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

'(.'CELEMTED DJiIBUTJONDEMONS~TIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:8712310143 DOC.DATE:

87/12/23NOTARIZED:

YESDOCKETFACIL:50-388 Susquehanna SteamElectricStation,Unit2,Pennsylva 05000388AUTH.NAMEAUTHORAFFILIATION KENYON,B.D.

Pennsylvania Power&LightCo.RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R.

ProjectDirectorate I-2p~gI

SUBJECT:

Forwardsapplication forProposedAmend58toLicenseNPF-22,changing TechSpecstosupportCycle3reload.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:

LTRENCLiSIZE:+!,TITLE:ORSubmittal:

GeneralDistribution NOTES:1cy NMSS/FCAF/PM.

LPDR2cysTranscripts.

05000388RECIPIENT IDCODE/NAME PD1-2LATHADANI,M COPIESRECIPIENT LTTRENCLIDCODE/NAME 10PD1-2PD11COPIESLTTRENCL55AINTERNAL:

ACRSNRR/DEST/ADSNRR/DEST/MTB NRR/DOEA/TSB OGC/HDS2RES/DE/EIB 661'111111011ARM/DAF/LFMB NRR/DEST/CEB NRR/DEST/RSB NRR8/ILRBEGFI01111110111I'D8EXTERNAL:

LPDR.,NSICNOTES:-.221133NRCPDR11R8A'DTOTALNUMBEROFCOPIESREQUIRED:

LTTR30ENCL278 OEG231987alt~~IIPennsylvania Power8LightCompany,TwoNorthNinthStreet,~Allentown, PA18101~215/7706151 IBruceD.KenyonSeniorVicePresident-Nuclear 215/770-4194DirectorofNuclearReactorRegulation Attention:

Dr.W.R.Butler,ProjectDirectorProjectDirectorate I-2DivisionofReactorProjectsU.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEHANNA STEAMELECTRICSTATIONPROPOSEDAMENDMENT 58TOLICENSENO.NPF-22:UNIT2CYCLE3RELOADSUBMITTAL PLA-2953FILESR41>>2,A17-2,A7-8CDocketNo.50-388

DearDr.Butler:

ThepurposeofthisletteristoproposechangestotheSusquehanna SESUnit2Technical Specifications insupportoftheensuingCycle3reload.Changestothefollowing Technical Specifications arerequested:

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~B3/4.2.3B3/4.4.1IndexAveragePlanarLinearHeatGeneration RateAPRMSetpoints MinimumCriticalPowerRatioLinearHeatGeneration RateControlRodBlockInstrumentation Recirculation SystemSafetyLimitsAveragePlanarLinearHeatGeneration RateAPRM'etpoints MinimumCriticalPowerRatioRecirculation SystemThefollowing attachments tothisletterareprovidedtoillustrate andtechnically supporteachofthechanges:8712310i43 PDRADOCKPgooIt8712230500038)(Marked-up Technical Specification ChangesNoSignificant HazardsConsiderations PL-NF<<87-007 "Susquehanna SESUnit2Cycle3ReloadSummaryReport",December1987Susquehanna SESUnit2Cycle3ProposedStartupPhysicsTestsSummaryDescription, November1987ANF-87-125, Revision1,"Susquehanna Unit2Cycle3PlantTransient Analysis",

November1987ANF-87-126, Revision1,"Susquehanna Unit2Cycle3ReloadAnalysis",

November1987 DEC23l98i,-2-FILESR41-2,A17-2,A7-8CPLA-2953Dr.W.R.ButlerSusquehanna SESUnit2iscurrently scheduled tobeshutdownforrefueling andinspection onMarch5,1988andtorestartasearlyasMay3,1988.Werequestthatyourapprovalbeconditioned tobecomeeffective uponstartupafterthisoutage,andwewillkeepyouinformedofanyschedulechanges.Anyquestions withrespecttothisproposedamendment shouldbedirectedtoMr.R.Sgarroat(215)770-7916.

Pursuantto10CFR170, theappropriate feeisenclosed.

Verytrulyyours,B.D.KenyonSr.VicePresident-Nuclear Attachments cc:iNRCDocumentControlDesk(original) gNRCRegionIMr.J.Stair,NRCResidentInspector-SSES Mr.M.C.Thadani,NRCProjectManager-Bethesda Mr.T.M.Gerusky,Pennsylvania DER 1IBASESINDEX~8712310143l SECTION3/4.0APPLICABILITY.3/4.1REACTIVITY CONTROLSYSTEMS3/4.l.1SHUTDOMNMARGIN...

3/4.1.2REACTIVITY ANOMALIES....,

..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.....,.............

7.3/4.2POWERDISTRIBUTION LIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATION ATE~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~RB3/41"4B3/42-1B3/42"2IB3/42"A~3/4.2.4LINEARHEATGENERATION RATE.........,...

B3/42-JSB3/4.3INSTRUMENTATION 3/4.3.13/4.3.23/4.3~33/4.3.43/4.3.53/4.3.6REACTORPROTECTION SYSTEMINSTRUMENTATION...

ISOLATION ACTUATION INSTRUMENTATION....,....

EMERGENCY CORECOOLINGSYSTEMACTUATION INSTRUMENTATION....

RECIRCULATION PUtIPTRIPACTUATION INSTRUMENTATION.

REACTORCOREISOLATION COOLINGSYSTEM ACTUATION INSTRUMEHTATIOH.

CONTROLRODBLOCKINSTRUMENTATION.

B3/43-1B3/43"2B3/43-283/43-3B3/43-4B3/43-4'SUSQUEHANNA "UNIT2'11 lI00 LISTOFFIGURESINDEXFIGURE3.1.5-13.l.'5"23.2.1-1SODIUMPENTABORATE SOLUTIONTEMPERATURE/

CONCENTRATION REQUIREMENTS

..SODIUMPENTABORATE SOLUTIONCONCENTRATION MAXIMUMAVERAGEPLANARLINEARHEATGENERATION RATE'(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"1MAXIMUMAVERAGEPLANARLINEARHEATGENERATION RATE(MAPLHGR)

VS.AVERAGEPLANAREXPOSURE, GEFUELTYPE8CR233(2.33KENRICHED)

................

3/42-3MAXIMUMAVERAGEPLANARLINEARHEATGENERATION RATE(MAPLHGR)

VS.AVERAGEBUNDLEEXPOSURE,

~it9x9FUEL..............

.........3/42-4REFLINEARHEATGENERATION RATEFORAPRMSETPOINTS VERSUSAVERAGEPLANAREXPOSURE,

~~C-...,.....

3/42-6aRlVFFvE.LFLOWDEPENDENT MCPROPERATING LIMIT..3/42"8REDUCEDPOWERMCPROPERATING LIMIT..............

3/42-9LINEARHEATGENERATION RATE(LHGR)L:MITVERSUSAVERAGEPLANAREXPOSURE,

&HNN'x9FUEL..........

