletflange),intothevalvenozzle,andoutthroughtheoutletflange.Thenozzlehasashortflowlength,anditactsasastandardnozzleorventuritube.Valuesofcriticalpressureratio,rarefoundasafunctionofd/d,andkonpageA-21ofthereference.Thevalueofrtheratio'fdischargebackpressuregPggtoinletpressure,Pdecreasesasd/d~decreases.USARRevision65.2-3April1994 NineMilePointUnit2FSARThevalueof.d/d~isminimizedwhen'theoutletvalveflangediameterisusedasthevalueofd~.Inthiscase,.d,/d~=4.84/10=0.484.Thecriticalpressureforsonicflowoccurswherer=0.553(usingk=1.3forsteam)and,therefore,sonicflowoccurswhen<(0553)Pg(PggPgginpsia)SRVdischargelinesarerequiredtobedesignedandconfiguredsothatthedischargebackpressureatthevalveoutletisnotgreaterthan40percentoftheinletpressureusingpressuresmeasuredinpsig.Forabsolutepressure,thecorrespondinglimitislessthan41percentofinletacrosstherangeofoperatingconditions.Thislimitanddischargelinedesignensuresthatrwillnotbeexceeded.Therefore,sonicflowisensured.Table5.2-3liststhesystemsthatcouldinitiateduringthedesignbasisoverpressureevent.5.2.2.2DesignEvaluation5.2.2.2.1MethodofAnalysisThemodelusedtoanalyzeoverpressurizationisprovidedinSectionS.2.3ofGESTARII"'.5.2.2.2.2SystemDesignAparametricstudywasconductedtodeterminetherequiredsteamflowcapacityoftheSRVsbasedonthefollowingassumptions.Cycle-specificinformationiscoveredinAppendixA,SectionA.5.2.2.2.2.Operationwithasinglerecirculationsystemloopinoperation,orwithoneMSIVoutofservice,hasalsobeenevaluated.SeeAppendices15Band15D,respectively.0eratinConditionsTheoperatingconditionsare:1.Operatingpower=3,466MWt(104.3percentofnuclearboilerratedpower).2.Vesseldomepressure=1,020psig.3.Steamflow=15.013x10'b/hr(105percentofnuclearboilerratedsteamflow).Theseconditionsarethemostseverebecausemaximumstoredenergyexistsattheseconditions.Atlowerpowerconditions,thetransientswouldbelesssevere.USARRevision65.2-4April1994 NineMilePointUnit2FSARA,transientanalysisstudyhasbeenperformedforatypicalBWRtoinvestigatetheeffectsofincreasingtheinitialreactorpressureonthepeaktransientvesselpressure.Twomodels,onefromtheREDYandonefromtheODYNcodes,wereusedinthestudy.ThemodelintheREDYcodeismoreconservativethanthatintheODYNcode.Theconclusion,evenforthemoreconservativemodel,wasthatincreasingtheinitialoperatingpressureuptothehigh-pressurescramsetpoint(analyticalupperlimitof1,071psig)resultsinanincreaseofthepeaksystempressureoflessthanhalftheinitialpressureincreasefortheoverpressuredesigntransient(i.e.,allMSIVclosurewithindirecthighneutronfluxscram).ThesamegeneraltrendisexpectedtoexistforNineMi'lePointNuclearStation-Unit2(Unit2).Sincethereisasignificantmargin(107psibycomparingthepeakvesselpressureof1,268psigwiththeASMECodelimitof1,375psig)forUnit2,nosafetyconcernwouldresultfromtheabove-assumedinitialdomepressure.TransientsTheoverpressureprotectionsystemmustaccommodatethemostseverepressurizationeventdescribedinSectionS.3ofGESTARII"'.Table5.2-4liststhesequenceofeventsforthisworst-casetransient,theMSIVclosurewithfluxscram,basedontheinstalledSRVcapacity.SafetReliefValveTransientAnalsisSecification1.Valvegroups:Spring-actionsafetymode-5groups2.Springpressuresetpoint(maximumsafetylimit)andnumberofvalvespergroup:Group1:Group2:Group3:Group4:Group5:1/1771,1871,1971,2071/217psigpsigpsigpsst.gpsig2SRVs4SRVs4SRVs4SRVs4SRVsThesetpointsareassumedat.aconservatively-highlevelabovethenominalsetpoints.Thisistoaccountforinitialsetpointerrorsandanyinstrumentsetpointdriftthatmightoccurduringoperation.Typically,theassumedsetpointsintheanalySisare1to2percentabovetheactualnominalsetpoints.ConservativeSRVresponsecharacteristicsarealsoassumed.SafetReliefValveCaacitSizingoftheSRVcapacityisbasedonestablishinganadequatemarginfromthepeakvesselpressuretothevesselcodelimit(1,375ps'ig)inresponsetothereferencetransients.Reference7providessufficientinformationanddocumentationtoshowcompliancewithallrequirementsofArticleNB-7000oftheUSARRevision65.2-5April1994 NineMilePointUnit2FSARASMEBoilerandPressureVesselCode,SectionIII,NuclearPowerPlantComponents,Division1,1971Edition,withAddendatoandincludingWinter1972,intheareaofoverpressureprotectiondesignoftheUnit2nuclearpressurevesselandotherRCPBcomponents.Theeffectsofvalve-capacityonthepressuretransientsareshownalso.Theoverpressureprotectionanalysisalsoincludesthesimulationofanticipatedtransientwithoutscram(ATWS)recirculationpumptrip(RPT)onhighreactorpressure.5.2.2.2.3EvaluationofResultsSafetReliefValveCaacitTherequiredSRVcapacityisdeterminedbyanalyzingthepressurerisefromaMSIVclosurewithfluxscramtransientasdocumentedinSectionS.3ofGESTARII.ResultsofthisanalysisareshownonFigure5.2-1.PressureDroinInletandDischarePressuredroponthepipingfromthereactorvesseltothevalvesistakenintoaccountincalculatingthemaximumvesselpressures.PressuredropinthedischargepipingtothesuppressionpoolislimitedbyproperdischargelinesizingtopreventbackpressureoneachSRVfromexceeding40percentofthevalveinletpressure,thusassuringchokedflowinthevalveorificeandnoreductionofvalvecapacityduetothedischarge.piping.EachSRVhasitsownseparatedischargeline.Cycle-specificevaluationiscoveredinAppendixA,SectionA.5.2.2.2.3.5.2.2.3PipingandInstrumentDiagramsFigures5.2-2and10.1-3showtheschematiclocationofpressure-relievingdevicesfor:1.Reactorcoolantsystem.2.Primarysideoftheauxiliaryoremergencysystemsinterconnectedwiththeprimarysystem.3.Anyblowdownorheatdissipationsystemconnectedtothedischargesideofthepressure-relievingdevices.TheschematicarrangementsoftheSRVsareshownonFigures5.2-2and5.2-3.USARRevision65.2-6April1994 NineMilePointUnit2FSAR3.IncludedwiththeSRVisaninstructionmanualprovidedto'hecustomer.Withinthismanualwillberecommendedperiodicmaintenanceprogramsasrecommendedbythemanufacturerbaseduponhisexperience.AllSRVswillbesubjecttothefollowingtestsandinspectionsinaccordancewithanapprovedprogram:Duringeveryrefuelingoutage,,atleast50percentoftheinstalledvalveswillbetestedforverificationofset-pressuresopeningandclosingusingthepneumaticpoweractuator,testingofallb'oltedclosures,andtestingofpneumaticactuatorleakage.Aftertheprecedingtesting,thevalveswillundergopreventativemaintenanceinaccordancewithanapprovedprocedure.Alldisassembledvalveswillbeinspectedforwear,damage,anderosion.Allgaskets,seals,andpartswillbereplacedasneededinaccordancewithinspectionresults.Valveswillberelapped,asrequired,andlubricated.Alldisassembledvalveswillberetested,andappropriateadjustmentswillbemadepriortouse.ItisnotfeasibletotesttheSRVsetpointswhilethevalvesareinplace.Thevalvesaremountedon1,500-lbprimaryserviceratingflanges.Theycanberemovedformaintenanceorbenchchecksandreinstalledduringnormalplantshutdowns.Thevalveswillbetestedtocheckset-pressureinaccordancewiththerequirementsoftheplantTechnicalSpecifications.Allvalvestestedwillberesetto+1percentofthesafetyset-pressureslistedintheTechnicalSpecifications.Avalueof+3percentofthesafetyset-pressurewillbeusedtodetermineanincreaseinthetestsamplesizeasspecifiedinthecodeadoptedbythein-serviceinspection/in-servicetesting(ISI/IST)program.TheexternalsurfaceandseatingofallSRVsare100-percentvisuallyinspectedwhenthevalvesareremovedformaintenanceorbenchchecks.ValveoperabilityisverifiedduringthepreoperationaltestprogramasdiscussedinChapter14.AdiscussionofSRVoperabilitytestingfortwo-phaseflow,inaccordancewithNUREG-0737,isprovidedinSection1.10,TaskII.D.l.5.2.3ReactorCoolantPressureBoundaryMaterials5.2.3.1MaterialSpecificationsTable5.2-5liststheprincipalpressure-retainingcomponentsandmaterialsandtheappropriatematerialspecificationsfortheRCPBcomponents.USARRevision65.2-15April1994 NineMilePointUnit2FSAR5.2.3.2CompatibilitywithReactorCoolant5.2.3.2.1PWRChemistryofReactorCoolantNotapplicabletoboilingwaterreactors(BWRs).5.2.3.2.2BWRChemistryofReactorCoolantMaterialsintheRCSareprimarilyausteniticstainlesssteel,carbonsteel,andZircaloycladding.Thereactorwaterchemistrylimitsareestablishedtoprovideanenvironmentfavorabletothesematerials.Limitsareplacedonconductivityandchlorideconcentrations.Conductivityislimitedbecauseitcanbecontinuouslyandreliablymeasuredaridgivesanindicationofabnormalconditionsandthepresenceofunusualmaterialsinthecoolant.Chloridelimitsarespecifiedtopreventstresscorrosioncrackingofstainlesssteel.ThewaterqualityrecpxirementsaresupportedbyGeneralElectricCompany(GE)stresscorrosiontestdatasummarizedasfollows:Type304stainlesssteelspecimenswereexposedinaflowingloopoperatingat537'F.Thewatercontained1.5ppmchlorideand1.2ppmoxygenatapHof7.Testspecimenswerebentbeamstripsstressedovertheiryieldstrength.After2,100-hrexposure,nocrackingorfailuresoccurred.2.WeldedType304stainl'esssteelspecimenswereexposedinarefreshedautoclaveoperatingat550'F.Thewatercontained0.5ppmchlorideand1.5ppmoxygenatapHof7.Uniaxialtensiletestspecimenswerestressedat125percentoftheir550'Fyieldstrength.Nocrackingorfailuresoccurredat15,000-hrexposure.Whenconductivityisinitsnormalrange,pH,chloride,andotherimpuritiesaffectingconductivityarealso,withintheirnormalrange'.Whenconductivitybecomesabnormal,chloridemeasurementsaremadetodeterminewhethertheyarealsooutoftheirnormaloperatingvalues.Conductivitymaybehighduetothepresenceofaneutralsaltwhichdoesnot.haveaneffectonpHorchloride.Insuchacase,highconductivityaloneisnotacauseforshutdown.Insometypesofwater-cooledreactors,conductivitiesarehighbecauseofthepurposefuluseofadditives.InBWRs,however,wherenoadditivesareusedandwherenear-neutralpHismaintained,conductivityprovidesagoodandpromptmeasureofthequalityofthereactorwater.SignificantchangesinconductivityprovidetheOperatorwithawarningmechanismsohecaninvestigateandremedytheconditionbeforereactorwaterlimitsarereached.MethodsavailabletotheOperatorforcorrectingtheout-of-specificationconditionincludeoperationoftheRWCUsystemorplacingthereactorinthecoldshutdowncondition.Themajorbenefitofcoldshutdownistoreducethetemperature-dependentcorrosionratesandUSARRevision65.2-16April1994 NineMilePointUnit2FSARConservative.corrosionallowancesareprovidedforall.exposedsurfacesofcarbonandlow-alloysteels.Contaminantsinthereactorcoolantarecontrolledtoverylowlimitsbythereactorwaterqualityspecifications.Nodetrimentaleffectswilloccurtoanyofthematerialsfromallowablecontaminantlevelsinthehigh-purityreactorcoolant.ExpectedradiolyticproductsintheBWRcoolanthavenoadverseeffectsontheconstructionmaterials.5.2.3.2.4CompatibilityofConstructionMaterialswithExternalInsulationandReactorCoolantConstructionmaterialsexposedtoexternalinsulationare:Solution-annealedausteniticstainlesssteels.Types304,304Lwith0.035-percentmaximumofcarboncontent,316and316Kwith0.02-percentweightmaximumofcarboncontent.2.Carbonandlow-alloysteel.TwotypesofexternalinsulationareemployedonBWRs.Stainlesssteelreflectivemetalinsulationuseddoesnotcontributetoanysurfacecontaminationandhasnoeffectonconstructionmaterials.Similarly,thefibrous(nonmetallic)insulationisencapsulatedinmetalsheetingwhichpreventsdirectcontactwiththeRCSmaterials.Inaddition,thefibrousinsulationusedisassessedtomeettherequirementsofRG1.36,andhastheproperratiosofleachablesodiumandsilicateionstochlorideandfluorideions.SincetherearenoadditivesintheBWRcoolant,leakagewouldexposematerialstohigh-purity,demineralizedwater.Exposuretodemineralizedwaterwouldcausenodetrimentaleffects.5.2.3.3FabricationandProcessingofFerriticMaterials5.2.3.3.1FractureToughnessMaterialsintheRCPB,otherthantheRPV,arerequiredby10CFR50.55aandAppendixGtomeetthefracturetoughnessrequirementsofASMESectionIII,NB-2300.Thesefracturetoughnessrequirementsforferriticpiping,valve,bolting,andpumpmaterialsaremetasfollows:PipingandweldfillermaterialsareinaccordancewithASMESectionIII,NB-2300,1974Edition;fieldweldfillermaterialsareto1974Edition.2.ValvesareinaccordancewithASMEIII,NB-2300'sfollows:USARRevision65.2-21April1994 NineMilePointUnit2FSARa..Motor-operatedvalves(MOVs),Winter1975,exceptasnotedinAppendix5A,1971EditionandWinter1973Addenda.b.MSIVs,Summer1977.c.CarbonSteelManualValves,Winter1973.3.Materialsforboltswithdiametersexceeding1inmeetthe25-millateralexpansionrequirementofASMESectionIII,NB-2300,ofthesamecodedateas-theassociatedequipment.Inaddition,boltinggreaterthan1inisrequiredtomeet.aminimumof45ft-lbabsorbedenergy.4.TherearenoferriticpumpsintheRCPB.ThefracturetoughnesspropertiesoftheRPVarediscussedinSection5.3.1andAppendix5A.5.2.3.3.2ControlofWeldingControlofPreheatTemeratureEmloedforWeldinofLow-AlloSteelRelatorGuide1.50RG1.50delineatespreheattemperaturecontrolrequirementsandweldingprocedurequalificationssupplementingthoseinASMESectionsIIIandIX.Theuseoflow-alloysteelisrestrictedtotheRPV.OtherferriticcomponentsintheRCPBarefabricatedfromcarbonsteelmaterials.Preheattemperaturesemployedforweldingoflow-alloysteelmeetorexceedtherecommendationsofASMESectionIII,AppendixD.Componentswereeitherheldforanextendedtimeatpreheat.temperaturetoassureremovalofhydrogen,orpreheatwasmaintaineduntilpostweldheattreatment'.Theminimumpreheatandmaximuminterpasstemperatureswerespecifiedandmonitored.ControlofElectroslaWeldProertiesRelatorGuide1.34NoelectroslagweldingwasperformedonRCPBcomponents.WelderuglificationforAreasofLimitedAccessibilitRelatorGuide1.71QualificationforareasoflimitedaccessibilityisdiscussedinSection5.2.3.4.2.USARRevision65.2-22April1994 NineMilePointUnit2FSARThesesatisfy.positionc.8.PlantTechnicalSpecificationscomplywithpositionc.9byspecifyinglimitingconditionsforidentifiedandunidentifiedleakageandbyaddressingtheavailabilityofvarioustypesofinstrumentstoassureadequatecoverage.RelatorGuide1.22AssessmentTheproperoperationoftheLDSsensorsandlogicisverifiedduringthepreoperationaltestsandduringplantoperation.Eachtemperatureswitch(bothambientanddifferentialtypes)thatprovidesisolationsignalsisconnectedtooneelementofadualthermocouple.Alightilluminateswhenthetemperatureexceedsthesetpoint.Verificationofthethermocoupleinputisaccomplishedbycomparingthereadingfromthetripchannelwiththerecorderchannelwhichisconnectedtotheotherelementofthedualthermocouple.ThetriplogicsaretestedbyapplyingasimulatedtripsignalfromanexternalsourcetotheLDSchannel.Keylocktestswitchesareusedtopreventtheisolationsignalfromperformingitsisolatingfunction.USARRevision65.2-47April1994 NineMilePointUnit2FSAR5.2.6References2.3.4.5.7.GeneralElectricStandardApplication.forReactorFuel-UnitedStatesSupplement,NEDE-24011-P-A-US,(latestapprovedrevision).Skarpelos,J.M.andBagg,J.W.ChlorideContxolinBWRCoolants,NEDO-10899,June1973.GEAP-5620,FailureBehaviorinASTMA106BPipesContainingAxialThrough-WallFlaws,byM.B.Reynolds,April1968.InvestigationandEvaluationofCrackinginAusteniticStainlessSteelPipingofBoilingWaterReactorPlants,NUREG-76/067,NRC/PCSG,October1975.CraneTechnicalPaperNo.410,1974Edition.PressureRelievingDeviceCertifications,NationalBoardofBoilerandPressureVesselInspectors,1979Edition.GeneralElectricDesignReport22A7122,OverpressureProtectionReport,Revision2.USARRevision65.2-48April1994 NineMilePointUnit2FSARTABLE5.2-2NUCLEARSYSTEMSAFETY/RELIEFSETPOINTS*No.ofValvesSpringSetPressureSiASMERatedCapacity8103%SpringSetPressurelbhreachPressureSetpointforPower-ActuatedModeSi1,1481,1751,1851,1951,205882,000902,000910,000'17,000925,0001,0761,0861,0961,1061,116NOTE:SevenoftheSRVsareusedfortheautomaticdepressurizationfunction.*Cycle-specificvaluesarecoveredinAppendixA,TableA.5.2-1.USARRevision61of1April1994

NineMilePointUnit2FSARTABLE5.2-3ISYSTEMSTH'ATMAYINITIATEDURINGOVERPRESSUREEVENTCycle-specificinformationiscoveredinAppendixATableA.5.2-2~SstemInitiatinTriSinalsReactortripswithhighflux~SetointRCICONwithreactorlowwaterlevel>L2OFFwithreactorhighwaterlevel<L8HPCSONwithreactorlowwaterlevelONwithhighdrywellpressureOFFwithreactorhighwaterlevel>L2<2psig<L8RecirculationOFFwithreactorlowwaterlevel<L2RWCUOFFwithreactorhighpressureOFFwithreactorlowwaterlevel>1050psig<L2USARRevision61of1April1994

NineMilePointUnit2FSARTABLE5.2-4SEQUENCEOFEVENTSFORFIGURE5.2-1Cycle-specificvaluesarecoveredi;nAppend'ixA.,TableA.5.2-3Time~secEventClosureofallMSIVswasinitiated.0.3MSIVsreached85%open.Failureofdirectpositionscramwasassumed.1.7NeutronfluxreachedAPRMfluxsetpointandinitiatedreactorscram.2.29Sensedreactordomepressure'reachedsetpointofrecirculationpumptrip.2.35Recirculationpump/motorinitiatedtocoastdown.2.7SteamlinepressurereachedGroup1SRVspressuresetpoint(spring-actionsafetymode),whilepower-actuatedreliefmodewasignored.(SeeSection5.2.2.2.2.)3.33.68SRVsallopenedduetohighpressure.Vesselbottompressurereacheditspeakvalue.USARRevision61of1April1994

OI-100CC0I-z501NEUTRONFLUX2PEAKFUELCENTERTEMP3AVESURFACEHEATFLUX4FEEDWATERFLOW5VESSELSTEAMFLOW2001VESSELPRESRISElpsi)2STMLINEPRESRISElpsi)3SAFETYVALVEFLOWlo)4RELIEFVALVEFLOWlo)5BYPASSVALVEFLOWlo)6TURBINESTEAMFLOWlI)TIME)sec)1046TIME)sec)10221IILEVELlinchrefcepokirt)2WRSENSEDLEVELlinchesi3NRSENSEDLEVELlinches)4COREINLETFLOWlo)5DRIVEFLOWIlo)ErrI-0IVrllL1VOIDREACTIVITY2DOPPLERREACTIVITY3SCRAMREACTIVITY4TOTALREACTIVITY-100046TIMElsec)1023TIMElsec)FIGURf52-1SAFETYRELIEFVALVECAPACITYSIZINGTRANSIENT"MSIVCLOSUREWITHHIGHFLUXTRIP"NOTE:Forcycle-specificresultsseeAppendixA,FigureA.5.2-1.NIAGARAMOHAWKPOWERCORPORATIONNINEMILEPOINT-UNIT2UPDATEDSAFETYANALYSISREPORTUSARREVISION3OCTOBER1991

PBTEDNLxYIKTVNINEMILKPOITNUCLEARSTATIONUNIT'2y7NIAGARAUMOiAWKVOL.17

\I,i NineMilePointUnit2FSARTABLEOFCONTENTSSectionCHAPTER1TitleINTRODUCTZONANDGENERALDESCRIPTIONOFPLANTVolume1.11.21.31.41.51.61.71.81.91.101.111.12CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractorsRequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformationConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2.12.22.32.42.5Appendix2AAppendix2BAppendixes2Cthrough2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andGeotechnicalEngineering3,45678CHAPTER33.13.23.33.4DESIGNOFSTRUCTURESgCOMPONENTS~EQUIPMENT,ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionApril1994 NineMilePointUnit,2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume3.53.6A3.6B3.7A3.7B3.83.9A3.9B3.10A3.10B3.11AppendixesCHAPTER4MissileProtectionProtectionAgainstEffectsAssociatedWiththePostulatedRuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociatedWithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesignDesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWECScopeofSupply)MechanicalSystemsandComponents(GEScopeof'upply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipmentthrough3EREACTOR9,101010101012121212124.14.24.34.44.54.6Appendix4ACHAPTER5SummaryDescriptionFuelSystemDesignNuclearDesignThermal-Hydrauli.cDesi.gnReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTSYSTEMANDCONNECTEDSYSTEMS121212121212125.15.25.35.4Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevisionOctober1994 NineMilePointUnit2FSAR'ection'ITABLEOFCONTENTS(Cont'd.)TitleVolumeCHAPTER6ENGINEEREDSAFETYFEATURES136.16.26.36.46.56.6Appendixes6Athrough6DEngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Components13141515151515CHAPTER7INSTRUMENTATIONANDCONTROLSYSTEMS157.17.27.37.47.57.67.7Appendixes7A,CHAPTER8IntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWER15151516161616168.18.28.3Appendix8ACHAPTER9IntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMS161616,1717179.19.29.39.49.5Appendixes9A,CHAPTER10FuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEM17181920,2121,22232310.110.210.3SummaryDescriptionTurbineGeneratorMainSteamSupplySystem232324USARRevision7October1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)Section10.4CHAPTER11TitleOtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTVolume2411.111.211.311.411.5Appendix11ACHAPTER1212.112.212.312.412.5CHAPTER1313.113.213.'313.413.5,13.6CHAPTER1414.114.2CHAPTER15RADIATIONPROTECTIONEnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurityINITIALTESTPROGRAMSpecificIncludedAnalysisSpecificIncludedAnalysisInformationToBeinPreliminarySafetyReport.(PSAR)InformationToBeinFinalSafetyReport(FSAR)ACCIDENTANALYSISSourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems24242525252525252525262626262626262626262626,272715.015.115.2GeneralDecreaseinReactorCoolantTemperatureIncreaseinReactorPressure272727USARRevisionivApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)'ectionTitleVolume15.315.415.515.615.715.8AppendicesCHAPTER16CHAPTER1717.017.117.2CHAPTER18DecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistributionAnomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientswithoutScram(ATWS)15Athrough15HTECHNICALSPECZFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEM27272727.27272828282828282818.118.2APPENDIXAAPPENDIXBDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1)~NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE28282828USARRevision6April1994

MineHklePointUnit2FSARTABLE8.3-1(Cont'd.)PowerSource:2EJSsUS1DesignBasksAccidentDieselGeneratorLoadingPossibilitiesNonaccidentLoadingSimultaneousLOOP4LOCALOOPWithDelayedLOCALOCAWithDelayedDQPIDOPWithUnitTripEquipIDDesc.RatingUnitsVoltsPhaseSTPFRUHPFSTKW1STKVR1STTIMEIRUHKM1RUNKVR1STKW2STKVR2STTIHE2RUNKM2RUHKVR2STKM3STKVR3STTIME3RUNKM3RUHKVR3STKM4STKVR4STTIHE4RUHKW4RUHKVR42EJSsX1A2EJSsX1B2HCSsPHL22A2HVKsCHL1ALoadCenterXfrmrLoadCenterXfrnrHydrogenReconbControlBldg.Chiller1A1500.KVA1500.120.KM180.KM-0-3-0-3575.3575.30.20.850.20.850.350.853600.18000.3600.18000.120.0.378.1012.T0T0T>2.5HrHanT3019.0.19.0.120.0.153.95.4360018000.3600.18000.120.0,378.1012.T0T0T>2.5HrManT3019019.0.120.0.153.95.43600.8000.3600.8000120.0378.1012.Tw0T0T>2.5HrManT~3019.0.19.0~120.0.153.95.43600.8000.36008000.0.0.378.1012T0T0HotReq'dT3019.0.19.0.00.153.95.42HVRsUC413AReactorBldg.UnitCoolerA150.HP575.30.350.85315.843.T25127.579.5315.843.T25127.579.5315.843.T25127.5315.79.5843.T25127.579.52LAR-PHL200LightingPanel200.60030.20.90.0.Mote10.0.-00Mote1-0-000-Mote1-0-04802400.T0180.87.1USARRevision53of32October1993

NineNilePointUnit2PSARTABLE8.3-1(Cont'd.)TotalLoadOn:2EJS~US1SimultaneousLOOP4LOCADesignBasisAccidentDieselGeneratorLoadingPossibilitiesIOOPWithDelayedLOCALOCAWithDelayedLOOPNonaccidentLoadingLOOPWithUnitTripStartingKMKYAR720036000315843693185537810121200RunningKMKYAR38038038016579318175318175438115TimeSpan0<T<0.1sec0.1<-T<25sec25<T<30sec30<T<31sec31<T<36sec36<-T<9000sec9000<T<9006sec9006sec<TStartingKMKVAR720036000315843693185531810121200RunningKMKYAR38038038016519318175318175438175TimeSpan0<T<0.1sec0.1<-T<25sec25<T<30sec30<T<31sec31<T<36sec36<-T<9000sec9000<T<9006sec9006sec<TStartingKMKVAR72003600031584369318553781012001200RunningKWKVAR38038038016579318115318175438175TimeSpan0<T<0.1sec0.1<T<25sec25<T<30sec30<-T<31sec31<~T<36sec36<T<9000sec9000<MT<9006sec9006sec<TStartingKWKYAR76803840031584369318553781012RunningKWKVAR2188721887'1887346167499262TimeSpan0<T<0.1sec01<T<25sec25<~T<30sec30<T<31sec31<T<36sec36sec<~TUSARRevision54of32October1993 0

tlineHilePointUnit2FSARTABLE8.3-1(Cont'd.)PowerSource:2EHSaHCC103DesignBasisAccidentDieselGeneratorLoadingPossibilitiesNonaccldentLoadingSimultaneousLOOP4LOCALOOPWithDelayedLOCALOCAWithDelayedLOOPLOOPWithUnitTripEquipIDDesc.RatingUnitsVoltaPhaseSTPFRVNPFSTKWISTKVR1STTIMEIRUNKMIRVNKVR1STKW2STKVR2STTIME2RUtlKM2RVNKVR2STKW3STKVR3STTIME3RUtiKW3RUNKVR3STKM4STKVR4STTIHE4RUtIYW4RUtlKVR42RHSaHOV113ShutdownCoolingSupplyOutboardZsolat.19.2HP575.30.60.85115.2153.6T032.6420.35115.2153.6T032.6420.35115.2153.6T>>032.6420.35115.2153.6T>>>10min(HAN)32.6420.352RHSaHOV12A2RHSiHOV1422RHSaNOVISA2RHSaHOVIA2RHSaHOV22A2RHSaHOV23A2RHSaHOV24A2RHSaHOV25A2RHSiHOV26AHeatSxchgrAtoReactorHestExchgrBtoLMSCont.SprayASupp.PooltoRHRPumpASteamCondtoExchgrASteamCond.toExchgrALPCZInletACont.SprayAHeatExchgrAVentToSuppPool0.1HP0.33IIP2.6HP1.6HP1.6HP1.6HP6.6HP2.6HP0.13HP575.3575.3575.3575.3515.3575.3575.3575.3575.30.60.850.60.850.60.850.60.850.60.850.60.850.60.850.60.850.60.854.25.62~2.615.620.89.612.89.612.89.612.839.652.815.620.80.781.T>10min(HAN)T0T>10min(MAN)T>10min(MAN)T0T>>0T0T>>0T>10min(HAN)1.20.140.560.354.42.162.71.72.71.72.71.7'11.227.4.42.I60.220.144.25.62.2.615.620.89.612.89.612.89.612.839.652.815.620.80.78l.T>10min(MAN)T0T>>>10min(NQI)T>10min(NQI)T0T0T0T0T>10min(HAN)1.20,140.560.35442762.71.72.71.72.71.711.227~4.42.760.220.144.25.62.2.615.620.89.612.89.612.89.612.839.652.815.620.80.18l.T>>>10min(HAN)T0T>10min(HA)I)T>10min(WQI)T0T0T>>0T0T>10min(MIQI)1.20.740.560.354.42.762.71.72.71.72.71.711.227~4.42.'160.220.144.25.62~2.6-15.620.89.612.89.612.89.612.80.0.0.0.0.78l.T>10min(NQI)T>>>10min(NQI)T>10min(WQI)T>10min(WQI)T>10min(NQI)T>10min(HA)I)tlotReq'dNotReq'dT>10min(NQI)1.20740.560.354.42.762~7I72.11.72.71.7-0--0--0--00.220.14USARRevision517of32October1943

'I IIineWilePointUnit2FSARerTABLK8.3-1(Cont~d)TotalLoadOn:2EIIS'HCC103SimultaneousLOOPCLOCADesignBasisAccidentDieselGeneratorLoadingPossibilitiesLOOPWithDelayedLOCALOCAWithDelayedLOOPNonaccidentLoadingLOOPWithUnitTripStartingKWKYARRunningKWKYARTimeSpanStartingKWKYARRunningKWKYARTimeSpanStartingKWKVARRunningKWKVARTimeSpanStartingKWKYARRunningKWKVARTimeSpan792168111150076105281175280174283176199123199123221137202125000<T<6sec6<T<9sec9<T<15sec15<T<120sec120<T<600sec600<T<606sec606<T<720sec720sec<T7921681111576105281175280174283.1761991231991232211372021250<T<6sec6<T<9sec9<T<15sec15<T<120sec120<T<600sec600<T<606sec606<T<720sec720sec<T79216811115761052811752801742831761991991991992211372021250<T<6sec6<~T<9sec9<-T<15sec15<T<120sec120<T<600sec600<T<606sec606<T<720sec720sec<T51513113044082021251911181911182771732001242001242011252001240<~T<6sec6<T<120sec120<"T<600sec600<T<606sec606<T<720sec720<T<1800sec1800<T<1806sec1806<T<1920sec1920sec<TUSARRevision520of32Octohr1903

NineNilePointUnit2FSARTABLE8.3-2(Cont'd.)PoserSource:2EHSsHCC303DesignBasisAccidentGeneratorLoadingPossibilitiesNonaccidentLoadingSimultaneousLOOPcLOCALOOPMlthDelayedLOCALOCAMlthDelayedLOOPLOOPMlthUnitTripEquipID2RHSs)%V115DescSMInQac'ttoReactorRatlngUnits1.6HPVoltsPhase515.3STPFRUlfPF0.60.85STKMlSTKVR10.0.STTIHE1ffotReq'dRUNKM1RUNKVR10.0.STKM2STKVR20.0.STTIHE2NotReq'dRUflKW2RUffKVRC00.STKM3STKVR30.0.STTI)fE3NotReq'dRUNKM3RUNKVR30.0STKM4STKVR400STTIHE4NotReq'RUNKM4RUNKVR40.0.2RHSsHOV1162RHSi)NV12BSMInject.toReactorHeatExchgrBtoReactor1.6HP0.7HP515.3515.30.60.850.60.850.0.~.25.6NotReq'dT>10min(fUQf)0.0.1.207400.4.25.6NotReq'dT>10min(f(AN)0.0.1.20.740.0.4.25.6NotReq'dT>10min(HAN)0..0.1.20740.0.4.25.6NotReq'dT>10min(HAN)001.20742RHSif(OV1492RHS~f4OV15B2RHSiHOV1$HeatExchgrBtoLMSCont.SprayBSupp.PooltoRHRPumpB0.33HP2.6IIP4.HP515.3515.3575.30.60.850.60.850.60.852.2~115.620.824.32.T0T>10min(HAlf)T>10min(MAf>>0560354.422.746.84.22.2.115.620.824.32.T0T>10minwu>>T>>>10min(MAN)0.560.354.422.746.84.22.2715.620.824.32T>>0T>10min(f(AN)T>10min(NQi)~0.560+35,4.422.746.84.22.2.7-0-0-2432.T>10mi,n(f(AN)NotReq'dT>>>10min(HAff)0560.350--06.8422RHSi)KfVICSupp.PooltoRHRPumpC1.6HP575.30.60F8500.NotReq'd00.0.0.NotReq'd0.000lfotReq'd0.000NotReq'd0.0.2RHSi)NV22BSteamCond.toExchgrB1.6HP515.30.60.859.612.8T02.721.6996128T02.721.699.612.8T02.721.699.6128T>10min(MAN)2.721.692RHS~HOV23BSteamCond.toExchgrB1.6HP575.30.60.859.612.8T>>02.721699.612.8T02.729.61.6912.8T02.121.699.612.8T>10csin(HAN)2.121.692RHSsHOV24B2RHSsffOV24CLPCIInletBLPCIInletC6.6HP6.6HP515.3575.30.60.850.60.8539.652.839.652.8T0T>>011.226.9539.652.811.2239.66.9552.8T>>0T>>011.226.4539.652.811'239.66.9552.8T0T011.226.9511.226.95-0--0-NotReq'dReq'd0-0-0-0-USARRevision516of31Octob>>r1943

