ML18040B194

Forwards Application for Proposed Amend 58 to License NPF-22,changing Tech Specs to Support Cycle 3 Reload.Unit Scheduled to Shutdown on 880305 & Restart on 880503.Reload Summary & Transient Analysis Repts Encl.Fee Paid

ML18040B194
Person / Time
Site:	Susquehanna
Issue date:	12/23/1987
From:	KENYON B D PENNSYLVANIA POWER & LIGHT CO.
To:	BUTLER W R Office of Nuclear Reactor Regulation
Shared Package
ML17146B090	List: ML17146B089 ML17146B092 ML17146B094 ML17146B095 ML17146B096 ML17146B102 ML18040B194
References
PLA-2953, NUDOCS 8712310143
Download: ML18040B194 (62)

Text

'(.'CELEMTEDDJiIBUTJONDEMONS~TIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:8712310143DOC.DATE:87/12/23NOTARIZED:YESDOCKETFACIL:50-388SusquehannaSteamElectricStation,Unit2,Pennsylva05000388AUTH.NAMEAUTHORAFFILIATIONKENYON,B.D.PennsylvaniaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONBUTLER,W.R.ProjectDirectorateI-2p~gI

SUBJECT:

ForwardsapplicationforProposedAmend58toLicenseNPF-22,changingTechSpecstosupportCycle3reload.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRENCLiSIZE:+!,TITLE:ORSubmittal:GeneralDistributionNOTES:1cyNMSS/FCAF/PM.LPDR2cysTranscripts.05000388RECIPIENTIDCODE/NAMEPD1-2LATHADANI,MCOPIESRECIPIENTLTTRENCLIDCODE/NAME10PD1-2PD11COPIESLTTRENCL55AINTERNAL:ACRSNRR/DEST/ADSNRR/DEST/MTBNRR/DOEA/TSBOGC/HDS2RES/DE/EIB661'111111011ARM/DAF/LFMBNRR/DEST/CEBNRR/DEST/RSBNRR8/ILRBEGFI01111110111I'D8EXTERNAL:LPDR.,NSICNOTES:-.221133NRCPDR11R8A'DTOTALNUMBEROFCOPIESREQUIRED:LTTR30ENCL278 OEG231987alt~~IIPennsylvaniaPower8LightCompany,TwoNorthNinthStreet,~Allentown,PA18101~215/7706151IBruceD.KenyonSeniorVicePresident-Nuclear215/770-4194DirectorofNuclearReactorRegulationAttention:Dr.W.R.Butler,ProjectDirectorProjectDirectorateI-2DivisionofReactorProjectsU.S.NuclearRegulatoryCommissionWashington,D.C.20555SUSQUEHANNASTEAMELECTRICSTATIONPROPOSEDAMENDMENT58TOLICENSENO.NPF-22:UNIT2CYCLE3RELOADSUBMITTALPLA-2953FILESR41>>2,A17-2,A7-8CDocketNo.50-388

DearDr.Butler:

ThepurposeofthisletteristoproposechangestotheSusquehannaSESUnit2TechnicalSpecificationsinsupportoftheensuingCycle3reload.ChangestothefollowingTechnicalSpecificationsarerequested:3/4.2.13/4.2.23/4.2.33/4.2.43/4.3.63/4.4.1B2.1B3/4.2.1B3/4.2.2~B3/4.2.3B3/4.4.1IndexAveragePlanarLinearHeatGenerationRateAPRMSetpointsMinimumCriticalPowerRatioLinearHeatGenerationRateControlRodBlockInstrumentationRecirculationSystemSafetyLimitsAveragePlanarLinearHeatGenerationRateAPRM'etpointsMinimumCriticalPowerRatioRecirculationSystemThefollowingattachmentstothisletterareprovidedtoillustrateandtechnicallysupporteachofthechanges:8712310i43PDRADOCKPgooIt8712230500038)(Marked-upTechnicalSpecificationChangesNoSignificantHazardsConsiderationsPL-NF<<87-007"SusquehannaSESUnit2Cycle3ReloadSummaryReport",December1987SusquehannaSESUnit2Cycle3ProposedStartupPhysicsTestsSummaryDescription,November1987ANF-87-125,Revision1,"SusquehannaUnit2Cycle3PlantTransientAnalysis",November1987ANF-87-126,Revision1,"SusquehannaUnit2Cycle3ReloadAnalysis",November1987 DEC23l98i, FILESR41-2,A17-2,A7-8CPLA-2953Dr.W.R.ButlerSusquehannaSESUnit2iscurrentlyscheduledtobeshutdownforrefuelingandinspectiononMarch5,1988andtorestartasearlyasMay3,1988.Werequestthatyourapprovalbeconditionedtobecomeeffectiveuponstartupafterthisoutage,andwewillkeepyouinformedofanyschedulechanges.AnyquestionswithrespecttothisproposedamendmentshouldbedirectedtoMr.R.Sgarroat(215)770-7916.Pursuantto10CFR170,theappropriatefeeisenclosed.Verytrulyyours,B.D.KenyonSr.VicePresident-NuclearAttachmentscc:iNRCDocumentControlDesk(original)gNRCRegionIMr.J.Stair,NRCResidentInspector-SSESMr.M.C.Thadani,NRCProjectManager-BethesdaMr.T.M.Gerusky,PennsylvaniaDER 1IBASESINDEX~8712310143lSECTION3/4.0APPLICABILITY.3/4.1REACTIVITYCONTROLSYSTEMS3/4.l.1SHUTDOMNMARGIN...3/4.1.2REACTIVITYANOMALIES....,..3/4.l.3CONTROLRODS.PAGEB3/40-1B3/41-1B3/41-18.3/41"2.3/4.1.4CONTROLRODPROGRAMCONTROLS........~.......,...B3/41-33/4.2.2APPMSETPOINTS~~~~~~~~~~~~~~~~~~~3/4.2.,3MIHIMUMCRITICALPOWERRATIO.3/4.1.5STAHDBYLIQUIDCONTROLSYSTEM.....,.............7.3/4.2POWERDISTRIBUTIONLIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONATE~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~RB3/41"4B3/42-1B3/42"2IB3/42"A~3/4.2.4LINEARHEATGENERATIONRATE.........,...B3/42-JSB3/4.3INSTRUMENTATION3/4.3.13/4.3.23/4.3~33/4.3.43/4.3.53/4.3.6REACTORPROTECTIONSYSTEMINSTRUMENTATION...ISOLATIONACTUATIONINSTRUMENTATION....,....EMERGENCYCORECOOLINGSYSTEMACTUATIONINSTRUMENTATION....RECIRCULATIONPUtIPTRIPACTUATIONINSTRUMENTATION.REACTORCOREISOLATIONCOOLINGSYSTEMACTUATIONINSTRUMEHTATIOH.CONTROLRODBLOCKINSTRUMENTATION.B3/43-1B3/43"2B3/43-283/43-3B3/43-4B3/43-4'SUSQUEHANNA"UNIT2'11 lI00 LISTOFFIGURESINDEXFIGURE3.1.5-13.l.'5"23.2.1-1SODIUMPENTABORATESOLUTIONTEMPERATURE/CONCENTRATIONREQUIREMENTS..SODIUMPENTABORATESOLUTIONCONCENTRATIONMAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE'(MAPLHGR)VS.AVERAGEPLANAREXPOSURE,GEFUELTYPE8CR183(1.83KENRICHED)PAGE3/41-213/41-223/42"23.2.1-23.2.1-33.2.2-13~2.3"13.2.323.2.4.2"13.4.1.1"13i4.1mZ3.4.6.1"1MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(MAPLHGR)VS.AVERAGEPLANAREXPOSURE,GEFUELTYPE8CR233(2.33KENRICHED)................3/42-3MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(MAPLHGR)VS.AVERAGEBUNDLEEXPOSURE,~it9x9FUEL.......................3/42-4REFLINEARHEATGENERATIONRATEFORAPRMSETPOINTSVERSUSAVERAGEPLANAREXPOSURE,~~C-...,.....3/42-6aRlVFFvE.LFLOWDEPENDENTMCPROPERATINGLIMIT..3/42"8REDUCEDPOWERMCPROPERATINGLIMIT..............3/42-9LINEARHEATGENERATIONRATE(LHGR)L:MITVERSUSAVERAGEPLANAREXPOSURE,&HNN'x9FUEL..........3/42-10b/cozet=L.oW4~~THERMALPOWERALIMITATIONS'''''''''''344lb>>+"~~aPO4'8Rw'imTH&RPl~lPo~6Ru~~TATiousMINIMUMREACTORVESSELMIFTALTEMPERATUREVS.REACTORVESSELPRESSURE...........3/44-184.7.4"1B3/43"1B3/4.4.6"15.1.1-15.l.2-15.l.3-la5.1.3"lbSAMPLEPLAN2)FORSNUBBERFUNCTIONALTEST....REACTORVESSELWATERLEVEL.....FASTNEUTRONFLUENCE(E>1MeV)AT1/4TASAFUNCTIONOFSERVICELIFEEXCLUSIONAREA.......