3/42-10b/cozet=L.oW4~~THERMALPOWERALIMITATIONS

'''''''''''

344lb>>+"~~aPO4'8Rw'imTH&RPl~lPo~6Ru~~TATious MINIMUMREACTORVESSELMIFTALTEMPERATURE VS.REACTORVESSELPRESSURE...........3/44-184.7.4"1B3/43"1B3/4.4.6"1 5.1.1-15.l.2-15.l.3-la5.1.3"lbSAMPLEPLAN2)FORSNUBBERFUNCTIONAL TEST....REACTORVESSELWATERLEVEL.....FASTNEUTRONFLUENCE(E>1MeV)AT1/4TASAFUNCTIONOFSERVICELIFEEXCLUSION AREA.......~LOWPOPULATION ZONE.MAPDEFININGUNRESTRICTED AREASFORRADIOACTIVE GASEOUSANDLIQUIDEFFLUENTS MAPDEFININGUNRESTRICTED AREASFORRADIOACTIVE GASEOUSANDLIQUIDEFFLUENTS 3/4?"15B3/43-8B3/44"75"25-35-5SUSQUEHANNA

-'UNIT2xx11Amendment No.3) 4eQ~('IAi~uv~~0ii0ei~

2.1SAFETYLIMITSBASES

2.0INTRODUCTION

Thefuelcladding, reactorpressurevesselandprimarysystempipingaretheprincipal barrierstothereleaseofradioactive materials totheenvirons.

SafetyLimitsareestablished toprotecttheintegrity ofthesebarriersduringnormal.plantoperations andanticipated transients.

Thefuelcladdingintegrity SafetyLimitis'setsuchthatnofueldamageiscalculated tooccurifthelimitisnotviolated.

Becausefueldamageisnotdirectlyobservable, astep-back approachisusedtoestablish aSafetyLimitsuchthattheMCPisnotlessthanthelimitspecified inSpecification 2.l.2forbothGEandn..fuel.MCPRgreaterthanthespecified limitrepresents aconser-vativemarginrelativetotheconditions requiredtomaintainfuelcladdingintegrity.

Thefuelcladdingisoneofthephysicalbarrierswhichseparatetheradioactive materials fromtheenvirons.

Theintegrity ofthiscladdingbarrierisrelatedtoitsrelativefreedomfromperforations orcracking.

Al-thoughsomecorrosion oruserelatedcrackingmayoccurduringthelifeofthecladding, fissionproductmigration fromthissourceisincrementally cumulative andcontinuously measurable.

Fuelcladdingperforations, however,canresultfromthermalstresseswhichoccurfromreactoroperation significantly abovedesignconditions andtheLimitingSafetySystemSettings.

Whilefissionpro"ductmigration fromcladdingperforation isjustasmeasurable asthatfromuserelatedcracking, thethermally causedcladdingperforations signalathreshold beyondwhichstillgreaterthermalstressesmaycausegrossratherthanincre-mentalcladdingdeterioration.

Therefore, thefuelcladdingSafetyLimitisdefinedwithamargintotheconditions whichwouldproduceonsetoftransition boiling,MCPRof1.0.Theseconditions represent asignificant departure fromthecondition intendedbydesignforplannedoperation.

TheMCPRfuelcladdingintegrity Safetylimitassuresthatduringnormaloperation andduringantici-patedoperational occurrences, atleast99.9Xofthefuelrodsinthecoredonotexperience transition boiling(ref.XN-NF-524(A)).

2.'l.lTHERMALPOWERLowPressureorLowFlow~<'P~~C~l+hENSE'TheuseoftheXN-3correlation isnotvalidforallcriticalpowecalcu'satpressures below785psigorcoreflowslessthan1ofratedflow.There,thefuelcladdingintegrity SafetyLimitiablishedbyothermeans.Ths'sdonebyestablishing alimitingctiononcoreTHERMALPOWERwiththellowingbasis.Sincetheessuredropinthebypassregionisessentially alletionhead,threpressuredropatlowpowerandflowswillalwaysbegreatern4si.Analysesshowthatwithabundleflowof28x10~lbs/hr,buessuredropisnearlyindependent ofbundlepowerandhasavalue.5psi.thebundleflowwitha4.5psidrivingheadwillbegrethan28x10'bs/.FullscaleATLAStestdatatakenatpressures m14.7psiato800psiaindicatatthefuelassemblycriticalpowethisflowisapproximately 3.35MWt.Wiedesignpeakingors,thiscorresponds toaTHERMALPOWERofmorethaXofRATEDTHEPOWER.Thus,aTHERMALPO'WERlimitof25KofRATEDTHERMALforeactorressurebelow785siisconservative.

SUSQUEHANNA "UNIT2B2-1Amendment No.31 7heuse.ofPAeA'rer3corre,la~i'on t'sva.lidforcrier'ce.l powercalcaladi'ons atpressures gree,A<+Aan5'$'0psi'~artd4nndietttassfluxesIrea*rtAavtC7r7Sx/D~/bsj'Ar-F+.Faopal-atI'encLP/0wprt.ssuresor/ouiFlows,Shef'uelclad'drvtgnterriPy>afe~p<r'rnids tstaklis.hed'p' lt'rnid'np conclrtiortoncore~HEQIrIJQ PO&ORnrr'tA7theto/louring basislrovrPeel+ha~tAewat'el.leveli'nt'Aevessel+twitcorneti-smaintatnedahov.e 7Ae9opof7h<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'rtirnutvt bundle5litnit'sgrea,terteavt~P>ooo/hs/Prrortxllctvs/gxtzv+Aecco/trankFlowandxrtaxlrnuN f/owo.reeissue,g+Aa7'Qemassflexisaltvaysgrqa7crOAanc7~S4v'Olbsgg,-Fl,FuIIscaltcrr'9('ca Ipowys~~tosht'often.a.'Fpressure.es Journtor'~lpsialndt'ca,~e

%ha,k+hefueleessetnbyl crr'~ical pontet-c+

NtVSeRTg(con4nwi8 D.Rs~toIhs/hr-As 995Hw9orgreg,%et.

AS%+Acrmal.ponier a.bnndlgPowercorrespencis too.bundleradi'o-Ipea)i'ngFacforofgree~cr+A<<n3.+wgi'cliissunniFlcanRy higherVAeexpec/e,d peck'ngFactor.71,,7a<ewxcPo~E'0/,'87'EDTge<MRLPooJERForreactorpressures gqlow'8'5 psiJisconservefive'~

SAFETYLIMITSBASES2.1.2THERMALPOWERHihPressureandHihFlowOnsetoftransition boilingresultsinadecreaseinheattransferfromthecladand,therefore, elevatedcladtemperature andthepossibility ofcladfailure.However,theexistence ofcriticalpower,"orboilingtransition, isnotadirectlyobservable parameter inanoperating reactor.Therefore, themargintoboilingtransition iscalculated fromplantoperating parameters suchascorepower,coreflow,feedwater temperature, andcorepowerdistribution.