NineHilePointUnit2FSARTABLE8~3-2(Cont'd.)PowerSources2EHSatr;C303DesignSasisAccidentDieselGeneratorLoadingPossibilitiesNonsccldentLoadingSimultaneousLOOP4LOCALOOPWithDelayedLOCAIOCAWithDelayedLOOPLOOPWithUnitTripEquipID2RHSaHOV2582RHSaHOV26SDesc.Cont.Spray8HestExchngr8VenttoSupp.PoolRatingUnits2.6HP0.13HPVoltsPhase5753575.3STPFRUIIPF0.60850.60.85STKWISTKVRI15.620.80.781.STTIHEIT>10min(NQI)TH>10min(NQI)RUNKMIRUNKVRI4.42.70220.14STKM2STKVR215.620.80.781.STTIHE2T>10min(HAN)T>10min(HAtl)RUNKW2RUNKVR24.42.70.220.14STKW3STKVR315.620.80781.STTIHE3T>10min(HAN)T>10min(HAN)RUtIKW3RUNKVR3442l0.22014STKW4STKVR40.781.STTIHE4tiotReq'dT0RUNKW4RUNKVR4-0--00220.142IVISaHOV2782RHSaHOV282RHSa)K)V308HestExchngr8VenttoSupp,PoolReactortoRHRPump8RHRBRtntoSupp.Pool0.13HP0.83HP1.6HP575.3575.3575.30.60850.60.850.60.850.78I~00.9.612.8T>10min(NQI)NotReq'dT>10min(NQI)0.220.140.02.71.70.781.0.0.9.612.8T>10min(tUQI)NotReq'dTH>IOmin(HAN)0.220.1400.2.71.70.78I00.9.612.8T~>IOcain(HMI))IotReq'dT>10min(NQI)0.22014-0.027I70.78I5.6.64-0--0-T>10min(NQI)NotReq'd0.220.141.410.87-0-02RHSaHOV328HeatExchngr8toRCIC0.7HP575.30.60.854.25.6T01.20.744.25.6T01.20.74425.6T01.20.744.25.6T>10min(HAN)1.20.742RHSaHOV338Supp.PoolSprayHeader80.33HP575.30.60852.27T00.560.3522~7T00.560.352.2.7T00.560.35NotReq'd0--0-2RHSaHOV378RHRLine8toSuppPool0.33HP57530.60.852.270.560.352.2.7T00.560.352.2.70.560.352.2~7T>10min(NQI)0.560.352RHSaHOV4082RHSaHOV48ShutdownCoolingRtn8RHRHin.FloutoSupp,Pool103HP1.9HP575.3575.30.60.850.60.8561882.411.415.2T9sec17.5110.853.232~61.882.411.415.2T0T9sec17.5110.853.232.61.882.411.415.2T0T9sec17.5110853.232.61.8'2.411.415.2T>10min(NQI)T>10min(HAN)17.5110.853.232.USARRevision517of31October1493

WineMilePointUnit2PSARTABLE8.3-2(Cont'd.ITotalLoadOnz28ilSoHCC303SinultaneousLOOP4LOCA,DesignBasisAccidentDieselCenoratorLoadingPossibilitiesLOOPWithDelayedLOCALOCAWithDelayedLOOPWonaccidentLoadingLOOPWithUnitTripStartingKMKVAR8121708111523301115129200Runni,ngKWKYAR287178287178287178290180293182199123199123238147211130TineSpan0<T<6soc6<T<9soc9<T<14soc14<~T<15soc15<T<20soc20<T<120soc120<T<600sec600<~T<606soc606<T<720soc720sec<TStartingKWKVAR8121708111523301115129200RunningKWKYAR287178287178287178290180293182199123199123238147211130TlatSpan0<T<6sec6<T<9sec9<T<14sec14<T<15sec15<T<20sec20<T<120sec120<T<600sec600<T<606sec606<~T<720sec720sec<TStartingKWKYAR8121708111523301115129200RunningKWKYAR287178287178287178290180293~182199123199123238147211130TimaSpan0<T<6sec6<T<9sec9<~T<14sec14<T<15sec15<T<20sec20<T<120sec120<T<600sec600<T<606sec606<T<720sec720sec<TStartingKWKVAR5121307320455RunningKWKYAR201124189117189117282175206128-0-0--0--0--0-0-0-TineSpan0<T<6sec6<T<120sec120<T<600sec600<~T<606sec606<T<720sec720sec<TUSARRevision520of31October1493

NineMilePointUnit2FSARTABLE8.3-3AHPCSDIESELGENERATORCONDITIONSANDCORRESPONDINGMAINCONTROLROOMANNUNCIATIONSHPCSDieselGeneratorConditionMainControlRoomRemoteAnnunciationLowfueloillevelindaytankLowstartingairpressureControlpowerfailureEngineinmaintenancepositionDieselenginetrip/lockoutnotresetGeneratortrip/lockoutnotreseta.Lossofexcitation.GeneratorreversepowerngineoverspeedGeneratordifferentialManualout-of-service(mainbreakersordieselgeneratorinoperable)(controlroom)LowlubricationoilpressureHighjacketwateroutlettemperaturengineovercrank'nginetroubleEnginetroubleDGinoperableDieselengineinmaintenancepositionDieselenginetrip/troubleGeneratortrip/lockoutEngineoverspeedGeneratortrip/lockoutEnginebypassed/inoperableEnginetroubleEnginetroubleEnginetrouble'~'Duringemergency(LOCA)operation,theseconditionsarebypassedanddonotshutdowntheHPCSDG.Amendment271of1July1986

NineMilePointUnit2FSARTABLE8.3-4LISTOFCLASSlESAFETY-RELATEDLOADSBYPOWERSOURCEEquipmentIdentityNo.2HVC<UC108A2SWP*FV54A2SWP+FV54B2VBS*PNLA1032VBS*PNLA1042VBS*PNLA1052VBS*PNLA1062VBS*PNLA1102VBSAPNLB1032VBS*PNLB1042VBS*PNLB1052VBS*PNLB1062VBS*PNLB1102EQS*EG12EGS*EQ22EGS*EG32BYS*SWG002A2BYS+SWG002B2BYS+BAT2ADescription"UnitcoolerCBstandbyswitchgearroomAMotor-operatedpressurevalveMotor-operatedpressurevalveControlroomRPSandNS4distributionpanelRPSandN54distributionpanelMSZVdistributionpanelMSIVdistributionpanelControlroomRPSdistributionpanelControlroomRPSdistributionpanelRPSandNS4distributionpanelMSIVdistributionpanelMSIVdistributionpanelControlroomRPSdistributionpanelDGDiv.IDGDivIZZDGDiv.IZ12S-Vdcswitchgear125-Vdcswitchgear125-VlEstandbybatteryDiv.IDivision'"B/WBO/WRating10hp0.7hp0.7hp200A200A200A200A200A200A200A200A200A200A5,500kVA3,250kVAS,SOOkVA2,000A2,000A2,500AHVolts5755755751201201201201201201201201201204,1604,1604,160125125125Phase3AmpsFullLoad10.80100.0100.0100.0100.00100.00100.0100.0200.0200'100.0763.3451<763.3449283330AmpsLockedRotor64.329.2029.20PowerSourceZdentityNo.2EJS*PNL102A2EHS*MCC1032EHSAMCC3032VBS*PNLA1002VBS*PNLA1002VBS+PNLA1002VBS*PNLA1002VBS*PNLA1002VBS*PNLB1002VBS*PNLB1002VBS*PNLB1002VBS*PNLB1002VBS*PNLB100Diesel,generatorDieselgeneratorDieselgeneratorXBYS*BAT2A2BYS*BAT2B2BYS*CHGR2A1USARRevision51of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2BYS*SWG002A2BYS*SWG002A2BYS*BAT2B2BYS+SWG002B2BYS*SWG002B2BYS*BAT2C2BYS*PNL204A2BYS*PNL204B2BYS*PNL201A2BYS*PNL202A2DMS+MCCA12BYS*PNL201B2BYS*PNL202B2DMS*MCCB12ICS*FV1082ICSAMOV1162ICS*MOV1202ZCS*MOV1222ZCS*MOV1242ICS*MOV1262ICS*MOV1292ZCS+MOV136Description"'25-Vdcswitchgear125>>Vdcswitchgear125-V1EstandbybatteryDiv.IZ125-Vdcswitchgear125-Vdcswitchgear125-V1EstandbybatteryDiv.ZZZ125-Vdcdistributionpanel125-Vdcdistributionpanel125-Vdcdistributionpanel125-Vdcdistributionpanel125-VdcMCCreactorbuildingel240'25-Vdcdistributionpanel125-Vdcdistributionpanel125-VdcMCCreactorbuildingel240'CICpumptocondensatestorageLubeoilcoolingwatersupplyRCZCsteamsupplyRCICturbineexhaustRCICpumptocondensatestorageRCICpumpto<reactorCondensatestoragetoRCZCpumpSuppressionpoolintoRCZCpumpDivision'"Rating2i000A2i000A2,500AH2,000A2,000A60AH225A225A400A225A600A400A225A600A0.36hp0.36hp0.72hp1.8hp0'2hpF00hp0'2hp0.72hpVolts125125125125125125125125125125125125125125125125125125125125125125PhaseAmpsFullLoad330330330330330552252252002006004002006004.24.08.0014.508.0024.008.008.00AmpsLockedRotor20.821.0039.0082391043939PowerSourceIdentityNo.2BYS*CHGR2Al2BYS*CHGR2A22BYS*CHGR2B12BYS+CHGR2B12BYS*CHGR2B22BYS*CHGR2C12BYS*SWG002A2BYS*SWG002B2BYS*SWG002A2BYS*SWG002A2BYS*SWG002A2BYS*SWG002B2BYS*SWG002B2BYS*SWG002B2DMS*MCCAl2DMS*MCCA12DMS*MCCA12DMSAMCCA12DMS*MCCAl2DMS*MCCA12DMS*MCCA12DMS*MCCA1USARRevision52of26October1993

NineMilePointUnit2FSARTABLE8.3-4{Cont'd.)EquipmentIdentityNo.2ICS*MOV1432ICS*MOV1502ICS*MOV1592ICS*MOV1642ICS*MOV1482HVY*UC2A2HVY*UC2C28NP*MOV1A2SNP*MOV1C28NP*MOV1E2SWP*MOV3A28NP*MOV30A2SWP*MOV50A28NP+MOV74A28NP*MOV74C2SWP+MOV74E2SWP*MOV77A28NP*SSRlA2SNP*SSR2A2SWP*SSR3ADescription"'CICpumpminimumflowtosuppressionpoolRCICtripthrottlevalveRCICbypasstosteamsupplyVacuumbreakervalveoutboardVacuumbreakervalveinboardServicewaterpumppressureindicatortransmitterunitcoolerServicewaterpumppressureindicatortransmitterunitcoolerServicewaterbackwashlineServicewaterbackrashlineServicewaterstrainerbackwashServicewatertoturbineplantMotor-operatedgatevalveServicewaterpumpdischargeheadervalveServiceraterpumpdischargeblockvalveServiceraterpumpdischargeblockvalveServicewaterpumpdischargeblockvalveMotor-operatedgatevalveBarrackheaterBarrackheaterBarrackheaterDivision'"Rating0.36hp0.33hp0.13hp0.14hp0.14hp40hp40hp0.13hp0.13hp0.13hp4hp1hp9.90hp2.6hp2.6hp2.6hp0.70hp3.15kW3.15kW3.15kWVolts125125125125125575575575575575575575575575575575575332332332PhaseAmpsrullLoad4.04.02.31.61.640.040.0.36.36~365.602.2415.604.74.74.,71.910.510.510'AmpsLockedRotor21'021.7016.615.915.93243242'2.52.548.012.8104.0030.030.030.010PowerSourceIdentityNo.2DMS*MCCA12DMS*MCCA12DMS*MCCA12DMS*MCCA12DMS*MCCB12EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS>MCC1012EHS*MCC1012EHSAMCC1012EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS*MCC1012EHS*MCC101USARRevision53of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2SWP*SSR4A2SWP*SSRSA2SWP*SSR6ADescription"'arrackheaterBarrackheaterBarrackheaterDivision'"Rating3.15kW3.15kW3.15kWVolts332332332PhaseAmpsFullLoad10.510.510.5AmpsLockedRotorPowerSourceIdentityNo.2EHS*MCC1012EHS*MCC1012EHS*MCC1012SWP*STR4A2SWP*STR4C2SWP*STR4E2EJS*PNL101A2EJS*PNL103A2EJS*PNL104A2FWS*MOV21A2FWS*MOV21B2GTS>FNlA2GTS*MOV1A2GTS+MOV2A2GTS*MOV3A2GTS*MOV4A2HCS*MOV1A2HCS*MOV2A2HCS+MOV3A2CMS*P2AStrainerservicewaterStrainerservicewaterStrai'nerservicewaterSwitchgearroomAemergency600-VpanelAB-Nemergency600-VpanelAB-Nemergency600-VpanelFeedwatertoreactorFeedwatertoreactorSGTSfiltertraindischargefanReactorbuildingventilationmixplenumtogratesSGTSfiltertrainAinletSGTSfiltertrainAdischargeDecayheatcooltotrainAWetwellhydrogenrecombinerisolationvalveWetwellhydrogenrecombinerisolationvalveWetwellhydrogenrecombinerisolationvalveQ/O~analyzerpump3hp3hp3hp400A400A400A26.4hp26.4hp40hp0.33hp2.0hp2.0hp1.0hp0.7hp0.33hp0.7hp1.0hp5755755756006006005755755755755755755755755755755753.683.683~6815015015029.929.938.51.682.5252'1.90.641.91.7023'2EHS*MCC10123.02EHS*MCC10124.12EHS*MCC1012EHS*MCC102A2EHS*MCC102A2EHS*MCC102A297.02EHS*MCC102A5.02EHS*MCC102A2EHS*MCC102A2EHS*MCC102A12.52EHS*MCC302B10.02EHS*MCC102A4.642EHS+MCC102A10.02EHS*MCC102A2EHS*MCC102A297.02EHSAMCC102C285.02EHS*MCC102AUSARRevision54of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2GTS*MOV28ADescription"'ross-bleedLVLVDi.vislonn'ating2.0hpVolts575PhaseAmpsFullLoad2.50AmpsLockedRotorPowerSourceIdentityNo.2EHS*MCC102A2HCS*MOV4A2HCS*MOV5A2HCS*MOV6A2MSS*MOV1122MSS*MOV1192MSS>MOV2082SWP>MOV17A2SNP>MOV18A2SNP+MOV19A2SNP*MOV21AWetwellhydrogenrecombinerisolationvalveWetwellhydrogenrecombinerisolationvalveWetwellhydrogenrecombinerisolationvalveMainsteamtocondenserVentvalveMainsteamvalveServicewatertoRBCLCWRBCLCNtoservicewaterServicewatertoRBCLCWheatexchangerRBCLCNtoSFCcoolingpool0.33hp0.33hp0.33hp1.6hp0.33hp0.33hp16hp1.6hp1.0hp0.33hp5755755755755755755755755755750.640.640~643.20.640.643.23.22.20.644.642EHS*MCC102A4.642EHS*MCC102A4.642EHS*MCC102A20.02EHS*MCC102A4.54.52EHS*MCC102A2EHS*MCC102A20.02EHS*MCC102A20.02EHS*MCC102A12.52EHS+MCC102A4.52EHS*MCC102A2SWP*MOV33ARHRheatexchangerAtodischargetunnel0.83hp5753.510.32EHS*MCC102A12SNP*MOV90A2CSL*FV1142CSL~MOV1042CSL*MOV1072CSL*MOV1122CSL*P2ServicewatertoRHSheatexchangerLPCStestLPCSpumptoreactorLPCSminimumflowtoRHRSuppressionpooltoLPCSpumpLPCSsystempressurepump0.83hp0.33hp7.80hp1~9hp0.70hp10hp5755755755755755753.50.669.122.81.810.310.32EHS>MCC102A21.02EHS*MCC102C11.252EHSAMCC102C56.22EHSAMCC102C4.142EHS+MCC102C..75.002EHSAMCC102C,2DER*MOV1202DER*MOV131ContainmentisolationvalveReactorbuildingequipmentdrainsTR1vent0'6hp0.33hp5755750.860'44.54.52EHS*MCC102C2EHS*MCC102CUSARRevision55of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2DFRAMOV1202DFR*MOV1392ICSAMOV121Description"'eactorbuildingfloordraindischargeisolationvalveReactorplantfloordrainventisolationvalveTurbinesteamsupplyisolationoutboardDivision"'ating1.4hp0.33hp7.8hpVolts575575575PhaseAmpsFullLoad1.750.649.12AmpsLockedRotor8.04.574.3PowerSourceIdentityNo.2EHS>MCC102C2EHS*MCC102C2EHS*MCC102C2ICS*P22SLS*MOV1A2SLS*MOVSARCICsystempressurepumpAStandbyliquidcontrolSLCSoutboardisolationvalve10hp0.33hp0.70hp57557557510.300.71.9056.22EHSAMCC102C4.82EHS*MCC102C10.62EHS*MCC102A2SLS*P1AStandbyliquidpumpA40hp57538.82532EHS"MCC102C2WCS+MOV112RWCUsystemoutboardsteamisolationvalve5.2hp5758.4848.002EHS*MCC102C2WCS*MOV2002CCP*MOV1242CCP*MOV14ARWCUreturnisolationvalveDomesticwatercoolertoRBCLCWoutboardIRBCLCWtoSFCheatexchangerA1.6hp1hp1.6hp5755755753.202.232020.012.520.02EHS*MCC102A2EHS*MCC103A2EHS>MCC103A2CCP*MOV18ASFCheatexchangerAtoRBCLCW1.6hp5753.2020~002EHS*MCC103A2CCP*MOV2652CCP*MOV15A2CCP*MOV15B2CCP*MOV17AIsolationvalvecontainmentRBCLCWtoRCSpumpAoutboardIRBCLCWtoRCSpumpBoutboardIToRBCLCWRCSpumpAoutboardI1hp0.33hp0.33hp0.33hp5755755755752.20.640.640.64-12.54.54.54.52EHS*MCC103A2EHS*MCC103A2EHS*MCC103A2EHS*MCC103A2CCP*MOV17B2EGA*M1A2EGA*M2A2EGF*P1AToRBCLCWRCSpumpAoutboardIDG1aircomplAmotorDG1aircomp2AmotorDG1fueloiltransferpumpA0.33hp15hp15hp1.5hp5755755755750.6415.8015.801.824.52EHS*MCC103A84.02EHS*MCC103A9.042EHS*MCC103A8402EHS*MCC103AUSARRevision56of26October1993

NineMilePointUnit2FSARTABLE8.3-4{Cont'd.)EquipmentIdentityNo.Description"'ivision"'atingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2EGF~P1C2EGO*PlA2EGS*PlA2EGT*CH22EGT*CH42HVC>ACU1A2HVC*ACU2A2HVC*ACU3ADG1fueloiltransferpumpCLubeoilcirculationpumpJacketwatercirculationpumpLubeoilheaterJacketwaterheaterContxolzoomA/Cunit1ARelayroomA/Cunit2ARemoteshutdownonroomA/Cunit1.5hp15hp5hp12kW18kW40hp40hp2hp57557557557557557557557531.7614'5.6121839.539.52.489.042EHS*MCC103A83.52EHS*MCC103A34'2EHS+MCC103A2EHS*MCC103A2EHS*MCC103A219.02EHS+MCC103A219.02EHS*MCC103A16.302EHS*MCC103A2HVCsFNllA2HVC*FN2A2HVC*FN4A2HVC*MOV1AMakeupairswitchgearfloorControlroomA/CboosterfanABatteryzoomAexchangefanContzolroomA/Cspecialfilterbypass7.5hp10hp3hp0.25hp5755755755758.210.53.70'48.06523.44.52EHS*MCC103A2EHS+MCC103A2EHS*MCC103A2EHS*MCC103A2HVR*CHLlA2HVK*P1A2$WP*FV47A2SWP*MOV66AAuxiliaryoilpumpControlbuildingchilledwatercirculatingpumpAServicewateztoCWSpumpsSezvicewatertostandbyDGcoolersE3A0.75hp1Shp0.7hp1hp5755755755750914.81.102.24.832EHS*MCC103A94.82EHS"MCC103A29.202EHSAMCC103A12.82EHS*MCC103A2$WP*MOV67AServicewatertocontrolDGrelayroomcoil0.66hp5750.864.52EHS*MCC103A2SWP+MOV5992SWP*MOV93A2SWP*MOV95AServicewatertodischargetunnelisolationServicewatertodischargetunnelisolationServicewatertostandbyDGcoolers1.6hp1hp1hp5755755753'2.202'20.02EHS>MCC103A12.502EHS<MCCI03A12.52EHS*MCC103AUSARRevision57of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.Description"Di.vision"'atingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2SNP*P2A2HVP~FN1A2HVP*FN1C2RHS*FV38A2RHS~MOVSOA2RHS*MOV1A2RHS*MOV1042RHS*MOV1132RHS*MOV12A2RHS*MOV1422RHS*MOV15A2RHS*MOV2A2RHS*MOV22A2RHS*MOV23A2RHS*MOV24A2RHS*MOV25AControlbuildingchillerservicewaterpumpADG1exhaustfanlADG1exhaustfan1CTestlineAtosuppressionpoolGlobevalveSuppressionpooltoRHRpumpAHeatsprayinoutboardisolationCoolingsupplyoutboardisolationHeatexchangerAtoreactorHeatexchangerBtoliquidradwastesystemContainmentsprayAReactortoRHRpumpASteamcondensingtoheatexchangerASteamcondensingtoheatexchangerALPCIinletAContainmentsprayA10hp30hp30hp0.33hp0.13hp1.6hp0.7hp19.2hp0.7hp0.33hp2.6hp0.83hp1.6hp1.6hp6.6hp2.6hp57557557557557557557557557557557557557557557557510.532.03200.660.46.01.820.51.90.644.73.53.23.28.04.764002EHS*MCC103A3.82EHS*MCC103C2.502EHS*MCC103C38.02EHSAMCC103C9.01562EHS*MCC103C2EHS*MCC103C10.02EHS*MCC103C4.52EHS~MCC103C30.02EHS*MCC103C10.32EHS*MCC103C20'2EHS*MCC103C20'2EHSAMCC103C74.22EHS*MCC103C30.02EHS*MCC103C232.02EHS*MCC103C232.02EHS*MCC103C2RHS>MOV26A2RHS*MOV27AHeatexchangerAventtosuppressionpoolHeatexchangerAventtosuppressionpool0.13hp0.13hp5755750.830'32.52.52EHS*MCC103C2EHS*MCC103C2RHS*MOV30A2RHS*MOV32ARHRreturntosuppressionpoolHeatexchangerAtoRCIC1.6hp0.7hp5755753.201.820.002EHSAMCC103C2EHS*MCC103C9.0USARRevision58of26October1993

NineMilePointUnit2FSARTABLE8.3-4{Cont'd.)EquipmentIdentityNo.2RHS"MOV33A2RHS"MOV37A2RHS*MOV4A2RHS*MOV40A2RHS*MOV67A2RHS<MOVSA2RHS*MOV9A2BYS*CHGR2Cl2BYS*CHGR2C22CSH'~MOV1012CSH~MOV1052CSH<MOV1072CSH+MOV1102CSH*MOV1112CSH~MOV1122CSH+MOV1182CSH*P22EGF*P2A2EGF*P2B2EGO*Pl2EGT>CH12EGT+HlDescription"'uppressionpoolsprayheaderARHRlineAtosuppressionpoolRHRminimumflowtosuppressionpoolShutdowncoolingreturnARHRshutdownbypassHeatexchangerAbypassRHRpumpAtoheatexchangerA125-VbatterychargerstandbyDiv.III125-VbatterychargerCondensatestoragetoHPCSpumpFlowbypasstosuppressionpoolHPCSpumptoreactorTestbypasstocondensatestorageTestbypasstosuppressionpoolTestbypasstocondensatestorageSuppressionpooltoHPCSStandbywaterlegpumpE22M003DG2fueloiltransferpumpADG2fueloiltransferpumpBHPCSDG2circulatingoilpumpHPCSDG2immersionheaterHPCSDG2spaceheaterDivislon~nRating0.33hp0.33hp1.9hp10.3hp0.33hp1.6hp07hp50Adc50Adc0.7hp3.3hp19.2hp13'hp9.9hp13.1hp3.3hp10hp1.5hp1.5hp1hp15kW3.0kwVolts575575575575575575575575575575575575575575575575575575575575575575PhaseAmpsFullLoad0.640642'12.00.643.21.912F0012.001.94.220.518.410.618.44.210.31.821.821.615.02.15AmpsLockedRotor4.54.5210091.44.5020.010.01029.0156131104.013129.0519.049.04PowerSourceIdentityNo.2EHS*MCC103C2EHS+MCC103C2EHS*MCC103C2EHSAMCC103C2EHS<MCC103C2EHS<MCC103C2EHS+MCC103C2EHS'AMCC2012EHS<MCC2012EHS+MCC2012EHS+MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS+MCC201USARRevision59of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2HVC*UC1022HVP*FN2A2HVP*FN2B2HVP*UC22HVR*UC403A2HVR*UC403B2IAC*XLE032SCV*XD200P2SWP*MOV1SA2SWP*MOV15B2SWP*MOV94A2SWP*MOV94B2HVY~UC2B2HVY*UC2D2SWP~MOVIB2SWP*MOV1D2SWP*MOV1F2SWP*MOV3B2SWP*MOV30BDescription"'PCSswitchgearroomunitcoolerDG2exhaustfan2ADG2exhaustfan2BDG2unitcoolerHPCSDGroomReactorbuildingHPCSseparatorcoolerel196'eactorbuildingseparatorcoolerel196'TGtzansformer600-208Y/120-,VDistributiontransformer600-120-VServicewatertoHPCSunitcoolerServicewatertoHPCSunitcoolerServicewatertostandbyD/GcoolersE3BServicewatertostandbyDGcoolersE3BServicewaterpumpPITunitcoolerServicewaterpumpPITunitcoolerServicewaterbackwashlineServicewaterbackwashlineServicewaterstrainerbackwashServicewatertoturbineplantMotor-operatedgatevalveDivision'"Rating5hp30hp30hp5hp2motors15hptotal2motors15hptotal30kVA25kVA0.33hp033hp1hp1hp40hp40hp0.13hp0.13hp0.13hp4hp1hpVolts575575575575575575600600575575575575575575575575575575575Phase3AmpsFullLoad5'32.032.05'416.0016.0030.0432.400640.642.22.240.040.00.360.360.365'2.24AmpsLockedRotor32.9232.0232.0129.20129.204.504'012.512.5324.00324.002.52.52.548.012.8PowerSourceIdentityNo.2EHS*MCC2012EHS*MCC2012EHSAMCC2012EHSAMCC2012EHS*MCC2012EHS*MCC201.2EHS*MCC2012EHS*MCC2Cl2EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC2012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC301USARRevision510of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2SWP+MOVSOB2SWP*MOV74B2SWP*MOV74D2SWP*MOV74F2SWP+MOV77B2SWP*SSR1B2SWP*SSR2B2SWP*SSR3B2SWP*SSR4B2SWP*SSRSB2SWP*SSR6B2SWP*STR4B2SWP*STR4D2SWP+STR4F2EJS+PNL302B2EJS*PNL303B2EJS*PNL304B2GTSAFN1B2GTS*MOV1B2CMS*P2B2GTS*MOV2BDescription"'ervicewaterpumpdischargeheaderServicewaterdischargeblockvalveServicewaterpumpdischargeblockvalveServicewaterpumpdischargeblockvalveMotor-operatedgatevalveBarrackheaterBarrackheaterBarrackheaterBarrackheaterBarrackheaterBarrackheaterStrainerservicewaterStrainerservicewaterStrainerservicewaterAB-Semergency600-VpanelAB-Semergency600-VpanelAB-Semergency600-VpanelGTSfiltertraindischargefanHVPmixplenumtoGTSH,/O,analyzerpumpGTSfiltertrainBinletDivision"'ating9.9hp2.6hp2.6hp2.6hp0'hp3.15kW3.15kW3.15kW3.15kW3~15kWF15kW3hp3hp3hp400A400A400A40hp0.33hp1hp2.0hpVolts575575575575575332332332332332332575575575600600600575575575575PhaseAmpsFullLoad15.604.74.74.71.910.510.510.510.51Q.510.53.683.683.6815015015039.201.681.702.5AmpsLockedRotor104.0030.030'30.010.023.023.023.0232.005.0PowerSourceIdentityNo.2EHS*MCC3012EHS*MCC301'EHSAMCC3012EHS*MCC3012EHS*MCC3012EHSAMCC3012EHS*MCC3012EHS*MCC3012EHS+kCC3012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC3012EHS*MCC302B2EHS+MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302BUSARRevision511of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.3GTS*MOV3B2GTS>MOV4B2HCS*MOV1B2HCS*MOV2B2HCS*MOV3B2HCSiMOV4B2HCS*MOV5B2HCS*MOV6B2SWP*MOV17B2SWP*MOV18B2SWP>MOV19B2SLS*MOVSB2GTS*MOV28B2SWP*MOV21B2SWP*MOV33B2SWP*MOV90B2DER*MOV1192DER*MOV130Descriptionu'TSfiltertrainBdischargeDecayheatcoolertotrainBWetwellhydrogenrecombinerisolationvalveWetwellhydrogenrecombinerisolationvalveWetwellhydrogenrecombinerisolationvalveDrywellhydrogenrecombinerisolationvalveDrywellhydrogenrecombinerisolationvalveDrywellhydrogenrecombinerisolationvalveServicewatertoRBCLCWRBCLCWtoservicewaterServicewatertoRBCLCWheatexchangerSLCSinboardisolationvalveCross-bleedLVLVRBCLCWtoSFCcoolingpoolRHRheatexchangerBtodischargetunnelRHRheatexchangerinletContainmentisolationvalveDerTK1ventDivision'"Rating2.0hp1.0hp0.7hp0.33hp0.7hp0.33hp0.33hp0.33hp1.6hp1.6hp1.0hp0.70hp2.0hp0.33hp0.83hp0.83hp0'6hp0.33hpVolts575575575575575575575575575575575575575575575575575575PhaseAmpsFullLoad2.52.21.90.641.90.640.640.643'3.22'1~902.500.643.53.50.860.64AmpsLockedRotor12.810.04.6410.04.644.6446420.0020.012.510.004.510.310.34'4.5PowerSourceIdentityNo.2EHS*MCC302B2EHS*MCC102A2EHS*MCC302B2EHS*MCC302B2EHSAMCC302B2EHS*MCC302B2EHSAMCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS*MCC302B2EHS+MCC302B2EHS+MCC302B2EHS*MCC302D2EHS*MCC302DUSARRevision512of26October1993

NineMilePointUnit2FSARTABLE8.3-4{Cont'd.)EquipmentIdentityNo.2DFR*MOV1212DFR~MOV1402ICS*MOV1282ICS*MOV1702MSS*MOV1112MSS*MOV1182SLS+MOV1B2SLS*PlB2WCS*MOV1022HVK*CHLIB2CCP*MOV1222CCP*MOV14B2CCP*MOV18B2CCP*MOV16A2CCP*MOV16B2CCP*MOV2732CCP*MOV94A2CCP*MOV94B2EGF*P1B2EGF*PlDDescription'"DrywellfloordraindischargeisolationvalveDrywellfloordraindischargeisolationvalveMOVsteamsupplylineBypassofMOV128MainsteamtocondensateinboardisolationVentvalveStandbyliquidcontrolStandbyliquidpumpBRWCUinboardisolationvalveAuxiliaryoilpumpDrywellcoolertoRBCLCWi.nboardIRBCLCWtoSFCheatexchangerBSFCheatexchangertoRBCLCWRBCLCWfromRCSpumpARBCLCWfromRCSpumpBRBCLCWtodrywellcoolerinboardisolationCoolingwatertoP1ACoolingwatertoP1BDG3fueloiltransformerpumpBDG3fueloiltransformerpumpDDivision"'ating1.4hp0.33hp7.80hp0.13hp1~6hp0.33hp0.33hp40hp5.2hp0.75hp1hp1.6hp1.6hp1.6hp0.33hp1.0hp0.33hp0.33hp1.Shp1.5hpVolts575575575575575575575575575575575575575575575575575575575575PhaseAmpsFullLoad1.70.649.120.363.20.640.738.88.480.92.23.203.203.20.642.20.640.641.731.73AmpsLockedRotor8.04.575.42.520.04.54.00253.048.004.8312'20.0020.0020~04.512.54.504.509.049.04PowerSourceIdentityNo.2EHSAMCC302D2EHS*MCC302D2EHS*MCC302D3EHS*MCC302D2EHS*MCC302DI2EHS*MCC302D2EHS*MCC302D2EHS*MCC302D2EHS*MCC302D2EHS*MCC303B2EHS"MCC303B2EHS*MCC303B2EHS*MCC303B2EHS>MCC303B2EHS*MCC303B2EHS+MCC303B2EHS*MCC303B2EHSCMCC303B2EHS*MCC303B2EHS+MCC303BUSARRevision513of26October1993 e