~LOWPOPULATIONZONE.MAPDEFININGUNRESTRICTEDAREASFORRADIOACTIVEGASEOUSANDLIQUIDEFFLUENTSMAPDEFININGUNRESTRICTEDAREASFORRADIOACTIVEGASEOUSANDLIQUIDEFFLUENTS3/4?"15B3/43-8B3/44"75"25-35-5SUSQUEHANNA-'UNIT2xx11AmendmentNo.3) 4eQ~('IAi~uv~~0ii0ei~

2.1SAFETYLIMITSBASES

2.0INTRODUCTION

Thefuelcladding,reactorpressurevesselandprimarysystempipingaretheprincipalbarrierstothereleaseofradioactivematerialstotheenvirons.SafetyLimitsareestablishedtoprotecttheintegrityofthesebarriersduringnormal.plantoperationsandanticipatedtransients.ThefuelcladdingintegritySafetyLimitis'setsuchthatnofueldamageiscalculatedtooccurifthelimitisnotviolated.Becausefueldamageisnotdirectlyobservable,astep-backapproachisusedtoestablishaSafetyLimitsuchthattheMCPisnotlessthanthelimitspecifiedinSpecification2.l.2forbothGEandn..fuel.MCPRgreaterthanthespecifiedlimitrepresentsaconser-vativemarginrelativetotheconditionsrequiredtomaintainfuelcladdingintegrity.Thefuelcladdingisoneofthephysicalbarrierswhichseparatetheradioactivematerialsfromtheenvirons.Theintegrityofthiscladdingbarrierisrelatedtoitsrelativefreedomfromperforationsorcracking.Al-thoughsomecorrosionoruserelatedcrackingmayoccurduringthelifeofthecladding,fissionproductmigrationfromthissourceisincrementallycumulativeandcontinuouslymeasurable.Fuelcladdingperforations,however,canresultfromthermalstresseswhichoccurfromreactoroperationsignificantlyabovedesignconditionsandtheLimitingSafetySystemSettings.Whilefissionpro"ductmigrationfromcladdingperforationisjustasmeasurableasthatfromuserelatedcracking,thethermallycausedcladdingperforationssignalathresholdbeyondwhichstillgreaterthermalstressesmaycausegrossratherthanincre-mentalcladdingdeterioration.Therefore,thefuelcladdingSafetyLimitisdefinedwithamargintotheconditionswhichwouldproduceonsetoftransitionboiling,MCPRof1.0.Theseconditionsrepresentasignificantdeparturefromtheconditionintendedbydesignforplannedoperation.TheMCPRfuelcladdingintegritySafetylimitassuresthatduringnormaloperationandduringantici-patedoperationaloccurrences,atleast99.9Xofthefuelrodsinthecoredonotexperiencetransitionboiling(ref.XN-NF-524(A)).2.'l.lTHERMALPOWERLowPressureorLowFlow~<'P~~C~l+hENSE'TheuseoftheXN-3correlationisnotvalidforallcriticalpowecalcu'satpressuresbelow785psigorcoreflowslessthan1ofratedflow.There,thefuelcladdingintegritySafetyLimitiablishedbyothermeans.Ths'sdonebyestablishingalimitingctiononcoreTHERMALPOWERwiththellowingbasis.Sincetheessuredropinthebypassregionisessentiallyalletionhead,threpressuredropatlowpowerandflowswillalwaysbegreatern4si.Analysesshowthatwithabundleflowof28x10~lbs/hr,buessuredropisnearlyindependentofbundlepowerandhasavalue.5psi.thebundleflowwitha4.5psidrivingheadwillbegrethan28x10'bs/.FullscaleATLAStestdatatakenatpressuresm14.7psiato800psiaindicatatthefuelassemblycriticalpowethisflowisapproximately3.35MWt.Wiedesignpeakingors,thiscorrespondstoaTHERMALPOWERofmorethaXofRATEDTHEPOWER.Thus,aTHERMALPO'WERlimitof25KofRATEDTHERMALforeactorressurebelow785siisconservative.SUSQUEHANNA"UNIT2B2-1AmendmentNo.31 7heuse.ofPAeA'rer3corre,la~i'ont'sva.lidforcrier'ce.lpowercalcaladi'onsatpressuresgree,A<+Aan5'$'0psi'~artd4nndietttassfluxesIrea*rtAavtC7r7Sx/D~/bsj'Ar-F+.Faopal-atI'encLP/0wprt.ssuresor/ouiFlows,Shef'uelclad'drvtgnterriPy>afe~p<r'rnidststaklis.hed'p'lt'rnid'npconclrtiortoncore~HEQIrIJQPO&ORnrr'tA7theto/louringbasislrovrPeel+ha~tAewat'el.leveli'nt'Aevessel+twitcorneti-smaintatnedahov.e7Ae9opof7h<4ctt'vt.Suelirta1turaIct'rcrlc7tonizs-afgicien7toassurea.xrtr'vtivrtuntbundle+lonif'ic.llfelassernbltee'wAi'cQhavea.relo.ti'velyht'IApowet"andlxoien>ie.Ilycanoptoroa,c.Acxcritr'ca.IAea7+luxcont'ic'7ti'on,Car+hetRN<'9X9foeIelespr>>neer'nintutvtgundleF!owltiprea*r7Aanzo>ooo/ks/hr.FortjiPrtttivKand8.FFxj'uel>+hemt'rtirnutvtbundle5litnit'sgrea,terteavt~P>ooo/hs/Prrortxllctvs/gxtzv+Aecco/trankFlowandxrtaxlrnuNf/owo.reeissue,g+Aa7'Qemassflexisaltvaysgrqa7crOAanc7~S4v'Olbsgg,-Fl,FuIIscaltcrr'9('caIpowys~~tosht'often.a.'Fpressure.esJourntor'~lpsialndt'ca,~e%ha,k+hefueleessetnbylcrr'~icalpontet-c+

NtVSeRTg(con4nwi8D.Rs~toIhs/hr-As995Hw9orgreg,%et.AS%+Acrmal.poniera.bnndlgPowercorrespencistoo.bundleradi'o-Ipea)i'ngFacforofgree~cr+A<<n3.+wgi'cliissunniFlcanRyhigherVAeexpec/e,dpeck'ngFactor.71,,7a<ewxcPo~E'0/,'87'EDTge<MRLPooJERForreactorpressuresgqlow'8'5psiJisconservefive'~