Themarginforeachfuelassemblyischaracterized bythecriticalpowerratio(CPR),whichistheratioofthebundlepowerwhichwouldproduceonsetoftran-sitionboilingdividedbytheactualbundlepower.Theminimumvalueofthisratioforanybundleinthecoreistheminimumcriticalpowerratio(MCPR).TheSafetyLimitMCPRassuressufficient conservatism intheoperating MCPRlimitthatintheeventofananticipated operational occurrence fromthelimitingcondition foroperation, atleast99.9Xofthefuelrodsinthecorewouldbeexpectedtoavoidboilingtransition.

Themarginbetweencalculated boilingtransition (MCPR=1.00)andtheSafetyLimitMCPRisbasedonade-tailedstatistical procedure whichconsiders theuncertainties inmonitoring thecoreooerating state.Onespecificuncertainty includedinthesafetylimitistheuncertainty inherentintheXN-3criticalpowercorrelation.

XN-NF-524 describes themethodology usedindetermining theSafetyLimitMCPR..X,HsE.RV S.TheXN"3'critical powercorlationisbasedonasignificant bodyofprac-ticaltestdata,providing a'ghdegreeofassuranCe thatthecriticalpowerasevaluated bythecorrelat'on iswithinasmallpercentage oftheactualcriti-calpowerbeingestimated.

eassumedreactorconditions usedindefiningthesafetylimitintroduce conservatism intothelimitbecauseboundinghighradialpowerfactorsandboundingflatlocalpeakingdistributions areusedtoestimatethenumberofrodsinboilingtransition.

Stillfurtherconservatism isinducedbythetendencyoftheXN-3correlation tooverpredict thenumberofrodsinboilingtransition.

Theseconservatisms andtheinherentaccuracyoftheXN-3correlation provideareasonable degreeofassurance thatduringsus-tainedoperation attheSafetyLimitMCPRtherewouldbenotransition boilinginthecore.Ifboilingtransition weretooccur,hereisreasontobelievethattheintegrity ofthefuelwouldnotnecessarily becompromised.

Significant testdataaccumulated bytheU.S.NuclearRegulatory Commission andprivateor-ganizations indicatethattheuseofaboilingtransition limitation toprotectagainstcladdingfailureisaveryc'onservative approach.

Muchofthedatain-dicatesthatLMRfuelcansurviveforanextendedperiodoftimeinanenviron-mentofboilingtransition.

SUSQUEHANNA

-UNIT282-2Amendment No.31 AslongasWAecorepressureand+lonso,re.will'n+dera,nateofya.IiI'lWy'ofVAeXS-3corr8la1~~n(reFertoSeci~/on04I./)>

3/4.2POWERDISTRIBUTION LIMITS3/4.2.1AVERAGEPLANARLINEARHEATGENERATION RATELIMITINGCONDITION FOROPERATION Rowan(RPIR6R~Q3.2.1AllAVERAGEPLANARLINEARHEATGENERATION

~&4e~&AVBQ~ttNBtC"

~NHI'VERAGE PLANAREXPOSUREshallnotexceedthelimitsshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3."

+4>~BCS<etawd~QE~6E.Q,QNhlP.pgpyS+gg6'AlF+Me/APPLICABILITY:

OPERATIONAL CONDITION 1,whenTHERMALPOWERisgreaterthanor*ACTION:WithanAPLHGRexceeding thelimitsofFigure3.2.1-1,3.2.1-2,or3.2.1-3,initiatecorrective actionwithin15minutesandrestoreAPLHGRtowithintherequiredlimitswithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCE REUIREMENTS 4.2.1AllAPLHGRsshallbeverifiedtobeequaltoorlessthanthelimitsdetermined fromFigures3.2.1-1,3.2.1-2,and3.2.1-3:a.Atleastonceper24hours,b.Within12hoursaftercompletion ofaTHERMALPOWERincreaseofatleast15KofRATEDTHERMALPOWER,andc.Initially andatleastonceper12hourswhenthereactorisoperating withaLIMITINGCONTROLR00PATTERNforAPLHGR.d.Theprovisions ofSpecification 4.0.4arenotapplicable.

• SeeSpecification

.3.4.1.1.2.a forsingleloopoperation requirements.

SUSQUEHANNA

-UNIT23/42"1Amendment No.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)MAXIMUMAVERAGEPLANARLINEARHEATGENERATION RATE(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~~~~~~~~:.PERMISSABLE REGIONOFOPERATION

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~I~~~~~~~~II~I406759.2~~~~~~~~~~~~~~~II~~~~~~~~~~~I~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~050001000015000200002500030000350004000045000AveragePlanarExposure{MWD/MT)MAXIMUMAVERAGEPLANARLINEARHEATGENERATION RATE(MAPLHGR)

VERSUSAVERAGEPLANAREXPOSUREGEFUELTYPES8CR233{2.33%ENRICHED)

FIGURE3.2.1-2 dNk 12<<g~11g)vC010g)OEc)8QvtQxI8(5I~~0.0;.10.2..:...';..:....

':...:...:...:.