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.Description"'ivision'"RatingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2EGO*P1B2EQS*P1B2EGT*CH32EGT*CH52HVC*ACUlB2HVC+ACU2B2HVC*ACU3B2HVC*FNllB2HVC*FN2B2HVC*FN4B2HVC*MOV1B2EQA*M1B2EGA*M2B2HVK*P1B2SWP*FV47B2SWP*MOV66BLubeoilcirculationpumpJacketwatercirculationpumpLubeoilheaterJacketwaterheaterControlroomA/Cunit1BRelayzoomA/Cunit2BRemoteshutdownonroomA/CunitMakeupairswitchgearfloorControlroomA/CboosterfanBBatteryroomBexchangefanControlroomA/CspecialfilterbypassDQ3aircomp1BmotorDG3aircomp2BmotorControlbuildingchilledwatercirculatingpumpBServicewatertoCWSpumpsServicewatertostandbyDQcoolersE3B1Shp5hp12kW18kW40hp40hp2hp7.5hp10hp3hp0.25hp15hp1Shp1Shp0'0hp1hp57557557557557557557557557557557557557557557557514.95.6121839.539~52.488.210.53.74.515.815.814.81~12.223.42EHS*MCC303B28.12EHS*MCC303B84.002EHS*MCC303B84.002EHS*MCC303B94.82EHSAMCC303B29.22EHS*MCC303B12.52EHSAMCC303B83.52EHS*MCC303B34.22EHS*MCC303B2EHS*MCC303B2EHS*MCC303B21902EHS*MCC303B219.02EHS*MCC303B16,32EHS*MCC303B48.02EHS*MCC303B65.62EHS*MCC303B2SWP*MOV67BServicewatertocontgroundrelayroomcoil0.66hpS750.864.52EHS*MCC303B2SWP*MOV93B2$WP*MOV95B2SWP*P2BServicewatertodischargetunnelisolationServicewatertostandbyDQcoolersCatchbasinchillerservicewaterpumpB1.0hp1hp10hp5755755752'2.210.512.52EHS*MCC303B12.52EHS*MCC303B63.22EHS*MCC303BUSARRevision514of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.Description"'ivision'"RatingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2HVP*FN1B2HVP+FNlD2RHS*FV38B2RHSoFV38C2RHS*MOV1B2RHS+MOVlC2RHS+MOV1122RHS+MOV1152RHS*MOV116DG3exhaustfan1BDG3exhaustfan1DTestlineBtosuppressionpoolRHRpumpCtosuppressionpoolSuppressionpooltoRHRpumpBSuppressionpooltoRHRpumpCShutdowncoolingsupplyinboardisolation.ServicewaterbypasstoreactorServicewaterbypasstoreactor30hp30hp0.33hp0.33hp4.0hp1.6hp19.2hp1.6hp1.6hp57557557557557557557557557532.032.00.660.666.03.220.53.23'3.83.82EHS*MCC303D2EHS*MCC303D38.02EHSAMCC303D20.02EHSAMCC303D1552EHSAMCC303DI20.02EHSAMCC303D20.02EHSAMCC303D.23202EHS+MCC303D232.02EHS*MCC303D2RHS*MOV12B2RHS*MOV149HeatexchangerBtoreactorHeatexchangerBtoliquidradwastesystem0.7hp0.33hp5755751.90.6410.04.52EHS*MCC303D2EHS"MCC303D2RHS~MOV15BContainmontsprayB2.6hp5754.730F002EHS*MCC303D2RHS>MOV2BReactortoRHRpumpB0.83hp5753.510.32EHS*MCC303D2RHS*MOV22B2RHS>MOV23B2RHS*MOV24B2RHS*MOV24C2RHS*MOV25B2RHS+MOVSOB2RHS*MOV26BSteamcondensingtoheatexchangerBSteamcondensingtoheatexchanger'LPCIinletBLPCIinletCContainmentsprayBGlobovalveHeatexchangerBventtosuppressionpool1.6hp1.6hp6.6hp6.6hp2.6hp0.13hp0.13hp5755755755755755755753'3.28.08.04.70.360.420.02EHS*MCC303D20.02EHS*MCC303D74.22EHS~MCC303D2.52EHSAMCC303D74.2EHS*MCC303D30.02EHSAMCC303D2.502EHS*MCC303DUSARRevision515of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2RHS*MOV27B2RHS*MOV30B2RHS*MOV32B2RHS~MOV33B2RHS*MOV37B2RHS*MOV4B2RHS*MOV4C2RHS*MOV40B2RHS*MOV67B2RHS*MOVSB2RHS*MOV9B2RHS*P22EJA*PNL100A2EJA*PNL101A2EJA*PNL300B2EJA*PNL301B2BYS*CHGR2A22EJA*XD100A2EJA*XD101ADescription"'eatexchangerBventtosuppressionpoolRHRreturntosuppressionpoolHeatexchangerBtoRCICSuppressionpoolsprayheaderBRHRlineBtosuppressionpoolRHRminimumflowtosuppressionpoolRHRminimumflowtosuppressionpoolShutdowncoolingreturnBRHRshutdownbypassHeatexchangerBbypassRHRpumpBtoheatexchangerBRHRsystempressurepumpReactorbuilding120-VheaterpanelControlbuilding120/240-VheaterpanelReactorbuilding120-VheaterpanelControlbuilding120/240-Vheaterpanel125-VbatterychargerDistributiontransformer600V-208Y/120-VDistributiontransformer600V-120/240-VDivision"'ating0.13hp1.60hp0.7hp0.33hp0.33hp1.9hp1.9hp10.3hp0.33hp1.6hp0.7hp10hp150A150A150A150A300Adc30kVA25kVAVolts575575575575575575575575575575575575208240208240575600600PhaseAmpsFullLoad0.833.201.800.640.642.82.812.00.643.21.910'83.0104.083,0104.08030.043.40AmpsLockedRotor2.5~20.009'4.54.521.021.091.44F5020.0010.051PowerSource,IdentityNo.2EHSAMCC303D2EHS+MCC303D2EHS*MCC303D2EHS*MCC303D2EHS*MCC303D2EHS*MCC303D2EHSAMCC303D2EHS*MCC303D2RHS*MCC303D2EHS*MCC303D2EHS*MCC303D2EHS*MCC303D2EJA*XD100A2EJA*XD101A2EJA*XD300B2EJA*XD301B2EJS*PNL100A2EJS*PNL100A2EJS*PNL100AUSARRevision516of26October1993 0

NineMilePointUnit2FSARTABLE8.3-4tCont'd.)EquipmentIdentityNo.Description"'ivision'"RatingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2EJS*PNL102A2HVC*CHllA2HVC*CH12A2SCV*XD101A2VBA*UPS2A2HVR*UC40IA2HVR*UC401D2HVR*UC402A2HVR*UC402B2HVR*UC404A2HVR*UC404B2HVR+UC414A2HVC*XD2A2HVC*UC101A2HVC*UC103A2HVC+UC1042HVC*UC1062HVP*UC1A2HVR*UC4052HVR*UC407ASwitchgearroomAemergency600-VpanelControlbuildingequipmentroom306heaterControlbuildingequipmentroom288Distributiontransformer600-V-120/240-VDiv.1AcontrolUPSReactorbuildingspacecoolerel175'eactorbuildingspacecoolerel175'eactorbuildingspacecoolerel175'eactorbuildingspacecoolerel175'eactorbuildingspacecoolerel196'eactorbuildingspacecoolerel196'eactorbuildingspacecoolerel175'pecfiltertrainelectricheaterStandbyswitchgearroomAunitcoolerChlorideroomunitcoolerControlbuildingcabletunnelunitcoolerCableareabaseunit.coolerDG1unitcoolerstandbyDOroomReactorbuildingspacecoolerel198'eactorbuildingspacecoolerel215'00A60kW40kw25kVA25kVA2hp2hp10hp10hp3hp3hp3hp15kVA75hp1hp15hp15hp5hp3hp1.5hp60057557560057557557557557557557557557557557557557557557557510060.3040.2043.407Q.002.52.511.2011.203.603.603.36158.51.2415.015.05443.721.8516.016.078.4078.4036.002525.0045.710.539.2023.112'2EJS*PNL100A2EJS+PNL100A2EJS*PNL100A2EJS*PNL100A2EJS*PNL100A2EJS*PNL101A'EJS*PQL101A2EJS*PNL101A2EJS+PNL101A2EJS*PNL101A2EJS*PNL101A2EJS*PNL104A2EJS*PNL102A2EJS*PNL102A2EJS*PNL102A2EJS*PNL102A2EJS+PNL102A2EJS+PNL102A2EJS+PNL103A2EJS*PNL103AUSARRevision517of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2HVR*UC407B2HVR*UC407C2HVR+UC41SA2HVC*CAB18A2HVC*CAB18C2GTS*XD1A2HVR*UC408A2HVR*UC408B2HVR+UC410A2HVR~UC411A2HVR*UC412A2BYS+CHGR2B22EJA*XD300B2EJA*XD301B2EJS*PNL301B2HVC*CH11B2HVR*CAB14A2HVR*CAB32A2SWP*CAB146BDescription"'eactorbuildingspacecoolerel215'eactorbuildingspacecoolerel215'GTspacecoolerel261'ont/reIayroomsintakeradnCont/relayroomsintakeradnFiltertrainAheaterReactorbuildingspacecoolerel240'eactorbuildingspacecoolerel240'eactorbuildingspacecoolerel240'eactorbuildingspacecoolerel261'eactorbuildingspacecoolerel261'25-VbatterychargerDistributiontransformer600-V208T/120-VDistributiontransformer600-V-120/240-VSwitchgearroomBemergency600-VpanelControlbuildingequipmentroom306heaterReactorbuildingaboverefuelfloorradnReactorbuildingbelowrefuelfloorradnServicewatereffluentradiationmonitorDivisionu'ating1.5hp1.5hp2hp1.5hp1'hp20kW5hp5hp1.5hp3hp3hp300Adc30kVA25kVA400A60kW1.5hp1.5hp1.5kWVolts57557557557557557557557557557$575$75600600600$7557$575575PhaseAmpsFullLoad1.851.852~21.81.820'5.685.681.853.363'803043.4010060.301.81.81.84AmpsLocked~RotorPowerSourceIdentityNo.12.42EJS*PNL103A12'2EJS*PNL103A16802EJS*PNL103A12'02EJS+PNL204A25252EJS*PNL104A2EJS*PNL101A2EJS*PNL300B2EJS*PNL300B2EJS*PNL300B2EJS*PNL300B2EJS*PNL300B10.002EJS*PNL104A10002EJS*PNL104A2EJSAPNL301B10502EJS*PNL102A10.50.2EJS*PNL102A2EJS*PNL104A36.702EJS*PNL104A36.702EJS*PNL104AUSARRevision518of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.Description"'ivision'"RatingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2HVC+PNLCH12B2SCV*XD301B2VBA*UPS2B2HVC*XD2B2HVC*UC101B2HVC*UC103BControlbuildingequipmentroomDistributiontransformer600-V-120/240-VDiv.IIAcontrolUPSTransformer600V-480VStandbyswitchgearroomBunitcoolerChlorideroomunitcooler40kW25kVA25kVA15kVA7'hp1hp575600575575$7$$7540.2043.4076.001$Q.51.242EJS*PNL300B2EJS+PNL300B2EJS*PNL300B2EJS*PNL301B45.72EJS*PNL301B10.52EJS*PNL301B2HVC*UC105Contxolbuildingcabletunnelunitcooler5hp5755.4352EJS*PNL301B2HVC*UC1072HVC*UC108B2HVP*UC1B2HVR*UC401BCableareabaseunitcoolerControlbuildingstandbyswltchgearroomBDQ3unitcoolerstandbyDGroomReactorbuildingspacecoolerelL75'5hp10hp5hp2hp$75$75575$751$.010.805.442.52EJS*PNL301B64.32EJS*PNL301B39.202EJS+PNL301B17.102EJS*PNL302B2HVR*UC401C2HVR*UC401E2HVC*CAB18B2HVC*CAB18D2HVR*UC401FReactorbuildingspacecoolerel175'eactorbuildingspacecoolerel175'ont/relayroomsintakeradnCont/relayroomsintakeradnReactorbuildingspacecoolerel175'hp2hp1.5hp1'hp2hp57$57$5755755752.52.51.81.82.5161610.510.5162EJS*PNL302B2EJS*PNL302B2EJS*PNL301B2EJS+PNL301B2EJS*PNL302B2HVR*UC404C2HVR*UC404D2HVR*UC414B2HVR*UC4062HVR*UC407DReactorbuildingspacecoolerel196'eactorbuildingspacecoolerel196'eactorbuildingspacecoolerel175'eactorbuildingspacecoolerel198'eactorbuildingspacecoolerel215'hp3hp3hp2hp1.5hp5755755755755753.363.363.362.41.8525252EJS*PNL302B2EJS*PNL302B25.002EJS*PNL304B15.72EJS*PNL303B12.62EJS*PNL303BUSARRevision519of26October1993

NineMilePointUnit2PSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2HVR*UC407E2HVR*UC415B2GTS*XD1B2HVR*UC409A2HVR*UC409B2HTS*XD0042HTS*XD0032HVR*UC410B2HVR~UC410C2HVR*UC411B2HVR*UC411C2HVR*UC412B2EHS*MCC1012EHS*MCC1022EHS*MCC1032EJS*PNL100A2HCS*PNL22A2HVK*CHL1A2HVR*UC413A2LAC*PNL100A2EHS*MCC301Description"'eactorbuildingspacecoolerel215'GTspacecoolerel261'iltertrainBheaterReactorbuildingspacecoolerel240'eactorbuildingspacecoolerel240'eattracingtransformerHeattracingtransfozmerReactorbuildingspacecoolerel240'eactorbuildingspacecoolerel240'eactorbuildingspacecholerel261'eactorbuildingspacecoolerel261'eactorbuildingspacecoolerel261'00-VMCCscreenwellel261'00-VMCCreactorbuildingel240'00-VMCCcontrolbuildingel240'witchgearroomAemergency600-VpanelHydrogenrecombinerpowercabinetControlbuildingchiller1AReactorbuildingunitcoolerAControlroomAemergencylightingpanel600-VMCCscreenwellel261'ivision'"Rating1.5hp2hp20kWShp5hp25kVA25kVA1~5hp1.5hp3hp3hp3hp600A600A600A600A120kW180kW150hp400A600AVolts575575575575575575575575575575575575600600600600575575575600600PhaseAmpsrullLoad1.852.220.05.685.6843.4043.401.851.853.363.363'6600600600600120161140400600AmpsLockedRotor12~616.8034.2034'12.4012.60252525725782.40PowerSourceIdentityNo.2EJSAPNL303B2EJSAPNL303B2EJS*PNL304B2EJS*PNL304B2EJS*PNL304B2EJS*PNL302B2EJS*PNL302B2EJS+PNL304B2EJS+PNL304B2EJS*PNL304B2EJS*PNL304B2EJS*PNL302B2EJS*US12EJS*US12EJSAUS12EJS*US12EJS*US12EJS*USl2EJSAUS12EJS*US12EJS*US3USARRevision520of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2EHS+MCC3022EHS*MCC3032EJS*PNL300B2HCS*PNL22BDescription"600-VMCCreactorbuildingel240'00-VMCCcontrolbuildingel261'witchgearzoomBemergency600-VpanelHydrogenrecombinerpowercabinetDivision'"Rating600A600A600A120kWVolts600600600575PhaseAmpsFullLoad600600600120AmpsLockedRotorPowerSourceIdentityNo.2EJS~US32EJS*US32EJS*US32EJS*US32HVK*CHL1B2HVK*UC413B2LAC*PNL300B2EHS*MCC201Controlbuildingchiller1BReactorbuildingunitcoolerBControlroomBemergencylightingpanel600-VMCCHPCSswitchgearzoomP180kN150hp400'A600A575575600600161140400600725.002EJS*US3782.42EJS+US32EJS<US32EJS*X22CSL*P12EJS*US12RHS+PIA2SFC~PIA2SWP*P1A2SNP*PIC2SHP*P1E2CSH*P12EJS*X22EJS*US32RHS*PIB2RHS*P1C2SFC*PlBLPCSpump600-VUSemergencyswitchgearroomARHRpumpASFCwatercirculatingpumpAServicewaterpumpAServicewaterpumpCServicewaterpumpPIEHPCSpump4160/600-VHPCStransformer600-VemezgencyswitchgearzoomBRHRpumpBRHRpumpCSFCwatercirculatingpumpB1,500hp1,600A1,000hp450hp600hp6DDhp600hp3,050hp225kVA1,600A1,000hp1,000hp450hp4,0006004,0004~0004,0004~0004,0004,0004,1606004~0004,0004,000187.09621265677.2767637831.096212612656li2168203294474472,4578208203292ENS*SWG1012ENS*SHG1012ENS*SWG1012ENS*SNG1012ENS*SNG1012ENS*SWQ1012ENS*SWQ1012ENS*SNG1022ENS*SWG1022ENS*SNQ1032ENS*SNG1032ENS*SWG1032ENS*SWG103USARRevision521of26October1993 0

Ni.neMilePointUni.t2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2SNP+PlB2SWP+PlD2SWP*P1F2EPS*SNG002Descriptionu'ervicewaterpumpBServicewaterpumpDServicewaterpumpP1FEmergencyswitchgearDivisi.on'"Rating600hp600hp600hpli200AVolts4,0004t0004t00013.8kVPhaseAmpsFullLoad7676761200AmpsLockedRotor447PowerSourceIdentityNo.2ENS*SWG1032ENS*SWG1032ENS*SNG1032EPS*SNG0012EPS*SWG0042BYS*CHGR2A12LAC*XLEOl2LAC>XLE042LAC*XLE062SCM*XD101A2SCM*XD102A2SCM*XD103A2VBA*UPS2A2BYS<CHGR2B12LAC+XLE022LAC*XLE052LAC*XLE072SCM*XD301B2SCM*XD104A2SCM*XD105A2SCM*XD302BEmergencyswitchgear125-VbatterychargerDiv.ILightingtransformer600-208Y/120-VLightingtransformer600-20BY/120-VLightingtransformer600-20BY/120-VDi.stributiontransformer600-120/240-VDistributiontransformer600-120/240-VDistributiontransformer600-120/240-VDiv.IAcontrolUPS125-VbatterychargerstandbyDiv.IILightingtransformer600-208Y/120-VLightingtransformer600-208Y/120-VLightingtransformer600-208Y/120-VDi.stributi.ontransformer600-V-120/240-VDistributiontransformerDistributiontransformer120-Vdistributionpanelli200A300Adc30kVA30kVA30kVA25kVA25kVA25kVA25kVA300Adc30kVA30kVA30kVA25kVA25kVA25kVA25kVA13.8kv5756006006006006006005755756006006006006006006003012008030.030.03043.4043.4043'068.008030.030.03043.4043'043.4043.402EPS*SNG0032LAC*PNL100A2LAC>PNL100A,2LAC+PNLlOOA2LAC*PNL100A2LAC*PNL100A2LAC*PNL100A2LAC*PNL100A2LAC+PNL100A2LAC*PNL300B2LAC*PNL300B2LAC*PNL300B2LAC*PNL300B2LAC*PNL300B~2LAC*PNL100A2LAC*PNL100A2LAC*PNL300BUSARRevision522of26October1993 00 NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2SCM*XD303B2VBA*UPS2B2LAC<PNLE012LAC*PNLE022LAC*PNLE042LAC*PNLE052LAC*PNLE062LAC*PNLE072LAC*PNLE032SCM*XD304BDescription"'20-VdistributionpanelDiv.TIAcontrolUPSLightingpanelLightingpanelLightingpanelLightingpanelLightingpanelLightingpanelLightingpanel120-VdistributiontransformerDivision'"Rating25kVA25kVA100A100A100A100A100A100A100A25kVAVolts600575208208208208208208208600PhaseAmpsPullLoad43.4068.00100A100A100A100A100A100A100A4340AmpsIockedRotorPowerSourceIdentityNo.2LAC*PNL300B2LAC"PNL300B2LAC*XLE012LAC*XLE022LAC*XLE042LAC*XLE052LAC*XLE062LAC*XLE072LAC*XLE032LAC*PNL300B2SCM*XD305B2RCS*MOV10A2RCS*MOV18A2WCS*MOV101120-VdistributiontransformerRecirculationpumpAsuctionvalveRecirculationpumpAdischargevalveRCStowatercleanupNN25kVA4hp4hp0.70hp60057557557543.405.65.61.802LAC*PNL300B47.802NHS-MCC01149.72NHS-MCC0119.002NHS-MCC0112NCS*MOV1032NCS*MOV1042NCS*MOV1052DER*MOV128RCStowatercleanupRCStowatercleanupRCStowatercleanupRPVdrainisol.valveN1.6hp0'hp0~7hp0.33hp5755755755753~21.91.80.641610.09.04,52NHS-MCC0112NHS-MCC0112NHS-MCC0112NHS-MCC0122DER*MOV1292MSS*MOV1082MSS*MOV1892MSS~MOV207RPVdrainisol.valveVentvalveMainsteamvalveMainsteamvalveN0.33hp0.33hp0.33hphp5755755755750.640.640.643'4.52NHS-MCC0124+52NHS-MCC0124.52NHS-MCC01220.02NHS-MCC012USARRevision523of26October1993

NineMilePointUnit2FSARTABLE8,3-4(Cont'd.)EquipmentIdentityNo.Description"'ivision'"RatingVoltsPhaseAmpsFullLoadAmpsLockedRotorPowerSourceIdentityNo.2RCS*MOV10B2RCS*MOV18BRecirculationpumpBsuctionvalveRecirculationpumpBdischargevalveN4hp4hp5755755.66.047.82NHS-MCC01238.02NHS-MCC0122MHR*CRN12ENS*SWG1022ENS+SWG1012ENS*SWG1032EPS*SWG0012EPS*SWG0032SCV*PNL101A2SCV*PNL200P2SCV+PNL301B2VBS*PNL101A2VBS*PNL102A2VBS*PNL301B2VBS*PNL302B2HTS*XD0012HTSAXD0022SWP*CAB146A2GTS*PNLSAReactorbuildingpolarcranemotorel387'160-VHPCSswitchgear1024160-Vemergencyswitchgear1014160-Vemergencyswitchgear102EmergencyswitchgearEmergencyswitchgearGTSmisc.120/240-VpanelHPCSswitchgearroom120-Vmisc.panelGTSmisc.120/240-Vpanel120<<VUPSdistributionpanel120-VUPSdistributionpanel120-VUPSdistributionpanel120-VUPSdistributionpanelHeattracingtransformerHeattracingtransformerServicewatereffluentradiationmonitorReactorbuildingin/outdiffpressN200hp1,200A1,200A1,200A1,200A1,200A150A225A150A200A200A200A200A25kVA25kVA1.5hp1~5hp5754,1604,1604,16013.8kV13.8kv2402402401201201201205755755755751921200120'200'200120010410410420010020010043'043.401.843.01,1522NJS-US22NNS-SWG16/172NNS-SWQ16/182NNS-SWQ17/18'NPS-SWQ0012NPS-SWG0032SCV*XD101A2SCV*XD200P2SCV*XD301B2VBA*UPS2A2VBA*UPS2A2VBA*UPS2B2VBA*UPS2B2EJS*PNL103A2EJS*PNL103A2EJS*PNL102A2EJS*PNL103A2CMS*CAB10AContainmentatmosphereleakageradn1~5hp5751.810~02EJS*PNL104AUSARRevision524of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)EquipmentIdentityNo.2SWP~CAB23A2CMS*CAB10B2HVR*CAB14B2HVR*CAB32B2GTSePNL5B2SWP*CAB23BDescription"'HRservicewaterAradiationmonitorContainmentatmosphereleakageradnReactorbuildingaboverefuelfloorradnReactorbuildingbelowrefuelfloorradnReactorbuildingin/outdiffpressRHRservicewaterBradiationmonitorDivision'"Rating1~5kW1.5hp1.5hp1.5hp1.5hp1.5kWVolts575575575575575575PhaseAmpsFullLoad1.841.81.81.83.01.84AmpsIockedRotor10.010.010.0,10.010.0PowerSourceIdentityNo.2EJS>PNL104A2EJS*PNL303B2EJS+PNL303B2EJS*PNL303B2EJSePNL303B2EJS*PNL303BKEYTODESCRIPTIONSA/CCWSDGGTSHPCSHVRLPCSMCCMSIVPITRBCLCWRCICRHRRPSRWCUSFCSFPSGTSSWTTBCLCWUPSAirconditioningCirculatingwatersystemDieselgeneratorGastreatmentsystemHigh~ressurecoresprayReactorbuildingventilationLow-pressurecoresprayMotorcontrolcenterMainsteamisolationvalvePressureindicatortransmitterReactorbuildingclosedloopcoolingwaterReactorcoreisolationcoolingResidualheatremovalReactorprotectionsystemReactorwatercleanupSpentfuelcoolingandcleanupSpentfuelpoolStandbygastreatmentsystemServicewatertravelingscreens,washanddisposalTurbinebuildingclosedloopcoolingwaterUninterruptiblepowersupplyUSARRevision525of26October1993

NineMilePointUnit2FSARTABLE8.3-4(Cont'd.)KEYTODIVISIONtP0BG/WY/WNB/W0/WCreen(DivisionI-ECCS,HVAC~SWP~etc.Dl-RPS,NMS,NSSSSCh-liDl-MSLIV)Yellow(DivisionII-ECCS,HVAC,SWP,etc.D2-RPSgNMSiNSSSSCh-l,D2-MSLIV)Purple(DivisionIII-ECCS(HPCS))Orange(D3-RPS,NMS,NSSS)Blue(D4-RPS,NMS,NSSSS)Creen/White(Ch>>2,Dl-MSLIV,Ch-A1,Dl-RPStrip)Yellow/White(Ch-2,D2-MSLIV,Ch-Bl,D2-RPStrip)Noncolor(Nonsafetysystems)Blue/White(Ch-B2,D4-RPStrip)Orange/White(Ch-A2,D3-RPStrip)USARRevision526of26October1993

NineMilePointUnit2FSARTABLE8.3-5DIVISIONISTANDBYDIESELGENERATOR2EGS*EG1LOADSUMMARYSIMULTANEOUSLOOPANDLOCALOCAWITHDELAYEDLOOPStartKWStartKVARRunKWRunKVARTotalKWTotalKVAR0<T<0.1sec0.1<T<0.9sec0.9<~T<2.9sec2.9<T<5.5sec5'C~TC6sec6<~T<8.8sec8.8<T<9sec9<~T<15sec15<T<25sec25<T<30sec30<T<31sec31<~T<32sec32<T<36sec36<~T<38sec38<T<70sec70<~T<76sec76<T<98sec98<T<104sec104<T<2min2min<~T<10min982819183036191831291211315693378109271471486435093669920136691114074711584318551012381127992799228163163885885171427912790279327932793292029203073351635163958395839933821757538338379112331232123412341234131313131409164016401870187018911784982820813199280340142925279128012793310834863298401237873516423039584044399338214350937449276405211523826212331247123420773089232551244208164044391870209818911784USARRevision51of6October1993

NineMilePointUnit2FSARTABLE8.3-5(Cont'd.)SIMULTANEOUSLOOPANDLOCALOCANITHDELAYEDLOOP(cont'd.)StartKWStartKVARRunKNRunKVARTotalKWTotalKVAR10min<>>T<10.1min10.1min<T<12min12min<>>T<2hr2hr<T<2hr6sec2hr6sec<T<2.5hrT<<>2.5hr4885906742018382139623842384241724292178918721796179619341934430939623842443241724292245818721796381419341934USARRevision52of6October1993

NineMilePointUnit2FSARTABLE8.3-5(Cont'd.)LOOPWITHDELAYEDLOCALStartKWStartKVARRunKWRunKYARTotalKWTotalKVAR0<T<0.1sec0.1<T<5.5sec5.5<>>T<6sec6<T<8.8sec8.8<T<9sec9<>>T<15sec15<T<2Ssec25<T<30sec30<>>T<31sec31<>>T<36sec36<>>T<70sec70<T<76sec76<T<98sec98<T<104sec104<T<2min2min<T<10min10min<>>T<10.1min10.1min<>>T<12sd.n12min<>>T<2hr2hr<T<2hr6sec9828191831291211315693378714864885904350936691114074711584318551012279922867420181165132813282157323432343236323632363363351635163958395839933821382139623842384253861361310211464146414651465143651S4416401640187018701891178417841872179617961099332464457336832343244323635513929374135164230395840443993382143093962384244324404742821175384921464147814652308332025561640443918702098189117842458187217963814USARRevision53of6October1993

NineMilePointUnit2FSARTABLE8.3-5(Cont'd.)LOOPWITHDELAYEDLOCAL(Cont'd.)StartKWStartKVARRunKWRunKVARTotalKWTotalKYAR2hr6sec<T<25hrT~>2.5hr41724292193419344172429219341934USARRevision54of6October1993

~.

NineMilePointUnit2FSARTABLE8'-5(Cont'd.)LOOPWITHUNITTRIP0<>>T<0.1sec0.1<>>T<6sec6<T<25sec25<>>T<30sec30<>>T<31secStartKW100051615315693StartKVAR4552232828431855RunKW343108910891089RunKVAR162517517517TotalKW100051958108914041782TotalKVAR4552234445171360237231<T<32sec32<>>T<36sec36<T<38sec38<T<70sec70<>>T<76sec76<T<2min120<>>T<10min10min<>>T<10.1min10.1min<T<12min12min<>>T<30min30min<T<30.1min30.1min<>>T<32min32min<T<1hr1hr<>>T<1hr2sec1hr2sec<>>T<2hr2hr<>>T<2hr6sec2hr6sec<>>T378109271470611185901012381127992799964553220181217121713701813181322552169216923712195219521962195219529172917324759759769292292211531099109912261115111511161115111514221422'1560159523092084181325272255216928752371219521952196219533132917350732471609440834919223721115310992063122611151115111611156647142234401560USARRevision75of6October1994 e

NineMilePointUnit2E'SARTABLE8.3-5(Cont'd.)NOTES:UnderthescenarioofaLOOP<<ithasubsequentLOCA,theClass1Eloadsonthestandbydieselgenerators<<illbeadministrativelycontrolledbyNMP2StationBlackoutoperatingprocedures.Time,T,ismeasuredfromtheinstantthedieselgeneratorattainsitsratedvoltageandfrequencyandisconnectedtoitsbusbyclosingthesupplybreaker101<<1(2ENS*SWQ101).USARRevision56of6October1993

NineMilePointUnit2FSARTABLE8.3-6D1VISIONIISTANDBYDIESELGENERATOR2EGS*EG3LOADSUMMARYSIMULTANEOUSLOOPANDLOCALOCAWITHDELAYEDLOOPStartKWStartKVARRunKWRunKVARTotalKWTotalKYAR0<>>T<0.1sec0.1<>>T<0.9sec0.9<T<2.9sec2.9<T<5sec5<T<5.5sec5.5<>>T<6sec6<T<7.5sec7.5<T<9sec9<T<11sec11<>>T<14sec14<>>T<15sec15<T<20sec20<T<30sec30<T<32sec32<T<36sec36<T<38sec38<T<70sec70<T<76sec76<T<98sec98<T<104sec97491736285417842099321714813633262337810927140-714864305833078839337042139745643890685815301510123811279927992281411418638638631617233923532481248124842487248724872641308330833526352650503583583587461054106211421142114411461146114612411471147117011701974918772995264729624080309827022679249225042495248728653579335430833797352636124305833578889372845711010371841960192011571172115911462158495740401471'427017011929USARRevision51of6October1993

NineHoylePointUnit2FSARTABLE8.3-6(Cont'd.)SIMULTANEOUSLOOPANDLOCALOCAWITHDELAYEDLOOP(Cont'd.)StartKWStartKYARRunKWRunKVARTotalKWTotalKVAR104<T<120sec120<<<T<218sec218<T<10min10min<T<10.1min10.1min<T<12min12min<T<1hrihr<T<1hr6sec1hr6sec<~T<1hr2min1hr2min<~T<2hr2hr<T<2hr6sec2hr6sec<>>T<2.5hrT)25hr2095903272018356034063405340534683425342534263425342537553875172216291629162916691641164116421641164117791779356034063405361434683425342934263425401537553875172216291629195516691641164716421641365917791779USARRevision52of6October1993

NineMilePointUnit2FEARTABLE8.3-6(Cont'd.)LOOPWITHDELAYEDLOCAL0<~T<0.1sec0.1<~T<0.9secStartKW97491736StartKVAR430583307RunKW11651306RunKVAR538588TotalKW109143042TotalKVAR4359638950.9<T<2.9sec2.9<T<5sec5<T<6sec6<T<9sec9<T<llsec11<T<14sec14<T<15sec15<~T<20sec20<T<30sec30<T<36sec36<T<70sec70<T<76sec76<T<98sec98<T<104sec104<T<.120sec120<T<218sec218<~T<10min10min<T<10.1win285417842099363326233787148620988393370421390685815301510122799228327130620282028278227962924292429272930293030833083352635263560340634053405588896896128412921372137213741376137614711471170117011722162916291629416038124127314531222935294629382930330830833797352636123560340634053614942742665109219021501387140213891376238814714270170119291722162916291955USARRevision53of6October1993

NineMilePointUnit2FSARTABLE8.3-6(Cont'd.)LOOPNITHDELAYEDLOCAL(Cont'd.)StartKNStartKVARRunKHRunKVARTotalKNTotalKVAR10.1min<T<12min12min<T<1hr1hr<T(lhr6sec1hr6sec<~T<1hr2min1hr2min<~T<2hr2hr<T(2hr6sec2hr6sec<T<2.5hrT)2.5hr590201834683425342534263425342537553875166916411641164216411641177917793468342534293426342540153755387516691641164716421641365917791779USARRevision54of6October1993

NineNilePointUnit2FSARTABLE8.3-6(Cont'd.)LOOPWITHUNITTRIPStartKWStartKYARRunKWRunKVARTotalKWTotalKVAR0<T<0.1sec0.1<T<5sec5<~T<6sec6<T<11sec11<~T<30sec30<~T(32sec32<T<36sec36<T<38sec38<T<70sec70<T<76sec76<T<2min120<~T<10min10min<T(10.1min10.1min<~T<12min12min<~T<1hr1hr<T<1hr2sec1hr2sec<~T<1hr6sec1hr6sec<T<1hr2min1hr2min<~T<2hr2hr<~T<2hr6sec94491436175131537810927147143901122590426572906374984310123811279927995685532201814114180993793793710901533153319761904190420191929192926512652265126515050384424559789789101997897810519959951303130413031303944915771892112493713152029180415332247197619042294201919293051265626S226513251426572956~37991227464147642753358789358810199781546105199565271309130413033321USARRevision55of6October1993

NineMilePointUnit2F'SARTABLE8.3-6(Cont'd.)LOOPWITHUNITTRIP(Cont'd.)StartKWStartKVARRunKWRunKVARTotalKWTotalKVAR2hr6sec<T2982144029821440NOTES0UnderthescenarioofaLOOPwithasubsequentLOCA,theClass1EloadsonthestandbydieselgeneratorswillbeadministrativelycontrolledbyNMP2StationBlackoutoperatingprocedures.Time,T,ismeasuredfromtheinstantthedieselgeneratorattainsitsratedvoltageandfrequencyandisconnectedtoitsbusbyclosingthesupply.breaker103-14(2ENS*SW0103).USARRevisionS6of6October1993