SAFETYLIMITSBASES2.1.2THERMALPOWERHihPressureandHihFlowOnsetoftransitionboilingresultsinadecreaseinheattransferfromthecladand,therefore,elevatedcladtemperatureandthepossibilityofcladfailure.However,theexistenceofcriticalpower,"orboilingtransition,isnotadirectlyobservableparameterinanoperatingreactor.Therefore,themargintoboilingtransitioniscalculatedfromplantoperatingparameterssuchascorepower,coreflow,feedwatertemperature,andcorepowerdistribution.Themarginforeachfuelassemblyischaracterizedbythecriticalpowerratio(CPR),whichistheratioofthebundlepowerwhichwouldproduceonsetoftran-sitionboilingdividedbytheactualbundlepower.Theminimumvalueofthisratioforanybundleinthecoreistheminimumcriticalpowerratio(MCPR).TheSafetyLimitMCPRassuressufficientconservatismintheoperatingMCPRlimitthatintheeventofananticipatedoperationaloccurrencefromthelimitingconditionforoperation,atleast99.9Xofthefuelrodsinthecorewouldbeexpectedtoavoidboilingtransition.Themarginbetweencalculatedboilingtransition(MCPR=1.00)andtheSafetyLimitMCPRisbasedonade-tailedstatisticalprocedurewhichconsiderstheuncertaintiesinmonitoringthecoreooeratingstate.OnespecificuncertaintyincludedinthesafetylimitistheuncertaintyinherentintheXN-3criticalpowercorrelation.XN-NF-524describesthemethodologyusedindeterminingtheSafetyLimitMCPR..X,HsE.RVS.TheXN"3'criticalpowercorlationisbasedonasignificantbodyofprac-ticaltestdata,providinga'ghdegreeofassuranCethatthecriticalpowerasevaluatedbythecorrelat'oniswithinasmallpercentageoftheactualcriti-calpowerbeingestimated.eassumedreactorconditionsusedindefiningthesafetylimitintroduceconservatismintothelimitbecauseboundinghighradialpowerfactorsandboundingflatlocalpeakingdistributionsareusedtoestimatethenumberofrodsinboilingtransition.StillfurtherconservatismisinducedbythetendencyoftheXN-3correlationtooverpredictthenumberofrodsinboilingtransition.TheseconservatismsandtheinherentaccuracyoftheXN-3correlationprovideareasonabledegreeofassurancethatduringsus-tainedoperationattheSafetyLimitMCPRtherewouldbenotransitionboilinginthecore.Ifboilingtransitionweretooccur,hereisreasontobelievethattheintegrityofthefuelwouldnotnecessarilybecompromised.SignificanttestdataaccumulatedbytheU.S.NuclearRegulatoryCommissionandprivateor-ganizationsindicatethattheuseofaboilingtransitionlimitationtoprotectagainstcladdingfailureisaveryc'onservativeapproach.Muchofthedatain-dicatesthatLMRfuelcansurviveforanextendedperiodoftimeinanenviron-mentofboilingtransition.SUSQUEHANNA-UNIT282-2AmendmentNo.31 AslongasWAecorepressureand+lonso,re.will'n+dera,nateofya.IiI'lWy'ofVAeXS-3corr8la1~~n(reFertoSeci~/on04I./)>

3/4.2POWERDISTRIBUTIONLIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATELIMITINGCONDITIONFOROPERATIONRowan(RPIR6R~Q3.2.1AllAVERAGEPLANARLINEARHEATGENERATION~&4e~&AVBQ~ttNBtC"~NHI'VERAGEPLANAREXPOSUREshallnotexceedthelimitsshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3."+4>~BCS<etawd~QE~6E.Q,QNhlP.pgpyS+gg6'AlF+Me/APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanor*ACTION:WithanAPLHGRexceedingthelimitsofFigure3.2.1-1,3.2.1-2,or3.2.1-3,initiatecorrectiveactionwithin15minutesandrestoreAPLHGRtowithintherequiredlimitswithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.2.1AllAPLHGRsshallbeverifiedtobeequaltoorlessthanthelimitsdeterminedfromFigures3.2.1-1,3.2.1-2,and3.2.1-3:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingwithaLIMITINGCONTROLR00PATTERNforAPLHGR.d.TheprovisionsofSpecification4.0.4arenotapplicable.*SeeSpecification.3.4.1.1.2.aforsingleloopoperationrequirements.SUSQUEHANNA-UNIT23/42"1AmendmentNo.3l f~I~v-f6s~~~gto~'PeÃ'f]'w~~$fe1v>>~gg,EtlsfII' ADm13~c~12~c0)I1110g)(Dc~~0~~~~..:PERMISSABLE.':REGIONOF~OPERATIO16536'102;12.112.0o220;'.::~11,023':':':'.:~11.611.9:.:j21'.:::::22,04B;..-'3,069;11.2~'~O06000...1000016000200002600030000~36000AveragePlanarExposure(MWD/MT)MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(MAPLHGR)VERSUSAVERAGEPLANAREXPOSUREGEFUELTYPESBCR233(2.33'j6ENRICHED)FIGURE3.2.1-2

~~~~~G)~g)~12ICO(9CD0P-11~QC~(3xQ)]0CU~CQlDt:9~~~~~5512;'121:1102::::;12.0:::~p~~~~~~16,535;~~~I~~~~~~~~~~~~~~~~~,~~~~~~~~~~~I~I~~~~~~~~~~~~~~~~~~~~~~:.27.558.:11.6~~~I~~,02312.1~~~~~~~220;11.9~~~IIII\~~~~~~~I~'22.046:12.1~IIII~~II~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~33,069;11.2~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~\i~~~~~~~I~~I~~~~~~II~~~~~I~~~~~~~~~I~I~~~I~~~~~\~~~~~~~~~~~~~~~~~~~~~~IIII~~~~~I~I,~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~:.PERMISSABLEREGIONOFOPERATION~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~I~~~~~~~~II~I406759.2~~~~~~~~~~~~~~~II~~~~~~~~~~~I~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~050001000015000200002500030000350004000045000AveragePlanarExposure{MWD/MT)MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE(MAPLHGR)VERSUSAVERAGEPLANAREXPOSUREGEFUELTYPES8CR233{2.33%ENRICHED)FIGURE3.2.1-2 dNk 12<<g~11g)vC010g)OEc)8QvtQxI8(5I~~0.0;.10.2..:...';..:....':...:...:...:.~~I~ERMlSSADLREGIONOFOPERATION~~~~~~~I0~~\~~~~~I~~\z6000~~~~~~~40,000;:,1.520,000;10.2600010016000200002600000003600040000erageBundleExposure(MWDjT}MAXIMUMAVERAGEPlANARLINEARHEGENERATIONRATE(MAPLHGR)VERSUSAVERAGEBUNDLEEXPOSUREEXXON9X9FUELFlGURE3.2.1-3SUSQUEHANNA-UNIT23/42"4AmendmentNo.3]