~~I~ERMlSSADL REGIONOFOPERATION

~~~~~~~I0~~\~~~~~I~~\z6000~~~~~~~40,000;:,

1.520,000;10.2600010016000200002600000003600040000erageBundleExposure(MWDjT}MAXIMUMAVERAGEPlANARLINEARHEGENERATION RATE(MAPLHGR)

VERSUSAVERAGEBUNDLEEXPOSUREEXXON9X9FUELFlGURE3.2.1-3SUSQUEHANNA

-UNIT23/42"4Amendment No.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)MAXIMUMAVERAGEPLANARLINEARHEATGENERATION RATE{MAPLHGR)

VERSUSAVERAGEBUNDLEEXPOSUREANF9X9FUELFIGURE3.2.1-3 A/I.IP;t POWERDISTRIBUTION LIMITS3/4.2.2APRMSETPOINTS LIMITINGCONDITION FOROPERATION 3.2.2TheAPRMflowbiasedsimulated thermalpower-upscale scramtripsetpoint(S)andflowbiasedneutronflux-upscale controlrodblocktripsetpoint(SRB)shallbeestablished according tothefollowing relationships:

TriSetointAllowable ValueS<0.58W-+59K)TSRB<(0.58W+50K)TSRB-0'58W+53Twhere:SandSBareinpercentofRATEDTHERMALPOWER,W=too/recirculation flowasapercentage ofthelooprecirculation flowwhichproducesaratedcoreflowof100millionlbs/hr,T=LowestvalueoftheratioofFRACTIONOFRATEDTHERMALPOWERdividedbytheMAXIMUMFRACTIONOFLIMITINGPOWERDENSITY.%here:a~b.TheFRACTIONOFLIMITINGPOWERDENSITY(FLPD)forGEfuelistheactualLINEARHEATGENERATION RATE'(LHGR) dividedby13:4perSpecification 3.2.4.1,andRNPTheFLPDfor~mfuelistheactualLHGRdividedbytheLINEARHEATGENERATION RATEfromFigure3.2.2-1.Tisalwayslessthanorequalto1~0.APPLICABILITY:

OPERATIONAL CONDITION 1,whenTHERMALPOWERisgreaterthanorEEACTION:WiththeAPRMflowbiasedsimulated thermalpower-upscale scramtripsetpointand/ortheflowbiasedneutronflux-upscale control'rodblocktripsetpointlessconservative thanthevalue.shownintheAllowable ValuecolumnforSorSB,asabovedetermined, initiatecorrective actionwithin15minutesandadjust3and/orSRBtobeconsistent withtheTripSetpolntvalue*within2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLANCE REUIREMENTS 4.2.2TheFRTPandtheMFLPDshallbedetermined, thevalueofTcalculated, andthemostrecentactualAPRMflowbiasedsimulated thermalpower-upscale scramandflowbiasedneutronflux-upscale controlrodblocktripsetpoints verifiedtobewithintheabovelimitsoradjusted, as.required:

a*WithMFLPDgreaterthantheFRTPduringpowerascension upto90KofRATEDTHERMALPOWER,ratherthanadjusting theAPRMsetpoints, theAPRMgainmaybeadjustedsuchthatAPRMreadingsaregreaterthanorequalto100KtimesMFLPD,providedthattheadjustedAPRMreadingdoesnotexceed100KofRATEDTHERMALPOWER,therequiredgainadjustment increment doesnotexceed10KofRATEDTHERMALPOWER,andanoticeoftheadjustment ispostedonthereactorcontrolpanel.SeeSpecification 3.4.1.1.2.aforsingleloopoperation requirements.

SUSQUEHANNA

-UNIT23/42-5Amendment No.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)60000ILIRHEATGENERATION RATEFORAPRMSPOINTSVERSUSAVERAGEPLANAREXPOSUREEXXONFUELFIGURE3.2.2-1~cp(KgeJvent.gIvzupp,cyan,pzSUSQUEHANNA

-UNIT23/42-6eAmendment Np3]

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)50000LINEARHEATGENERATION RATEFORAPRMSETPOINTS VERSUSAVERAGEPLANAREXPOSUREANFFUELFIGURE3.2.2-1

1.7CURVEA:EOC-RPTtnoperabfe; MafnTurbineBypa:ssOperableCURVE8:MainTurbineBypassfnoperable; EOC-RPTOperableRVEC:EOC-RPTandMainTurbineByassOperableICOUl1.5CCLO1.4CL(31.3AC1.311.304050607080TotalCoreFlow(%OFRATED)90100O.FLOVlDEPENDENT MGPROPERATlNG LIMITF!GURE3.2.3-'I~<P~~tdu)(~g~<~~iqu+tC 0t 1.71.6(40,1.61}

CURVEA:EOC-RPTInoperable; MainTurbineBypassOperableCURVEB:EOC-RPTOperable:

MainTurbineBypassInoperable CURVEC: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)90100FLOWDEPENDENT MCPROPERATING LIMITFIGURE3.2.3-1 1.7ADmCURVEA:EOC-RPTInoperable:

MainTurbineBypassOperableCURVE8:MainTurbineBypassInoperabe;EOC-RPTOperableCURVEC:EOC-RPTandMainTurbeBypassOperable1.6~~CLO1ACLO1.3BDQ.9f+?.'1.220803040606070'orePower(%OFRATED)REDUCEDPOWERNtCPROPERATING LIMITFigure3.2.3-2QephwCedmc%hHE'~Fisvy~K.Z.5-290 1.6(25,1.52)

{40,1.50)

CURVEA:EOC-RPTInoperable:

MainTurbineBypassOperableCURVE8:EOC-RPTOperable:

MainTurbineBypassInoperable CURVEC: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)REDUCEDPOWERMCPROPERATING LIMITFigure3.2.3-290100 POWERDISTRIBUTION LIMITS3/4.2.4LINEARHEATGENERATION RATEVNFFUELLIMITINGCONDITION FOROPERATION puP3.2.4.2TheLINEARHEATGENERATION RATE(LHGR)forMC.fuelshallnotexceedtheLHGRlimitdetermined fromFigure3.2.4.2-1.APPLICABILITY:

OPERATIONAL CONDITION 1,whenTHERMALPOWERisgreaterthanorACTION:WiththeLHGRofanyfuelrodexceeding thelimit,initiatecorrective actionwithin15minutesandrestoretheLHGRtowithinthelimitwithin2hoursorreduceTHERMALPOWERtolessthan25KofRATEDTHERMALPOWERwithinthenext4hours.SURVEILLA'NCE REUIREMENTS A~F4.2.4.2LHGRsforM&fuelshallbedetermined tobeequaltoorlessthanthe1imit:a.Atleastonceper24hours,b.Within12hoursaftercompletion ofaTHERMALPOWERincreaseofatleast15XofRATEDTHERMALPOWER,andc.Initially andatleastonceper12hourswhenthereactorisoperating onaLIMITINGCONTROLRODPATTERNforLHGR.d.Theprovisions ofSpecification 4.0.4arenotapplicable.

SUS(UEHANNA

-UNIT23/42-10aAmendment No.31 r-)v0C-12..0.0,13.0'.----.:-.--:"-.

--:.---.'--...

---:""24,000;....'...-.-"'.-

'"."..'-...:....:...'...:...

'12.0C0EQL10CQ84QC~~:.PERMlSSE:.REGlOFOPATlON~~~~~~~~35.000;48,000;7.72~~100002000030000400AveragePlanarExposure{MID/MT)60000L(NEARHEATGENERATlON RATE(LHGR)LlMlTVERSUSAYERAGEPLANAREXPOSUREEXXON&X9FUELFlGURE3.2.4.2-]

p,~q(a.c.el mith~e~Fi+<<<>~8~'L

'le.+14E..0.0;13.0~~~~~~~~\~~~~~~.:...:,...:,.......:

...24,000;

....:12.0~~~~J~~~~~~~~~h~~'~~~~~~~~~I>~~~~I~~120CQLtD10C6)(98LCQtDC6~~~~~~~~I~L~~~~Ph~~I~~~~~~~\~~'LlERMISSABLE REGIONOFOPERATION