NineMilePointUnit2FSARTABLE8.3-10DIVISIONZII125-VDCBATTERY2BYS*BAT2CLOADPROFILEA.NormalLoadDescritionofLoad4.16-kVswitchgear(onebreakerclosing)4.16-kVswitchgearscontrolrelays/indicationsDieselgeneratorfieldflashingSolenoidvalves(dieselairstart)DieselgeneratorfuelpumpRelaysandindicatorlampsindieselgeneratorpanelsRelaysandindicatorlampsinmaincontrolroompanelsTurbochargerlubeoilpump*Lubeoilcirculatingpump*DivisionZIItransientanalysisrecordersystemlocalpanel(2CES*PNL520)Total0-1Minute~am14.02.16.32.53.77.46.947.91-120Minutes~am2.16.32.33.715.4*ThesepumpsrunonlyduringlossofacpoweratE22-S002(HPCSmotorcontrolcenter)whentheacpumpmotorsarenotrunning.USARRevision31of1October1991

NineMilePointUnit2FSARTABLE8.3-11NORMAL125-VDCBATTERY2BYS-BATlALOADPROFILEDescritionofLoadCircuitbreakertrip0-1Minute~(am274.661-45Minutes~am45-9090-120MinutesMinutes~am~(amlIndicatinglightsforswitchyardandnormal13.8-kV,4.16-kV,anddcswitchgear13.9813.9813.9813.98IMisc.controlandinstrumentationloadsEssentiallighting(2VBB-UPSlc)NormalUPSsystem:(2VBB-UPS1A)Bearinglubeoilpump6754550468467591547207.256763759067618StandbydieselgeneratorfuelpumpRandomloads(1min)30(1)7.5787.57.5Total211864(1)143373(2)1315'8706'8I(1)30-amplockedrotorusedasarandomloadonly.(2)Doesnotincludetherandomloadof78ampswhichappearsfor1minonlyattheendofthisperiod.USARRevision01of1April1989

NineMilePointUnit2FSARTABLE8.3-12NORMAL125-VDCBATTERY2BYS-BAT1BLOADPROFILEDescritionofLoadCircuitbreakertrip'ndicatinglightsfor.switchyardandnormal13.8-kV,4.16-kV,anddcswitchgear0-1'-9090-120MinuteMinutesMinutes~am~am~(am274.6612.9312.9312.93Misc.controlandinstrumentationloadsEssentiallighting(2VBB-UPS1D)NormalUPSsystem:(2VBB-UPS3B)EmergencysealoilpumpTurbineglandsealcompressor605469437014560638110141586011558Standbydieselgeneratorfuelpump30(1)7.57.5Randomloads(1min)Total711532.59(1)1027.43(2)253.43(l)30-amplockedrotorusedasarandomloadonly.(2)Doesnotincludetherandomloadof71ampswhichappearsfor1minonlyattheendofthisperiod.USARRevision01of1April1989

NineMilePointUnit2FSARTABLE8.3-13NORMAL125-VDCBATTERY2BYS-BAT1CLOADPROFILEDescritionofLoadPlantcomputerUPSsystem(2VBB-UPS1G)Total0-1Minute~ams5055051-119Minutes~ams562562119-120Minutes~ams619619Amendment231of1December1985

NineMilePointUnit2FSARTABLE8.3-14NORMAL24-VBATTERY2BWS-3AAND2BWS-3CLOADPROFILEDescritionofLoadControlNeutronmonitoringTotal0-1Minute~am0.31255.005.31251-119Minutes~am0~31255.005.3125119-120Minutes~am0.31255.005.3125' 0

NineMilePointUnit2FSAR'TABLE8.3-15NORMAL24-VBATTERY2BWS-3BAND2BWS-3DLOADPROFILEDescritionofLoad0-1Minute~am1-119Minutes~am119-120Minutes~amControlNeutronmonitoringT,otal0.31255.0005.31250.31255.0005.31250.31255.0005.3125

'0

~DTEDiLYIF'TY.'INEMILEPOINTNUCLEARSTATION~UNIT0///////IAGARA4MOHAWKVOL.25 iQ NineMilePointUnit2FSARiQSectionTitleTABLEOFCONTENTSVolumeCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANT1.11.21.3-1.41.51.61.7~1.81.91.101.11Q1.12CHAPTER2IntroductionGeneralPlantDescriptionComparisonTablesIdentificationofAgentsandContractors'RequirementsforFurtherTechnicalInformationMaterialIncorporatedbyReferenceDrawingsandOtherDetailedInformation.ConformancetoNRCRegulatoryGuidesStandardReviewPlanConformancetoAcceptanceCriteriaUnit2ResponsetoRegulatoryIssuesResultingfromThreeMileIsland(TMI)AbbreviationsandAcronymsGenericLicensingIssuesUnit2PositiononUnresolvedSafetyIssuesSITECHARACTERISTICS2222.12.22.32.42.5GeoteccalEngAppendix2A,Appendix2BAppendixes2Cthrough.2HAppendixes2I,2JAppendixes2K,2L,2M,2N,2P,2QGeographyandDemographyNearbyIndustrial,Transportation,andMilitaryFacilitiesMeteorologyHydrologicEngineeringGeology,Seismology,andhniineering3333,445678CHAPTER33.13.2DESIGNOFSTRUCTURES,COMPONENTS/EQUIPMENT~ANDSYSTEMSConformancewithNRCGeneralDesignCriteriaClassificationofStructures,Systems,andComponentsWindandTornadoLoadingsWaterLevel(Flood)DesignUSARRevisionApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume3.53.6A3.6BI3.7A3.7B3.8':9A3.9B3.10A3.10B3.11Appendixes3Athrough3EMissileProtectionProtectionAgainstEffectsAssociatedWiththePostulated.RuptureofPiping(SWECScopeofSupply)ProtectionAgainstDynamicEffectsAssociatedWithPostulatedRuptureofPiping(GEScopeofSupply)SeismicDesignSeismicDesignDesignofSeismicCategoryIStructuresMechanicalSystemsandComponents(SWEC,ScopeofSupply)MechanicalSystemsandComponents(GEScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment.(SWECScopeofSupply)SeismicQualificationofSeismicCategoryIInstrumentationandElectricalEquipment(GEScopeofSupply)EnvironmentalDesignofMechanicalandElectricalEquipment9,101010101012121212CHAPTER4REACTOR124.14.24.34.44.54.6Appendix4ACHAPTER5SummaryDescriptionFuelSystemDesignNuclearDesignThermal-HydraulicDesignReactorMaterialsFunctionalDesignofReactivityControlSystemsREACTORCOOLANTS'STEMANDCONNECTEDSYSTEMS121212121212125.15.25.35.4Appendixes5A,SummaryDescriptionIntegrityofReactorCoolantPressureBoundaryReactorVesselComponentandSubsystemDesign5B1313131313USARRevision7.October1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionCHAPTER6TitleENGINEEREDSAFETYFEATURESVolume136.16.26'.6.46.56.6AppendixesCHAPTER7EngineeredSafetyFeatureMaterialsContainmentSystemsEmergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandContxolSystemsInserviceInspectionofSafetyClass2andClass3Components6Athrough6DINSTRUMENTATIONANDCONTROLSYSTEMS131415151515157.'17.27.37.47.57.67.7Appendixes7A,CHAPTER88.18.28.3Appendix8ACHAPTER9IntroductionReactorProtection(Trip)System(RPS)Instrument'ationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplay~InstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7BELECTRICPOWERIntroductionOffsite.PowerSystemOnsitePowerSystemAUXILIARYSYSTEMS151515161616161616161616,1717179.19.29.39.49.5Appendixes9A,CHAPTER10FuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilatingSystemsOtherAuxiliarySystems9CSTEAMANDPOWERCONVERSIONSYSTEM17181920,2121,22232310.110.210.3SummaryDescriptionTurbineGeneratorMainSteamSupplySystem232324USARRevision7October1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume10.4CHAPTER1111.111.211.311.411.5Appendix11ACHAPTER1212.112.212.312'12.5CHAPTER1313.113.213.313.413.513.6CHAPTER1414.114.2CHAPTER15OtherFeaturesofSteamandPowerConversionSystemRADIOACTIVEWASTEMANAGEMENTRADIATION'ROTECTIONEnsuring.ThatOccupationalRadiationExposures'AreAsLowAsReasonablyAchievable(AL2QQ.)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgramCONDUCTOFOPERATIONSOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurityINITIALTESTPROGRAMSpecificIncludedAnalysisSpecificIncludedAnalysisInformationToBeinPreliminarySafetyReport(PSAR)InformationToBeinFinalSafetyReport(FSAR)ACCIDENTANALYSISSourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringand.SamplingSystems.242424242525252525252525262626262626262626262626,272715.015.115.2GeneralDecreaseinReactorCoolantTemperatureIncreaseinReactorPressure272727USARRevisionivApril1994 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd.)SectionTitleVolume15.315.415.515.615.715.8AppendicesCHAPTER16CHAPTER1717.017.117.2CHAPTER18DecreaseinReactorCoolantSystemFlowRateReactivityandPowerDistribution'nomaliesIncreaseinReactorCoolantInventoryDecreaseinReactorCoolantInventoryRadioactiveReleaseFromSubsystemsorComponentsAnticipatedTransientswithoutScram(ATWS)15Athrough15HTECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYPAR2QIETERDISPLAYSYSTEM2727272727272828282828282818.118.2APPENDIXAAPPENDIXBDetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSISNIAGARAMOHAWKPOWERCORPORATZONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1)~NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASE28282828USARRevision6April1994

NineMilePointUnit2FSARventilationandmechanicalvacuumpumparebasedonNUREG-0016Revision01.'hedesignannualaveragereleaseconcentrationsareshowninTable11.3-3asactivityinuCi/cc,andasafractionofmaximumpermissibleconcentration.11.3.3.3DilutionFactorsTheatmosphericdilutionfactorassociatedwithnormalplantreleasesisbasedontheaverageannualmeteorologicalconditionsapplicabletothesiteaswellastheeffectivereleaseheightoftheeffluentdischargepathway.ThesitemeteorologicalconditionsaregiveninSection2.3.11.3.3.4EstimatedDosesAsummaryoftheestimatedannualradiationdosesispresentedinAppendix11A.andshowsthattheestimatedannualdosesfromgaseouseffluentsarebelowthedosecriteriasetforthin10CFR50AppendixIandarewellbelowthedosecriteriaspecifiedin40CFR190and10CFR20.Themaximumhypotheticalgammaandbetaairdosesfromnoblegasreleasesoccurattheexclusionareaboundary(EAB),1,603meastofthesite.Thedosesatthislocationareestimatedtobe0.06mrad/yrgammaand0.04mrad/yrbeta,ascomparedwiththe10CFR50Appendix1designobjectiveforgammaandbetaairdosesof10.0mrad/yrand20.0mrad/yr,respectively.USARRevision611.3-9April1994

NineMilePointUnit.2FSARTABLE11.3-1EXPECTEDRADIOACTIVEGASEOUSEFFIUENTFROMALLSOURCES(CI/YR)~lentoeI-131I-132I-133I-134I-135Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Xe-131mXe-133mXe-133Xe-135mXe-135Xe-137Xe-138Cr-51Mn-54Fe-59Co-58Co-60Zn-65Sr-89Sr-90Zr-95Nb-95Mo-99Ru-103Ag-110mSb-124Cs-134Cs-136Cs-137Ba-140Ce-141Reactor~Buildin2.3-024.1-013.0-017.5-013.2-013.0+002.1+003.8+002.4+001.1+026.1+011.3+021.9+027.3+009.7-041.3-033.5-042.9-045.1-034.1-031.7-047.9-066.2-041.1-026.3-025.9-042.6-062.1-054.3-034.9-045.7-031.4-027.9-04TurbineBuilding1.1-011.9+001.6+004.7+001.6+002.5+016.1+019.1+015.8+021.5+024.0+023.3+021.0+031.0+039.0-046.0-041.0-041.0-031.0-036.0-036.0-032.0-054.0-056.0-062.0-035.0-051.0-042.0-041.0-041.0-031.0-021.0-02Radwaste~Buildin1.8-02F9-011.5-013.4-011.4-01F9+012.2+025.3+022.8+028.3+012.0+007.0-064.0-053.0-062.0-067.0-053.0-068.0-064.0-083.0-081.0-087.0-072.4-054.0-054.0-087.0-08Mechan-icalVacuum~Bum4.3-027.4-015.9-011.7+006.1-011.3+035.0+02Off-Gas~Bstem7.7-017.3+022'+022.2-021.7+025.3+014.6+005.8+032.2-12Amendment12of2June1984

NineMileFointUnit2FSARTABLE11.3-1(Cont)ReactorTurbineRadwaste~lentoeBuildinq~Buildin~BuildinMechan-icalVacuum~PumOff-Gas~SstemAr-41H-3C-141.5+012.6+012.6+017.1+019.5+00NOTE:3.0+00=3.0x10'of2 0

NineMilePointUnit2FSARTABLE11.3-2DATA,USEDINCALCULATINGANNUALRELEASESOFRADIOACTIVEGASEOUSEFFLUENTS.ParameterMaximumcorethermalpowerTotalsteamflowrateOffgascharcoalbedholdup*timesperNUREG-0016(Kr)(Xe)PlantcapacityfactorExpectedreleasessourcetermfailedfuelbasisDesignreleasessourcetermfailedfuelbasisOffgassystemcharcoalmass/trainDynamicadsorptioncoefficients(Kr)(Xe)CharcoaldelaysystemnormaloperatingtemperatureCharcoaldelaysystemdewpointtemperatureVentilationsystemsDecontaminationfactorsNormaloperationsRadwastebuildingAllotherbuildings/systemsShutdownData3,489(MWt)1.5x10~lb/hr29.6hr21.75days80%0.05Ci/sec(after30min)0,3489Ci/sec(after30min)48,000lb25cm~/gm440cm/gm70oF-20FSeeSection9.499%efficientHEPAfilterUnfilteredRadwastebuilding99%efficientHEPAfilterUSARRevision61of2April1994 NineMilePointUnit2FSARTABLE11.3-2(Cont'd.)'arameterDataReactorbuilding10%ofeffluentsunfiltered90%ofeffluents90%efficientiodinefilter99%efficientHEPAfilterAllotherbuildings/systemsUnfiltered*TheoffgassystemholduptimespresentedarebasedonNUREG-0016calculationmethods.TheholduptimevaluesinthistableareusedonlytocalculateannualradioactivegaseouseffluentreleasesfromUnit2.TheoffgassystemholduptimesdiscussedinSection11.3.2.1arebasedondesignsystemparameters.USARRevision62of2April1994 NineMilePointUnit2FSARTABLE11.3-3DESIGNANNUALAVERAGEGASEOUSRELEASESVS.MPC~Isotoe.ContinuousAnnuaIActivityatEABuCiccAveraFractionofMPCInermittenMVPFractionofMPCActivityatEABuCiccMainStackReleasesAnnuaIAveraeMPC>>~UCIccFractionofMPCActivityatEABuCiccRadwaste/ReactorBuildingVentReleasesTotaIRelease(fraction~of'PCI-131I-132I-133I-134I-135Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Xe-131mXe-133mXe-133Xe-135mXe-135Xe-137Xe-138Cr-51Mn-54Fe-59Co-58Co-60Zn-65Sr-89Sr-90Zr-95Nb-95Mo-99Ru-103Ag-110mSb-124Cs-134Cs-136Cs-137Ba-1403.2-163.9-153.2-159.8-153.3-151.5-151.5-124.9-131.2-135.2"131.2-121.0-139.0-151.2-118.4-136.7-132.0-122.0-122.6-192.6-191.9-191.9-179.0-191.7-181.3-164.9-191.6-193.2-201.6-171.0-192.7-222.0-198.9-194.1-192.2-181.6-163.2-061.3-067.7-061.6-063.3-065.0-081.5-051.6-066.2-062.6-054.0-052.6-073.0-084.0-052.8-056.7-066.7-056.8-053.3-122.6-101.0-109.6-093.0-098.5-104.5-071.6-081.6-101.1-112.3-093.5"119.0-132.9-102.3-096.7-114.5-091.6-077.1-169.1-157.0-152.0"147.8-151.6-116.0-127.1-063.0-061.8-053.4-067.8-065.2-056.0-051.9"152.1-141.5-143.8-141.6-141.0-137.6"141.3-131.1-121.2-112.1-111.5-119.7"123.3-135.0-181.0-171.2-179.6-178.1-172.1-176.9-173~4-184.2-177.8-169.0-152.1-172.0-187.,7-193.3"163.5-172.2-164.0-151.9"057.0-063.9-056.3-061.6-051.0-063.8-066.6-063.8-054.0-057.0-041.5-043.2-041.1-056.3-111.0-086.0-094.8-082.7-071.1-082.3-071.1-074.2-082.7-071.3-066.9-096.5-091.1-098.3-075.9-094.5-074.0-061.0-103.0-094.0-106.0-091.0-093.0-081.0-073.0-072.0-082.0"083.0-084.0-073.0-073.0-073.0-081.0-073.0-083.0-088.0-081.0-092.0-092.0-093.0-102.0-093.0-103.0-111.0-093.0-097.0-093.0-093.0-107.0-104.0-106.0-095.0-101.0-093.0-051.1-056.5-051.1-052.7-055.0-081.6-051.6-061.0-053.3-057.8-052.6-073.0-081.3-047.3-0II2.2"043.9-047.9-056.6-111.0-086.1-095.8-082.7-071.2-086.8-071.3-074.2-082.7-071.3-066.9-096.5-091.4-098.3-076.0-094.5-074.2-06Amendment121of2June1984

NineNilePointUnit2FSARTABLE11.3-3(Cont)~leocoeHainSackReleasesIntermittentHVPActivityatEABuCiccFractionof'PCActivityatEABuCiccFractionofHPCContinuousAnnualAveraeActivityatEABuCiccFractionof'PCHPC>>~ocicoRadwaste/ReactorBuildingVentReleasesAnnualAveraeTotalRelease(fraction~ofNPCCe-141Ar-41II-3C-14TotaI2.0-172.5-147.6-152.8-154.1-096.3-073.8"082.8-083.2-041.5-042.8-171.3-135.6-096.5-071.3-035.0-094.0-082.0-071.0-079.7-096.3-076.9-072.8-081.8-03+Inaccordancewith10CFR20,AppendixBAmendment122of2June1984 1lI,1 THISFIGUREHASBEENDELETEDFIGURE11.3-2NIAGARAMOHAWKPOWERCORPORATIONNINEIVIILEPOINT-UNIT2uPDATEDSAFETYANALYSISREPORTUSARREYlSION4OCTOBER1992

NineMilePointUnit2FSAR11.4SOLIDWASTEMANAGEMENTSYSTEMPowerplantoperationresultsinvarioussolidradioactivewastesthat,requiredisposal.Theradioactivesolidwastesystemisdesignedtocollect,hold,monitor,process,package,andprovidetemporarystoragefacilitiesforradioactivematerialspriortoshipmentoffsiteandultimatedisposal.ThesolidwastemanagementsystemisshownonFigure11.4-1.11.4.1DesignBasisTheradioactivesolidwastesystemisdesignedtothefollowingcriteria:Thesystemprovidesforthesolidificationandpackagingofwetsolidwasteswithasphaltintoshippingcontainersasaliquid-freehomogeneous,immobilemixpriortoshipmentforoffsitedisposal.2.Allsolidwastecontainers,shippingcasks,andmethodsofpackagingmeetapplicablestateandfederalregulations.WasteswillbeshippedtoalicensedburialsiteinaccordancewithapplicableNRCandDepartmentofTransportation(DOT)regulations(i.e.,10CFR71and49CFR171-178).3.Thefillingofcontainers,solidification,andstorageofradioactivesolidwasteconformsto10CFR20and10CFR50requirementsandRG8.8guidelines'intermsofAL2~dosestoplantpersonnelandthegeneralpublic.4.Remoteautomaticand/ormanualoperationisprovidedbytheradwastesolidificationsystemcontrolpanelandwastehandlingcontrolpanel.5.Systemreliabilityisemphasizedthroughredundancyindesignofprimarycomponents,compartmentalizationofequipmentlayout,shielding,containmentofpossiblespills,remotedecontamination(ifrequired),accurateprocessmonitoring,andinterlockingofprocesscontrols.6.TheseismiccriteriaandanalyticalproceduresforstructureshousingthesolidradwastesystemaregiveninSection3.2.1and3.7.ThequalitygroupclassificationforthesystemcomponentsandpipingisgiveninTable3.2-1.11.4.2SystemInputsRadioactivesolidwastesthatofconcentratedliquidwastesradioactiveLWS,spentresinshandlingradioactiveliquids,resultfromplantoperationconsistfromtheevaporatorsinthefromall'lantdemineralizersfiltersludgesfromLWSfilters,USARRevision611.4-1April1994 NineMilePointUnit2FSARphaseseparators,and.miscellaneoussolidmaterials'hat.becomecontaminatedduringplantoperationand,maintenance.Table11.4-1isaconservativelyhighestimateoftheexpectedvolumesofboththewetanddryradioactivesolidwastegeneratedbytheunit.11.4.2.1SysteminputsActivityExpectedanddesignwetsolidwasteactivitiesaregiveninTable11.4-2.Thepredictionofsolidradwasteprincipalnuclidecurieinventorieswasobtainedfromamathematicalmodelofexpectedanddesignvaluesofreactorcoolantandmainsteamradionuclideconcentrations,asdiscussedinSection11.1andfoundinTable11.4-3.ExpectedandmaximumdrysolidradwasteinventoriesandannualcuriecontentforbothcompactibleandnoncompactiblewastesareprovidedinTables11.4-5and11.4-6.Thevaluesinthesetablesarebasedondataonradionuclidespresentindrysolidradwastefromoperatingplants"',andarecalculatedforUnit2usingtheparametersinTable11.4-7.11.4.3SystemDescriptionTheradioactivewastesolidificationsystem(WSS)equipmentis(>)describedinTopicalReportsWPC-VRS-001"'ndWPC-VRS-002.Ztisoperatedonabatchbasisandequipmentcapabilitiesaredesignedtomeetdesignthroughputrates.Thesolidificationsystemconsistsofawastefillstation,amonitorandcappingstation,anextruder/evaporator,controlconsole,andpiping,meteringpumps,andprocessequipmentrequiredfortransferandsolidificationofwastes.Table11.4-4liststhemajorequipmentofthesolidwastesystem.Thesolidificationequipment.requiresaminimumofmanualaction,andinconjunct'onwiththebuildinglayoutisdesignedtominimizeoccupationalradiationexposures.Thesolidifiedcontainersarehandledbya30-toncapacityoverheadbridgecranewithan81/2-tonauxiliaryhoist.ThecraneisremotelyoperatedfromthecontrolconsolebytheOperatorusingclosed-circuitTV.Theasphalthandlingsystemconsistsofastoragetank,redundantrecirculationpumps,andredundantrecirculationfilters.Alllinesthatcarrytheasphaltaresteamheattracedandequippedwithreliefvalvesthat,dischargeintotheasphaltstoragetank.Usingaclosedlooprecirculationpathfromthestoragetankthroughthepumpsandstrainers,andbacktothetank,thissystemkeepsthemoltenasphaltinconstantrecirculationexceptduringperiodsofsystemmaintenance.Thespentresinandfiltersludgehandlingsystemconsistsofawastesludgetankwithagitator,redundanttransferpumps,andadecantpump.Thesystemprovidesforholdup,recirculation,andUSARRevision611.4-2April1994 NineMilePointUnit2FSARsamplingofwaste,anddecantingofexcesswaterprior.totransfertothesolidificationportionofthesystem.Theevaporatorbottomshandlingsystemincludesaconcentratedwastetransferpump.InconjunctionwiththeLWSevaporatorbottomstank,thissystemprovidesforholdup,recirculation,andsamplingofevaporatorconcentratespriortotransfertosolidification.Alllinesandcomponentsinthewasteconcentratesystemareheattraced(topreventcrystallizationofthewastesaltsinthesystem)andequippedwithreliefvalvesthataredischargedtothebuildingfloordrains.ThevariousplantsystemsthatinterfacewiththewastesolidificationsystemareshownonFigures11.4-1ato11.4-1gandareasfollows:LWSprovidesthewastefeedstreams.2.Radwasteauxiliarysteam(ASR)provideshotflushwater.3.Steamreleasedfromreliefvalvesisdischargedtotheauxiliaryboilersteam(ASM)reliefheader.4.Makeupwatersystem(MWS)suppliesboilerfeedwatertotheWSSboiler.Condensatemakeupanddrawoffwater(CNS)isusedforequipmentflushing.6.Instrumentairsystem(IAS)suppliesairtoallinstrument.andair-operateddevices.7.Serviceairsystem(SAS)providesairforclearinglinesviahoseconnections.8.Allequipmentisprovidedwithdrainstotheradwastebuildingfloorandequipmentdrainssystem(DFW).AllliquideffluentfromtheWSSisreturnedtotheliquidwastesystem.9.Exhaustairfromtheequipmentisventedtotheradwastebuildingventilationsystem(HVN).10.Turbinebuildingclosedloopcoolingwater(CCS)providescomponentcooling.11.Radwastesamplingsystem(SSW)providesprocesssampling.12.Radwastesealwatersystem(SWR)providessealwaterforpumpswithdoublemechanicalseals.DetailsaregiveninSection11.2.USARRevision611.4-3April1994 NineMilePointUnit2FSARAcompactoris.providedtocompressdrywastessuchas~aper,rags,andplasticforpackaginginmetalboxes.Incompressiblesolidwastesarepackagedinmetalboxes,55-galdrums,orencapsulatedinlinersranginginsizefrom50to200cuft.Design.oftheWSSandequipmentisinaccordancewithTopicalReportNo.WPC-VRS-001,withthefollowingdifferences:1.Onewastesludgetankisusedtoreceivebothspentresinandfiltersludgeinlieuofatankforeachfeedstream(WPC-VRS-001,DrawingNo.SK-VRS-2-Rl).2.ThewastesludgetankisdesignedtoASMESectionVIIIDivisionIincompliancewithRG1.143insteadofAPI620(seeFSARSecti.on1.8).3.Asphaltstoragetankoverflowanddrainaredirectedintothetankcubicleinsteadofoutdoors(WPC-VRS-001,AmendmentII).ThetankcubicleisdesignedtoAmericanNuclearInsurers(ANI)requirements.Ithasa3-hrfireratingandiscapable.ofretainingthetankcontentsandpotentialfiresuppressionwater.4~TheventilationhoodatthecontainerfillstationisnotfittedwithHEPAandcharcoalfilters(WPC-VRS-001,AmendmentI,Response2).Instead,ventilationairfromthefillstationisprocessedthroughtheradwastebuildingHVWsystem,whichisconsistentwiththegaseousradwastemanagementdesigninteriordiscussedinFSARSection11.3.Reliefsteamfromtheauxiliaryst'earnsystemwill.betotallycondensedinsteadofdischargedtotheatmosphere.Dampersareinstalledontheasphalttankandwastesludgetankoverflowlinestoisolatethetankvaporspacefromthebuildingatmosphere.6.Materialsfordistillatecollectiontank2WSS-TK-17andsystempipingandvalvesareinaccordancewitheithertheASMEorASTMspecifications.Items1,2,and6arechangesinitiatedbytheWSSvendor,andallchangesareconsistentwiththerequirementsofRG1.143,asdiscussedinFSARSection1.8.11.4.3.1SpentResin/FilterSludgePackagi.ngThewastesludgetankreceivesspentresin/filtersludgefromtheLWSspentresintank,floordrainfilter,andradwastefilterbackwashtank.Excesswatermayberemovedfromthesludgetankbythedecantpumpthroughretentionscreenstopreventresincarryover.USARRevision611.4-4April1994 NineMilePointUnit2FSARWhenthewaste.istobesolidified,theagitatedwasteisrecirculatedviaoneoftworedundantsludgetransferpumps.Recirculatedwasteprovidessuctiontooneoftworedundantsludgemeteringpumpsthatfeedwastetotheevaporator/extruder.Atthesametime,moltenasphaltismeteredtotheextruderfromtheasphalthandlingsystembyoneoftworedundantasphaltmeteringpumps.Intheextruder,waterisevaporatedandthesolidwasteismixedwiththeasphalt.Atthecontainerfillstation,theasphalt/wastemixtureisdischargedfromtheextruderintoapprovedshippingcontainers.AventilationhooddirectsairfromthefillstationareatothefiltrationsystemoftheradwastebuildingHVWsystem.Thefilledcontainersaremovedtothemonitoringstationwheretheyarecappedandradioactivelymonitored,andmonitoredforremovablecontaminationbytheswipemethodbeforebeingplacedintotemporarystorage.Theevaporatedwaterfromtheextruderiscondensed,cooled,filtered,andthenreturnedtotheLWSfor'furtherprocessing.11.4.3.2EvaporatorBottomsPackagingEvaporatorbottomsareprocessedfromtheLWSevaporatorbottomstank">>.Whenthewasteistobesolidified,thecontentsarerecirculatedbytheconcentratedwastetransferpump.Recirculatedwasteprovidessuctiontooneoftworedundantconcentratedwastemeteringpumpswhichfeedswastetotheextruder/evaporator.Atthesametime,asphaltismeteredtotheextruder/evaporator.Intheextruder,thewaterisevaporated,theevaporatedwaterfromtheextruderiscondensed,cooled,filtered,andreturnedtotheLWS,andthecrystallizedsaltsaremixedwiththeasphalt.Theasphalt/wastemixtureisdischargedtoshippingcontainersatthecontainerfillstation.Thecontainersaremovedtothemonitoringstation.Thecontainersarecappedandradiologicallysurveyedbeforebeingplacedintotemporarystorage.11.4.3.3RadwasteBackupSystemTheradwastebackupsystemprovidesanalternatemethodforthesolidificationofspentresin/filtersludgeandevaporatorbottomsbyamobile,skid-mountedsolidificationsystemwhichwouldbetemporarilylocatedintheradwastebuildingtruckbay.Intheeventthattheextruderisoutofservice,threepipelineswillbypasstheextruderandgodirectlytoahosestationinthetruckbayarea.Thesethreepipelinesconsistof:A11/2-indiameter,electrically-tracedlinethatcarriesevaporatorbottomswastedirectlyfromtheevaporatorbottomstransferpump.2.A11/2-indiameterlinethatcarriesspentbeadresinsandfiltersludgedirectlyfromthewastesludgetankpumps'SARRevision611.4-5April1994 NineMilePointUnit2FSAR3...A2.-indiameter,linethatcarriesspentpowderresin'romtheinfluentheaderfeedline.ofthespentresintank.Flexiblehoseswillbeusedtotransferthespentwastefromthehosestationtoamobilesolidificationunit.ThetruckbayareaisclassifiedasRadiationZoneI/IV,restrictedduringtheradwasteloadingoperation.Thisbackupfacilityconsistsentirelyoftransferpipingandvalves.1tispartofandisdesignedandconstructedtothesamecriteriaastheLWSandWSSsystemswithwhichitinterfaces.Alltransferoperationsaremanuallycontrolledfromacontrolpanellocatedinthetruckdockarea.11.4.3.3.1RadwasteDewateringSystemTheradwastedewateringsystemprovidesanalternatemethodofwastevolumereductionbyaself-contained,freestanding,portabledewateringsystemlocatedintheradwastebuildingtruckbay,el261'.Thisunitconsistsofadewateringskid,aplantconnectionsta'nd,acontrolmodule,acontainerfillhead,andawastecontainerandassociatedinterconnectinghosesandcables.Plantservicesrequiredtoproperlyoperatethedewateringsystemincludeserviceair,servicewater,electricalpower,andwasteasshownonFigure11.4-1.Thedesign,operation,andsafetyevaluationofthisdewateringsystemisdescribedinChemNuclearSystems,Inc.,TopicalReportRDS-25506-01-P/NP"',whichhasbeenreviewedandacceptedbyNiagaraMohawkPowerCorporation(NMPC)andtheNRCasapplicable.11.4.3.4DryWastePackagingContaminateddrycompressiblematerialsarecollectedatvariouslocationsintheplantandtransportedtotheradwastebuildingforpackaging.Thedrysolidwaste,suchaspaperandrags,iscompactedintometalboxesbythewastecompactor.Theboxesareplacedintoatemporarystorageareapriortoshipmenttoawasteburialsite.Theboxesarehandledbyamanually-operatedforklift.Duringthewastecompactingoperation,theairflowinthevicinityofthecompactorisdirectedbyanexhausterthroughahigh-efficiencyairfilter,andthentotheradwastebuildingHVWsystem.11.4.3.5IncompressibleWastePackagingComponentsoflowactivity,suchascontaminatedtools,canbepackagedinavailableorspecially-designedshippingcontainersandstored,ifnecessary,intheradwastebuildingpriortoshipment.SpentcorecomponentswithveryhighactivitylevelsarehandledunderwaterwithinthereactorrefuelingcavityandfueltransferUSARRevision611.4-6April1994 NineMilePointUnit2FSARcanal,andstoredinthefuelpooluntiladequatepackagingisprovidedforoffsiteshipment.RefertoSection9.1foradditionalinformationonspentfuelhandling.11.4.3.6WastePackagingControlsCompletesolidificationoftheprocessedwasteisensuredbypreoperationaltestingandtheimplementationofaprocesscontrolprogramdescribedinWPC-VRS-001'ndWPC-VRS-002Wastesludgeandevaporatorbottomstanksareprovidedwithmeansforobtainingrepresentativesamplesviaashieldedsamplingstationlocatedintheradwastebuilding.Wastepackagingcontrolsaridmonitoringareprovidedfromthe'solidificationsystemcontrolpanel.Thesystemisdesignedtopreventexternalcontaminationofthecontainersbyinstrumentationinterlocksthatpreventoverfilling.Electricalinterlocksareprovidedwithallradioactivewastefeedsystemstoensurethatasphaltisavailableandflowingtoprovidethesolidificationmatrixwheneverwasteisfedtotheextruder/evaporator.11.4.3.7WasteHandlingWastehandlingisprovidedbya30-ton,overhead,travelingbridgecranewithan81/2-tonauxiliaryhoist.Remotehandlingofpro'cessedwasteisdonebyclosed-circuitTVmonitoringfromthewastehandlingcontrolpanel.11.4.4PackagingFillingofcontainersandstorageofradioactivesolidwastesconformswith10CFR20and10CFR50requirements.Packagesmeetshippingregulationsof49CFR171-178and10CFR71,asapplicable.ThewastepackagingprocedureisdescribedinSection11.4.3.Containersusedare50-to200-cuftliners,55-galdrums,andmetalboxeswithsupplementaryleadorsteelshieldingasrequiredforshipment.11.4.5StorageFacilitiesAlimitedaccessstorageareaisprovidedforstorageofdry,low-levelwastepackagedbythecompactor.Thestoragecapacityofcompactedwasteintheradwastebuildingisapproximatelya3-monthoutputofpackagedtrashatexpectedgenerationrates.Solidifiedwasteisstoredinashieldedareawithintheradwastebuildinginlinersranginginsizefrom50to200cuft.Thestoragecapacityofprocessedwasteisapproximatelya4-monthoutputofpackagedwasteatexpectedgenerationrates.=11.4.6ShipmentShipmentofradioactive'olid.wastesconformswith10CFR50,10CFR61g10CFR71fand49CFR171through49CFR178requirements.USARRevision6April1994 NineMilePointUnit2FSARHigher-activitywastesareshippedinshieldedcasks,as.applicable.Solidwasteistransportedbyalicenseddisposalcontractororacommoncarriertoalicensedburialsite.Tables11.4-1and11.4-2summarizetheannualnumberofpackagedcontainers,expectednumberofshipmentstobemade,andexpectedanddesignactivitiesofthewastes.USARRevision6April1994 NineMilePointUnit2FSAR11.4.7References2.3.4~Phillips,J.,Feizollahi~FgMartineitiRgandBell,W.WasteReportforReactorandFuel-FabricationFacilityWastes,ONWI-20/NUS-3314,NUSCorporation,March1979.RadwasteVolumeReductionandSolidificationSystem-TopicalReport,ReportNumberWPC-VRS-001,Revision1,WernerandPfleidererCorporation,May1978.TopicalReport,10CFR61,WasteFormConformanceProgramforSolidifiedProcessWasteProductsbyaWastechemCorporationVolumeReductionandSolidification(VRS)System,ReportNo.VRS-002'evision1,August1987.TopicalReport,RDS-1000RadioactiveWasteDewateringSystem,ReportNo.RDS-25506-01-P/NP,Revision1,ChemNuclearSystems,Inc.USARRevision611.4-9April1994 III NineMilePointUnit2FSARTABLE11.4-2EXPECTEDANDDESIGNWETSOLIDWASTEACTIVITIESSourceofWetWastesSpentresin(radwastedemin-eralizer,conden-satedemineralizer)Filtersludges1.Radwastefilter2.FloordrainfilterEvaporatorbottoms(radwasteandregenerative)uCzcc58.621.585.4635.50EectedCxft1.660.050.161.00TotalActivity2.Olx10~43.42598.958.18x10~l~lCxcc497.962.609.18293.02DesiCxft14.100.070.268.30TotalActivitycir6.20x104I133.471,884.601.22xlO~USARRevision0lof1April1989