12~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~Cg(9~CUtL~g)C(6~L6)e+cE+XQCg~(0C1088~I~~~~~~~+~~~~~~~~~~~~00~Mg~~~~~~~~~~~~~~~~~~~~~~~I~~~~~20,000;10.2~~~~~~~~~~~~~~~~~~~I~~~~~~~~~I~~~~\~~~~~~~~~~~~~~~~I~H~~Ji44)~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~1C'C'I30,000;'.8.9~~~~~~~~,'.:...:..:...40,007.5C~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~0;.~~~~~~~~~~~~~~~~~~~~~~~~~~~~.:PERMISSABLE;.:,:REGIONOFOPERATION~~~~~~~~~~~~I~t'25,000;9.6~~~~~~~~~~t~'i1t'i'~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~<~~2~i~L~J~~JL~\~2~'4IL~2~~~~~~I~~~~~~~i~~~~~~~~~~~~~~~~~\~~~~~I1~J'iI~J'1[~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~C'I1~~~~~~~~~~~~~tJ'~~~~~~I;.35,000;.:.~sS2I~~~~~~~~~~~~~~~~~~~~II~-~~~0500010000150002000025000300003500040000AverageBundleExposure{MWD/MT)MAXIMUMAVERAGEPLANARLINEARHEATGENERATIONRATE{MAPLHGR)VERSUSAVERAGEBUNDLEEXPOSUREANF9X9FUELFIGURE3.2.1-3 A/I.IP;t POWERDISTRIBUTIONLIMITS3/4.2.2APRMSETPOINTSLIMITINGCONDITIONFOROPERATION3.2.2TheAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpoint(S)andflowbiasedneutronflux-upscalecontrolrodblocktripsetpoint(SRB)shallbeestablishedaccordingtothefollowingrelationships:TriSetointAllowableValueS<0.58W-+59K)TSRB<(0.58W+50K)TSRB-0'58W+53Twhere:SandSBareinpercentofRATEDTHERMALPOWER,W=too/recirculationflowasapercentageofthelooprecirculationflowwhichproducesaratedcoreflowof100millionlbs/hr,T=LowestvalueoftheratioofFRACTIONOFRATEDTHERMALPOWERdividedbytheMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY.%here:a~b.TheFRACTIONOFLIMITINGPOWERDENSITY(FLPD)forGEfuelistheactualLINEARHEATGENERATIONRATE'(LHGR)dividedby13:4perSpecification3.2.4.1,andRNPTheFLPDfor~mfuelistheactualLHGRdividedbytheLINEARHEATGENERATIONRATEfromFigure3.2.2-1.Tisalwayslessthanorequalto1~0.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorEEACTION:WiththeAPRMflowbiasedsimulatedthermalpower-upscalescramtripsetpointand/ortheflowbiasedneutronflux-upscalecontrol'rodblocktripsetpointlessconservativethanthevalue.shownintheAllowableValuecolumnforSorSB,asabovedetermined,initiatecorrectiveactionwithin15minutesandadjust3and/orSRBtobeconsistentwiththeTripSetpolntvalue*within2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCEREUIREMENTS4.2.2TheFRTPandtheMFLPDshallbedetermined,thevalueofTcalculated,andthemostrecentactualAPRMflowbiasedsimulatedthermalpower-upscalescramandflowbiasedneutronflux-upscalecontrolrodblocktripsetpointsverifiedtobewithintheabovelimitsoradjusted,as.required:a*WithMFLPDgreaterthantheFRTPduringpowerascensionupto90KofRATEDTHERMALPOWER,ratherthanadjustingtheAPRMsetpoints,theAPRMgainmaybeadjustedsuchthatAPRMreadingsaregreaterthanorequalto100KtimesMFLPD,providedthattheadjustedAPRMreadingdoesnotexceed100KofRATEDTHERMALPOWER,therequiredgainadjustmentincrementdoesnotexceed10KofRATEDTHERMALPOWER,andanoticeoftheadjustmentispostedonthereactorcontrolpanel.SeeSpecification3.4.1.1.2.aforsingleloopoperationrequirements.SUSQUEHANNA-UNIT23/42-5AmendmentNo.3l

,0~C~CCgO~~co0~~0~CLC9e.~COCOgKlZ~CL~oAU141210~~~0.0;-....:..OI-:'~~~~~~~0~~~~~~~~~~~~0~~~~II25,400;':14.0~~lI....::...43,200;.S.O~1II48,0008.3I~I00"-200003000040000'veragePIanarExposure{MWDT)60000ILIRHEATGENERATIONRATEFORAPRMSPOINTSVERSUSAVERAGEPLANAREXPOSUREEXXONFUELFIGURE3.2.2-1~cp(KgeJvent.gIvzupp,cyan,pzSUSQUEHANNA-UNIT23/42-6eAmendmentNp3]

18~~~~~e~CM0~g)V2cQ)~~C0Ue~ge>ZKCLhQ6)U16141210ee16.0~,~~~e~~~~~~~e~~~~~~ereh'~~~~~~~~~~~~e~~25,400;14.0~~~e~~~~~~~~~~~t~re~~~~~rr~e~~~~\~ee~~~~ee'er~i~~~~43,200;S.O~I~~e~ee\~~~~~~~~~e~~48,000;8.3e\~4JIlh~JrJ~Lh~~iJ10000200003000040000AveragePlanarExposure(MWD/MT)50000LINEARHEATGENERATIONRATEFORAPRMSETPOINTSVERSUSAVERAGEPLANAREXPOSUREANFFUELFIGURE3.2.2-1

1.7CURVEA:EOC-RPTtnoperabfe;MafnTurbineBypa:ssOperableCURVE8:MainTurbineBypassfnoperable;EOC-RPTOperableRVEC:EOC-RPTandMainTurbineByassOperableICOUl1.5CCLO1.4CL(31.3AC1.311.304050607080TotalCoreFlow(%OFRATED)90100O.FLOVlDEPENDENTMGPROPERATlNGLIMITF!GURE3.2.3-'I~<P~~tdu)(~g~<~~iqu+tC 0t 1.71.6(40,1.61}CURVEA:EOC-RPTInoperable;MainTurbineBypassOperableCURVEB:EOC-RPTOperable:MainTurbineBypassInoperableCURVEC:EOC-RPTandMainTurbineBypassOperableG)C~~CULCL1ACCCLU1.3(50,1.44)&(50.77,1.43)(57.69,1.34)(59.23,1.32)ABC1.431.341.321.240607080TotalCoreFlow(%OFRATED)90100FLOWDEPENDENTMCPROPERATINGLIMITFIGURE3.2.3-1 1.7ADmCURVEA:EOC-RPTInoperable:MainTurbineBypassOperableCURVE8:MainTurbineBypassInoperabe;EOC-RPTOperableCURVEC:EOC-RPTandMainTurbeBypassOperable1.6~~CLO1ACLO1.3BDQ.9f+?.'1.220803040606070'orePower(%OFRATED)REDUCEDPOWERNtCPROPERATINGLIMITFigure3.2.3-2QephwCedmc%hHE'~Fisvy~K.Z.5-290 1.6(25,1.52){40,1.50)CURVEA:EOC-RPTInoperable:MainTurbineBypassOperableCURVE8:EOC-RPTOperable:MainTurbineBypassInoperableCURVEC:EOC-RPTandMainTurbineBypassOperableg)1.5~~COLICL01.4CLU(25,1.44)(25,1.39)(40,1.42)(40,1.37)(65,1.47){66,1.39)(65,1.34)(S0,1.44)(s,.)(75,1.32)1A21.341.321.220304080506070CorePower(%OFRATED)REDUCEDPOWERMCPROPERATINGLIMITFigure3.2.3-290100 POWERDISTRIBUTIONLIMITS3/4.2.4LINEARHEATGENERATIONRATEVNFFUELLIMITINGCONDITIONFOROPERATIONpuP3.2.4.2TheLINEARHEATGENERATIONRATE(LHGR)forMC.fuelshallnotexceedtheLHGRlimitdeterminedfromFigure3.2.4.2-1.APPLICABILITY:OPERATIONALCONDITION1,whenTHERMALPOWERisgreaterthanorACTION:WiththeLHGRofanyfuelrodexceedingthelimit,initiatecorrectiveactionwithin15minutesandrestoretheLHGRtowithinthelimitwithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLA'NCEREUIREMENTSA~F4.2.4.2LHGRsforM&fuelshallbedeterminedtobeequaltoorlessthanthe1imit:a.Atleastonceper24hours,b.Within12hoursaftercompletionofaTHERMALPOWERincreaseofatleast15XofRATEDTHERMALPOWER,andc.Initiallyandatleastonceper12hourswhenthereactorisoperatingonaLIMITINGCONTROLRODPATTERNforLHGR.d.TheprovisionsofSpecification4.0.4arenotapplicable.SUS(UEHANNA-UNIT23/42-10aAmendmentNo.31 r-)v0C-12..0.0,13.0'.----.:-.--:"-.--:.---.'--...:---:""24,000;....'...-.-"'.-'"."..'-...:....:...'...:...'12.0C0EQL10CQ84QC~~:.PERMlSSE:.REGlOFOPATlON~~~~~~~~35.000;48,000;7.72~~100002000030000400AveragePlanarExposure{MID/MT)60000L(NEARHEATGENERATlONRATE(LHGR)LlMlTVERSUSAYERAGEPLANAREXPOSUREEXXON&X9FUELFlGURE3.2.4.2-]p,~q(a.c.elmith~e~Fi+<<<>~8~'L