'I~~'ltC~~~~~~~~~35,000;95~~hJ~Ill'~~I~~J~i~~L~~%~h~~~J~48,0007.72010000200003000040000AveragePlanarExposure(MWD/MT}50000LINEARHEATGENERATION RATE(LHGR}LIMITVERSUSAVERAGEPLANAREXPOSUREANF9X9FUELFIGURE3.2.4.2-1 I'

TABLE3.3.6-2CONTROLRODBLOCKINSTRUMENTATION SETPOINTS TRIPFUNCTIONRODBLOCKMONITORa.Upscalettb.Inoperative c.DownscaleTRIPSETPOINT0.66W+42XNA>5/125divisions offullscaleALLOWABLE VALUE<0.66W+45KNA>3/125ofdivisions fullscale2.3.APRHa.FlowBiasedNeutronFlux-Upscale'~

b.Inoperative c.Downscale d.NeutronFlux-UpscaleStartupSOURCERANGEMONITORS<0.58W+50K*NA>SXofRATEDTHERMALPOWER<12KofRATEDTHERMALPOWER<0.58W+53K~NA>3XofRATEDTHERMALPOWER<14KofRATEDTHERHALPOWERa.b.C.d.DetectornotfullinUpscaleInoperative Downsca1e NA<2x10cpsNA)07cps')kNA<4xlOcpsNA>0.5cps*"4.INTERMEDIATE RANGEMONITORSaob.C.d.DetectornotfullinUpscaleInoperative Downscale NANA<108/125divisions offullscale<110/125divisions offullscaleNANA>5/125divisions offullscale>3/125divisions offullscale5.6.SCRAMDISCHARGE VOLUMEa.WaterLevel-High<44gallonsREACTORCOOLANTSYSTEMRECIRCULATION FLOW<44gallonsa.Upscale<108/125divisions offullscale<ill/125divisions offullscaleb.Inoperative NANAc.Comparator

<lOXflowdeviaticn

<llXflowdeviation TheAveragePowerRangeMonitorrodblockfunctionisvariedasafunctionofrecirculation loopflow(W).Thetripsettingofthisfunctionmustbemaintained inaccordance withSpecification 3.2.2.""Provided signal-to-noise ratiois>2.Otherwise, 3cpsastripsetpointand2.8cpsforallowable value.HSeeSpecification 3.4.1.1.2.a forsingleloopoperation requirements.

3/4.4REACTORCOOLANTSYSTEM3/4.4.1RECIRCULATION SYSTEMRECIRCULATION LOOPS-TWOLOOPOPERATION LIMITINGCONDITION FOROPERATION 3.4.1.1.1 Tworeactorcoolantsystemrecirculation loopsshallbeinoperationy and:a..Totalcoreflowshallbegreaterthanorequalto~millionlbs/hr,orthe,+Cat.+vtaasF0+C,&La~Ccsadi+ic3u RMALPOWER~lessthanorequaltothelimitspecified inFigure3.4.1.1.1"1.APPLICABILITY:

OPERATIONAL CONDITIONS 1"and2",exceptduringsingleloopoperation.4 ACTION:a.Withonereactorcoolantsystemrecirculation loopnotinoperation, complywiththerequirements ofSpecification 3.4.1.1.2,ortaketheassociated ACTION.~c4~~Wi~><ve+4a.'YH+g~ALblocc.a~d-i+i'.Withnoreactorcoolantsystemrecirculation loopsinoperation, immediately initiateanorderlyreduction ofTHERMALPOWERtolessthanorequaltothelimitspecified inFigure3.4.l.1.1-1,andinitiatelmeasurestoplacetheunitinatleastSTARTUPwithin6hoursandinHOTSHUTOOWNwithinthene'xt6hours.gheeWe,chi:+oY 0+oc.Withtworeactorcoolantsysrecirculation looinoperation andtotalcoreflowlessthanmillionlbs/hrandHERMALPOWERgreaterthanthelimitspecified inFigure3.4.1.1.1-1:

4/covCSlo~}es+tsVC+beC4.'43.C+n+

+oct.Cashd>te43>1.lessthanorequaltothelimitspecified inFigure3.4.1.1.1-1, orF<<s'ee~'~<<Mti+lowI2.Increasecoreflowtogreaterthan4millionlbs/hr,or3.Determine theAPRMandLPRM"""neutronfluxnoiselevelswithin1hour,and:a)IftheAPRMandLPRM"*"neutronfluxnoiselevelsarelessthanthreetimestheirestablished baselinelevels,continuetodetermine thenoiselevelsatleastonceper8hoursandwithin30minutesafterthecompletion ofaTHERMALPOWERincreaseofatleast5XofRATEDTHERMALPOWER,orb)IftheAPRMorLPRM*""neutronfluxnoiselevelsaregreaterthanorequaltothreetimestheirestablished baselinelevels,immediately initiatecorrective actionandrestorethenoiselevelstowithintherequiredlimitswithin2hoursbyincreasing coreflowtogreaterthanml>onsr,and/orbyuc4Ae~rf-TitERM~CMN

~~</co<elessthanorequaltothelimitspecified inFigure3.4.l.1.1-1.I"SeeSpecialTestException 3.10.4."""Detectors AandCofoneLPRMstringpercoreoctantplusdetectors AandCofoneLPRMstring'in thecenterofthecoreshouldbemonitored.

OSeeSpecification 3.4.1.1.2 forsingleloopoperation requirements.

SUSQUEHANNA

-.UNIT23/44-1Amendment No.26

80Figure3.4.1.1.1-1 THERMALPOWERLIMITATIONS 70C}LU~~eo(60'040E3020L0O10REGIONGRTERTHANUMIT04~Ir~~\p)h"REGIONLESSTHANMITJI~~~02030406080CoreRow(%RAYED)7080SUSIlUEHAHHA "UNIT23/44-1bAmendment H0..26'-4 80C570'<j:>orpo40CD30Lf-20L10Eigure3'.4..1.1.1

-1THERMALPOWER/CORE FLOWLIMITATIONS

---

.-REGIONGREATER-.:-"--..:

.THANLIMITIREGIONLESSTHANLIMIT02030406060CoreFlow(%RATED)7080 0

REACTORCOOLANTSYSTEMRECIRCULATION LOOPS-SINGLELOOPOPERATION LIMITINGCONDITION FOROPERATION 3.4.1.1.2 Onereactorcoolantrecirculation loopshallbeinoperation withthepumpspeed<40Koftheratedpumpspeed,andBo&~a.thefollowing revisedspecification limitsshalloefollowed:

l.Specification 2.1.2:theMCPRSafetyLimitshallbeincreased to1.07.2.Table2.2.1-1:theAPRMFlow-Biased ScramTripSetpoints shallbeasfollows:TriSetoint<0.58W+55Allowable Value<0.58W+58.3.4.INSERTS.4xS<(0.58W+55K)TSRB<(0.58W+46K)TAllowable Value'l)SRB<(0.58W+49K)TTable3.3.6-2:theRBM/APRMControlRodBlockSetpoints shallbeasfo1'1ows:a.,RBM-UpscaleAllowable ValueTriSetointSpecification 3.2.1:TheHAPLHGRlimitsshallbethelimitsspecified 4-.I.Rio~d~Fluvc.8.2.1-3Specification 3.2.2:theAPRHSetpoints shallbeasfollows:'mvltiq6ed 4y'L.0~<0.66W+3<0.66W+40k-.a;-1-and~~?-shaR-be-used

-ie-eonjunet+o~~4e-M b.APRM-Flow BiasedTriSetointAllowable Value<0.58W+46b.APRMandLPRM"""neutronfluxnoiselevelsshallbelessthanthreetimestheirestablished baselinelevelswhenTHERMALPOWERisgreaterthanthelimitspecified inFigure3/4.l.1.2-1.2c.Totalcoreflowshallbegreaterthanorequalto42millionlbs/hrwhenTHERMALPOWERisgreaterthanthelimitspecified inFigure3.4.1.1.Z-1.

zAPPLICABILITY:

OPERATIONAL CONDITIONS 1"and2",exceptduringtwoloopoperation.0ACTION:a.Withnoreactorcoolantsystemrecirculation loopsinoperation, taketheACTIONrequiredbySpecification 3.4.1.1.1.SUS(UEHANNA "UNIT23/44-lcAmendment No.31 0CI Speci&ico+'aaa