NineMilePointUnit2FSARTABLE11.4-4SOLIDWASTEMANAGEMENTSYSTEMMAJOREQUIPMENTLISTComonentParameterWastesludgetank2WSS-TK8NumberCapacity,galMaterialofconstructionAsphaltstoragetank2WSS-TK2NumberCapacity,galMaterialofconstruction11,355Type316Lstainlesssteel110,800CarbonsteelExtruder/evaporator2WSS-EV25NumberCapacity,gpmMaterialofconstructionAsphaltmeteringpump2WSS-P5A&BNumberCapacity,gpmMaterialofconstruction1Varies(-1.0)Mfgstandard20.3CastironAsphaltrecircpump2WSS-P3A&BNumberCapacity,gpmMaterialofconstruction220CastironWastesludgetransferpump2WSS-P50A&BNumber2~Capacity,gpm50MaterialofconstructionHighchromeironWastesludgemeteringpump2WSS-P12A&BNumber2Capacity,gpm0.2-0.8MaterialofconstructionType316stainlesssteelDecantpump2WSS-P10NumberCapacity,gpmMaterialofconstruction140Type316stainlesssteelWasteconcentratetransferpump2WSS-P6Number1Capacity,gpm50Materialofcons'tructionAlloy20USARRevision61of2April1994 NineMilePointUnit2FSART2Q3LE11.4-4(Cont'd.)ComonentParameterWasteconcentratemeteringpump2WSS-P7AGBNumber2Capacity,gpm0.4-0.8Materialofconstruction316TIstainlesssteelSteamdomeboilouttank2WSS-TK46Number1Capacity,gal3MaterialofconstructionType304stainlesssteelOverheadcrane2MHN-CRN1NumberCapacity-mainhoistauxiliaryhoist130tons8-1/2tonsUSARRevision62of2April1994 NineMilePointUnit2FSARTABLE11.4-5EXPECTEDDRYSOLIDRADNASTEANNUALNUCLIDEINVENTORIES~ZsotoeCr-51Mn-54Fe-59Co-58Co-60Zn-65Zr-95Nb-95Cs-134Cs-137ComactibleCi5.3-01*4.3-015.1-021.4-011.9+007.5-011.3-024.5-026.5-011.2+00NoncomactibleCi4.0+013.3+013.9+001.1+011.4+025.7+019.6-013.4+005.0+018.9+01Total5.6+004.3+02*5.3-01is5.3x10iUSARRevision61of1April1994 II NineMilePointUnit2FSARTABLE11.4-6MAXIMUMDRYSOLIDRADNASTEANNUALNUCLIDEINVENTORIES~Isoto8Cr-51Mn-54Fe-59Co-58Co-60Zn-65Zr-95Nb-95Cs-134Cs-137ComactibleCia8.9-01*7.2-018.6-022.4-013.1+001.3+002.1-027.5-021.1+001.9+00NoncomactibleCi6.7+015.5+016.6+001.8+012.4+029.5+011.6+005.7+008.3+011.5+02Total9.4+007.2+02*8.9-01is8.9x10USARRevision61of1April1994

NineMilePointUnit2FSARTABLE11.4-7PARAMETERSUSEDTOCALCULATEDRYSOLIDRADWASTEINVENTORIESANDANNUALCURIECONTENTAverageplantwasteactivityforBWRs(fortrash)'~>Net(expected)electricaloutputforUnit2Volumeofdrysolidradwaste(design)forUnit2Volumeofdrysolidradwaste(expected)forUnit2CompactibleNoncompactible5.20-03Ci/MW(e)-yr3.97-01Ci/MW(e)-yr1,080MW(e)17105410,234ftPhillips,J.,Feizollahi,F.,Martineit,R.,andBell,W.,WasteReportforReactorandFuel-FabricationFacilityWastes,ONWI-20/NUS-3314,NUSCorporation,March1979(Table4.2-49andp.4-88).USARRevision61of1April1994 II NineMilePointUnit2FSARguidelinesestablishedinANSI13.10.CalibrationstandardsandfrequencyaredescribedinSection11.5.2.3.2.Thequalityassurance(QA)criteriaisconsistentwiththefunctionofthemonitor.Safety-relatedmonitorsareprocuredanddesignedto10CFR50AppendixBcriteria.Nonsafety-relatedmonitorsaredesignedandprocuredunderstandardsthatmeetthecriteriaestablishedinRG1.143.11.5.2.3.1InspectionandTestsInspectionandtestingofthemonitorsspecifiedinSection11.5.2.3isdescribedintheTechnicalSpecificationsandStationprocedures.11.5.2.3.2CalibrationTheradiationmonitor'scalibrationistraceabletotheNationalBureauofStandardsandisaccuratetoatleast%15percent.Thesource-detectorgeometryduringinitialcalibrationisidenticaltothesample-detectorgeometryinactualuse.Secondarystandardsthatwerecountedinareproduciblegeometryduringtheinitialcalibrationareusedforcalibrationafterinstallation.Whereapplicable,eachmonitoriscalibratedinaccordancewiththefrecgxenciesprovidedintheplantTechnicalSpecificationsduringplantoperationorduringtherefuelingoutageifthedetectorisnotreadilyaccessible.11.5.2.3.3MaintenanceThechanneldetector,electronics,andrecorderareservicedandmaintainedinaccordancewithmanufacturers'ecommendationstoensurereliableoperations.Suchmaintenanceincludescleaning,lubrication,andassuranceoffreemovementoftherecorderinadditiontothereplacementoradjustmentofanycomponentsrecpxiredafterperformingatestorcalibrationcheck.Ifanyworkisperformedthatwouldaffectthecalibration,arecalibrationisperformedatthecompletionofthework.11.5.2.4SamplingSection9.3.2discussesvariousprocessandeffluentsamplesperiodicallytakenforchemicalandradiochemicalanalysis.Liquidprocessandeffluentsamplesareperiodicallytakenandmonitoredforradioactivity.ThoseprovisionsforsamplingnotcoveredinSection9.3.2aredescribedintheindividualsystemdesignsections.Samplingofthesefluidsystemsisvialocalsamplingconnections.TheTechnicalSpecificationsdesex;ibevariouslicgxidsamplesandtheanalysisrequired,includingthesamplingfrequencies.Additionally,theprocessandeffluentradiologicalmonitoringsystemcanprovidegrabsamplesthat,areusedtolocatemanuallyUSARRevision611.5-11April1994

'NineMilePointUnit2FSARaspecificsourceofhighradioactivitywhenacontinuousradiologicalmonitorsignalsahighradioactivityalarminthemaincontrolroom.Tritiumintheplantareasisdeterminedonthebasisofrepresentativegrabsamplescollectedfromtheeffluentpointsorventilationexhaustducts.GrabsamplesareobtainedfromlocationsindicatedinTable.11.5-2.SamplesareanalyzedintheHealthPhysicslaboratory,orbycontractedlaboratories.11.5.3EffluentMonitoringandSampling,Allpotentially-radioactivegaseousandliquideffluentdischargepathsareeithercontinuouslymonitoredorroutinelysampledforradiationlevelduringdischarge(Section11.5.2).Solidwasteshippingcontainersaremonitoredwithgamma-sensitiveportablesurveyinstruments.Thefollowinggaseouseffluentpathsaresampledandmonitored:1.Plantmainstackexhaust.2.Combinedradwaste/reactorbuildingventilationexhaust.Thefollowinglipoideffluentpathsaresampledandmonitored:1.LWSeffluent.2.CWScoolingtowerblowdownline.3.SWPdischarge.AllmonitorrangesarelistedinTable11.5-1.Anisotopicanalysisisperformedperiodicallyonsamplesobtainedfromeachliquideffluentreleasepathtoverifytheadequacyofeffluentprocessingtomeetthedischargelimitstounrestrictedareas.Thiseffluentmonitoringandsamplingprogramiscomprehensiveandprovidestheinformationfortheeffluentmeasuringandreportingprogramsrecpxiredby10CFR50Section36a,AppendixA,GDC64,andAppendixIandRG1.21insemiannualreportstotheNRC.ThefrequencyoftheperiodicsamplingandanalysisdescribedintheTechnicalSpecificationsisaminimumandisincreasedifeffluentlevelsapproachTechnicalSpecificationlimits.Isotopiccontentofgaseouseffluentsiscontinuouslymonitoredbyoff-linemonitors.Allpotentially-significantradioactivedischargepathsareequippedwithacontrolsystemtoisolatethedischargeautomaticallyonindicationofahighradiationlevel.Theseinclude:1.Offgaspretreatment.2.SGTSdischarge(isolatescontainmentpurgesystem).USARRevision611.5-12April1994 NineMilePointUnit2FSAR3..Reactorbuildingventilationexhaust.4~Liquidradwasteeffluent.TheeffluentisolationfunctionsforeachmonitoraregiveninTable11.5-1andinSection11.5.2.Radiationlevelsinradioactiveandpotentially-radioactiveprocessstreamsaremonitoredbytheprocessandeffluentmonitorsgiveninTable11.5-1.Airborneradioactivityinthefuel-handlingareaandtheradwastebuildingisdetectedbyCAMandarearadiationmonitors.AirborneradioactivityinthedrywellisdetectedbythedrywellatmospheremonitorsandtheSGTSdischargemonitorwhichisolatesthecontainmentpurgeonhighradioactivity.ThesemonitorsarealsodescribedinSection12.3.4sincetheyareusedtomonitorin-plantairborneradioactivitytoprotectplantpersonnel.TheareaRMSisalsodescribedinSection12.3.4.Asystemlevel/qualitative-typefailuremodesandeffectsanalysis(FMEA)oftheMSLradiationmonitoring'isprovidedinAppendix15A.TheFMEAforothersafety-relatedradiationmonitorsisprovidedintheFMEA.Report.USARRevision611.5-13April1994

NineMilePointUnit2FSARTABLE11.5-2GRABSAHPLESFORRADIOLOGICALANALYSISSamlePointLocationNo.ReacorSteamSuISstemReactorrecirculationsystempumpdischargeHainsteamlineReactorWaterCleanuSstemCommonfiIter/demineraIizerinfluentIndividualfilter/demineralizeroffluents(4)FuelPoolCoolinandCleanuSstemPumpdischargeCommonfilterinfluentIndividualfiltereffluents(2)Individualheatexchangereff'luents(2)ReactorBuiIdinClosedLooCooIinWaterCoolingwatersample(outletofRWCUandSFCheatexchangers)TurbineBuildinClosedLooCoolinWaterCoolingwatersample(commonoutletofradwastesystemexchangers)ResidualHeaRemovalSstemIndividualheatexchangeroutlet(servicewater)(2)Individualheatexchangeroutlet(RHR)(2)ControlRodDriveSsemCommonCRDfiItereffluentHIh-PressureCoreSraSsemTestreturnlinetocondensatestoragetankGrabSampleatSamleStaionXXXXXXXXLocaIGrab~SamleGrabSampleatRadiaionMonitorXX1of4

NineMilePointUnit2FSARTABLE11.5-2(Cont)SamlePoinLocationNoRadwasteSsemIndividualwastecollectortankpumpeffluents(3)Individualdemineralizereffluents(2)FiltratepumpeffluentIndividualfiltereffluents(2)Demineralizer(acidinfluent)Demineralizer(causticinfluent)Individualrecoverysamplepumpeffluents(2)Individualfloordraincollectorpumpeffluents(2)FloordrainfiltereffluentpumpdischargeLiquidradwastefinaldischargeRegenerantwastepumpeffluents(2)RegenerantrecircuIationpumpsuctionanddischarge(2)PhaseseparatortankpumpdischargeWasteevaporatorrecircuIationpumpsuctionanddischarge(2)WasteevaporatordistillateIndividuaIwastesamplepumps,discharge(2)RegenerantevaporatordistiIlateCommondischargefloordraincollectorsurgepumpsCommondischargewastecollectorsurgepumpsIndividuaIradwasteauxiliarysteamcoolereffluents(2)WaerTreatinSstemDiluteacideffluentDilutecausticeffluentWastewatereffluentCondensaeDemineralizerSsemCommondemineraIizerinfluentCommondemineralizereffluentResinholdtankeffluentIndividualdemineralizerseffluent(9)UltrasonicresincleanereffluentResinmixtankeffluentCationregenerationtankeffluentGrabSampleatSamleStationXXXXXXXXXXXXXXXXXXXX2of4LocalGrab~samleXXXXXXGrabSampleatRadiaionHonlor

NineMilePointUnit2FSARTABLE11.5-2(Cont)SamlePointLocationNo.AnionregenerationtankeffluentRecoveredacidtankeffluentRegenerationsystemeffluentUltrasonicresincleanerresinreceivertankeffluentUltrasonicresincleanerresineffluentLowconductivitywastetankeffluentDemineralizerwasteneutralixingtankeffluentDiluteacideffluentRecoveredcaustictankeffluentDilutecausticeffluentRecoveredwatersumpeffluentCondensateMakeuandDrawoffSstemGrabSampleatSamleStationXXXXXLocalGrab~saleXXXXGrabSampleatRadiationMonitorCondensatetransferlineMakeuWaterSstemDemineralizerwatertransferlineCondensateSstemCondensatepumpdischargeCondenserhotwells(6)LPheaterdrains(3)CommoneffluentfourthpointheatersLPheaterstringcommoneffluentReactorFeedwaterSstemFeedwater(afterlastheater)CirculatinWaterSstemEffluent(blowdownline)AuxiliarSteamSstemAuxiliaryboiler(steamoutlet)Feedwater(pumpdischarge)Auxiliaryboiler(blowdown)Auxiliaryboilerrecircpumpsealheatex-changeroutletandsamplecoolerdischarge(ServiceWater)(4)USARRevision03of4April1989 II NineMilePointUnit2FSARTABLE11.5-2(Cont)SamlePoinLocaionNo.SeaIinSteamSstemIndividualcleansteamreboileroutletsReacorBuildinentilationSstemGrabSampleatSamleSaionLocaIGrab~SamleGrabSampleatRadiationMoniorReactor/radwastebuildingventilationexhaustMainplantstackexhaustContainmentatmosphereContainmentpurgeStandbGasTreatmentSstemSGTSeffluentConrolBuildinVentilationSstemHaincontrolroomintakesRadwasteBuildinVentilationSstemVentilationexhaustRadwastetankventsTurbineBuildinVentilationSsemVentilationMechanicalvacuumpumpdischargeOff-gaspretreatment(2)TurbineglandsealdischargeServiceWaerSstemFinaIdischargeStorm,UnderdrainWater,andSieSewaeSsemsFinaldIschargeXXXXXXXXXXXNOTE:SeeSection9.3.2fordetailsregardingthereactor,turbine,andradwastesamplesystems.4of4

.NineMilePointUnit.2FSARAPPENDIX11ARADIOLOGICALDOSESTABLEOFCONTENTSSectionllA.lllA.2TitleSUMMARYOFANNUALRADIATIONDOSESCOST-BENEFITANALYSISPacaellA.l-lllA.2-1LISTOFTABLESTableTitlellA.1-1llA.1-211A.1-311A.1-411A.1-5ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMLIQUIDEFFLUENTSANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMLIQUIDEFFLUENTSANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHILDGROUPFROMLIQUIDEFFLUENTSANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMLIQUIDEFFIUENTSANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMGASEOUSEFFLUENTSAtMaximumResidenceLocationllA.1-611A.1-711A.1-8ANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMGASEOUSEFFIUENTSAtMaximumResidenceLocationANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHILDGROUPFROMGASEOUSEFFLUENTSAtMaximumResidenceLocationANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMGASEOUSEFFLUENTSAtMaximumResidenceLocation11A.1-9ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMGASEOUSEFFLUENTSAtMaximumCowLocation NineMile-PointUnit2FSARAPPENDIX11ALISTOFTABLES(Cont)TableTitle11A.1-10llA.1-11llA.1-12llA.1-13llA.1-1411A.1-15ANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMGASEOUSEFFIUENTSAtMaximumCowLocationANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHILDGROUPFROMGASEOUSEFFLUENTSAtMaximumCowLocationANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMGASEOUSEFFLUENTSAtMaximumCowLocationANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMGASEOUSEFFLUENTSAtMaximumBeefAnimalLocationANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMGASEOUSEFFLUENTSAtMaximumBeefAnimalLocation,ANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHIIDGROUPFROMGASEOUSEFFLUENTSAtMaximumBeefAnimalLocationllA.1-16llA.1-17llA.1-18llA.1-1911A.2-111'-2ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMGASEOUSEFFLUENTSAtMaximumBeefAnimalLocationCOMPARISONOFMAXIMUMCALCULATEDDOSESFROMUNIT2WITHAPPENDIXIDESIGNOBJECTIVECALCULATEDANNUALDOSESFORPOPULATIONWITHIN80-KM(SO-MI)RADIUSCALCULATEDPOPULATIONDOSECOMMITMENTBASECASEANNUALPOPULATIONDOSESDUETOLIQUIDEFFLUENTSBASECASEANNUALPOPULATIONDOSESDUETOGASEOUSEFFLUENTS NineMilePointUnit2FSARAPPENDIX11ARADIOLOGICALDOSES11A.lSUMMARYOFANNUALRADIATIONDOSESThecalculatedannualradiationdosestomaximumindividualsfromnormaloperationofUnit2arepresentedinTables11A.1-1throughllA.1-16.Table11A.1-17demonstratestha'tthecalculatedannualradiationdosesarebelowthedesignobjectivesof10CFR50,AppendixI.InprovidingguidancefortheimplementationofAppendixI,theNRChasmadeuseofthemaximumexposedindividualapproach.Maximumindividualsarecharacterizedasmaximumwithregardtofoodconsumption,occupancy,andotherusageoftheregioninthevicinityoftheplant'iteand,assuch,representindividualswithreasonabledeviationsfromtheaverageindividualconsideredrepresentativeofthepopulationingeneral.Forgaseousradioactivereleasestheanalyzedpathwaysincluded:standingoncontaminatedground,ingestionofvegetation,andinhalationofandsubmersion'ingaseouseffluents.Thesepathwayswereconsideredforalloftheresidentlocations.Residentlocationshavingcows,goats,andmeatanimalswerealsoanalyzedforingestionofcowmilk,goatmilk,andbeefmeat,respectively.Additionally,thedoses.associatedwithingestionofdeerwereconservativelyaddedtoallresidentlocationsanalyzed.Thecalculatedorgandoseduetoradioiodinesandparticulatesis1.7mRem/yr.Thisrepresentsthedosetothethyroidofaninfantlivingattheresidencelocation2,350meast-southeastofthesite.Themajorityofthisdosewasduetoconsumptionofcowmilk.Thehighestcalculatedexternalexposureratestothewholebodyandskinfromimmersioninnoblegasesatanoccupiedlocationwere0.03and0.06mRem/yr,respectively.Theseoccurredattheresidencelocation1,693meastofthesite.Thehighestcalculatedbetaandgammaairdosesatanunoccupiedlocationfromnoblegasreleaseswere0.04and0.06mrad/yr,respectively.Theseoccurredattheexclusionareaboundary(EAB)1,603meastofthesite.Forliquidreleases,themaximumindividualconsumedfishwhoseprincipalhabitatwasassumedtobetheedgeoftheinitialmixingzone.Thislocationwasalsoconservativelyusedincalculatingdosesfromswimmingandboating.

NineMilePointUnit2FSARThecalculatedannualdosestothepopulationresidingwithinan80-kmradiusofthesitearepresentedinTablellA.1-18.Populationdoseswerecalculatedforaprojectedpopulationof1.2millionresidingwithin80kmofthesiteintheyear2010.Gaseouspathwaysconsideredinthepopulationdoseanalysisincluded:inhalation,exposuretogrounddeposits,ingestionofvegetation,cowmilk,andbeefmeat,andsubmersioninnoblegases.Thecalculatedannualdosetothepopulationwas0.6man-Rem/yrwholebodyand3.3man-Rem/yrthyroid.Liquidpathwaysconsideredinthepopulationdoseanalysisincluded:ingestionofpotablewaterandfish,shorelinerecreation,andswimmingandboating.Thecalculatedannualdosetothepopulationwas1.4man-Rem/yrwholebodyand0.06man-Rem/yrthyroid.Inadditiontothe80-km(50-mi)radiuspopulationdoses,populationdosesassociatedwiththeexportoffoodcropsproducedwithinthe80-km(50-mi)regionandtheatmosphericandhydrospherictransportofthemoremobileeffluentspecies,suchasnoblegases,tritium,andcarbon-14,werecalculated.ThesecalculatedannualgaseousandliquiddosestothecontiguousU.S.populationarepresentedinTable11A.1-19.Forliquideffluents,thecalculateddosestothecontiguous!U.S.populationwere1.4man-Rem/yrwholebodyand0.06man-Rem/yrthryoid.Forgaseouseffluents,thecalculateddosestothecontiguousU.S.populationwere21.1man-Rem/yrwholebodyand24.9man-Rem/yrthyroid.USARRevision0April1989 NineMilePointUnit2FSARTABLEllA.1-1ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMLIQUIDEFFLUENTS(AnnualDoseinmRem/yr)P~athwaPotablewaterPishconsumptionShorelinerecreationFreshvegetationStoredvegetationDuckconsumptionSw'immingexposureBoatingexposureTotaldoseTotal~Bod3.5E-045.8E-012.3E-055.9E-OS4.1E"041.3E-043.3E-053.3E"05S.SE-01Skin0.00.02.6E-050.00.00.04.2E-OS4.2E-OS1.1E-04BoneLiver1.7E-044.1E-047eOE-018.2E-012.3E-OS2.3E-05~lhroid2.9E-043.6E-032.3E-OS~aidwe2.6E-042.7E-012.3E-OS4.4E-053.0E-042.1E-037.5E-OS5.2E-042.2E-042.6E-OS3,6E-OS1.1E-042.5E-041.4E-064.7E-053.3E-OS3.3E-057~OE-Ol8.2E-Ol3.3E-OS4.1E-033.3E-053.3E-OS2.7E-013.3E-053.3E-05.3.3E-OS~Lun2.1E-048.9E-022.3E-OS2.2E-051.6E-046.4E-063.3E-OS3.3E-058.9E-02GITract2.0E-.044.3E-022.3E-OS2.0E-051.4E-042.9E-043.3E-OS3.3E-054.4E-02NOTE:3.5E-04=3.5xlOUSARRevision01of1April1989

NineMilePointUnit2FSARTABLE11A.1-2ANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMLIQUIDEFFLUENTS(AnnualDoseinmRem/yr)p~aaaaaPotablewaterFishconsumptionShorelinerecreationFreshvegetationStoredvegetationDuckconsumptionSwimmingexposureBoatingexposureTotaldoseTotal~Bod2.2E"043.3E-011.38-043.28-054.4E-041.08-043.38-053.3E-OS3.38-01Skin0.00.01.5E-040.00.00.04.2E-054.2E-OS2.3E-04BoneLiver1.6E-043.5E-047.6E-018.4E-011.3E-041.3E-043.9E-OS6.3E-OS5.38-048.7E-041.88-031.8E"043.3E-OS3.38-053.3E-053.3E-057.68-018.48-01a~aaad2.2E-043.38-031.3E-041.8E-OS1.5E-049.9E-073.3E-OS3.3E-OS3.9E-03~Kidne3.2E-042.88-011.3E-045.1E-OS5.6E-043.0E-043.3E-053.3E-052.8E-01~Lun1.6E-041.1E-011.38-041.7E-052.4E-046.0E-063.3E-OS3.38-051.1E-01GITract1.4E-043.3E-021.38-041.38-051.8E-041.8E-043.3E-OS3.3E-OS3.48-02NOTE:2.2-04=2.2x10USARRevision01of1April1989 Et>Iftl

-INineMilePointUnit2FSARTABLE11A.1-3ANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHILDGROUPFROMLIQUIDEFFLUENTS(AnnualDoseinmRem/yr)P~athwaPotablewaterFishconsumptionShorelinerecreationFreshvegetationStoredvegetationDuckconsumptionSwimmingexposureBoatingexposureTotaldoseTotal~BodSkin3.3E-040.01.4E-010~02.6E-053.1E-OS2.5E-OS0.04.7E-040.01.6E-040.01.8E-052.4E-OS1.9E-OS2.4E-051.4E-017.9E-05Bone4.6E-049.5E-012.6E-OS6.8E-051.3E-033.4E-031.8E-OS1.9E-OS9.6E-01Liver6'E-047.5E-012.6E-057.9E-051.5E-032.5E-041.8E-051.9E-057.5E-01K~hroid4.7E-043.3E-032.6E-052.4E-052.4E-041.5E-061.8E-051.9E-054.1E-03~Kadra3.9E-042.4E-012.6E-053.4E-OS6.3E-044.2E-051.8E-051.9E-052.4E-01~Lun3.0E-048.5E-022.6E-OS2.0E-053.8E-047.1E-061.8E-051.9E-058.6E-02GITract2.5E-041.4E-022.6E-051.4E-OS2.6E-041.1E-041.8E-051.9E-051.5E-02NOTE:3.3E-04=3.3xlO4USARRevision01of1April1989

NineMilePointUnit2FSARTABLEllA.1-4ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMLIQUIDEFFLUENTS(AnnualDoseinmRem/yr)~ParheaPotablewaterTotaldoseTotal~Bod2.9E-042.9E-04Skin0.00.0Bone4.7E-044.7E-04Iiver7.9E-047.9E-04~Throid6.0E-046.0E-04~Kidlle3.9E-043.9E-04~Lun3.0E-043.0E-04'ITract2.5E-042.5E-04NOTE:2.9E-04=2.9xl04USARRevision0lollApril1989

NineMilePointUnit2PSARTABLE11A1-5ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMGASEOUSEPPLUENTS¹AtMaximumResidenceLocation(AnnualDoseinmRemlyr)~aathwaContaminatedgroundInhalationFreshvegetationStoredvegetationDeer1,603meastTotaldoseTotal~Bod7~9-0316-0475-0427-031C4-0412-02SkinBoneLiverT~hraidK~idaa92-037.9-037.9-0379-0316-0424-0413-021'-0311-0313-016.3-0332-0345-031.7-0419-043.2-040.000000092-0316-0213-021.6-017.9-033.0-041.2-0318-0392-051.1-02~Lun7.9-032.8-0421-0411-0331-0595-03GI-Tract79-032.1-0480-041.8-033.3-0411-02*Analysisperformedatmaximumresidencelocationis4,106m(13,471ft)east.NOTE:79-03=79x10-~1of1

NineMilePointUnit2FSARTABLE11A1-6ANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMGASEOUSEFFLUENTS+AtMaximumResidenceLocation(AnnualDoseinmRem/yr)~PathwacontaminatedgroundInhalationFreshvegetationStoredvegetationDeer1,603meastTotaldoseTotalBod~79-031.8-045.4-043.5-0378-0512-02SkinBoneLiverT~hteid~Kidee92-0379-0379-0379-032.2-0429-0417-0216-031.0-0311-011.1-0257-0373-030.00.00.00.01.4-041.5-0424-0492-0321-0215-021.4-0179-033.8-041.1-026.0-027.6-0387-02~Lun7-9-0338-0419-0420-032.7-051.0-02GI-Tract7.9-0323-0458-042.7-0319-0412-02*Analysisperformedatmaximumresidencelocationis4,106m(13,471ft)east.NOTE:79-03=79x10->1of1

NineMilePointUnit2FSARTABLEllA.1-7ANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHILDGROUPFROMGASEOUSEFFLUEHTS*AtMaximumResidenceLocation(AnnualDoseinmRem/yr)P~athaContaminatedgroundInhalationFreshvegetationStoredvegetationDeer1,603meastTotaldoseTotal~Bod7.9-031.8-047.1-045.7-038.6-051.5-02Skin9.2-030.00.00.00.09.2-03Bone7.9-033.0-042.9-032.8-022.5-043.9-02Liver7.9-032.8-041.4-031.1-022.0-042.1-02~lhroid7.9-032.1-021.6-011.5-023.6-042.0-01~Kidne7.9-033.6-041.4-036.2-039.5-051.6-02~Lun7.9-033.3-043.2-044.5-034.0-051.3-02GI<<Tract7.9-031.9-045.3-044.6-031.2-041.3-02*Analysisperformedatmaximumresidencelocationis4,106m(13,471ft)east.NOTE:7.9-03=7.9x10USARRevision01of1April1989

NineMilePointUnit2FSARTABLE11A.1-8ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMGASEOUSEFFLUENTS+AtMaximumResidenceLocation(AnnualDoseinmRem/yr)~PathwaContaminatedgroundInhalationTotaldoseTotal~Bod79-0312-048>>0-03SkinBoneLiverT~hreid~tidee92-0379-0379-0379-0322-0422-0419-020.092-0381-038.1-032.7-0279-0323-048.1-03Luna79-0324-0481-03GI-Tract79-0311-0480-03*Analysisperformedatmaximumresidencelocationis4,106m(13,471ft)east.NOTE:79-03=79x10->1of1

NineMilePointUnit2FSARTABLE11A.1-9ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEADULTGROUPFROMGASEOUSEFFLUENTS+AtMaximumCowLocation(AnnualDoseinmRem/yr)~PatheaContaminatedgroundInhalationFreshvegetationStoredvegetationCowmilkDeer1,603meastTotaldoseTotal~Bod13-0214-047.0-0424-0324-0314-0419-02SkinBoneLiverr~hreid~Kidae16-0213-0213-0213-020011-042.0-049.7-031.3-022.5-04000000004.3-0330-034.1-0330-0337-0322-0117-0419-0432-041.6-0222-0221-0238-011.4-0327-0392-051.9-0213-0311-0313-0111-03L~un13-0227-0413-0469-0445-0431-0515-02GI-Tract3-0219-047.3-041.4-0311-0333-0417-02+Analysisperformedatmaximumcowlocationis2,350m(7,710ft)east-southeast.NOTE:13-02=13x10-<1of1

NineMilePointUnit2FSARTABLE11A1-10ANNUALDOSESTOMAXIMUMINDIVIDUALINTHETEENGROUPFROMGASEOUSEFFLUENTS+AtMaximumCowLocation(AnnualDoseinmRem/yr)~aanhwaContaminatedgroundInhalationFreshvegetationStoredvegetationCowmilkDeer1,603meastTotaldoseTotal~Bod1.3-0215-044.8-0428-0330-037.8-0520-02SkinBoneLiverT~hroidKidney16-021.3-021.3-0213-021.5-042.4-041-3-0212-0395-0411-0177-0352-036.5-035.3-0364-0335-0114-0415-0424-04000000000016-022.7-022.6-0249-0213-0231-0412-0265-0247-0376-0310-01~Lun13-0236-041.2-0413-0385-0427-0516-02GI-Tract1.3-022.1-0451-041.9-031.5-031.9-041.7-02+Analysisperformedatmaximumcowlocationis2,350m(7,710ft)east-southeast.NCTE:13-02=13x10-~1of1

NineMilePointUnit2FSARTABLE11A1-11ANNUALDOSESTOMAXIMUMINDIVIDUALINTHECHILDGROUPFROMGASEOUSEFFLUENTS+AtMaximumCowLocation(AnnualDoseinmRem/yr)~PathwaContaminatedgroundInhalationFreshvegetationStoredvegetationCowmilkDeer1,603meastTotaldoseTotal~Bod1.3-0215-0458-0438-0343-038.6-0522-02SkinBoneLiverT~haid~Kidae16-021.3-0213-0213-021.6-02002.1-0423-040.02.2-0313-0316-011.9-0293-0313-0213-021.1-0271-012.5-042.0-043.6-040.0000.01.6-0248-0235-0291-011.3-022.9-041.3-034.4-0379-039.5-052.7-02~Lun13-0231-0418-0426-0316-030-0518-02GI-Tract1.3-021i7-043.9-042.6-0318-0312-0418-02*Analysisperformedatmaximumcowlocationis2,350m(7,710ft)east-southeast.NOTE::)3-02=13x10->1of1