'le.+14E..0.0;13.0~~~~~~~~\~~~~~~.:...:,...:,.......:...24,000;....:12.0~~~~J~~~~~~~~~h~~'~~~~~~~~~I>~~~~I~~120CQLtD10C6)(98LCQtDC6~~~~~~~~I~L~~~~Ph~~I~~~~~~~\~~'LlERMISSABLEREGIONOFOPERATION'I~~'ltC~~~~~~~~~35,000;95~~hJ~Ill'~~I~~J~i~~L~~%~h~~~J~48,0007.72010000200003000040000AveragePlanarExposure(MWD/MT}50000LINEARHEATGENERATIONRATE(LHGR}LIMITVERSUSAVERAGEPLANAREXPOSUREANF9X9FUELFIGURE3.2.4.2-1 I'

TABLE3.3.6-2CONTROLRODBLOCKINSTRUMENTATIONSETPOINTSTRIPFUNCTIONRODBLOCKMONITORa.Upscalettb.Inoperativec.DownscaleTRIPSETPOINT0.66W+42XNA>5/125divisionsoffullscaleALLOWABLEVALUE<0.66W+45KNA>3/125ofdivisionsfullscale2.3.APRHa.FlowBiasedNeutronFlux-Upscale'~b.Inoperativec.Downscaled.NeutronFlux-UpscaleStartupSOURCERANGEMONITORS<0.58W+50K*NA>SXofRATEDTHERMALPOWER<12KofRATEDTHERMALPOWER<0.58W+53K~NA>3XofRATEDTHERMALPOWER<14KofRATEDTHERHALPOWERa.b.C.d.DetectornotfullinUpscaleInoperativeDownsca1eNA<2x10cpsNA)07cps')kNA<4xlOcpsNA>0.5cps*"4.INTERMEDIATERANGEMONITORSaob.C.d.DetectornotfullinUpscaleInoperativeDownscaleNANA<108/125divisionsoffullscale<110/125divisionsoffullscaleNANA>5/125divisionsoffullscale>3/125divisionsoffullscale5.6.SCRAMDISCHARGEVOLUMEa.WaterLevel-High<44gallonsREACTORCOOLANTSYSTEMRECIRCULATIONFLOW<44gallonsa.Upscale<108/125divisionsoffullscale<ill/125divisionsoffullscaleb.InoperativeNANAc.Comparator<lOXflowdeviaticn<llXflowdeviationTheAveragePowerRangeMonitorrodblockfunctionisvariedasafunctionofrecirculationloopflow(W).ThetripsettingofthisfunctionmustbemaintainedinaccordancewithSpecification3.2.2.""Providedsignal-to-noiseratiois>2.Otherwise,3cpsastripsetpointand2.8cpsforallowablevalue.HSeeSpecification3.4.1.1.2.aforsingleloopoperationrequirements.

3/4.4REACTORCOOLANTSYSTEM3/4.4.1RECIRCULATIONSYSTEMRECIRCULATIONLOOPS-TWOLOOPOPERATIONLIMITINGCONDITIONFOROPERATION3.4.1.1.1Tworeactorcoolantsystemrecirculationloopsshallbeinoperationyand:a..Totalcoreflowshallbegreaterthanorequalto~millionlbs/hr,orthe,+Cat.+vtaasF0+C,&La~Ccsadi+ic3uRMALPOWER~lessthanorequaltothelimitspecifiedinFigure3.4.1.1.1"1.APPLICABILITY:OPERATIONALCONDITIONS1"and2",exceptduringsingleloopoperation.4ACTION:a.Withonereactorcoolantsystemrecirculationloopnotinoperation,complywiththerequirementsofSpecification3.4.1.1.2,ortaketheassociatedACTION.~c4~~Wi~><ve+4a.'YH+g~ALblocc.a~d-i+i'.Withnoreactorcoolantsystemrecirculationloopsinoperation,immediatelyinitiateanorderlyreductionofTHERMALPOWERtolessthanorequaltothelimitspecifiedinFigure3.4.l.1.1-1,andinitiatelmeasurestoplacetheunitinatleastSTARTUPwithin6hoursandinHOTSHUTOOWNwithinthene'xt6hours.gheeWe,chi:+oY0+oc.Withtworeactorcoolantsysrecirculationlooinoperationandtotalcoreflowlessthanmillionlbs/hrandHERMALPOWERgreaterthanthelimitspecifiedinFigure3.4.1.1.1-1:4/covCSlo~}es+tsVC+beC4.'43.C+n++oct.Cashd>te43>1.lessthanorequaltothelimitspecifiedinFigure3.4.1.1.1-1,orF<<s'ee~'~<<Mti+lowI2.Increasecoreflowtogreaterthan4millionlbs/hr,or3.DeterminetheAPRMandLPRM"""neutronfluxnoiselevelswithin1hour,and:a)IftheAPRMandLPRM"*"neutronfluxnoiselevelsarelessthanthreetimestheirestablishedbaselinelevels,continuetodeterminethenoiselevelsatleastonceper8hoursandwithin30minutesafterthecompletionofaTHERMALPOWERincreaseofatleast5XofRATEDTHERMALPOWER,orb)IftheAPRMorLPRM*""neutronfluxnoiselevelsaregreaterthanorequaltothreetimestheirestablishedbaselinelevels,immediatelyinitiatecorrectiveactionandrestorethenoiselevelstowithintherequiredlimitswithin2hoursbyincreasingcoreflowtogreaterthanml>onsr,and/orbyuc4Ae~rf-TitERM~CMN~~</co<elessthanorequaltothelimitspecifiedinFigure3.4.l.1.1-1.I"SeeSpecialTestException3.10.4."""DetectorsAandCofoneLPRMstringpercoreoctantplusdetectorsAandCofoneLPRMstring'inthecenterofthecoreshouldbemonitored.OSeeSpecification3.4.1.1.2forsingleloopoperationrequirements.SUSQUEHANNA-.UNIT23/44-1AmendmentNo.26

80Figure3.4.1.1.1-1THERMALPOWERLIMITATIONS70C}LU~~eo(60'040E3020L0O10REGIONGRTERTHANUMIT04~Ir~~\p)h"REGIONLESSTHANMITJI~~~02030406080CoreRow(%RAYED)7080SUSIlUEHAHHA"UNIT23/44-1bAmendmentH0..26'-4 80C570'<j:>orpo40CD30Lf-20L10Eigure3'.4..1.1.1-1THERMALPOWER/COREFLOWLIMITATIONS----.-REGIONGREATER-.:-"--..:.THANLIMITIREGIONLESSTHANLIMIT02030406060CoreFlow(%RATED)7080 0

REACTORCOOLANTSYSTEMRECIRCULATIONLOOPS-SINGLELOOPOPERATIONLIMITINGCONDITIONFOROPERATION3.4.1.1.2Onereactorcoolantrecirculationloopshallbeinoperationwiththepumpspeed<40Koftheratedpumpspeed,andBo&~a.thefollowingrevisedspecificationlimitsshalloefollowed:l.Specification2.1.2:theMCPRSafetyLimitshallbeincreasedto1.07.2.Table2.2.1-1:theAPRMFlow-BiasedScramTripSetpointsshallbeasfollows:TriSetoint<0.58W+55AllowableValue<0.58W+58.3.4.INSERTS.4xS<(0.58W+55K)TSRB<(0.58W+46K)TAllowableValue'l)SRB<(0.58W+49K)TTable3.3.6-2:theRBM/APRMControlRodBlockSetpointsshallbeasfo1'1ows:a.,RBM-UpscaleAllowableValueTriSetointSpecification3.2.1:TheHAPLHGRlimitsshallbethelimitsspecified4-.I.Rio~d~Fluvc.8.2.1-3Specification3.2.2:theAPRHSetpointsshallbeasfollows:'mvltiq6ed4y'L.0~<0.66W+3<0.66W+40k-.a; and~~?-shaR-be-used-ie-eonjunet+o~~4e-Mb.APRM-FlowBiasedTriSetointAllowableValue<0.58W+46b.APRMandLPRM"""neutronfluxnoiselevelsshallbelessthanthreetimestheirestablishedbaselinelevelswhenTHERMALPOWERisgreaterthanthelimitspecifiedinFigure3/4.l.1.2-1.2c.Totalcoreflowshallbegreaterthanorequalto42millionlbs/hrwhenTHERMALPOWERisgreaterthanthelimitspecifiedinFigure3.4.1.1.Z-1.zAPPLICABILITY:OPERATIONALCONDITIONS1"and2",exceptduringtwoloopoperation.0ACTION:a.Withnoreactorcoolantsystemrecirculationloopsinoperation,taketheACTIONrequiredbySpecification3.4.1.1.1.SUS(UEHANNA"UNIT23/44-lcAmendmentNo.31 0CI Speci&ico+'aaa~.2.>:T48PIINI&UMCRI'TICALPowFRIRIA~ID(Wc~IRIsIa.ll4ecgeoaew+Io.~oeeqao.(ao<Nelaw's+aswlesalia~lugaolaes:o.,h.31)b~+he8C'Pkide+e>yniNedSvo~FigurepIusa.al~a.ZdC.<4,l%CYAN>d,eke>mi~ed&&0~~iqwwe.E.Z.z-2.@~ASo.0h~