~.2.>:T48PIINI&UMCRI'TICAL PowFRIRIA~ID(Wc~IRIsIa.ll4ecgeoaew+Io.~oeeqao.(ao<Nelaw's+aswlesalia~lugaolaes:

o.,h.31)b~+he8C'Pkide+e>yniNed Svo~FigurepIusa.al~a.ZdC.<4,l%CYAN>d,eke>mi~ed

&&0~~iqwwe.E.Z.z-2.@~ASo.0h~

4Itka REACTORCOOLANTSYSTEMLIMITINGCONDITION FOROPERATION Continued b.C.d.e.Withanyofthelimitss'pecified in3/4.1.1.2anotsatisfied:

Cl.Uponenteringsingleloopoperation, complywiththenewlimitswithin6hoursorbeinatleastHOTSHUTDOWNwithinthefollowing 6hours.2.Iftheprovisions ofACTIONb.1donotapply,taketheACTION(s) requiredbythereferenced Specification(s).

WiththeAPRMorLPRM"""neutronfluxnoiselevelsgreaterthanorequaltothreetimestheirestablished baselinelevelswhenTHERMALPOWERisgreaterthanthelimitspecified inFig"ure3,4.1.1.-1,immediately initiatecorrective actionandresore.enoi'selevelstowithintherequi'red limitswithin2hoursbyinitiating anorderlyreduction ofTHERMALPOWERto~+lessthanorequaltothelimitspecified inFigure3.4.1.1.<l.Otherwise, beinatleastHOTSHUTDOWNwithinthenext12hours.Withoneormorejetpumpsinoperable, beinatleastHOTSHUTDOWNwithin12hours.Withtotalcoreflowlessthan42millionlbs/hrwhenTHERMALPOWERisgreaterthornthelimitspecified inFigure3~4.1.1.<l, immediately initiatecorrective actionbyeither:1.ReducingTHERMALPOWERtolessthanorequaltothelimitspecified inFigure3.4.1.1.W1 within4hours,'rp2.Increasing totalcoreflowtogreaterthanorequalto42millionlbs/hrwithin4hours.SURVEILLANCE REUIREMENTS 4.4.l.1.'2.14.4.l.l.2.24.4.1.1.2.3'ponenteringsingleloopoperation andatleastonceper24hoursthereafter, verifythatthepumpspeedintheoperating loopis<Sf%oftheratedpumpspeed.8O'PoWithTHERMAOWERgreaterthanthelimitspecified inFig-ure3.4.1.1.-1,determine theAPRMandLPRM"""neutronfluxnoiselevelswithin1hour.-Continuetodetermine thenoiselevelsatleastonceper8hoursandwithin30minutesafterthecompletion oftheTHERMALPOWERincrease)5XofRATEDTHERMALPOWER.Within15'minutes priortoeitherTHERMALPOWERincreaseresulting fromacontrolrodwithdrawal orrecirculation loopflowincrease, verifythatthefollowing differential temperature.

requirements aremetifTHERMALPOWERis<30K""*"ofRATEDTHERMALPOWERortherecirculation loopfTowintheoperating recirculation loopis<50K""""ofratedloopflow:SUSQUEHANNA.-

UNIT23/44-1dAmendment No.26 0

8070I-~60~O50040P302010O-Figure3.4.1.1.2-1 SINGLELOOPOPERATION THERMALPOWERLIMITATIONS

.--.-REGIONGREATERTHANLIMITREGIONLESSTHANLIMIT2030405060CoreFlow{%RATED)7080 3/4.2POMERDISTRIBUTION LIMITSBASESThespecifications ofthissectionassurethatthepeakcladdingtemperature following thepostulated designbasisloss-of-coolant accidentwillnotexceedthe2200Flimitspecified in10CFR50.46.3/4.2.1AVERAGEPLANARLINEARHEATGENERATION RATEThisspecification assuresthatthepeakcladdingtemperature following thepostulated designbasisloss-of-coolant accidentwillnotexceedthelimitspecified inl0CFR50.46.Thepeakcladdingtemperature (PCT)following apostulated loss-of-coolant accidentisprimarily afunctionoftheaverageheatgeneration rateofalltherodsof.afuelassemblyatanyaxiallocationandisdependent onlysecondarily ontherodtorodpowerdistribution withinanassembly.

forGEfuel,thepeakcladtemperature iscalculated assumingaLHGRforthehighestpoweredrodwhichisequaltolessthanthedesignLHGRcorrected fordensification.

ThisLHGRtimes1.02isusedintheheatupcodealongwiththeexposuredependent steadystategapconductance androd-to-rod localpeaki.ngfactor.TheTechnical Specification AVERAGEPLANARLINEARHEATGENERATION RATE(APLHGR)forGEfuelisthisLHGRofthehighestpoweredroddividedbyitslocalpeakingfactorwhichresultsinacalculated LOCAPCTmuchlessthan2200F.TheTechnical Specifi-cationAorfuelisspecified toassurethePCTfollowing apostu-latedLOCAwillnotexceedthe2200~Flimit.ThelimitingvalueforAPLHGRisshowninFigures3.2.1-1,3.2.1-2,and3.2.1-3.Thecalculational procedure usedtoestablish theAPLHGRshownonFig-ures3.2.1-1,3.2.1-2,and3.2.1-3isbasedonaloss-of-coolant accidentanalysis.

Theanalysiswasperformed usingcalculational modelswhicharecon-sistentwiththerequirements ofAppendixKto10CFR50.Thesemodelsaredescribed inReference 1orXN-NF-80-19, Volumes2,2A,2Band2C.3/4.2.2APRMSETPOINTS Theflowbiasedsimulated thermalpower-upscale scramsettingandflowbiasedsimulated thermalpower-upscale controlrodblockfunctions oftheAPRMinstruments limitplantoperations totheregioncoveredbythetransient andaccidentanalyses.

Inaddition, theAPRMsetpoints mustbeadjustedtoensurethat>1%plasticstrainandfuelcenterline meltingdonotoccurduringtheworstanticipated operational occurrence (AOO),including transients initiated frompartialpoweroperation.

RufFord~~fueltheTfactorusedtoadjusttheAPRMsetpoints isbasedontheFLPDcalculated bydividingtheactualLHGRbytheLHGRobtainedfrom,Figure3.2.2-1.TheLHGRversusexposurecurveinFigure3.2.2-1isbasedonPNFSExxen-'s Protection AgainstFuelFailure(PAFF)lineshowninFigure3.4ofXN-NF-85-67 Revision1.Figure3.2.2-1corresponds totheratioofPAFF/1.2unerwhachcladdingandfuelintegrity isprotected duringAOO's.SUS(UEHANNA "UNIT2B3/42-1Amendment No.31 (5~NV POWEROISTRIBUTION LIMITSBASESAPRHSETPOINTS (Continued)

ForGEfueltheTfactorusedtoadjusttheAPRHsetpoints isbasedontheFLPDcalculated bydividingtheactualLHGRbytheLHGRlimitspecified forGEfuehinSpecification 3.2.4.1.3/4.2.3HINIMUMCRITICALPOWERRATIOTherequiredoperating limitMCPRsatsteadystateoperating conditions asspeci-ifiedinSpecification 3.2.3arederivedfromthe.established fuelcladdingintegrity SafetyLimitHCPR,andananalysisofabnormaloperational transients.