NineMilePointUnit2FSARTABLE11A1-12ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMGASEOUSEFFLUENTS+AtMaximumCowLocation(AnnualDoseinmRem/yr)~PaaheaContaminatedgroundInhalationCowmilkTotaldoseTotal~Bod1-3-0296-056.6-0320-02SkinBoneLiverr~hroidKidney16-0213-021*3-0213-0215-0418-0415-0223-0222-0217+000.0001.6-023.6-023.5-0217+001.3-0218-0413-0226-02~Lun1.3-022.3-0432-0316-02GI-Tract1.3-0295-054.7-031.8-02*Analysisperformedatmaximumcowlocationis2,350m(7,710ft)east-southeast.NOTE:13-02=1.3x10-~1of1 4l NineNilePointUnit2PSARTABLE11A1-13ANNUALDOSESTONAXINUNINDIVIDUALINTHEADULTGROUPPRONGASEOUSEPFLUENTS+AtNaximumBeefAnimalLocation(AnnualDoseinmRem/yr)P~athaaContaminatedgroundInhalationPreshvegetation.StoredvegetationBeefDeer1,603meastTotaldoseTotalB~od2.4-0223-0416-035.7-039.7-0414-043.2-02SkinBoneLiverPa~raid~aidaa2-8-0224-022.4-0224-02001.3-0431-041-2-0227-032.4-0326-0184-037-4-037.9-0317-0314-031.5-020.0000019-0432-0417-040028-023.7-023.6-0232-0124-023.6-0423-033.1-038-1-049.2-0531-02~Lun2-4-0249-0424-0413-033.2-0431-0526-02GI-Tract2-4-0232-0417-033.0-0344-0333-0433-02+Analysisperformedatmaximumbeefanimallocationis1,693m(5,555ft)east.NOTE:2.4-02=2.4x10-iAmendment251of1Narch1986

NineNilePointUnit2PSARTABLE11A1-14ANNUALDOSESTOHAXIHUHINDIVIDUALINTHETEENGROUPPROHGASEOUSEPPLUENTS+AtHaximumBeefAnimalLocation(AnnualDoseinmRem/yr)PathvayContaminatedgroundInhalationPreshvegetationStoredvegetationBeefDeer1,603aeastTotaldoseTotalB~od2-4-0224-041-1-0363-036..1-047.8-0532-02SkinBoneLiverT~hroid0.018-0436-041.6-020.02.5-032.2-032.1-01Kid~no2-4-0243-0432-0215-0213-021.4-031.1-030.013-021.7-010.01.1-0292-027-6-0332-011.4-040.01.5-0424-0428-0243-024.1-0227-012.8"022.4-022.4-022-4-02Lung2.4-0266-0423-042.4-0326-0427-0528-02GI-Tract2-4-023.4-0412-034.0-032.5-0319-04I-32-02*Analysisperformedatmaximumbeefanimallocationis1,693a(5,555ft)east.NOTE:2.4-02=2.4xl0-~Amendment251of1Harch1986

NineNilePointUnit2FSARTABLE11A1-15ANNUALDOSESTOHAXIHUHINDIVIDUALINTHECHILDGROUPPROMGASEOUSEPPLUENTS<<AtHaxinumBeefAninalLocation(AnnualDoseinmRem/yr)PatgvaIContaminatedgroundInhalationFreshvegetationStoredvegetationBeefDeer1,603meastTotaldoseTotalB~od2-4-022.3-041.2-037..6-037..9-048.6-053.4-02SkinBoneLiverThyroidKid~ne2-8-022.4-022-4-0224-0224-043.4-0420-020.0000.00045-032.8-033.3-013.6-0222-0226-0225-0314-031.7-023,.6-040.02.5-042.0-042.8-026.7-025.1-024.2-012.4-0240-0426-0392-038.8-049.5-0537-02Lung24-025.6-043.1-0444-0344-0440-0530-02GI-Tract24-022-6-047.8-0444-031.6-031,.2-043.1-02<<Analysisperformedatmaximumbeefanimallocationis1,693n(5,555ft)east.NOTE:2.4-02=2.4x10-~Amendment251of1Harch1986

NineMilePointUnit2PSARTABLE11A.1-16ANNUALDOSESTOMAXIMUMINDIVIDUALINTHEINFANTGROUPFROMGASEOUSEFPLUENTS+AtMaximumBeefAnimalLocation(AnnualDoseinmRem/yr)~PatheacontaminatedgroundInhalaticnTotaldoseTotal~Bod2.4-0214-042.4-02SkinBoneLiverTorrid~ridre28-0224-0224-0224-021.8-042.5-041.8-020.028-0224-022.4-024.2-0224-0225-042.4-02Lun~24-024.1-0424-02GI-Tract2.4-021.4-0424-02+AnalysisPerformedatmaximumbeefanimallocationis1P693m(5,555ft)east.NOTE:2.4-02=2.4x10-<1of1

NineMilePointUnit2FSARTABLEllA.1-17COMPARISONOFMAXIMUMCALCULATEDDOSESFROMUNIT2WITHAPPENDIXIDESIGNOBJECTIVESCriterionGaseouseffluentsGammaairdose(2)>mRad/yrBetaairdose(2),mRad/yrNoblegas-totalbody(3),mRem/yrNoblegas-skin(3),mRem/yrAppendixIDesinOb'ective(1102015Unit2CalculatedDose5.8-024.2-022.9-026.1-02Iodinesandparticulates(4)Anyorgan(thyroid),mRem/yr151.7+00LiquideffluentsTotalbody,mRem/yrAnyorgan(5),mRem/yr.3105.8-019.6-01NOTE:5.8-02=5.8xl0(1)Perreactor.(2)Calculatedatexclusionareaboundary1,603m(5,259ft)east.(3)Calculatedat1,693m(5,554ft)east.(4)Infantthyroiddosefromcowmilk2,350m(7,710ft)east-southeast.(5)Childbonedoseiscalculatedtobethehighestorgandose~USARRevision0lof1April1989

NineMilePointUnit2FSARTABLEllA.1-18CALCULATEDANNUALDOSESFORPOPULATIONWITHIN80-KM(50-MI)RADIUSLiuidEffluentsWholeBodyman-RemThyroidman-RemIngestionofpotablewaterIngestionoffishShorelinerecreationSwimmingBoating3.8-021.3+002.2-024.5-052.2-053.4-024.6-032.2-024.5-052.2-05TotalGaseousEffluentsSubmersionInhalationStandingoncontaminatedgroundIngestionoffruits,grains,andvegetationIngestionofcowmilkIngestionofmeat1.4+003.3-011.4-027.3-021.7-014.8-023.8-036.1-023.3-019.9-017.3-021.2+006.8-017.1-03Total6.4-013.3+00NOTES:l.Baseduponaprojected80-km(50-mi)populationof1.2+06fortheyear2010.2.3.8-02=3.8x10'SARRevision01of1April1989

Nine.MilePointUnit2FSARTABLEllA.1-19CALCULATEDPOPULATIONDOSECOMMITMENT(ContiguousU.S.PopulationDose)AnnualDosePerSiteLiquideffluentsNoblegaseffluentsRadioiodinesandparticulates*TotalTotalBodyman-Rem1.4+001.14+001.9+012.1+01Thyroidman-Rem6.1-021.37+002.3+012.5+01NOTE:1.4+00=1.4xl04*Carbon-14andtritiumhavebeenaddedtothiscategory.USARRevision01of1April1989

NineMilePointUnit2FSAR.llA.2COST-BENEFITANALYSISThissectionpresentstheresultsofcost-benefitanalysesperformedinaccordancewithSectionII.Dof10CFR50,AppendixI.Augmentstotheliquidandgaseouseffluentsystemsandrespectivepotentialreductionstotheannual,-populationexposurearetakenfromRegulatoryGuide1.110.Thebeneficialsavingsofeachaugmentwerecalculatedbymultiplyingthecalculateddosereductionby$1,000/man-Remor$1,000/man-Rem/thyroid.AumentstotheLiuidEffluentTreatmentSstemTablellA.2-1presentsthecalculatedbasecaseannualtotalbodydose(man-Rem)andthyroiddose(man-Rem/thyroid)associatedwiththeoperationoftheplantliquidradwastesystemforthepopulationexpectedtolivewithinan80-kmradiusoftheplantfortheyear2010.Assumingthateachaugmentiscapableofreducingthepopulationdosestozero(anextremelyconservativeassumption),themaximumbenefittobederivedfromanyaugmentwouldbe$1,400forreducingman-Remexposurestozeroand$61forreducingman-Rem/thyroidexposurestozero.Inananalysisoftheannualizedprocurement,installation,operation,andmaintenancecosts,theleastexpensiveliquidradwasteaugmentwasfoundtobe$20,000/yrforaplantlocatedinthenortheasternUnitedStates.Sincethebenefitfromthisaugmentwouldbelessthanthecorrespondingtotalannualizedcost,thecost-benefitratioisgreaterthan1.Theoperationofadditionalequipmentforthepurposeofreducingtheannualpopulationdosewouldnotbecosteffective.Therefore,themostcost-beneficialsystemhasbeenincludedinthecurrentplantdesign.AumentstotheGaseousEffluentTreatmentSstemTablellA.2-2presentsthecalculatedbasecaseannualtotalbodydose(man-Rem)andthyroiddoseman-Rem/thyroid:-associatedwiththeoperationofthegaseousradwastesystemforthe80-kmradiuspopulation.Assumingthateachaugmentiscapableofreducingthepopulationdosestozero,themaximumbenefittobederivedfromanyaugmentwouldbe$640forreducingman-Remexposurestozeroand$3,300forreducingman-Rem/thyroidexposurestozero.USARRevision011A.2-1April1989 NineMilePointUnit2FSARInananalysisoftheannualizedprocurement,installation,operation,andmaintenancecosts,theleastexpensivegaseousradwasteaugmentwasfoundtobe$10,580/yrforaplantlocatedinthenortheasternUnitedStates.Sincethebenefitfromthisaugmentwouldbelessthanthecorrespondingtotalannualizedcost,thecost:-benefitratioisgreaterthan1.Theoperationofadditionalequipmentforthe.purposeofreducingtheannualpopulationdosewouldnotbecosteffective.Therefore,themostcostbeneficialsystemhasbeenincludedinthecurrentplantdesign.11A.2-2 NineMilePointUnit2FSARTABLE'11A.2-1BASECASEANNUALPOPULATIONDOSESDUETOLIQUIDEFFLUENTS~PathwaIngestionoffishIngestionofpotablewaterShorelinerecreationSwimmingBoatingTotalTotalBodyDose1.30+003.80-022.20-024.50-052.20-051.40+00ThyroidDose(man-throid-Rem4.60-033.40-022.20-024.50-052.20-056.10-02NOTE:1.30+00=1.30xl04USARRevision0lof1April1989

NineMilePointUnit2FSARTABLEllA.2-2BASECASEANNUALPOPULATIONDOSESDUETOLIQUIDEFFLUENTS~PathwaSubmersionInhalationStandingoncontaminatedgroundIngestionoffruits,grains,andvegetationIngestionofcowmilkIngestionofmeatTotalTotalBodyDose3.3-011.4-027.30-021.70-014'-023'-036.40-01ThyroidDose(man-throid-Rem3.3-019.90-017.30-021.20+006.80-017.10-033.30+00NOTE:3.3-01=3.3x10USARRevision01of1April1989 A