4Itka REACTORCOOLANTSYSTEMLIMITINGCONDITIONFOROPERATIONContinuedb.C.d.e.Withanyofthelimitss'pecifiedin3/4.1.1.2anotsatisfied:Cl.Uponenteringsingleloopoperation,complywiththenewlimitswithin6hoursorbeinatleastHOTSHUTDOWNwithinthefollowing6hours.2.IftheprovisionsofACTIONb.1donotapply,taketheACTION(s)requiredbythereferencedSpecification(s).WiththeAPRMorLPRM"""neutronfluxnoiselevelsgreaterthanorequaltothreetimestheirestablishedbaselinelevelswhenTHERMALPOWERisgreaterthanthelimitspecifiedinFig"ure3,4.1.1.-1,immediatelyinitiatecorrectiveactionandresore.enoi'selevelstowithintherequi'redlimitswithin2hoursbyinitiatinganorderlyreductionofTHERMALPOWERto~+lessthanorequaltothelimitspecifiedinFigure3.4.1.1.<l.Otherwise,beinatleastHOTSHUTDOWNwithinthenext12hours.Withoneormorejetpumpsinoperable,beinatleastHOTSHUTDOWNwithin12hours.Withtotalcoreflowlessthan42millionlbs/hrwhenTHERMALPOWERisgreaterthornthelimitspecifiedinFigure3~4.1.1.<l,immediatelyinitiatecorrectiveactionbyeither:1.ReducingTHERMALPOWERtolessthanorequaltothelimitspecifiedinFigure3.4.1.1.W1within4hours,'rp2.Increasingtotalcoreflowtogreaterthanorequalto42millionlbs/hrwithin4hours.SURVEILLANCEREUIREMENTS4.4.l.1.'2.14.4.l.l.2.24.4.1.1.2.3'ponenteringsingleloopoperationandatleastonceper24hoursthereafter,verifythatthepumpspeedintheoperatingloopis<Sf%oftheratedpumpspeed.8O'PoWithTHERMAOWERgreaterthanthelimitspecifiedinFig-ure3.4.1.1.-1,determinetheAPRMandLPRM"""neutronfluxnoiselevelswithin1hour.-Continuetodeterminethenoiselevelsatleastonceper8hoursandwithin30minutesafterthecompletionoftheTHERMALPOWERincrease)5XofRATEDTHERMALPOWER.Within15'minutespriortoeitherTHERMALPOWERincreaseresultingfromacontrolrodwithdrawalorrecirculationloopflowincrease,verifythatthefollowingdifferentialtemperature.requirementsaremetifTHERMALPOWERis<30K""*"ofRATEDTHERMALPOWERortherecirculationloopfTowintheoperatingrecirculationloopis<50K""""ofratedloopflow:SUSQUEHANNA.-UNIT23/44-1dAmendmentNo.26 0

8070I-~60~O50040P302010O-Figure3.4.1.1.2-1SINGLELOOPOPERATIONTHERMALPOWERLIMITATIONS:.--.-REGIONGREATERTHANLIMITREGIONLESSTHANLIMIT2030405060CoreFlow{%RATED)7080 3/4.2POMERDISTRIBUTIONLIMITSBASESThespecificationsofthissectionassurethatthepeakcladdingtemperaturefollowingthepostulateddesignbasisloss-of-coolantaccidentwillnotexceedthe2200Flimitspecifiedin10CFR50.46.3/4.2.1AVERAGEPLANARLINEARHEATGENERATIONRATEThisspecificationassuresthatthepeakcladdingtemperaturefollowingthepostulateddesignbasisloss-of-coolantaccidentwillnotexceedthelimitspecifiedinl0CFR50.46.Thepeakcladdingtemperature(PCT)followingapostulatedloss-of-coolantaccidentisprimarilyafunctionoftheaverageheatgenerationrateofalltherodsof.afuelassemblyatanyaxiallocationandisdependentonlysecondarilyontherodtorodpowerdistributionwithinanassembly.forGEfuel,thepeakcladtemperatureiscalculatedassumingaLHGRforthehighestpoweredrodwhichisequaltolessthanthedesignLHGRcorrectedfordensification.ThisLHGRtimes1.02isusedintheheatupcodealongwiththeexposuredependentsteadystategapconductanceandrod-to-rodlocalpeaki.ngfactor.TheTechnicalSpecificationAVERAGEPLANARLINEARHEATGENERATIONRATE(APLHGR)forGEfuelisthisLHGRofthehighestpoweredroddividedbyitslocalpeakingfactorwhichresultsinacalculatedLOCAPCTmuchlessthan2200F.TheTechnicalSpecifi-cationAorfuelisspecifiedtoassurethePCTfollowingapostu-latedLOCAwillnotexceedthe2200~Flimit.ThelimitingvalueforAPLHGRisshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3.ThecalculationalprocedureusedtoestablishtheAPLHGRshownonFig-ures3.2.1-1,3.2.1-2,and3.2.1-3isbasedonaloss-of-coolantaccidentanalysis.Theanalysiswasperformedusingcalculationalmodelswhicharecon-sistentwiththerequirementsofAppendixKto10CFR50.ThesemodelsaredescribedinReference1orXN-NF-80-19,Volumes2,2A,2Band2C.3/4.2.2APRMSETPOINTSTheflowbiasedsimulatedthermalpower-upscalescramsettingandflowbiasedsimulatedthermalpower-upscalecontrolrodblockfunctionsoftheAPRMinstrumentslimitplantoperationstotheregioncoveredbythetransientandaccidentanalyses.Inaddition,theAPRMsetpointsmustbeadjustedtoensurethat>1%plasticstrainandfuelcenterlinemeltingdonotoccurduringtheworstanticipatedoperationaloccurrence(AOO),includingtransientsinitiatedfrompartialpoweroperation.RufFord~~fueltheTfactorusedtoadjusttheAPRMsetpointsisbasedontheFLPDcalculatedbydividingtheactualLHGRbytheLHGRobtainedfrom,Figure3.2.2-1.TheLHGRversusexposurecurveinFigure3.2.2-1isbasedonPNFSExxen-'sProtectionAgainstFuelFailure(PAFF)lineshowninFigure3.4ofXN-NF-85-67Revision1.Figure3.2.2-1correspondstotheratioofPAFF/1.2unerwhachcladdingandfuelintegrityisprotectedduringAOO's.SUS(UEHANNA"UNIT2B3/42-1AmendmentNo.31 (5~NV