Foranyabnormaloperating transient analysisevaluation withtheinitial.con-ditionofthereactorbeingatthesteadystateoperating limit,itisrequiredthattheresulting MCPRdoesnotdecreasebelowtheSafetyLimitMCPRatanytimeduringthetransient assuminginstrument tripsettinggiveninSpecifica-tion2.2.Toassurethatthe,fuelcladdingintegrity SafetyLimitisnotexceededduringanyanticipated abnormaloperational transient, themostlimitingtransients havebeenanalyzedtodetermine whichresultinthelargestreduction inCRITICALPOWERRATIO(CPR).Thetypeoftransients evaluated werelossofflow,increaseinpressureandpower,positivereactivity insertion, andcoolanttemperature decrease.

Thelimitingtransient yieldsthelargestdeltaMCPR.WhenaddedtotheSafetyLimitMCPR,therequiredminimumoperating limitHCPRofSpecification 3.2.3isobtainedandpresented inFigure3.2.3-1and3.2.3-2.Theevaluation ofagiventransient beginswiththesysteminitialparameters showninthecyclespecifictransient analysisreportthatareinputtoe-i~emcoredynamicbehaviortransient computerprogram.TheoutputsofthisprogramalongwiththeinitialMCPRformtheinputforfurtheranalysesofthethermally limitingbundle.Thecodesandmethodology toevaluatepressurization andnon-pressurization eventsaredescribed inXN-NF-79-71 andXN-NF-84-105.

Theprinci-palresultofthisevaluation isthereduction inHCPRcausedbythetransient.

Figure3.2.3-1definescoreflowdependent MCPRoperating limitswhichassurethattheSafetyLimitHCPRwillnotbeviolatedduringaflowincreasetran-sientresulting fromamotor-generator speedcontrolfailure,Theflowdepend-entHCPRisonlycalculated forthemanualflowcontrolmode.Therefore, automatic flowcontroloperation isnotpermitted.

Figure3.2.3-2definesthepowerdependent HCPRoperating limitwhichassuresthattheSafetylimitHCPRwillnotbeviolatedintheeventofafeedwater controller failureinitiated fromareducedpowercondition.

Cyclespecificanalysesareperformed forthemostlimitinglocalcorewidetran-sientstodetermine thermalmargin.Additional analysesareperformed todetermine theMCPRoperating limitwitheithertheMainTurbineBypassinoperable ortheEOC-RPTinoperable.

Analysestodetermine thermalmarginwithboththeEOC-RPTinoperable andHainTurbineBypassinoperable havenotbeenperformed.

Therefore, operation inthiscondition isnotpermitted.

SUSQUEHANNA

-UNIT2B3/42"2Amendment No.31 I41 3/4.4REACTORCOOLANTSYSTEMBASES3/4.4.1RECIRCULATIONSYSTEMOperation withonereactorrecirculation loopinoperable hasbeenevaluated andfoundacceptable, providedthattheunitisoperatedinaccordance withSpecification 3.4.1~1.2.des-exuded-operatien~~n~o~s~

~+68Forsingleloopoperation, theRBMandAPRMsetpoints areadjustedbya7Xdecreaseinrecirculation driveflowtoaccountfortheactiveloopdriveflowthatbypassesthecoreandgoesupthroughtheinactiveloopjetpumps.Surveillance onthepumpspeedoftheoperating recirculation loopisimposedtoexcludethepossibility ofexcessive reactorvesselinternals vibration.

Surveillance ondifferential temperatures belowthethreshold limitsofTHERMALPOWERorrecirculation loopflowmitigates unduethermalstressonvesselnozzles,recirculation pumpsandthevesselbottomheadduringextendedopera-tioninthesingleloopmode.Thethreshold limitsarethosevalueswhichwillsweepupthecoldwaterfromthevesselbottomhead.THERMALPOWER,coreflow,andneutronfluxnoiselevellimitations areprescribed inaccordance withtherecommendations ofGeneralElectricServiceInformation LetterNo.380,Revision1,"BWRCoreThermalHydraulic Stability,"

datedFebru-ary10,1984.Aninoperable jetpumpisnot,initself,asufficient reasontodeclareare-circulation loopinoperable, butitdoes,'incaseofadesignbasisaccident, increasetheblowdownareaandreducethecapability ofreflooding thecore;thus,therequirement forshutdownofthefacilitywithajetpumpinoperable.

Jetpumpfailurecanbedetectedbymonitoring jetpumpperformance onaprescribed scheduleforsignificant degradation.

Recirculation pumpspeedmismatchlimitsareincompliance withtheECCSLOCAanalysisdesigncriteriafortwoloopoperation.

Thelimitswillensureanadequatecoreflowcoastdown fromeitherrecirculation loopfollowing aLOCA.Inthecasewherethemismatchlimitscannotbemaintained duringtheloopoperation, continued operation ispermitted inthesingleloopmode.Inordertopreventunduestressonthevesselnozzlesandbottomheadregion,therecirculation looptemperatures shallbewithin50Fofeachotherpriortostartupofanidleloop.Thelooptemperature mustalsobewithin50Fofthereactorpressurevesselcoolanttemperature topreventthermalshocktotherecirculation pumpandrecirculation nozzles.Sincethecoolantinthebottomofthevesselisatalowertemperature thanthecoolantintheupperregionsofthecore,unduestress.onthevesselwouldresultifthetemperature differ-encewasgreaterthan145'F.SUSQUEHANNA

-UNIT2B3/44-1Amendment No.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.rc I"I'r'nassrAreW3epeakc./aJg,'sed~rrrlga.2<CAei'enfee'.mar'os g/AQOCr'F:TgytlNlgvrlcaiT'ieger.

Poarb4R~ri'o$8fepg)/,'orsmy'leloopogero.froh assur<74<7w$esa+efy'lnileACIESisno7'ePeeeoeJ Forariylnfrcppaf<4 Operefiona/Cecuvrcncc.

CtPOo)grigFog73'.Reer'rerJ4fi'on Punt@5'eiZ,ure laic.id'end.

Attachment toPLA-2953Page1of4NOSIGNIFICANT HAZARDSCONSIDERATIONS Thefollowing threequestions areaddressed foreachoftheproposedTechnical Specification changes:Doestheproposedchangeinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated?

Doestheproposedchangecreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated?

Doestheproposedchangeinvolveasignificant reduction inamarginofsafety?Secificatioa 3/4.2.1,AveraePlanarLinearHeatGeneration RateThechangestothisspecification reflecteditorial changestocorrectmisarranged wordingthatwasissuedwithAmendment 31,andthereplacement ofreferences to"Exxon"with"ANF".AchangetoincreasetheallowedexposureforGE2.33Xenrichedfuelto40,675MWD/MTUisalsoproposed.