NineMilePointUnit2FSARCHAPTER12RADIATIONPROTECTIONTABLEOFCONTENTSSection12.112.1.112.1.1.112.1.1.212.1.1.312.1.1.412.1.1.512.1.1.612.1.1.712.1.1.812.1.1.912.1.1.1012.1.212.1.2.112.1.2.212.1.2.312.1.2.412.1.2.512.1.312.1.3.112.1.3.212.212.2.112.2.1.112.2.1.212.2.1.2.112.2.1.2.2TitleENSURINGTHATOCCUPATIONALRADIATIONEXPOSURESAREASLOWASREASONABLY'CHIEVABLEPolicyConsiderationsManagementAuditandReviewResponsibilitiesAuthoritytoPreventUnsafePracticesModificationstoOperating,Surveillance,andMaintenanceProceduresand,StationEquipmentVigilance-bytheRadiationProtectionStaffManagerRadiationProtectionSupervisorRadiationProtectionOperationsSupervisorInstrumentCalibrationSupervisorALARSupervisorInternalandExternalDosimetryDesignConsiderationsGeneralDesignConsiderationsforALAR%ExposuresEquipmentGeneralDesignConsiderationsforAL3~PlantLayoutGeneralDesignConsiderationsforAL2QQ.DecommissioningDesignConsiderationsforALARAExamplesofALARAImprovementsOperationalConsiderationsOperationalObjectivesImplementationofProceduresandTechniquesRADIATIONSOURCESContainedSourcesGeneralPrimaryContainment(Drywell)ReactorVesselSourcesRadioactiveSourcesintheReactorWater,Steam,andOffgasPacee12~1112.1-112.1-212.1-612.1-612.1-612.1-612.1-612~1712~1712.1-812.1-812.1-812.1-812.1-912.1-1012.1-1112.1-1112.1-1212.1-1212.1-1312.2-112.2-112.2-112.2-212.2-212.2-3USARRevision7.12iOctober1994 NineMilePointUnit2FSARSection12.2.1-312.2-1.3.112.2.1.3.212.2.1.3.312.2.1.3;412.2.1.3.512.2.1.3.612.2.1.3.712.2.1.3.812.2.1.412.2.1.4.112.2.1.4.212.2.1.4.312.2.1.512.2.1.5.112.2.1.5.212.2.212.2.2.112.2.2.212.2.2.2.112.2.2.2.212.2.2.2.312.2.2-2.412.2.2.2.512.2.2.2.'612.2.2.2.712;2.2.2-812.2.2.3CHAPTER12TABLEOFCONTENTS(Cont)TitleReactorBuildingReactorMaterCleanup{RNCU)SystemSourcesMainSteamSystemSourcesResidualHeatRemoval(RHR)SystemSourcesReactor'oreIsolationCooling(RCIC)SystemSourcesFuelPoolCoolingandCleanup(SFC)SystemSourcesLiquidRadwasteSystemSources(ReactorBuilding)StartupSourcesTraversingIncorePrabe(TIP)SystemSourcesTurbineBuildingTurbineSystemSourcesCondensate.andFeedwaterSystemSourcesOff-GasSystemSourcesRadwasteBuildingLiquidRadwasteSystemSources(RadwasteBuilding)SolidRadwasteSystemSourcesAirborneRadioactiveMaterial.SourcesMethodfarComputingtheAirborneRadionuclideCancentrationinaPlantAreaProductionofAirborneRadiaactiveMaterialSources.EffectofLeakagefromProcessEquipmentinRadioactive'SystemsEffe'ctafSumps,Drains,andTanksEffectofReliefValveExhaustEffectonRemovingRPVHeadandAssociatedInternalsEffectofSamplingEffectofSpentFuelMovementEffectafSolidRadwasteHandlingAreasEffectofLiquidRadwasteHandlingAreasReferencesPacCe12~2312~2~312.2-312.2-312.2-412.2-412.2-512.2-512.2-512.2-612.2-612.2-612.2-612~2712.2<<712.2-712~2712.2-812.2-912.2-1012.2-1112.2-1112.2-1312.2-1412.2-1412.2-1412.2-1412.2<<16Amendment,2412-iiFebruary1986 NineMilePointUnit2FSARCHAPTER12TM3LEOFCONTENTS(Cont'd.)Section12.312.3.1.1.212.3.1.212.3.1.312.3.212.3.2.112:3.2.1.112.3.2.1.2.2.2.1.2.212.3.212.3.212.3.212.3.212.3.212.3.312.3.312.3.312.3.312.3.312.3.4.2.3.3.2.3.412.3.4.112.3.4.1.1,12.3.4.1.212.3.4.1.312.3.4.1.412.3.4.1.512.3.4.212.3.4.2.112.3.4.2.212.3.4.2.3,123112.3.1.1'2.3.1.1.1TitleRADIATIONPROTECTIONDESIGNFEATURESFacilityDesignFeaturesPlantDesignDescriptionCommonEquipmentandComponent,DesignsCommonFacilityandLayoutDesignsRadiationZoningandAccessControlPostaccidentAccessandShieldDesignReviewShieldingDesignObjectivesRadiationExposureofIndividualsRadiation.ExposureofMaterialsandComponentsDesignDescriptionGeneralDesignGuidesShieldingMaterialsPlantShieldingDescriptionMethodofShieldingDesignVentilationDesignObjectivesDesignGuidelinesDesignDescriptionsAirCleaningSystemDescriptionAreaRadiationandAirborneRadioactivityMonitoringInstrumentationAreaRadiationMonitoringObjectivesAreaRadiationMonitoringSystemDesignCriteriaCriteriaforLocationofAreaMonitors.SystemDescription(AreaRadiationMonitoring)SafetyEvaluationCalibrationandTestingAirborneRadioactivityMonitoringObjectivesAirborneRadioactivityMonitoringSystemDesignCriteriaCriteriaforAirborneRadioactivityMonitorLocationsSystemDescription(AirborneRadioactivityMonitors)Pacae12.3-112~3112.3-112~3112.3-5:12.3-812.3-1112.3-1512.3-1512.3-1512.3-1612.3-1612.3-1612~31712.3-1712.3-1912.3-1912.3-1912.3-2012.3-2212.3-2212.3-2412.3-2412.3-2412.3-2512.3-2612.3-2612~32712~32712.3-2812.3-2912.3-30USARRevision7.12-iiiOctober1994 NineMilePointUnit2FSARCHAPTER12TABLEOFCONTENTS(Cont'd.)Section12.3.4.2.412.3.4.2.512.3.4.312.3.4.412.3.5TitleSafetyEvaluationSensitivitiesandRangesAccidentConsiderationPortableMonitorsReferencePacae12~33212.33212.3-3312.3-3412.3-3412.412.4.112.4.212."4.2.112.4.2.212';4.312.4.3.112.4.3.212'.3.312.4.3.412.4.412.4.5DOSEASSESSMENTDesignCriteriaExposuresWithin.thePlant-Man-RemEvaluationEstimatesofInhalationThyroidDoses'.Exposuresat.LocationsOutsidethePlantStructuresN-16DoseContributionsDoseContributionsDuetotheLoadingofSolidWasteLinersDoseContributionsfromUnit1andtheJAFPlantExposuresDuetoAirborneActivityEstimateofDosestoConstructionWorkersReferences12.4-112.4-112.4-112.4-112.4-1c12.4-1c12.4-212.4-212.4-2a12.4-312.4-312.4-312.512.5.112.5.1.112.5.1.212.5.212.5.2.112.5.2.1.112.5.2.1.212.5.2.1.312.5.2'.412.5.2.1.512.5.2.1.612.5.2.1.712.5.2.1.8RADIATIONPROTECTIONPROGRAMOrganizationProgramObjectivesPersonnelExperienceandQualificationsEquipment,Instrumentation,andFacilitiesLocationofEquipment,Instrumentation,andFacilitiesRadiationProtectionOfficeCountingRoomChemistryandRadiochemistryLaboratoryPersonnelDecontaminationFacilityLockerRoomsandToiletFacilitiesLaundryFacilitiesInstrumentStorageInstrumentCalibrationandRepairFacility12.5-112.5-112.5-112.5-112.5-112.5-112.5-112.5-112.5-212.5-212.5-212.5-212.5-212.5-2USARRevision7.12-ivOctober1994 NineMilePointUnit2FSARCHAPTER12TABLEOFCONTENTS(Cont'd.)Section12.5.2.1.912.5.2.1.1012.5.2.212.5.2.2.112.5.2.2.212.5.2.2.3TitleRespiratoryEquipmentRepair,Assembly,andTestingPersonnelMonitoringStationsRadiationProtectionInstrumentationCountingRoomInstrumentationPortableSurveyInstrumentationPersonnelMonitoringInstrumentationPacae12.5-212.5-312.5-312.5-312.5-312.5-4USARRevision7.12-ivaOctober1994 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKAmendment1212-ivbJune1984 NineMilePointUnit2FSARCHAPTER12TABLEOFCONTENTS(Cont'd.)Section12.5.2.2.412.5.312.5.3.112.5.3.212.5.3.2.112.5.3.2.212.5.3.2.312.5.3.2.412.5.3.2.512.5.3.2.612.5.3.2.712.5.3.2.812.5.3.312.5.3.3.112.5.3.3.212.5.3.3.312.5.3.3.412.5.3.3.512.5.3.3.612.5.3.3.712.5.3.412.5.3.512.5.3.612.5.3.7.12.5.3.8TitleRadiationProtectionEquipmentProceduresRadiationandContaminationSurveys,ProceduresandMethodstoMaintainExposuresALtQQ.RefuelingIn-serviceInspectionRadwasteHandlingSpentFuelHandling,Loading,andShippingNormalOperationRoutineandNonroutineMaintenance(Repair)SamplingCalibrationControlofPersonnelRadiationExposureAccessControlContaminationControlPersonnelProtectiveEquipmentRespiratoryProtectionBioassayandWhole-BodyCountingPostoperationReviewPersonnelDosimetryControllingPotentialAirborneRadioactivityConcentrationsRadiationWorkPermitRadiationProtectionTrainingProgram.RadioactiveMaterialsSafetyProgramCompliancewithRegulatoryGuidesPacae12.5-412.5-512.5-512.5-612.5-612.5-712.5-712.5-812.5-812.5-912.5-912.5-1012.5-1012.5-1012.5-1112.5-1212.5-1212.5-1312.5-1312.5-1312.5-1412.5-1412.5-1612.5-1712.5-18USARRevision7.12-vOctober1994I NineMilePointUnit2FSARTableNumber12.2-112.2-212.3-312.2-412.2-512.2-612'-712'-812.2-912.2-'012.2-1112.2-1212.2-1312.2-1412.2-15a12.2-15b12.2-1612.3-1CHAPTER12LISTOFTABLESTitleBASICREACTORDATAPOSTOPERATIONGAMMASOURCESINCORERADIATIONLEVELSINSIDEDRYWELLREACTORWATERCLEANUPSYSTEMSOURCESRESIDUALHEATREMOVALSYSTEMPUMPANDHEATEXCHANGERSOURCETERMSREACTORCOREISOLATIONCOOLINGSYSTEMDESIGNACTIVITIESSPENTFUELPOOLCOOLINGANDCLEANUPSYSTEMSOURCEACTIVITIESTRAVERSINGINCOREPROBESYSTEMMATERIALSANDRADIATIONSOURCESAVERAGEN-16ACTIVITIESINEQUIPMENTINTHETURBINEBUILDINGCONDENSATESYSTEMSOURCETERMSOFF-GASSYSTEMSOURCEACTIVITIESLIQUIDRADWASTESYSTEMCOMPONENTSDESIGNACTIVITIESSOLIDRADWASTESYSTEMCOMPONENTSDESIGNACTIVITIESDELETEDEXPECTEDAIRBORNERADIOACTIVITYCONCENTRATIONSATIN-PLANTAREASDURINGNORMALPOWEROPERATIONEXPECTEDAIRBORNERADIOACTIVITYCONCENTRATIONSATIN-PLANTAREASDURINGREACTORSHUTDOWNCRUDRADIATIONLEVELSAREARADIATIONMONITORLOCATIONSUSARRevision112-viOctober1989 NineMilePointUnit2FSARCHAPTER12LISTOFTABLES(Cont)TableNumberTitle12.3-2AIRBORNEPROCESSANDEFFLUENTRADIATIONMONITORS12~3312.3-412.4-1PERSONNELDOSESFORREQUIREDOCCUPANCYTIMESINVITALAREASDOSERATE(REM/HR)ATLOCATION:*ESTIMATEDDOSESATTHERESTRICTEDAREABOUNDARY12.4-212.4-312.4-412.4-5ESTIMATESOFINHALATIONTHYROIDDOSERATESINMAJORBUILDINGSESTIMATEDANNUALDOSETOUNIT2CONSTRUCTIONWORKERSDUETOTHEOPERATIONOFUNIT1ANDTHEJAMESA.FITZPATRICKPLANTESTIMATEDOCCUPATIONALRADIATIONDOSESFORUNIT2BYWORKFUNCTIONSOCCUPATIONALDOSEESTIMATESDURINGROUTINEOPERATIONSANDSURVEIILANCE12.4-6OCCUPATIONALDOSEESTIMATESDURINGNONROUTINEOPERATIONSANDSURVEILLANCE12.4-712.4-812.4-912.4-1012.4-11OCCUPATIONALDOSEESTIMATESDURINGROUTINEMAINTENANCEOCCUPATIONALDOSEESTIMATESDURINGWASTEPROCESSING(RADWASTEOPERATION)OCCUPATIONALDOSEESTIMATESDURINGREFUELINGOCCUPATIONALDOSEESTIMATESDURINGINSERVICEINSPECTIONOCCUPATIONALDOSEESTIMATESDURINGSPECIALMAINTENANCE24Amendment2412-viiFebruary1986 NineMilePointUnit2FSARCHAPTER12LISTOFTABLES(Cont)TableNumberTitle2412.4-1212.4-1312.5-112.5-212.5-312.5-4OPERATIONALMAN-REMPERYEARFORSELECTEDBWRPLANTSDISTRIBUTIONOFANNUALMAN-REMBYWORKFUNCTIONSBASEDONOPERATINGBWRDATACOUNTINGROOMINSTRUMENTATIONPORTABLERADIOLOGICALSURVEYINSTRUMENTATIONPERSONNELMONITORINGINSTRUMENTATIONRADIATIONPROTECTIONEQUIPMENTAmendment2412-viiaFebruary1986 NineMilePointUnit2FSARTHISPAGEINTENTIONALLYBLANKAmendment2412-viibFebruary1986 NineMilePointUnit2FSARCHAPTER12LISTOFFIGURESFigureNumberTitle12.3-112.3-2SHIELDINGARRANGEMENTANDFACILITIES,PLANTPLANVIEW-EL250'-0"SHIELDINGARRANGEMENTANDFACILITIES,PLANTPLANVIEW-EL277'-6"12.33SHIELDINGARRANGEMENTANDFACILITIESiPLANTPLANVIEW-EL306'-0"12.3-4SHIELDINGAREVXGEMENTANDFACILITIESiREACTORBUILDINGiEIi175012.3-5SHIELDINGARRANGEMENTANDFACILITIESiREACTORBUILDINGiEL196012.3-6SHIELDINGAMUKGEMENTANDFACILITIES,REACTORBUILDINGiEL215012.3-7SHIELDINGARRANGEMENTANDFACILITIES,REACTORBUILDINGiEL240'-0"12.3-8SHIELDINGARRANGEMENTANDFACILITIES,REACTORBUILDINGiEL261'0"12.3-9SH1ELDINGARRANGEMENT,ANDFACILITIES,REACTORBUILDING,EL289'-0"12.3-10SHIELDINGARRANGEMENTANDFACILITIES,REACTORBUILDING,EL306'-6"12.3-11SHIELDINGARRANGEMENTANDFACILITIES,REACTORBUILDING,EL328'-10"12.3-12SHIELDINGARRANGEMENTANDFACILITIESiREACTORBUILDING,EL353'-10"12.3-13SHIELDXNGAREVKGEMENTANDFACILITIES,TURBINEBUILDINGiEL2500iW12.3-14SHIELDINGAREVZGEMENTANDFACILITIESiTURBINEBUILDINGiEL250OHEUSARRevision212v3.3.3.October1990 NineMilePointUnit2FSARCHAPTER12LISTOFFIGURES(Cont'd)FigureNumberTitle12.3-15SHIELDINGAREUDGEMENTANDFACZLITXES,TURBINEBUILDINGSEL2776gW12.3-16SHIELDINGAREVQlGEMENTANDFACILITXES,TURBINEBUILDING@EL277'-6",E12.3-17SHIELDINGARRANGEMENTANDFACILITIES,TURBINEBUILDING/EL306'-0"W12,3"18SHIELDINGAEGVQ4GEMENTANDFACILITIES'URBINEBUILDINGSEL306'0",E12.3-19SHIELDINGARRANGEMENTANDFACILITIES,AUXILIARYBOILERBUILDING,EL261'-0"12.3-20SHIELDINGARRANGEMENTANDFACILITIES,SCREENWELLBUILDINGSEL261012.3-21SHIELDINGARE~GEMENTANDFACILITIES,SCREENWELLBUZLDING,EL280'-0"12.3"22SHIELDINGARRANGEMENTANDFACILITIES'CREENWELLBUILDINGSEL281012.3-23SHIELDINGARRANGEMENTANDFACILITIES,SCREENWELLBUILDINGgBELOWEL261012.3-24SHIELDXNGAE~NGEMENTANDFACILITIES'ADWASTEBUILDING~EL2610g2650~2790~287012.3-25SHIELDINGAEGVlNGEMENTANDFACZLITIESgRADWASTEBUILDINGSEL309'0"12.3-26SHIELDINGAEGVQlGEMENTANDFACILITIES,RADWASTEBUILDING@EL2402g2450g291612.3-27SHIELDINGARRANGEMENTANDFACILITIES,RADWASTEBUILDING,EL2790g3060ANDTURBINEBUILDINGSECTION1-112.3-28SHIELDINGARRANGEMENTANDFACILITIES,CONDENSATESTORAGEBUILDING,EL265'-0"USARRevision212ixOctober1990 NineMilePointUnit2FSARFigureNumber12.3-2912.3-3012.3-30a12.3-3112.3-3212.3-3312.3-3412.3-3512.3-3612.3-3712.3-3812.3-3912.3-4012.3-4112.3-4212.3-4312.3-4412.3-45CHAPTER12LISTOFFIGURES(Cont)TitleSHIELDINGARRANGEMENTANDFACILITIES/CONDENSATESTORAGEBUILDING/EL2510SHIELDINGARRANGEMENTANDFACILITIES/CONTROLBUILDING/EL306'-0"SHIELDINGARRANGEMENTANDFACILITIES,CONTROLBUILDING,EL288'-6"SHIELDINGARRANGEMENTANDFACILITIES,CONTROLBUILDING/EL261'-0"SHIELDINGARRANGEMENTANDFACILITIES/PIPINGTUNNELPLAN-SHIELDINGARRANGEMENTANDFACILITIES,STACK'RADIATIONZONES/PLANTPLANVIEWEL250'-0"RADIATIONZONES,PLANTPLANVIEWEL277'-6nRADIATIONZONES,PLANTPLANVIEW-EL306'-0"RADIATIONZONES/REACTORBUILDING/EL175'-0"RADIATIONZONES/REACTORBUILDING/EL1960RADIATIONZONES/REACTORBUILDING/EL215'-0"RADIATIONZONES/REACTORBUILDING/EL2400RADIATIONZONES/REACTORBUILDING/EL261'-0"RADIATIONZONES/REACTORBUILDING/EL289'-0"RADIATIONZONES/REACTORBUILDING/EL3606RADIATIONZONES/REACTORBUILDING/EL328'-10"RADIATIONZONES/REACTORBUILDING/EL353'-10"USARRevision012-xApril1989 NineMilePointUnit2FSARFigureNumberCHAPTER12LISTOFFIGURES(Cont)Title12.3-46'2.3-4712.3-4812.3-4912.3-5012.3-5112.3-5212.3-5312.3-5412.3-5512.3-5612.3-5712.3-5812.3-5912.3-6012.3-6112.3-6212.3-63RADIATIONZONESiTURBINEBUILDINGiEL2500iWRADIATIONZONESiTURBINEBUILDINGiEL2500iERADIATIONZONES,TURBINEBUILDING,EL277'-6"iWRADIATIONZONESiTURBINEBUILDINGiEL2776iERADIATIONZONESiTURBINEBUILDINGiEL3060iWRADIATIONZONESiTURBINEBUILDINGiEL3060iERADIATIONZONESiAUXILIARYBOILERBUILDINGiEL261'-0"RADIATIONZONESiSCREENWELLBUILDINGiEL2610RADIATIONZONESiSCREENWELLBUILDINGiEL2800RADIATIONZONESiSCREENWELLBUILDINGiEL2810RADIATIONZONES,SCREENWELLBUILDINGBELOWEL261'O'IRADIATIONZONESiRADWASTEBUILDINGiEL2610265'-0"i279'-0"287'-0"RADIATIONZONESiRADWASTEBUILDINGiEL3090RADIATIONZONESiRADWASTEBUILDINGiEL2402245'-0"i291'-6"RADIATIONZONES/RADWASTEBUILDINGiEL279'-0"i306'niANDTURBINEBUILDINGSECTION11RADIATIONZONESiCONDENSATESTORAGEBUILDINGiEL265'-0"RADIATIONZONESiCONDENSATESTORAGEBUILDINGiEL251'-0"RADIATIONZONESiCONTROLBUILDINGiEL3060USARRevision012-xiApril1989 NineMilePointUnit2FSARFigureNumber12.3-63a12.3-6412.3-6512.3-6612.3-6712.3-6812.3-69CHAPTER12LISTOFFIGURES(Cont)Title'RADIATIONZONESgCONTROLBUILDINGgEL2886RADIATIONZONESgCONTROL.BUILDINGgEL2610RADIATIONZONES,PIPINGTUNNELPLANRADIATIONZONESiSTACKSTANDBYGASTREATMENTSYSTEMFILTERARRANGEMENTMAINCONTROLROOMCHARCOALFILTRATIONSYSTEMARRANGEMENTPOSTACCIDENTVITALACCESSAREAS(SHEETS1THROUGH4)USARRevision012-xiiApril1989 NineMilePointUnit2FSAR12.2RADIATIONSOURCES12.2.1ContainedSources12.2.1.1GeneralThreetypesofradiationsourcesthatoccurinanuclearplantarediscussedinthissection:primaryradiationfromthereactorcore,secondaryradiationsourcesresultingfromnuclearreactionsbetweentheprimaryradiationandthereactorenvironment(activationproducts),andpossiblereleaseofradioactivematerialfromthereactorcore(fissionproducts).Duringnormaloperations,secondarysourcesandreleasedradioactivematerialsaretransportedbyeitherthereactorwaterorthesteamtoprocesscom-ponentsintheplant.Thissectiondiscussesthedesignsourceswhicharegroupedbylocationandequipmenttype(e.g.,primarycontainment,coresources).Thefollowingsectionspresentthesourcedataforvariouspiecesofequipmentthroughouttheplant.Generallocationsofequip-mentareshownonthegeneralplantarrangementdrawingsofSection1.2.Thebiologicalshieldwallandthedrywellwallaretheprincipalshieldsforradiationfromthereactorcore.Themaximumexpectedneutronfluxisafactorinthedesignofthethicknessofthesewalls.Considerationisalsogiventogammaraysemittedduetothermalizationofneutronsintheshields.Withtheexceptionofthebiologicalshieldwallanddrywellwall,shieldingdesignsarebasedonfissionproductandac-tivationproductsourcesconsistentwithSection11.1andTable12.2-16.Forshielding,itisconservativetodesignforfissionproductsourcesatpeakvaluesratherthananannualaverage,eventhoughexperienceindicatestheannualaverageisconsiderablylessthanthedesign.Activationproducts,principallyN-16,aretheprincipalsourceforshieldingcalculationsinmostoftheprimarysystem.Inareaswherefissionproductsaresignificant,conservativeallowanceismadefortransitdecay,whileatthesametimeprovidingfortransientincreaseofthenoblegassource,daughterproductformation,andenergylevelofemission.Areaswherefissionproductsaresignificantrelativetoac-tivationproductsinclude:thecondenseroff-gassystem'ownstreamofthesteamjetairejector,liquidandsolidradwasteequipment,portionsofthereactorwatercleanup(RWCU)system,andportionsofthefeedwatersystemdown-streamofthehotwellincludingcondensatetreatmentequipment.Amendmentll12'-1June1984 NineMilePointUnit2FSARAreviewofthesystemsthatcontainradioactivefluidwasperformedtodeterminewhetheranincreaseinsourcetermsduetocruddepositionwasrequired.BasedonUnit2cal-culatedcontactdoseratesandmeasureddata'(whichsum-marizesoperatingplantdataforvarioussystemsandequipment),itwasdeterminedthatvarioussystemcomponentsrequiredanincreasedsourceterm.Table12.2-16providestheadditionalcontactdoserateswhichareincludedintheshieldingdesignanalysisofthecorrespondingcomponents.Amendment1112.2-1aJune1984 NineMilePointUnit,2FSARTHISPAGEINTENTIONALLYBLANKAmendment1112.2-lbJune1984 NineMilePointUnit2'SAR12.2.1.2PrimaryContainment,(Drywell)12.2.1.2.1ReactorVesselSourcesThissectiondefinesthereactorvesselmodelfortheas-sociatedgammaandneutronradiationsourcesandprovidesdata.requiredforcalculationsbeyondthevessel.Thedataselectedwerenotchosenforanygivencomputerprogram,butwerechosentoprovideinformationforanyofseveralshieldanalysisprogramtypes.PhsicalDataTable12.2-1presentsthephysicaldatarequiredtoformareactorvesselmodel.Thedataincludecorematerialvolumefractions,thermalpower,averagepowerdensity,powerpeakingfactors,andnoncoreaveragewaterdensities.GammaRaSourceEnerSectraTheenergyspectra(presentedinthissection)includefis-siongammarays,fissionproductgammarays,andgammaraysresultingfrominelasticneutronscatteringandthermalneu-troncapture.Thetotalgammarayenergyreleaserateinthecoreisestimatedtobeaccuratetowithin+10percent,whiletheenergyreleaserateabove6MeVmaybeinerrorbyasmuchasafactorof+2.CoreSectrumAfter0erationTable12.2-2givesthegammarayenergyspectruminMeV/sec-wattinspentfuelatselectedtimeintervalsafteroperation.Thedatawerepreparedfromtablesoffissionproductdecaygammaenergiesfittedtointegralmeasurementsforoperationtimesof10sec(approximately3.2yr).Shutdownsourcesinthecorearefoundinthesamemannerasoperatingsources,bycom-biningtheshutdownspectrumwiththecorethermalpowerandpowerdistributions.Shutdownsourcesinasinglefuelelementcanbeobtainedbyusingthespectrumandthether-malpowerthattheelementcontainedduringoperation.AroundtheVessel-GammaRaandFast,NeutronFluxesTable12.2-3presentsthecalculatedgammarayenergyfluxesandfastneutronfluxeswithenergygreaterthan1MeVatthreepointsoutsideofthereactorvessel.Thecalculateddatacanvarybyafactorof+3.Also,thegammarayenergyfluxesinthissectiondonotincludeanyprovisionsforscatteringfrompointsoutsideofthevesselnorarethereanyprovisionsforgammarayfluxesfromdepositionsof12.2-2 NineMilePointUnit2FSARradioactiveisotopeswithinthevessel.12.2.1.2.2RadioactiveSourcesintheReactorWater,Steam,andOff,GasTheradioactivesourcesinthereactorcoolantandsteamarediscussedinSection11.1,andtheoff-gassourcesaredis-cussedinSection11.3.3.Thesesectionsprovideconcen-trations,duringnormaloperation,oftheradioisotopesleavingthereactorvesselandgasesleavingthecondenser.12.2.1.3ReactorBuilding12.2.1.3.1ReactorWaterCleanup(RWCU)SystemSourcesTheradioactivesourcesintheRWCUsystem(Section5.4.8)aretheresultoftheactivityinthereactorwaterintran-sitthroughthesystemoraccumulationofradioisotopesremovedfromthewater.Componentsforthissystemincluderegenerativeandnonregenerativeheatexchangers,pumps,valves,andfilterdemineralizers.'llmajorcomponentsofthecleanupsystemarelocatedinthereactorbuilding.Ac-tivitiesforthecleanupsystemaregiveninTable12.2-4.Thecontact,doseratesobtainedfromtheseactivitiesareaugmentedbythecrudcontributiongiveninTable12.2-16.12.2.l.3.2MainSteamSystemSourcesAllradioactivematerialsinthemainsteamsyst:emresultfromradioactivesourcescarriedoverfromthereactorduringplantoperation.InmostofthesecomponentsthesourceisdominatedbyN-16;wheretheN-16hasdecayed,theotherisotopescarriedbythesteambecomesignificant(Section12.2.1.4.1).12.2.1.3.3ResidualHeatRemoval(RHR)SystemSourcesThedesigngammasourcestrengthsintheRHRsystem(Section5.4.7)wereevaluatedforsystemoperationinthereactorshutdownmodeInthismode,thesystemrecir-culatesreactorcoolanttoremovereactordecayheat,operatingfromapproximately2hraftershutdownuntiltheendoftheshutdownperiod.Whennecessary,thissystemalsomaysupplementthespentfuelpoolcoolingsystemcapacity.TheRHRsystemisdescribedinSection5.4.7.ThesourceintheRHRsystemistheactivityinthevolumeofreactorwatercontainedinthesystem.Thesourcestren-gthsintheRHRequipment8hraftershutdownareshowninTable12.2-5.ThecontactdoseratesobtainedfromtheseactivitiesareaugmentedbythecrudcontributiongiveninTable12.2-16.Amendmentll12.2-3June1984 NineMilePointUnit2FSAR12.2.1.3.4ReactorCoreIsolationCooling(RCIC)SystemSourcesTheradioactive'ourcesintheRCICSystem(Section5.4.6)wereevaluatedforthesystemoperatinginthetestmode.Thissystemmaybeutilizedduringreactorshutdownifthemaincondenserorfeedwatersystemsareunavailable.Thesystemisoperatedfromthetimeofreactorshutdownforap-proximately2hruntilareactorpressureof150psiaisachieved.Below150psiatheRHRsystemisinitiatedtoachievecoldshutdown.Duringroutinetestingofthesystem,thesourceintheequipmentistheactivityofthesteamdrivingthesystemturbine.ThisactivityisdominatedbyN-16.TheradiationsourcedatausedintheshielddesignofthissystemareshowninTable12.2-6.ThecontactdoseratesobtainedfromthesesourcedataareaugmentedbythecrudcontributiongiveninTable12.2-16.12'.1.3.5FuelPoolCoolingandCleanup(SFC)SystemSourcesTheradiationsourceforspentfuelisgiveninSection12.2~1.2.1,GammaRaySourceEnergySpectra-CoreSpectrumAfterOperation,andTable12.2-2.Therearetwomajorsourcesofradioactivityinthespentfuelpool:themixingofthereactorcoolantwiththefuelpoolwateratthestart,ofrefueling,andthereleaseofcrudfromthesurfaceofthespentfuel.assembliesduringmovement.Theactiviti'esinthe=SFCfilter/demineralizerarede'ter-minedfrominitialreactorcoolantactivities.First,thecorrosionproductactivitiesof-thereactorcoolantaremul-tipliedby3toaccountforanincreaseinsolublespeciesduringthefirstweekfollowingshutdown.Next,theac-tivitiesaredecayedfor24hrandthendilutedbythefuelpoolwater.Thisspectrumisfedtothefilter/demineralizer(removalefficiencyassumed100percent)andbuiltupfor7days.Thespectrumobtainedhereisaddedtothespectrumgeneratedbytheoriginalcoo'lantactivitiesdecayedfor7daysandbuiltupinthefilter/demineralizer-for23da'ys.Thissumistheactivityusedforshielding;thistwo-partmethodresultsinaconservative,.shielddesign.TheradioactivityintheSFCheatexchangerisarrivedatbyassumingtheSFCfilter/demineralizerremoval-efficiency'is90percent.Thelong-livedcorrosionproductspectrumisdeterminedbythe10percentpassedthrough.Thisdis-tributionisnormalizedtogivedoseratesconsistentwithdatafromotherplantsduetotheplateoutaridbuildupofAmendment1112.2-4June1984 NineMilePointUnit2FSARthesecorrosionproductsintheheatexchanger.Theseandthespentfuelstoragepool,surgetank,andotheractivitiesshowninTable12.2-7,arebasedonliquidactivityandcrudbuildup,andareusedforshieldingdetermination.AllSFCcomponentsarelocatedwithinthereactorbuilding.'heSFCsystemisdescribedinSection9.1.3.12.2.1.3.6LiquidRadwasteSystemSources(ReactorBuilding)Componentsoftheliquidradwastesystem(LWS)locatedinthereactorbuildingincludetheLWSreactorwatercleanupphaseseparatortanksandpumps(el289ft),theLWSspentfuelpoolphaseseparatortankandpump(el289ft),andvariouspipesandvalves,includingdraindischargepiping.Allothercomponentsarelocatedintheradwastebuilding(Section12.2.1.5.1).12.2.1.3.7StartupSourcesThefourreactorstartupsourcesaretubularsourceholdersI,eachcontainingaCalifornium-252capsule.Californium-252producesneutronsbyspontaneousfission.TheCalifornium-252(Cf-252)capsulesareshippedtothesiteinaspecialshieldedcasktothesourceholders.Theyarethenloadedintothereactorwhilebeingkeptunderwater.Theyprovideasufficientsourceofneutronsinthecoretohelptesttheneutronfluxmonitors(ofdifferentranges)forproperoperationandresponsebeforeandduringfuelloading.Therearesevenalternatelocationsforvarioustests.Thesesourcesandsourceholdersmayberemovedfromthecoreattheendofthefirstfuelcycle.12.2.1.3.8TraversingIncoreProbe(TIP)SystemSourcesFiveTIPsprovideneutronfluxreadingsinthecoreforcalibrationofotherinstruments.ThemaximumradiationsourceforthissystemisgiveninTable12.2-8.Theradiationsourceisbasedupontheprobe'slocationwithinthecoreanditsresidencetime.Asindicatedinthetables,thesystemisdividedintothreesectionsforshieldingcalculations:theprobesfissionablematerial,nonfissionablematerial,andsignalcable.Sourcesareprovidedfor100-secirradiationandzero-secdecay.USARRevision012.2-5April1989 Nine-Mile'PointUnit2FSAR12.2.1.4TurbineBuilding12.2.1.4.1TurbineSystemSourcesPipingandequipmentthatcontainmainsteamaresourcesofradiationduetothepresenceofN-16,thepredominantsourceofactivityduringoperation.Fission'productgases(xenonandkrypton),wateractivationproducts(0-19andN-17),andthecarryoverofiodineandotherfissionproductspresentinsteamandcondensateareconsideredad-ditionalactivitysources.Thecarryoverisconservativelyassumedtobe2percentbyweightforhalogensandO.lpercentbyweightforotherfissionproducts.TheN-16concentrationsintheturbinesystemequipmentarelistedinTable12.2-9.Transitdecayoftheshort-livedN-16has-beenincludedinthesourceterms.12.2.1.4.2CondensateandFeedwaterSystemSourcesThesourcesinthecondensatesystemarebasedondecayedmainsteamactivities.ThesesystemsaredescribedinSection10.4.Thecondensatedemineralizersystemisdesignedtomaintainhighpurityofthecondensatetoassurehighqualityfeed-watertothereactorbyremovalofvariouscontaminants.Eachcondensatedemineralizerisatankfilledwithresinsthatservestoremoveionicimpuritiesandtofilterout,suspendedsolidsfromthecondensate.Resincanbereusedifthecollectedcrudisremovedandtheion-exchangepropertiesarerenewed(regenerated).Theseareaccom-plishedbyultrasonicresincleaningandbychemicalwashing.Almostallnoncondensablesenteringthecondenserareremovedbytheairejectors.Becauseofthisandtherelativelylongholduptime,theN-16andothergaseousac-tivityisverylowinthehotwellandnegligibleintheremainderofthecondensatesystem.Theactivitiescausedbyactivatedcorrosionandfission.productsareshowninTable12.2-10forthecondensatesystem.12.2.1.4.3Off-GasSystemSou'rcesThegaseouseffluenttreatmentsystem(Section11.3.2)isdesignedtolimitoffsitedosesfromroutinestationreleases.Theoff-gassystemcontainssourcesofradiationbasedontheholdupofnoncondensablegasesfromthemaincondenser.Thesegasesareremovedbythecondenserairremovalsystemandaretreatedthroughtheuseofequipment12.2-6 NineMilePointUnit2FSARincludingcatalyticrecombinersandambienttemperaturecharcoaladsorptiondecaybeds.TheN-16activityintheairremovalsystemisshowninTable12.2-9.TheN-16activityintheoffgassystem(downstreamoftheholduppipe)isnegligibleduetodecay.Therefore,thepredominantradiationsourcesarethefissionproductgases,xenonandkrypton,andtheirdaughterproducts.ThesourcetermsusedforshieldingaregiveninTable12.2-11.12.2.1.5RadwasteBuilding12.2.1.5.1LiquidRadwasteSystemSources(RadwasteBuilding)TheLWS(Section11.2.2)iscomposedoffoursubsystemsdesignedtocollect,treat,andthenrecycleordischargedifferentcategoriesofpotentiallyradioactivewastewater.TheactivitiesfromsourcesintheLWSsuchaspipes,tanks,filters,demineralizers,andevaporatorsusedinshieldingcalculationsarelistedinTable12.2-12.12.2.1.5.2SolidRadwasteSystemSourcesThesolidradwastesystemisdesignedtocollect,hold,monitor,process,package,andprovidetemporarystoragefacilitiesforsolidradioactivewastespriortoshipmentforoffsitedisposal.ThissystemisdescribedinSection11.4.Radioisotopicinventoriesofmajorcomponentsinthissystemthatareusedinshield'ingcalculationsarelistedinTable12.2-13.12.2.2AirborneRadioactiveMaterialSourcesUnit2isdesignedsothattheairborneradionuclideconcentrationinnormallyoccupiedareasiswellbelowthelimitsdiscussedin10CFR20.RadiationzoningisdiscussedinSection12.3.1.2.AreasthataredesignatedRadiationZoneIV,V,orVIareconsideredtobenormallyoccupiedareas.TableII,column1ofAppendixBto10CFR20providesthecriteriausedforZoneVandVIareas.TableI,column1ofAppendixBto10CFR20providesthecriteriausedforaZoneIVradiationarea.Radioactivematerialsbecomeairbornethroughevaporationandattachmenttosuspendedwaterdropletsandwatervapor.Thewatervaporcomesfromleaksinhighenergylines(pressurizedhotwater).Suspendedwaterdropletsarecreatedbyspraysandsplashing.Evaporationoccurswhereverthereisstandingwaterexposedtoair.ThelevelofairborneradioactivityisperiodicallydeterminedbytheUSARRevision212%27October1990 NineMilePointUnit2FSARradiationprotectionstafftoensurethatradiationexposureisaslowasreasonablyachievable(ALARA).12.2.2.1MethodforComputingtheAirborneRadionuclideConcentrationinaPlantAreaThemethodusedforcomputingtheairborneradionuclideconcentrationsforareasinthereactor,turbine,andradwastebuildingsisbasedondatagiveninNUREG-0016,Revision1,andEPRI-495,~'.Theactivityreleases(inuCi/yr)fromabuildingaredistributedthroughoutthevariousbuildingareasspecifiedasfollowsbyevaluatingtheventilationsystemdesignalongwiththedistributionsrecommendedinNUREG-0016andEPR1-495.Theseradionuclideconcentrationsresultintheexpectedannualreleasesspeci'fledinTable11.3-1aftercreditistakenforfiltrationofradioiodineandparticulates.Forbothpoweroperationsandshutdown,100percentofthereactorbuildingreleaseisassumedtocomefromtheareascontainingtheRHR,RWCU,andECCSequipmentandcomponents.Forfull-poweroperations,85percentoftheactivity.released'fromtheturbinebuildingisfromthemaincondenserarea,whichisnotnormallyoccupied.Theremaining15percentoftheturbinebuildingreleaseisfrommiscellaneousareas,includingthesteamjetairejectorarea,theturbineoperatingfloor,thefeedwaterpumparea,andthemechanicalvacuumpumparea.Noblegasconcentrationsduringfull-poweroperationsintheturbineoperatingfloor,feedwaterpumparea,andthemechanicalvacuumpumpareaareexpectedtobenegligible.Theradwastebuildingisdividedintothreemajorareascontributingtothetotalactivityrelease.Thesearethewastecollectionsystemareas,thefloordraincollectionsystemareas(bothofwhichareliquidradwastesystemareas),andthesolidwastesystemareas.Theliquidradwastesystemconsistsoffoursubsystems:wastecollection,floordrain,regenerantwaste,andphaseseparator(asdiscussedinSection11.2.2).Thecalculationsofairborneradionuclideconcentrationsaremadewiththeregenerantwastesystemareasandprocessingcapabilityconsideredaspartofthewastecollectionsystem,andwiththephaseseparatorsystemareasandprocessingcapabilityconsideredaspartofthesolidwastesystem.Amendment912.2-8March1984 NineMilePointUnit2FSARForpoweroperations,72percentoftheradwastebuildingreleasescomefromthewastecollectionsystemareas;18percent,fromthefloordraincollectorsystemareas;and10percent,fromthesolidwastesystemareas.Thebreakdownofreleasesfromtheliquidwastesystemareasisbasedontheexpectedprocessingcapabilityofthesubsystems.Amendment912.2-8aMarch1984 Nine'MilePoint,Unit2,FSARUTHISPAGEINTENTIONALLYBLANKAmendment.912.2-8bMarch1984 NineMilePointUnit2FSAR12.2.2.2ProductionofAirborneRadioactiveMaterialSourcesTheprimarypotentialsourcesofairborneradioactivityduringnormaloperationsare:1.Leakagefromprocessequipmentinradioactivesystems,suchasvalves,flanges,andpumps.2.Evaporationfromsumps,drains,tanks,andfilter/demineralizervesselsthatcontainradioactivefluid,exceptwherevaporishard-pipedtoanHVACsystem.3.Exhaustfromreliefvalves.4.GasesreleasedduringremovalofRPVheadandassociatedinternals.5.Evaporationandgasesreleasedfromsampling.6.Airborneradioactivityreleasedfromthespentfuelpoolwaterandspentfuelmovement.7.Maintenanceactivitiessuchasdecontamination.Sections12.2.2.2.1to12.2.2.2.6discusseachofthesesourcesandtheireffectontheairborneradionuclideconcentrationsinnormally-occupiedareas.Designfeaturesthatservetoreducetheseconcentrationsarealsodiscussed.Tables12.2-15aand12.2-15bpresenttheairborneradioactivityconcentrationsexpectedinreactorbuilding,radwastebuilding,andturbinebuildingareasforbothpoweroperationsandshutdown.Abnormaloccurrencesthatcancauseairborneradiationinclude:(1)spills(i.e.,overflowsandsplashing),(2)failureofaventilationsystem,(3)cracksinpiping,(4)failuresofpumpandvalveseals,and(5)malfunctioningequipment.Airborneradioactivityisexpectedinthedecontaminationarea,occasionallyinlabs,andduringrefuelingontherefuelingfloor.Theairborneradioactivityiscausedbyleaks,spills,venting,decontamination,etc.;concentrationsarecalculatedfortheoccurrencesthatarethemostcommon,leaksandventing.USARRevision312.2-9October1991 NineMilePointUnit2FSAR12.2.2.2.1EffectofLeakagefromProcessEquipmentinRadioactiveSystemsNormallythereisnoleakagefromequipmentinradioactivesystems.Ifaleakoccurs,itseffectisdeterminedbythreeitems.Ifaleakoccursfromacomponentlocatedinahighradiationarea,itdoesnotcontributetothe,airborneradionuclideconcentrationinanormallyoccupiedareabecause'heplantHVACsystemsaredesignedtoprovideairflowfromareasoflessertoprogressivelygreaterpotentialradioactivecontaminationpriortofinalexhaust.SeparateHVACsystemsareprovidedforeachbuildingtoaidintheisolationofcontamination.Areaswhereradiationlevelsvaryareregardedashavingahighpotentialforairborneradioactivity.Aircontainedintheseareasistreatedasifthehighestpotentialofradioactivityexists,sothatitwillnotaffecttheairborneradionuclideconcentrationofanormallyoccupiedarea.Thesystemoperatingpressureaffectsthepossibleleakagerate.Asystemsuchasthemainsteamsystem,whichoperatesathighpressure,isexpectedtohaveahigherleakageratethanasystemthatoperatesatatmosphericpressure.However,radioactivesystemsthatoperateathighpressurearelocatedinhighradiationareas.Thus,thesesystemsdonotsignificantlycontributetotheairborneradioactivitylevelinnormallyoccupiedareasduetotheHVACairflowdiscussedearlier.Asystemthatcanleakhighlyradioactivefluidsuchasreactorcoolantormainsteamisofgreaterconcern,initially,thanasystemthatcanleakalesscontaminatedfluidsuchascondensatestoragetankwater.Systemsthatcanleakhighlyradioactivefluidarelocatedinhighradiationareas,andthisactivityisnottransportedtolowerradiationareasbyHVACairflow,asdiscussedearlier.Therearemanysystemscontainingradioactivefluidsthatarelocatedinlowradiationareas.Eachsystemhasbeenevaluatedtodeterminetheeffectivepotentialofcreatinganairborneradiationhazard.Designfeatureshavebeenincorporatedtoreducethepossibilityofhazard.Thesemeasures.includehardpipingallreliefvalvesontheauxiliaryboilersteamsystemtoacontactcondenser.Gaseouseffluentsfromthistankareventedtotheauxiliaryboilerbuildingventilationsystem,whichisductedtoamonitoredreleasepoint.Amendment2512.2-10March1986 NineMilePointUnit2FSAR12.2.2.2.2EffectofSumps,Drains,andTanksThefloorandequipmentdrainsinthereactor,radwaste,andturbinebuildingsaredesignedtocollectandtransportvarioustypesofwastetotheLNSforprocessing.Thesedrainsystemsconveywastebygravitytotheirrespectivesumps;wasteispumpedfromthesumpstotheradwastebuilding.Drainsandsumpsinthesystemsnotedarenotsignificantsourcesofairborneradionuclidesforthefollowingreasons:Eachsumpiscoveredwithasteelplate.Thefreevolumeinthesumpismaintainedatanegativepressurewithrespecttothesurroundingareabytheuseofariservent,whichisconnectedtotheHVACsysteminthebuildingofconcern.Thesteelplatecoveringthesumpdoesnotprovideanairtightseal.AirisdrawnintothesumparoundtheedgesofthesteelcoverandexhaustedthroughtheriserintotheHVACsystem.AnyradionuclidesthatescapeintothefreevolumeofthesumparedischargedtotheHVACsystemanddonotescapeintotheareasurroundingthesump.2.Topreventcrudbuildup,thedrainsemptybygravitywithnowatertrapsorlevelpiperuns.AirisdrawnthroughthedrainstothesumpbythesameriserventdiscussedinthepreviousparagraphandouttotheHVACsystem.Sump2DFT-SUMP2Hreceivescondensateeffluentintermittentlyfromthemainsteamlinedraintothecondenser.Thissumpisnotventedtothebuildingventilationsystembecausethereisnoflashingconcernwhichcouldresultinairborneradioactivityduetothetemperaturebeinglessthan212'F.Also,noblegases,whichcouldbecomeairborneevenintheabsenceofflashing,areexpectedtobenegligible.Theholdingtanksandfilter/demineralizerunitsthatcontainsignificantinventoriesofradionuclidesarehardpipedtotheHVACsystem.Thesetanksandfilter/demineralizervesselsarelocatedinhighradiationareas.Evenifanyairborneradionuclideswerereleasedfromthesecomponents,therewouldbenoeffectonnormallyoccupiedareasduetotheHVACsystemdesignfeaturesdiscussedinSection12.2.2.3.1.12.2.2.2.3EffectofReliefValveExhaustThereliefvalvesfoundinthevariousplantsystemswhichcanexhaustradioactivefluidsarenotconsideredasignificantsourceofairborneradioactivityinnormallyoccupiedareasforthefollowingreasons:1.Theexhaustofmanyreliefvalvesispipeddirectlytothecondenser,withnoaccesstotheatmosphere.USARRevision412.2-11October1992 NineMilePointUnit2FSAR2.Theexhaustofotherrelief-valvesiseitherpipeddirectlytothesuppressionpoolortothefloororequipmentdrains.ThesedrainsleadtotheLNS(Section12.2.2.2.2).Amendment712.2-12December1983 NineMilePointUnit2FSAR12.2.2.2.4EffectonRemovingRPVHeadandAssociatedInternalsExperienceatBWRplantshasshownthataninventoryofradioactivegaseswillaccumulateinsidethereactorvesselheadbetweenthetimeofshutdownandheadremoval.Thesegasesconsistprimarilyofthelonger-livedradiohalogensandnoblegases.Topreventthesegasesfrombeingreleasedtotherefuelingarea,provisionsaremadefortheventingofthegasestotheHVACsystempriortoRPVheadremoval.Thesegasesareventedthroughan8-indiameterductconnectedbetweenthereactorheadandreactorheadevacuationfilterassemblycontainingparticulate-andcharcoalfilterunits.Experiencethatsomefollowing:atDresdenandQuad-CitiesstationshasshownairborneradioactivitycanresultfromtheWhenthe.reactorwaterinthereactorcavitygoesabove100F,noticeableincreasesintheI-131airborneactivityresult,increasingwithtemperature.2:Whenthereactorwaterlevelinthevesselislow,previously'coveredmetallicsurfacesdryout.Ifcobaltdioxide(CoOz)isplatedoutonthesesurfaces,airmovingacrossthesesurfacescandislodgefineparticlesofCoOz.Thedryerand.separatorarealsosusceptibletothisphenomeon.Thesetwoairborneactivityproblemshavebeensolvedbymaintainingwatertemperaturesbelow100Fandbymakingprovisions'orcleanwaterservicestotheRPVcavityarea.Amendment712.2-13December1983

.NineMilePointUnit",2..FSARThispermitswettingoftheRPVcavityandcomponents.Byfollowingtheseprocedures,itisanticipatedthatRPVheadandreactorinternalsremovalwillhaveaminimaleffectontheairborneradionuclidelevelin.thespentfuelarea.12.2.2.2.5EffectofSamplingE;Thepossibilityofreleasingradionuclidesthatcouldbecomeairborneduringsamplingoperationsisrecognized.Designfeaturesare'ncorporatedintothesamplesystemtolimittheradionucliderelease.Radioactivefluidsthatrequirefrequentgrabsamplingarepipedviasamplelinestofumehoodslocatedinsamplerooms..Grabsamplingwillbeaccomplishedinthefumehoods.Duringsampling,aninflowairvelocityofapproximately100ft/minwillbemaintainedtosweepanyairborneradioactiveparticlestotheexhaustduct.Administrativecontrol,isusedbyfollowingprocedureswhenprocessfluidsaresampled.Thisminimizesthereleaseofradioactivefluidsand,hence,exposuretopersonnelduringthesamplingprocess..12.2.2.2.6EffectofSpentFuelMovementExperienceatoperatingBWRplantshasshownthatfuelmovementnormallydoes.notpresentanyunusualradiologicalproblems.TheexpectedlevelofradioactivityinthespentfuelpoolwaterislistedinTable12.2-7;thisincludesactivitydueto.crudbuildup.Evaporationofthespentfuelpoolwateristhemajor,possiblecontributortoairborneactivity,butisnotexpectedtobesignificant.12.2.2.2.7Effect;ofSolidRadwasteHandlingAreasThesolidradwastehandlingequipmentlocatedintheradwastebuildingisdesignedforsemi-remoteoperation.Entryformaintenanceactivitieswillnormallyentailshutdownandflushingofsystemsandequipment.Theventilationsupplyfortheradwastebuildingisfilteredoutsideair.TheairflowaroundallcomponentsthatarepossiblesourcesofairborneradioactivecontaminationisducteddirectlytotheHVACsystem.ExpectedairborneradioactivityconcentrationsinthesolidradwastehandlingareasareprovidedinTable12.2-15.12.2.2.2.8EffectofLiquidRadwasteHandlingAreasLowmaintenancetypeequipmentisdesigned,fortheLWS,locatedintheradwastebuilding.Allcomponentsthat,containradioactivematerialsandarelocatednearnormallyfAmendment912.2-14March1984 NineMilePointUnit2FSARoccupiedareasareshielded.Theventilationof.theliquid,radwastehandlingareasissimilartothatofthesolidrad-wastesystem.Thesupplyair,isfilteredoutsideair,andtheairflowaroundcomponentsthat,arepossiblesourcesofairborneradioactivityisreturnductedeitherindividuallyorbycubicledirectlytotheHVACsystem.Expectedair-borneradioactivityconcentrationsinliquid-wastehandling,areasareprovidedinTable12.2-15:Amendment9"12.2-15March1984 NineMilePointUnit2FSAR12.2.2.3References51.CalculationofReleasesof'adioactive'aterialsinGaseousandLiquidEffluentsfromBoilingWaterReactors(BWR-GALECode),NUREG-0016,Revision1,January1979.2,:Sources.ofRadioiodineat-BoilingWaterReactors,EPRI495,February1978.3.Hazzan,M.J.;Stocknoff,M.S.;Barcomb,D.;Irving,T.RadiationIevelsDuetoCrudDepositioninBoilingWaterReactors.PresentedatAmericanNuclearSociety1983WinterMeeting,SanFrancisco,CA.Amendment1112.2-16June.1984 NineMilePointUnit2FSARTABLE12.2-1BASICREACTORDATAA.Reactorthermalpower*B.AveragepowerdensityC.Corepowerpeakingfactors:l.Atcorecenter:3,489MW50.7watts/cm'avI(axial)l.5pmaxZP~avI(radial)l.4maxiR2.Atcoreboundary:Pave[I(axial).0.5maxIZD.Corevolumefractions:P~avI(radial)0.7maxiRMaterialDensityCCVolumeFractionUO2ZrH20Void10.46.41.0(liquid)00.2540.1400.2740.332E.AveragewaterdensitybetweencoreandvesselandbelowthecoreF.Averagewater-steamdensityabovecore:l.Intheplenumregion2.Abovetheplenum(homogenized)G.Averagesteamdensity0.74g/cc0.23g/cc0.6g/cc0.036g/cc*Apowerlevelof105percentofratedpower(3,323MW)ischosentoensurethatthecalculateddesignbasessourcesboundtheexpectedsourcesinthereactoratthelicensedratedpowercondition.USARRevision0lof1April1989

NineMilePointUnit2PSARTABLE12.2-2POSTOPERATIONGAMMASOURCESINCORE*(MeV/sec-watt)EnergyBoundsMeV0sec1week~ldaTimeAfterShutdown1month4.0-6.03.0-4.02.6-3.02.2-2.61.8-2.21.4-1.80.9-1.40.4-0.90.1-0.48.2+91.8+101.1+101.7+102.1+103.3+103.7+105.1+101.2+10<1.0+67.0+65.7+62.9+84.5+83.1+92.3+97.5+91.8+9<1.0+64.6+63.7+61.7+84.0+72.1+91.6+93.8+98.7+8<1.0+6I<1.0+6<1.0+6<2.0+74.0+76.4+81~1+9'.1+93.6+8*Operatinghistoryof3.2yr.NOTE:8.2+9=8.2x10~USARRevision01of1April1989 I

NineMilePointUnit2FSARTABLE12.2-3RADIATIONLEVELSINSIDEDRYWELL'h7.4-43.2-11.2+24.5+34.0+43.1+5GammaFluxMevcm~-sec*Location1Mev1.5Mev2.3Mev3Mev5Mev7MevA9.4+26.9+39.4+49.3+51.2+64.7+63.0+71.7+81.1+97.4+92.2+94.4+9FastNeutronFlux(>1Mev)ncm'-sec4~3-1Il.0+7I4.7-7I*Thefluxlevelsrepresentdirectcorefluxes.Contri-butionscausedbyscatteringfromwallsandsurfacesoutsidethereactorvesselarenotincluded.NOTE:9.4+2=9.4xl0KEY(Allonoutersurface):A=TopofRPVB=SideofRPV(athighestcoreaxialfluxheight)C=BottomofRPVUSARRevision01of1April1989