POWEROISTRIBUTIONLIMITSBASESAPRHSETPOINTS(Continued)ForGEfueltheTfactorusedtoadjusttheAPRHsetpointsisbasedontheFLPDcalculatedbydividingtheactualLHGRbytheLHGRlimitspecifiedforGEfuehinSpecification3.2.4.1.3/4.2.3HINIMUMCRITICALPOWERRATIOTherequiredoperatinglimitMCPRsatsteadystateoperatingconditionsasspeci-ifiedinSpecification3.2.3arederivedfromthe.establishedfuelcladdingintegritySafetyLimitHCPR,andananalysisofabnormaloperationaltransients.Foranyabnormaloperatingtransientanalysisevaluationwiththeinitial.con-ditionofthereactorbeingatthesteadystateoperatinglimit,itisrequiredthattheresultingMCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytimeduringthetransientassuminginstrumenttripsettinggiveninSpecifica-tion2.2.Toassurethatthe,fuelcladdingintegritySafetyLimitisnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtransientshavebeenanalyzedtodeterminewhichresultinthelargestreductioninCRITICALPOWERRATIO(CPR).Thetypeoftransientsevaluatedwerelossofflow,increaseinpressureandpower,positivereactivityinsertion,andcoolanttemperaturedecrease.ThelimitingtransientyieldsthelargestdeltaMCPR.WhenaddedtotheSafetyLimitMCPR,therequiredminimumoperatinglimitHCPRofSpecification3.2.3isobtainedandpresentedinFigure3.2.3-1and3.2.3-2.Theevaluationofagiventransientbeginswiththesysteminitialparametersshowninthecyclespecifictransientanalysisreportthatareinputtoe-i~emcoredynamicbehaviortransientcomputerprogram.TheoutputsofthisprogramalongwiththeinitialMCPRformtheinputforfurtheranalysesofthethermallylimitingbundle.Thecodesandmethodologytoevaluatepressurizationandnon-pressurizationeventsaredescribedinXN-NF-79-71andXN-NF-84-105.Theprinci-palresultofthisevaluationisthereductioninHCPRcausedbythetransient.Figure3.2.3-1definescoreflowdependentMCPRoperatinglimitswhichassurethattheSafetyLimitHCPRwillnotbeviolatedduringaflowincreasetran-sientresultingfromamotor-generatorspeedcontrolfailure,Theflowdepend-entHCPRisonlycalculatedforthemanualflowcontrolmode.Therefore,automaticflowcontroloperationisnotpermitted.Figure3.2.3-2definesthepowerdependentHCPRoperatinglimitwhichassuresthattheSafetylimitHCPRwillnotbeviolatedintheeventofafeedwatercontrollerfailureinitiatedfromareducedpowercondition.Cyclespecificanalysesareperformedforthemostlimitinglocalcorewidetran-sientstodeterminethermalmargin.AdditionalanalysesareperformedtodeterminetheMCPRoperatinglimitwitheithertheMainTurbineBypassinoperableortheEOC-RPTinoperable.AnalysestodeterminethermalmarginwithboththeEOC-RPTinoperableandHainTurbineBypassinoperablehavenotbeenperformed.Therefore,operationinthisconditionisnotpermitted.SUSQUEHANNA-UNIT2B3/42"2AmendmentNo.31 I41 3/4.4REACTORCOOLANTSYSTEMBASES3/4.4.1RECIRCULATIONSYSTEMOperationwithonereactorrecirculationloopinoperablehasbeenevaluatedandfoundacceptable,providedthattheunitisoperatedinaccordancewithSpecification3.4.1~1.2.des-exuded-operatien~~n~o~s~~+68Forsingleloopoperation,theRBMandAPRMsetpointsareadjustedbya7Xdecreaseinrecirculationdriveflowtoaccountfortheactiveloopdriveflowthatbypassesthecoreandgoesupthroughtheinactiveloopjetpumps.Surveillanceonthepumpspeedoftheoperatingrecirculationloopisimposedtoexcludethepossibilityofexcessivereactorvesselinternalsvibration.SurveillanceondifferentialtemperaturesbelowthethresholdlimitsofTHERMALPOWERorrecirculationloopflowmitigatesunduethermalstressonvesselnozzles,recirculationpumpsandthevesselbottomheadduringextendedopera-tioninthesingleloopmode.Thethresholdlimitsarethosevalueswhichwillsweepupthecoldwaterfromthevesselbottomhead.THERMALPOWER,coreflow,andneutronfluxnoiselevellimitationsareprescribedinaccordancewiththerecommendationsofGeneralElectricServiceInformationLetterNo.380,Revision1,"BWRCoreThermalHydraulicStability,"datedFebru-ary10,1984.Aninoperablejetpumpisnot,initself,asufficientreasontodeclareare-circulationloopinoperable,butitdoes,'incaseofadesignbasisaccident,increasetheblowdownareaandreducethecapabilityofrefloodingthecore;thus,therequirementforshutdownofthefacilitywithajetpumpinoperable.Jetpumpfailurecanbedetectedbymonitoringjetpumpperformanceonaprescribedscheduleforsignificantdegradation.RecirculationpumpspeedmismatchlimitsareincompliancewiththeECCSLOCAanalysisdesigncriteriafortwoloopoperation.ThelimitswillensureanadequatecoreflowcoastdownfromeitherrecirculationloopfollowingaLOCA.Inthecasewherethemismatchlimitscannotbemaintainedduringtheloopoperation,continuedoperationispermittedinthesingleloopmode.Inordertopreventunduestressonthevesselnozzlesandbottomheadregion,therecirculationlooptemperaturesshallbewithin50Fofeachotherpriortostartupofanidleloop.Thelooptemperaturemustalsobewithin50Fofthereactorpressurevesselcoolanttemperaturetopreventthermalshocktotherecirculationpumpandrecirculationnozzles.Sincethecoolantinthebottomofthevesselisatalowertemperaturethanthecoolantintheupperregionsofthecore,unduestress.onthevesselwouldresultifthetemperaturediffer-encewasgreaterthan145'F.SUSQUEHANNA-UNIT2B3/44-1AmendmentNo.31

+~.~Tg S/AJleloof>of>elofrobt]gJlfJgpg77(rg/,~rfsrnhlkrpie)Iryr.fo,<forofCr,-$'/f~p>+e~JFuel.>leserichlfipl;<ap/,n~~amLC7Ca"e'usesini7ro-fedFiornco&Jj+j~~gPf""~"""'>ier~rlrlHC.rcI"I'r'nassrAreW3epeakc./aJg,'sed~rrrlga.2<CAei'enfee'.mar'osg/AQOCr'F:TgytlNlgvrlcaiT'ieger.Poarb4R~ri'o$8fepg)/,'orsmy'leloopogero.frohassur<74<7w$esa+efy'lnileACIESisno7'ePeeeoeJForariylnfrcppaf<4Operefiona/Cecuvrcncc.CtPOo)grigFog73'.Reer'rerJ4fi'onPunt@5'eiZ,urelaic.id'end.

AttachmenttoPLA-2953Page1of4NOSIGNIFICANTHAZARDSCONSIDERATIONSThefollowingthreequestionsareaddressedforeachoftheproposedTechnicalSpecificationchanges:Doestheproposedchangeinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated?Doestheproposedchangecreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated?Doestheproposedchangeinvolveasignificantreductioninamarginofsafety?Secificatioa3/4.2.1,AveraePlanarLinearHeatGenerationRateThechangestothisspecificationreflecteditorialchangestocorrectmisarrangedwordingthatwasissuedwithAmendment31,andthereplacementofreferencesto"Exxon"with"ANF".AchangetoincreasetheallowedexposureforGE2.33Xenrichedfuelto40,675MWD/MTUisalsoproposed.No.Theeditorialchangestocorrectmisarrangedwordingandthevendorreferencearewhollyeditorialinnatureandthereforehavenoimpactonanysafetyanalysis.ThechangetotheGElimitisbasedonaGELOCAanalysis.ThisnewcurvewaspreviouslyapprovedbytheNRCinAmendment64totheUnit1OperatingLicense,itisafuel-dependentlimit,andisbeingappliedtothesametypeofGEfuelinthisUnit2proposal.AsstatedinthestaffsafetyevaluationforAmendment64,"Theresultingpeakcladdingtemperature(PCT)limitandlocaloxidationfractionwerecalculatedbyGEbasedonthesameplantconditionsandsystemsanalysisusedtoderivethecurrentMAPLHGRlimitsdefinedintheSSESFSAR.ThecalculatedvaluesarewellwithinthelOCFR50.46AppendixKlimits."Theseconclusionsstillapply.No.Theeditorialchangescannotcreatenewconcerns;basedonthemethodsandresultsoftheGEanalysisdiscussedabove,noneweventsarepostulatedduetotheextendedburn-uplimit.No.Theeditorialchangeshavenosafetyimpact.ThepreviouslyapprovedmethodsandresultsoftheGEanalysisensurethatthemarginofsafetyisnotreducedduetothechangeintheGEfuelMAPLHGRlimit.

UUIk~kUP AttachmenttoPLA-2953Page2of4Secification3/4.2.2,APRMSetpintsAllproposedchangestothisspecificationareeditorial.No.Theproposedchangescorrectthevendorreferencefrom"Exxon"to"ANF".Thishasnoimpactonsafetyanalysessinceitisentirelyadministrativeinnature.II.No.SeeIabove.III.No.SeeIabove.Secification3/4.2.3,MinimumCriticalPowerRatioThechangestothisspecificationreflecttheresultsofthecycle-specifictransientanalyses.No.Limitingcore-widetransientswereevaluatedwithANF'sCOTRANSAcode(seeSummaryReportReference18)andthisoutputwasutilizedbytheXCOBRA-Tmethodology(seeSummaryReportReference19)todeterminedeltaCPRs.BothCOTRANSAandXCOBRA-ThavebeenapprovedbytheNRCinpreviouslicenseamendments.Allcore-widetransientswereanalyzeddeterministically(i.e.,usingboundingvaluesasinputparameters).Twoloadevents,RodWithdrawalErrorandFuelLoadingError,wereanalyzedinaccordancewiththemethodsdescribedinXN-NF-80-19(A)Vol.1"(see"SummaryReport'Reference15).Thismethodologyhasbeenapproved'bytheNRC.Basedontheabove,themethodologyusedtodevelopthenewoperatinglimitMCPRsfortheTechnicalSpecificationsdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.No.Themethodologydescribedcanonlybeevaluatedforitsaffectontheconsequencesofanalyzedevents;itcannotcreatenewones.TheconsequencesofanalyzedeventswereevaluatedinIabove.No.AsstatedinIabove,andingreaterdetailintheattachedSummaryReport,themethodologyusedtoevaluatecore<<wideandlocaltransientsisconsistentwithpreviouslyapprovedmethodsandmeetsallpertinentregulatorycriteriaforuseinthisapplication.Therefore,itsusewillnotresultinasignificantdecreaseinanymarginofsafety.Secification3/4.2.4,LinearHeatGenerationRateAllproposedchangestothisspecificationareeditorial.No.Thepropose'dchangescorrectthevendorreferencefrom"Exxon"to"ANF".Thishasnoimpactonsafetysinceitisentirelyadministrativeinnature.

kg,,',)hg'g4.R~~,,~R<RRP4',,I=I44Rt44$RP'r,4,~,,t41rt4L4lh4eIR~t;~ERRIIt=~4'.'I4lhhIIhIl~"4RI

~~arAttachmenttoPLA-2953Page3of4II.No.SeeIabove.III.No.SeeIabove.Secification3/4.3.6,ControlRodBlockInstrumentationTheproposedchangetothisspecificationiseditorialandwaspreviouslysubmittedtotheNRCviaproposedamendment52,datedJune30,1987.No.Theproposedchangerestoresfootnote"////"toTripFunction2a.Thisfootnotewasalwaysmeanttoapplyinthislocation.Thischangehasnoimpactonsafetysinceitisentirelyeditorialinnature.II.No.SeeIabove.III.No.SeeIabove.Secification3/4.4.1,RecirculationSstema.TwoLoopOperation:Thechangestotheserequirementsareduetothecyclespecificstabilityanalysis.Thenewanalysisresultedinavarying"detectandsuppress"regionflowboundary,whichinturnresultedintheneedfortheeditorialchangestotheactionstatements.No.COTRANcorestabilitycalculationsperformedforU2C3predictstablereactoroperationoutsideofthedetectandsuppressregionofoperationinSSESUnit2.Thedetectandsuppressregionisdefinedbytheareaaboveandtotheleftofthe80%RodBlockline,the45Xconstantflowline,andthelineconnectingthe66XPower/45XFlow,69%Power/47XFlowpointsextrapolatedtotheAPRMRodBlockline.OperationoutsideorontheboundaryofthisregionissupportedbyCOTRANcalculationswhichresultindecayratiosoflessthanorequalto0.75asrequiredbytheNRCSERonCOTRAN(seeSummaryReportReference14).ThisregionisslightlylargerthantheregionpreviouslyspecifiedforSSESUnit2.TheresultsofthisanalysisarepresentedinSummaryReportReference4.PP&LhasperformedastabilitystartuptestinSSESUnit2duringinitialstartupofCycle2todemonstratestablereactoroperationwithANF9x9fuel.Thetestresults(seeSummaryReportReference7)showverylowdecayratioswithacorecontaining324ANF9x9fuelassemblies.Basedontheabove,operationwithinthelimitsspecifiedbytheproposedTechnicalSpecificationswillnotsignificantlyincreasetheprobabilityorconsequencesofunstableoperation.

4h~hN~.I,~4~VI'V'NhVhylhIvV AttachmenttoPLA-2953Page4of4II.No.Themethodologydescribedabovecanonlybeevaluatedforitsaffectontheconsequencesofunstableoperation;itcannotcreatenewevents.TheconsequenceswereevaluatedinIabove.III.No.ThemethodologyusedtodeterminetheregionsofpotentiallyunstableoperationandstableoperationwerebasedontheguidanceprovidedintheNRCSERforCOTRAN.Also,SSESUnit2TechnicalSpecificationshaveimplementedsurveillancesfordetectingandsuppressingpoweroscillations.ThisalongwiththetestsandanalysesdescribedinIaboveassuresSSESUnit2complieswithGeneralDesignCriteria12,SuppressionofReactorPowerOscillations.Therefore,theproposedchangewillnotresultinasignificantdecreaseinsafetymargin.'b.SingleLoopOperation:TheproposedchangesreflectthechangessubmittedinsupportofCycle2operation(referenceproposedamendment52toLicenseNo.NPF-22,datedJune30,1987),whichisstillpendingwiththeNRC.Theonlychangenotexplicitlyevaluatedinthatsubmittalwasthecycle-specificsingleloopMCPRlimit,andanadministrativechangetotheSingleLoopOperation.(SLO)figureonThermalPowerLimitations.I.No.ThenewMCPRlimitisaresultoftheSLOanalysisdiscussedintheattachedANFreport,ANF-87-125.The0.01MCPRpenaltyduringSLOisstillproposed.Thechangetothefigurenumberisentirelyeditorialinnatureandthereforehasnoimpactonsafety.II.No.SeeIabove.III.No.SeeIabove.

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