NineMilePointUnit2FSARTABLE12.2-4REACTORWATERCLEANUPSYSTEMSOURCES(UCi/cc)~ZsotoeKr-83mXe-131mXe-133mXe-133Xe-135mXe-135N-170-19Nb-98Tc-104Br-83Br-84Br-85I-129I-131I-132I-133I-134I-135Np-239Rb-89Sr-89Sr-90Sr-91Sr-92Y-90Y-91mY-91Y-92Y-93Y-94,Zr-97Nb-95Nb-97mNb-97Mo-99Tc-99mTc-101RU-103RWCURegenerativeHeatExchaner1.23-044.93-098.68-071.22-059.92-041.56-041.84-061.87-011.48-023.19-012.29-022.85-021.38-022.76-181.30-022.19-011.60-013.86-011.70-012.40-012.12-023.10-032.30-046.89-021.10-013.54-084.72-041.10-041.93-021.20-024.00-054.20-051.69-059.34-082.20-022.80-013.65-015.40-05RWCUNonregenerativeHeatExchaner1.50-046.00-091.06-061.48-051.20-031.90-042.88-071.40-011.48-023.17-012.29-022.84-021.32-023.37-181.30-022.19-011.60-013.85-011.70-012.40-012.10-023.10-032.30-046.89-021.10-014.31-085.74-041.10-041.93-021.20-024.00-054.20-051.95-051.30-072.20-022.80-013.61-015.40-05RWCUFilter/Demineralizer4.20+004.99+016.00+002.06+022.61+018.70+019.64-017.14+004.20+001.14+004.39-022.61-131.36+023.16+022.56+022.55+018.70+011.03+033.96-015.06+014.11+005.13+012.26+013.02+003.08+016.17+012.27+017.72-022.73-084.13-027.53-013.96-024.13-021.09+001.30+026.35+008.59-01USARRevision01of3April1989

• I NineMilePointUnit2FSARTABLE12.2-4(Cont)~IsotoeRQ-105Ru-106Rh-103mRh-105mRh-105Rh-106Te-129mTe-129Te-131mTe-131Te-132Cs-134Cs-136Cs-137Cs-138Ba-137mBa-139Ba-140Ba-141Ba-142La-140La-141La-142Ce-141Ce-143Ce-144Pr-143Pr-144Nd-147Pm-147N-13F-18Na-24P-32Cr-51Mn-54Mn-56Fe-55Fe-59Co-58Co-60Ni-65Cu-64RWCURegenerativeHeatExchaner6.19-038.40-065.10-079.45-041.39-065.83-061.10-046.04-072.80-041.44-064.90-021.60-041.10-042.40-041.87-014.69-051.59-019.00-031.65-011.61-012.20-064.19-041.80-028.40-058.40-053.50-051.10-041.18-061.40-055.99-124.71-023.98-034.10-037.80-052.30-034.00-054.98-023.90-048.00-055.00-035.00-042.99-041.20-02RWCUNonregenerativeHeatExchaner6.18-038.40-066'.20-071.07-031.72-066.42-061.10-047.35-072.80-041.75-064.90-021.60-041.10-042.40-041.86-025.58-051.59-019.00-031.63-011.59-012.68-065.08-041.81-028.40-058.40-053.50-051.10-041.43-061.40-057.30-124.65-023.97-034.10-037.80-052.30-034.00-054.98-023.90-048.00-055.00-035.00-042.99-041.20-02RWCUFilter/Demineralizer2.10+001.49-018.56-012.12+004.74-031.49-011.72+001.70+006.46-011.29-012.78+021.61+002.76-024.28+001.84-033.94+001.69+011.13+023.73+002.09+009.82+013.99+001.99+002.32+002.13-016.17-011.51+006.15-011.67-019.65-047.12+004.73+001.02+003.48+017.06-019.85+006.95+001.29+008.38+018.93+005.85-021.19+01USARRevision02of3April1989

NineMilePointUnit2FSARTABLE12.2-4(Cont)~ieotoeZn-65Zn-69mAg-110mAg-110W-187N-16Zr-95Nb-95mZn-69Kr-85mKr-85RWCURegenerativeHeatExchaner7.80-058.19-046.00-055.96-073.00-034.78-038.46-063.37-053.86-13RWCUNonregenerativeHeatExchaner7.80-058.19-046.00-056.45-073.00-031.61-031.03-054.02-055.65-13RWCUFilter/Demineralizer1.37+008.67-011.05+00,2.10-025.51+007.40-013.44-03NOTE:1.23-04=1.23xl0USARRevision13of3October1989

NineMilePointUnit2FSARTABLE12.2-5RESIDUALHEATREMOVALSYSTEMPUMPANDHEATEXCHANGERSOURCETERMSAmendment9~Iso'to6Br-83I-131I-132I-133I-134I-135Nb-95Nb-97Nb-97mNb-98Ag-110Ag-110mW-187Np-239La-140La-141La-142Ce-141Ce-143Ce-144Pr-143Pr-144Nd-147F-18Na-24P-32Cr-51Mn-54Mn-56Fe-55Fe-59Co-58Co-60Ni-65Cu-64Zn-65Zn-69mZr-95Zr-97Sr-89Sr-901of2ActivityuCicc3(2)1~225.7-21~2-16.2-47.0-23.9-52.3-52.1-52.1-51.1-65.6-52~232.0-11~133~331.2-46.6-53.2-51.0-43.2-51.3-51.9-42.6-37.1-52~133.7-55.4-33'-47.4-54.6-34.6-43.2-57~237.2-55.1-43.7-52.2-5F9-32.1-4March1984

NineMilePointUnit2FSARTABLE12.2-5(Cont)~ieoooeSr-91Sr-92Y-90Y-91Y-91mY-92Y-93Mo-99Tc-99mRu-103RU-105Ru-106Te-129Te-129mTe-131Te-131mTe-132Cs-134Cs-136Cs-137Cs-138Ba-137mBa-139Ba-140Rh-103mRh-105mRh-106Activity~uCicc3.6-21~32l.7-52~8-42.4-23.0-2'.4-31.8-21.1-15.0-51.6-37.8-69.9-59.9-54.4-52.2-44'-21.5-49.8-52.2-45.8-62.0-42'-38.2-35.0-51.6-37.8-6'Valueslessthanlx10areassumedtobenegligible.'~'2.1-3=2.1x10Amendment92of2March1984 i

NineMilePointUnit2FSARTABLE12.2-6REACTORCOREISOLATIONCOOLINGSYSTEMDESIGNACTIVITIES~IeotoeKr-83mKr-85mKr-85Kr-87Kr-88Kr-89Kr-90Xe-131mXe-133mXe-133Xe-135mXe-135Xe-137Xe-138Br-83Br-84Br-85I-131I-132I-133I-134I-135Rb-88Rb-89Sr-89Sr-90Sr-91Sr-92Y-90Y-91mY-91Y-92Y-93Zr-95Zr-97Nb-95mNb-95Nb-97mNb-97Mo-99Tc-99mTc-101Activity~(uCioo2.95-045.16-041.65-061.78-031.79-031.02-021.42-021.27-062.44-057.05-042.25-031.97-031.17-027.35-031.60-052.51-051.44-051.22-051.50-041.22-043.60-041.27-043.17-051.01-061.46-071.08-083.24-065.16-068.89-138.09-095.18-098.99-075.64-071.88-091.50-092.27-151.97-094.00-101.16-121.03-061.32-051.75-05USARRevision1of3October1989

NineMilePointUnit2FSARTABLE12.2-6(Cont)~IeotoeRu-103Ru-105Ru-106Rh-103mRh-105mRh-106Te-129mTe-129Te-131mTe-131Te-132Cs-134Cs-136Cs-137Cs-138Ba-137mBa-139Ba-140Ba-141Ba-142La-140La-141La-142Ce-141Ce-143Ce-144Pr-143Pr-144Nd-147Pm-147N-13N-16N-170-19F-18Na-24-P-32Cr-51Mn-54Mn-56Fe-55Fe-59Co-58Co-60Activity~uCicc2.54-092.91-064.00-101.39-111.00-061.87-105.17-092.37-111.32-083.34-112.30-067.52-095.17-091.13-081.61-041.21-097.49-064.23-077.85-067.76-065.54-111.08-087.96-073.95-093.95-091.65-095.17-092.99-116.60-101.51-163.19-043.24-011.00-051.98-021.87-041.93-073.67-091.08-071.88-092.35-061.83-073.76-092.35-072.35-08USARRevision2of3April1989

NineMilePointUnit2FSARTABLE12.2-6(Cont)~IsotoeNi-65Cu-64Zn-65Zn-69mAg-110mAg-110W-187Nb-98Tc-104Np-239IActivity~ucicc1.41-085.64-073.67-093.85-082.82-093.03-111.41-077.01-071.52-051.13-05NOTE:2.95-04=2.95x103of3

NineMilePointUnit2FSARTABLE12.2-8TRAVERSINGINCOREPROBESYSTEMMATERIALSANDRADIATIONSOURCESA.MaterialCompositionofTIPSystemComponentsasUsedinActivationCalculationsWeightMaterialDetectorReionAISI304stainlesssteelCommerciallypuretitaniumFosteriteceramicNichromeUranium-2354.03.00.50.020.001Weight/LengthAISI3041stainlesssteelAISIC1070carbonsteelMagnesiumoxide0.122.100.12B.TIPDetectorDecayGammaActivitiesinMev/secof0.001gofU-235DecayTime=0secActivationTime=10~sec0.1-0.40.4-0.90.9-1.351.35>>1.81.8-2'2.2-2.62.6-3.03.0-3.53.5-4'4.0-4.54.5-5.05.0-5.5MeVSec3.4+91'+101.2+101.1+108.0+96.4+95.6+95.1+94.3+92.5+91.5+97.9+81of2 i

NineMilePointUnit2FSARTABLE12.2-8(Cont)C.TIPDetectorDecayGammaActivitiesofMaterialsinDetector(ExcludingU-235)inuCiinIrradiatedDetectorDecayTime=0secActivationTime=10~secActivateduCiFe-S9Mn-56Cr-51Mn-54Co-58mCo-58Ni-57Co-57Ni-65Co-60mCo-60Co-61Si-311.1+11.7+57.0+12.1+03.5+32.2-21~116.0-74.0+27.6+31.8-39.6+02.9+1D.DecayGammaActivitiesofMaterialsintheCableinuCi/inofIrradiatedCableDecayTime=0secActivationTipe=3,0~secActivatedu~ciinFe-59Mn-56Cr-S1Mn-54Co-58mCo-S8Ni-57Co-57Ni-65Co-60mCo-60Co-61Si-318.2+07.4+43.7+01.6+01.0+26.5-43~331.8-81.2+12.2+25.1-52.8-18;7-1NOTE:3.4+9=3.4x10~2of2

NineMilePointUnit2FSARTABLE12.2-9AVERAGEN-16ACTIVITIESINEQUIPMENTINTHETURBINEBUILDINGComonentEqualizertubeHigh-pressureturbineMoistureseparator/reheater,tubeMoistureseparator/reheater,shellMoistureseparatordraintankReheaterdraintankLow-pressureturbineCondenserAirremovalpipingSecondpointheaterdraincoolerThirdpointheaterdraincoolerFirstpointheater,shellsideSecondpointheater,shellsideThirdpointheater,shellsideFourthpointheater,shellsideFifthpointheater,shellsideSixthpointheater,shellsideCleansteamreboilersidesideActivity~uCi~8.56+017.70+015.49+016.79+014.80-023.40-027.03+012.97+012.68+00*2.06-0'42.02-036.26+015.75+018.46+001.17+003.83+004.07+004.98+01NOTE:8.56+01=8.56xlO'uCi/ccUSARRevision11of1October1989

NineMilePointUnit2FSARTABL'E12.2-10CONDENSATESYSTEMSOURCETERMS~ZeotoeKr-83mKr-85mKr-85Xe-131mXe-133mXe-133Xe-135mXe-135Br-83Br-84Br-8SI-129I-131I-132I-133I-134I-135Rb-89Sr-89Sr-90Sr-91Sr-92Y-90Y-91mY-91Y-92Y-93Zr-95Zr-97Nb-95mNb-95Nb-97mNb-97Mo-99Tc-99mTc-101Ru-103Ru-105Ru-106Hotwell(5-minDelay)andPipingUpstreamofCondensateDemineralizerActivity(uCicc0.00.00.00.00.00.00.00.03.32-044.84-041.02-040.02.60-043.12-032.59-037.21-032.68-031.75-053.10-062.30-076.86-051.08-042.07-102.67-061.11-072.05-051.19-054.00-083.19-081.86-134.20-082.92-081.10-092.20-052.78-042.98-045.40-086.12-068.40-09CondensateDemineralizerActivity(uCicc*1.25-017.69-041.59-067.83-022.47-018.49+004.31-012.80+001.25-014.05-027.69-041.35-117.86+001.74+008.50+009.96-012.80+007.00-043.18-013.38-021.03-014.62-023.14-025.99-026.15-025.76-021.89-024.41-038.50-052.87-055.62-038.05-058.53-052.29-014.65-011.11-025.05-034.29-031.17-03USARRevision11of3October1989

NineMilePointUnit2FSARTABLE12.2-10(Cont)~IsotoeRh-103mRh-105mRh-105Rh-106Te-129mTe-129Te-131mTe-131Te-132Cs-134Cs-136Cs-137Cs-138Ba-137mBa-139Ba-140Ba-141Ba-142La-140La-141La-142Ce-141Ce-143Ce-144.Pr-143Pr-144Nd-147Pm-147Na-24P-32'r-51Mn-54Mn-56Fe-55Fe-59Co-58Co-60Ni-65Cu-64Hotwell(5-minDelay)andPipingUpstreamofCondensateDemineralizerActivity(uCicc2.90-091.70-069.42-098.39-091.10-073.46-092.79-077.94-094.90-051.60-071.10-072.40-071.71-041.68-071.53-049.00-061.41-041.23-041.29-082.25-062.17-058.41-088.39-083.50-081.10-076.33-091.40-083.50-144.08-067.80-082.30-064.00-084.89-053.90-078.00-085.00-065.00-072.93-071.20-05CondensateDemineralizerActivity(uCicc*4.55-031.20-034.34-031.17-039.59-036.23-031.32-032.91-046.05-012.29-025.18-033.52-021.45-023.33-023.32-024.15-016.78-033.46-034.12-018.18-038.74-031.29-024.37-044.81-035.74-034.81-035.69-041.69-059.69-033.95-031.82-015.53-031.99-025.62-027.89-035.66-017.28-021.17-042.40-02USARRevision12of3October1989

NineMilePointUnit2FSARTABLE12.2-10(Cont)~ZsotoeZn-65Zn-69mAg-110mAg-110W-187Nb-98Tc-104Np-239Zn-69Pu-239H-3N-13F-18Hotwell(5-minDelay)andPipingUpstreamofCondensateDemineralizerActivityuCicc7.80-088.17-076.00-087.80-102.99-061.40-052.72-042.40-044.81-081.00-024.95-033.88-03CondensateDemineralizerActivityuCicc*1.06-021.77-038.17-031.06-041.13-021.88-031.29-022.14+001.78-038.88-061.46+031.30-011.15+00*Perccofresinvolume.NOTE:1.25-01=1.25xl0USARRevision13of3October1989

NineMilePointUnit2FSARTABLE12.2-11OFF-GASSYSTEMSOURCEACTIVITIES(Ci)~IsotoeXe-131mXe-133mXe-133Xe-135mXe-135Xe-137Xe-138Cs-138Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Rb-88CharcoalAdsorberActivities6.30+012.78+021.87+041.17+023.92+031.21+023.41+023.41+021.15+024.74+029.97+004.65+021.04+038.37+011F04+03NOTE:6.30+01=6.30x10'of1

NineMilePointUnit2FSARTABLE12.2-13SOLIDRADWASTESYSTEMCOMPONENTSDESIGNACTIVITIES(uCi/cc)~ZeotoeBr-83Br-84Br-85I-129I-131I-132I-133I-134I-135Rb-89Sr-89Sr-90Sr-91Sr-92Y-90Y-91mY-91Y-92Y-93Y-94Zr-95Zr-97Nb-95mNb-95Nb-97mNb-97Mo-99Tc-99mTc-101Ru-103Ru-105Ru-106Rh-103mRh-105mRh-105Rh-106Te-129mWasteSludgeTank1.56-14.22-21.63-31.09-111.94+12.12+11.01+19.43-13.22+01.47-22.68+13.49+01.90+08'5-13.43+01.15+03.49+18.41-12.87-31.01-91.58-32'1-11.51-31.58-36.93-24.85+02'5-14'6-17'8-21.18-14.06-17.84-22.26-41.18-17.44-1ExtruderEvaporatorWasteCasks2033-26.30-22.43-31.63-112.90+13.17+11.51+11.41+04.81+02.19-24.00+15.21+02.84+01.25+05.12+01.72+05.21+11.26+04.28-31.51-92.36-34.34-12.25-42.36-31.03-17.24+03.51-16.06-11.16-11.76-16.06-11.17-13.37-41.76-11.11+0USARRevision11of3October1989

NineMilePointUnit2FSARTABLE12.2-13(Cont)~ZsotoeTe-129Te-131mTe-131Te-132Cs-134Cs-136Cs-137Cs-138Ba-137mBa-139Ba-140Ba-141Ba-142La-140La-141La-142Ce-141Ce-143Ce-144Pr-143Pr-144Nd-147Pm-147F-18Na-24P-32Cr-51Mn-54Mn-56Fe-55Fe-59Co-58Co-60Ni-65Cu-64Zn-65Zn-69mAg-110mAg-110W-187Nb-98Tc-104Np-239WasteSludgeTank7.44-12.80-25.60-3.1.95+11.32+06.19-33.64+06.82-53.35+06.25-12.40+11.38-17~7322.60+11.48-17.39-29.88-19.53-34.79-13.40-14.79-13~1322.05-32.64-11.79-12.37-11.34+15.53-13.65-15.76+06.46-15.04+17.50+02.16-34.47-11.05+03.26-28.10-11.62-22.24-13.57-22.64-15.92+1ExtruderEvaporatorWasteCasks1.11+04.18-28.36-32.91+11.97+09.24-35.43+01.02-45.00+09.33-13.58+12.06-11.15-13.88+12.21-11.10-11.48+01.42-27.15-15.08-17.15-14.67-23.06-33.94-12.67-13.54-12.00+18.26-15.45-18.60+09.64-17.52+11.12+13~2236.67-11.57+04.87-21.21+02.42-23.34-15.33-23.94-18.84+1USARRevision12of3October1989

NineMilePointUnit2FSARTABLE12.2-13(Cont)~ZsotoeNb-98Tc-104Np-239WasteSludgeTank3.57-22.64-15.92+1ExtruderEvaporatorWasteCasks5.33-23.94-18,84+1NOTE:1.56-1=1.56xl0USARRevision03of3April1989

NineMilePointUnit2FSARTABIE12.2-14THEINFORMATIONONTHISPAGEHASBEENDELETED.Amendment71of1December1983

NineMilePointUnit2FSARTABLE12.2-16CRUDRADIATIONLEVELSComonentSstemRCICpiping/pumpRHRpiping/heatexchangerCRDdischargeheaderpumps/filterRWCUpiping/pumpsheatexchangerReactorbuildingequipmentdrain*tankcoolerpumpDrywellequipmentdrain*tankcoolerpumpAdditionalContactDoseRateDuetoCrudmremhr60600600502,0002,5006,0003,0002,00030,00015,00010,000*Theanalysesperformedforthesesystemsarebasedentirelyonthecrud."levelsquoted.Amendmentll1of1June1984 lg0I,tr NineMilePointUnit2FSAR6.Assureanextremelyhighprobabilityofaccomplishingtheirsafetyfunctionsintheeventofanticipatedoperationaloccurrences.AdditionalcriteriaarefoundinSection11.5.1.2.Theprimarydesigncriteriaforthenonsafety-relatedin-plantairborneradioactivitymonitoringsystemsareto:1.Providecontinuousdataoutputinthemaincontrolroomofradiationlevelsinselectedbuildingexhaustsystems.2.'ermitcheckingtheoperationalavailabilityofeachchannelduringreactoroperationwithprovisionforcalibrationfunctionandinstrumentchecks.3.Performtheirintendedfunctionsundernormaloperatingconditionsforthedesignlifeoftheplant.AdditionalcriteriaarefoundinSection11.5.1.2.12.3.4.2.2CriteriaforAirborneRadioactivityMonitorLocationsThefollowingcriteriaforlocatingairborneradioactivitymonitorsaredependentuponthepointofleakage,theabilitytoidentifythesourceofradioactivitysothatcorrectiveactionmaybeperformed,andthepossibilityforexposingpersonneltoairborneradioactivity:l.Airborneradioactivitymonitorssamplethedrywellatmosphereforreactorpressureboundaryleakdetection.2.Theoutsideairintakeductsforthemaincontrolroomareaaremonitoredtomeasurethepossibleintroductionofradioactivematerialsintothemaincontrolroomto'nsurehabitabilityofthoseareasrequiringpersonneloccupancyforsafeshutdown..3.Exhaustductsservicinganareacontainingprocesseswhich,intheeventofamajorleakage,couldresultinconcentrationswithintheplantapproachingthelimitsestablishedby10CFR20forplantworkersaremonitored.MonitorsensitivitycriteriaarenotedinSection12.3.4.2.5.AirborneprocessandeffluentradiationmonitorlocationsandfunctionsaresummarizedinTable12.3-2.ANSIN13.1wasusedasaguideinlocatingmonitorsandsamplepoints.Monitorlocationsareshownontheshieldingarrangementandfacilitiesdrawings,Figures12.3-1through12.3-33.IUSARRevision7.12.3-29October1994 NineMilePointUnit2FSAR12.3.4.2.3SystemDescription(AirborneRadioactivityMonitors)MonitorsReiredforSafetDrwellAtmoshereMonitorinThedrywellatmosphereradiationmonitorsaredesignedforearlyRCPBleakdetectioninaccordancewithRG1.45.Redundantoff-linegasandparticulatemonitorslocatedinthereactorbuildingarededicatedtosamplingthedrywellatmosphere.Samplesaredrawnfromthevariouselevationsofdrywellairbytheuseofsamplingtrees,arepumpedthroughthemonitoringsystem,andthenarereturnedtothedrywell.Eachsampleiscontinuouslymonitoredforparticulateandgaseousactivities.AcompletemonitordescriptionisfoundinSection11.5.2.1.1.Aremovableiodinecartridgefilter,whichmaybeusedforlaboratoryanalysis,isprovidedbetweenthemovingparticulatefilterandthegassamplechamber.Alarmsareprovidedforalertorhighradiationlevelsforeachchannel.Alarmsarealsoprovidedforchannelorsamplingsystemcomponentfailure.Allalarmsareannunciatedlocallyatthemonitorandinthemaincontrolroom.Recoidersareprovidedinthemaincontrolroomtomaintainapermanentrecordofdrywellradiationlevels.ReactorBuildinVentilationExhaustOneoff-linegasandparticulateandoneoff-linegasmonitor(Section11.5.2.1.1)areprovidedonthereactorbuildingventilationexhaustairductwork,bothaboveandbelowtherefuelingfloor.Theirfunctionistoindicatetheairbornelevelsofactivityinthereactorbuilding.Samplingisperformedbyanisokineticsamplingsystem.Onahighradiationalarmsignalthereactorbuildingventilationintakeandexhaustairi,sisolatedandthereactorbuildingairisrecirculated,withasmallfractionbeingdivertedthroughtheSGTSandexhaustedaftertreatment.MainControlRoomVent'ilationThemaincontrolroomventilationradiationmonitorsaredesignedtomeasuretheradiationlevelsinthejunctionofthetwoinletducts-ofthemaincontrolroomventilationsystem,and.automaticallydiverttheairthroughtheemergencyfiltersystemondetectionofhighradiation.Dualredundantoff-linegasmonitors(Section11.5.2.1.1)areprovidedinthemaincontrolroomoutsideairintakeducts'unction.Samplingisperformedbyasamplingsystemwithprobesandreturnslocatedneartheintakes.Themonitorsforthisintakearelocatedinthecontrolbuilding.Themaincontrolroomradiationmonitorsprovideasinglechannelforgaseousactivityonly.Fixed-particulateandiodinefiltersarelocatedupstreamofthegassamplechamberandcanberemovedforanalysisinthehealthphysicslaboratory.Alertandhighradiationlevels,channelfailure,andsamplingsystemfailurearealarmedlocallyandinthemaincontrolroom.USARRevision7.12.3-30October1994 NineMllePointUnit2FSARTABLE12.3-3PERSONNELDOSESFORREQUIREDOCCUPANCYTIMESINVITALAREASVitalAreaHaincontrolroomandrelayandcomputerroomHealthphysics/countingroomUnit1Radwastesampleroom/Unit1chemistrylab(PASS)(1,2)TurbinebuildingofflineisotopicmonitorTaskPerformedExecutethesafeshutdownoftheplantPerformroutinehealthphysicsfunctionsandanalyzeradioactivegrabsamplesa)ObtainandperformgeneralisotopicandBoronanalysisofdilutereactorcoolantsample(3)b)Obtainandperformisotopicanalysisofcontainmentatmospheresample(3)c)Determinelevelofdis-solvedgases(e.g,H2)lnreactorcoolantd)Obtainandperformchlorideanalysisofundilutedzeactorcoolantsample(3)Replacelargeliquidnitrogendewar(4)OccuancTimeContinuousfor30days8hr1hr,5min52min1hr,45min1hr18min22minDoserem1.73+02.37-11.84+02.10+02.07+03.73+06.38-16.38-14.41+01.60+13.62-1Notes30-dayaveragedoserate=5.50mRem/hrDosebaseduponcontinuousoccupancyforan8-hrworkdayatthetimeofmaximumdoserateWholebodyExtremityWholebodyExtremityWholebodyExtzemityWholebodyExtremityDoseincludesdosereceivedforoneroundtripbetweentheOSCandthemonitorlocationHainstackoffllneisotopica)Replacelargeliquidnitrogenmonitordewarandrefillsamplecar-tridgefeedhopper(4)24min2.44+0DoseincludesdosereceivedforoneroundtripbetweentheOSCandthemonitorlocation.Radwastecontrolroomb)Manualsampling(5)a)Turnoffreactorbuildingequipmentandfloordrainpumps53min12min2.73+02.79+05.96-1WholebodyExtremityDoseincludesdosereceivedforoneroundtripbetweentheOSCandtheradwastecontrolzoomUSARRevision01of2April1989

NineMilePointUnit2FSARTABLE12.3-3(Cont)VitalAreaAone-waytripbetweentheOSCandthecontrolroomemergencyzoneTechnicalsupportcenterTaskPerformedb)ServiceERFcomputersystemForinformationonlyPerNUREG-0696OccuancTime22min6minContinuousfor30daysinaccor-dancewiththeSiteEmergencyPlanproceduresDoserem8.0s-l1~92-14.30+0NotesWholebody(l)Maximumdoserateforeachsubtaskwasusedtodevelopthemaximumdoseforthetask.(2)SeeSection1.10,ItemII.B.3,forspecificinformationonthepost-accidentsamplingsystemandTableII.B.3-1f'rabreakdownofthetasksandrequiredoccupancytimes.(3)DoseincludesexposurereceivedforoneroundtripfromtheOSC,totheradwastesampleroom,totheUnit1chemlab,andbacktotheOSC.(4)Thisassumesthatthesparedewa?isstoredatthemonitorlocation.(5)DoseincludesexposurereceivedforoneroundtripfromtheOSC,tothemainstack,totheUnit1countingroomandbacktotheOSC.USARRevision02of2April1989

NineHilePointUnit2FSARTABLE12.3-4DOSERATE(REH/HR)ATLOCATION:*TimePost-LOCABH1369121824501002004005507207.31+12.25+02.34+02.44+01.77+01.69+01.67+01.39+01.38+01.34+08.18-14.73-12.19-17.33+12.49+02.64+02.74+02.09+02.03+02.01+0l.72+0l.71+01.67+01.02+05.85-12.73-17.40+03.42+03.45+0"3.63+02.74+02.64+02.57+02.16+02.14+02.07+01.27+07.27-13.38-17.42+03.73+03.86+04.05+03.19+03.11+03.06+02.61+02.60+02.53+01.55+08.89-14.13-17.42+03.73+03.86+04.05+03.19+03.11+03.06+02.61+02.60+02.53+01.55+08.89-14.13-17.46+14.31+04.57+04.83+04.00+03.95+03.91+03.42+03.44+03.35+02.05+01.18+05.49-19.23+14.59+04.89+05.17+04.26+04.21+04.17+03.67+03.69+03.60+02.21+01.27+05.92-18.97+23.99+04.52+04.81+04.19+04.22+04.27+03.86+03.91+03.83+02.35+01.35+06.31-18.98+24.07+04.56+04.85+04.17+0l4.20+04.22+03.79+03.83+03.76+02.31+01.32+06.18-11369121824501002004005507208.98+23.76+04.18+04.44+03.75+03.76+03.78+03.39+13.42+03.26+02.06+01.18+05.49-1K8.97+23.12+03.41+03.60+02.87+02.86+02.86+02.53+02.55+02.48+01.53+08.73-14.108.97+22.13+02.21+02.30+01.52+01.46+01.43+01.19+01.19+01.15+07.04-14.02-11.88-18.96+22.00+02.11+02.20+01.47+01.42+01.40+01.18+01.19+01.15+07.04-14.02-11.88-1N8.96+22.00+02.11+02.20+01.47+01.42+01.40+01.18+01.19+01.15+07.04-14.02-11.88-108.97+23.63+04.08+04.34+03.70+03.72+03.75+03.38+03.42+03.26+02.06+01.18+05'9-11.06+24.13+04.69+04.97+04.29+04.34+04.37+03.96+04.02+03.94+02.42+01.39+06.47-11.81+23.21+04.82+05.10+03.95+03.98+04.00+03.62+03.67+03.59+02.21+01.27+05.92-1R1.80+24.00+04.64+04.92+03.93+03.97+03.99+03.62+0I3.67+03.59+02.21+01.27+05.92-1<<RefertoFigure12.3-69.USARRevision1lof4October1989

NineMilePointUnit2PSARTABLE12.3-4(Cont)TimePost-LOCA~H1369121824501002004005507201.80024.00+04.64+04.92+03.93+03.97+03.99+03.62+03.67+03.59+02.21+01.27+05.92-11.80+2F81+04.42+04.68+03.67+03.71+03'3+03.37+03.41+03.34+02.05+01.18+05.49-11.79+23.23+03.71+03.90+02.86+02.87+02.88%02.56+02.57+02.52+01.55+08.87-14.13-11.79+22.50402.8840299+01.90+01.89+01.90+01.69+01.69+01.66+01.02+05.85-12.73-11.78+21.92+02.17+02.23+01.10+01.07+01.05+09.05-18.91-18.65-15.31-13.04-11.42-11.78+21.80002.02402.07+09.27-18.91-18.71-17.56-17.19-16.95-14.27-12.44-11.14-19.15+13.23+03.50403.68+03.05+02'9+02.95402'7+02.56+02.49+01.53-08.75-14.10-19.09+12.24+02.30+02.38+01.70+01.59+01.52+01.63401.20+01.15+07.05-14.04-11.88-11369121824501002004005507208.97+22.13+02.21+0230+01.52+01.46+01.43+01.19+01.19+01.15+07.04-14.02-11.88-19.15+13.23+03.50+03.68+03.05+02.99+02.95+02.97+02.56+02.49+01.53+08.75-14.10-19.15+13.23+0F50+03.68+03.05+02.99+02.95%02.97002.56+02.49+01.53+08.75-14.10-19.19+13.87+04.27+04.52403.93+03.89+03.87+03.83+03.43+03.26+02.06+01.18+05.49-1AE9.26+14.72+05.05+05.34+04.43+04.39+04.36+03.83+03.85+03.76+02.31+01.32406.18-1AF'.06+24.90405.28+05.57+04.60004.57+04.54+04.01+04.04+03.94+02.42+01.39+06.47-19.23+14.77+05.11+05.40404.50+04.45+04.44+03.91+03.93403.84+02.35+01.35406.31-19.22+14.59+04.89+05.17+04.26+04.21+04.17+03.67+03.69+03.60+02'1+01.27+05.92-19.23+14.77+05.11+05.40+04.50+04.45+04.44+03.91+03.93+03.84+02'5+01.35+06.31-1~RefertoFigure12.3-69.USARRevision12of4October1989

NineMilePointUnit2FSARTABLE12.3-4(Cont)TimePost-LOCA~H1369121824501002004005507209.21+14.30404.80005.08+04.52+04.51+04.49+04.41+04.03+03.94002.42+01.39+06.47-19.23+14.77+05.11+05.40+04.50+04.45+04.44+03.91+03.93+03.84+02.35+01.35+06.31-19.22+14.59+04.89+05.17+04.26+04.21+04.17+03.67+03.69+03.60+02.21+01.27+05.92-12.07+04.11+04.31+04.55+03.72+03.65+03.61+03.14+03.15+03.07+01.88%01.08+05.04-11.85+03.73003.86+04.05+03.19+03.11+0'.06+02.61+02.60+02.53+01.55+08.89-14.13-1AO1.85+03.73+03.86+04.05+03.19+03.11+03.06+02.61+02.60002.53+01.55+08.89-14.13-17.34+12.78+02.96+03.13+02.48+02.45+02.43+02.12+02.12+02.07+01.27+07.25-13.38-17.40+13.42+03.45+03.63+02.74+02.64+02.57+02.16+02.14+02.07+01.27+07.27-13.38-1TimePost-LOCA~H1369121824501002004005507207.34+12.78+02.96+03.13+02.48+02.45+02.43+02.12+02.12+02.07+01.27+07.25-13.38-17.31+12.25+02.34+02.44+01.77+01.69+01.67+01.39+01.38+01.34+08.17-14.73-12.19-1HealthPhysics/CountingRoomUnit12.46+02.96-22.81-22.81-27'7-35.24-34.06-31.02-36.07-41.15-45.23-52.08-57.59-6TurbineBuildingRadvasteSampleRoom1.41+13.50-13.18-12.97-11.43-11.04-18.22-23~2722.13-2l.43-28.90-35.18-32.46-3TurbineBuildingOfflineIsotopicMonitor9.15+13.23+03.50+03.68+03.05+02'.99+02.95%02.97+02.56+02.49+01.53408.75-14.10-1MainStackOff1incIsotoicMonitor4.44+04.71+06.32+05.43+05.53+05.85+04.99+05.54+05.74+05.44+02.90+01.72+01.17+0*RefertoFigure12'"69USARRevision03of4April1989

NineMilePointUnit2FSARTABLE12.3-4(Cont)TimePost-LOCA~H136912182450100200400550720RadvasteControlRoom3.51+11.25+01.21+01.19+08.25-17.18-16.14-14.67-14.10-13.79-12.34-11.35-16.35-2Unit1ChemistryLab5.12+06.50-26.19-26.17-21.77-21.26-29.71-32.62-31.53"34.35-42.34-41.18-45'8-5~RefertoFigure12.3-69USARRevision04of4April1989 "IF