No.Theeditorial changestocorrectmisarranged wordingandthevendorreference arewhollyeditorial innatureandtherefore havenoimpactonanysafetyanalysis.

ThechangetotheGElimitisbasedonaGELOCAanalysis.

Thisnewcurvewaspreviously approvedbytheNRCinAmendment 64totheUnit1Operating License,itisafuel-dependent limit,andisbeingappliedtothesametypeofGEfuelinthisUnit2proposal.

Asstatedinthestaffsafetyevaluation forAmendment 64,"Theresulting peakcladdingtemperature (PCT)limitandlocaloxidation fractionwerecalculated byGEbasedonthesameplantconditions andsystemsanalysisusedtoderivethecurrentMAPLHGRlimitsdefinedintheSSESFSAR.Thecalculated valuesarewellwithinthelOCFR50.46 AppendixKlimits."Theseconclusions stillapply.No.Theeditorial changescannotcreatenewconcerns; basedonthemethodsandresultsoftheGEanalysisdiscussed above,noneweventsarepostulated duetotheextendedburn-uplimit.No.Theeditorial changeshavenosafetyimpact.Thepreviously approvedmethodsandresultsoftheGEanalysisensurethatthemarginofsafetyisnotreducedduetothechangeintheGEfuelMAPLHGRlimit.

UUIk~kUP Attachment toPLA-2953Page2of4Secification 3/4.2.2,APRMSetpintsAllproposedchangestothisspecification areeditorial.

No.Theproposedchangescorrectthevendorreference from"Exxon"to"ANF".Thishasnoimpactonsafetyanalysessinceitisentirelyadministrative innature.II.No.SeeIabove.III.No.SeeIabove.Secification 3/4.2.3,MinimumCriticalPowerRatioThechangestothisspecification reflecttheresultsofthecycle-specific transient analyses.

No.Limitingcore-wide transients wereevaluated withANF'sCOTRANSAcode(seeSummaryReportReference 18)andthisoutputwasutilizedbytheXCOBRA-Tmethodology (seeSummaryReportReference 19)todetermine deltaCPRs.BothCOTRANSAandXCOBRA-ThavebeenapprovedbytheNRCinpreviouslicenseamendments.

Allcore-wide transients wereanalyzeddeterministically (i.e.,usingboundingvaluesasinputparameters).

Twoloadevents,RodWithdrawal ErrorandFuelLoadingError,wereanalyzedinaccordance withthemethodsdescribed inXN-NF-80-19 (A)Vol.1"(see"SummaryReport'Reference 15).Thismethodology hasbeenapproved'by theNRC.Basedontheabove,themethodology usedtodevelopthenewoperating limitMCPRsfortheTechnical Specifications doesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

No.Themethodology described canonlybeevaluated foritsaffectontheconsequences ofanalyzedevents;itcannotcreatenewones.Theconsequences ofanalyzedeventswereevaluated inIabove.No.AsstatedinIabove,andingreaterdetailintheattachedSummaryReport,themethodology usedtoevaluatecore<<wide andlocaltransients isconsistent withpreviously approvedmethodsandmeetsallpertinent regulatory criteriaforuseinthisapplication.

Therefore, itsusewillnotresultinasignificant decreaseinanymarginofsafety.Secification 3/4.2.4,LinearHeatGeneration RateAllproposedchangestothisspecification areeditorial.

No.Thepropose'd changescorrectthevendorreference from"Exxon"to"ANF".Thishasnoimpactonsafetysinceitisentirelyadministrative innature.

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

~~arAttachment toPLA-2953Page3of4II.No.SeeIabove.III.No.SeeIabove.Secification 3/4.3.6,ControlRodBlockInstrumentation Theproposedchangetothisspecification iseditorial andwaspreviously submitted totheNRCviaproposedamendment 52,datedJune30,1987.No.Theproposedchangerestoresfootnote"////"toTripFunction2a.Thisfootnotewasalwaysmeanttoapplyinthislocation.

Thischangehasnoimpactonsafetysinceitisentirelyeditorial innature.II.No.SeeIabove.III.No.SeeIabove.Secification 3/4.4.1,Recirculation Sstema.TwoLoopOperation:

Thechangestotheserequirements areduetothecyclespecificstability analysis.

Thenewanalysisresultedinavarying"detectandsuppress" regionflowboundary, whichinturnresultedintheneedfortheeditorial changestotheactionstatements.

No.COTRANcorestability calculations performed forU2C3predictstablereactoroperation outsideofthedetectandsuppressregionofoperation inSSESUnit2.Thedetectandsuppressregionisdefinedbytheareaaboveandtotheleftofthe80%RodBlockline,the45Xconstantflowline,andthelineconnecting the66XPower/45X Flow,69%Power/47X Flowpointsextrapolated totheAPRMRodBlockline.Operation outsideorontheboundaryofthisregionissupported byCOTRANcalculations whichresultindecayratiosoflessthanorequalto0.75asrequiredbytheNRCSERonCOTRAN(seeSummaryReportReference 14).Thisregionisslightlylargerthantheregionpreviously specified forSSESUnit2.Theresultsofthisanalysisarepresented inSummaryReportReference 4.PP&Lhasperformed astability startuptestinSSESUnit2duringinitialstartupofCycle2todemonstrate stablereactoroperation withANF9x9fuel.Thetestresults(seeSummaryReportReference 7)showverylowdecayratioswithacorecontaining 324ANF9x9fuelassemblies.

Basedontheabove,operation withinthelimitsspecified bytheproposedTechnical Specifications willnotsignificantly increasetheprobability orconsequences ofunstableoperation.

4h~hN~.I,~4~VI'V'NhVhylhIvV Attachment toPLA-2953Page4of4II.No.Themethodology described abovecanonlybeevaluated foritsaffectontheconsequences ofunstableoperation; itcannotcreatenewevents.Theconsequences wereevaluated inIabove.III.No.Themethodology usedtodetermine theregionsofpotentially unstableoperation andstableoperation werebasedontheguidanceprovidedintheNRCSERforCOTRAN.Also,SSESUnit2Technical Specifications haveimplemented surveillances fordetecting andsuppressing poweroscillations.

Thisalongwiththetestsandanalysesdescribed inIaboveassuresSSESUnit2complieswithGeneralDesignCriteria12,Suppression ofReactorPowerOscillations.

Therefore, theproposedchangewillnotresultinasignificant decreaseinsafetymargin.'b.SingleLoopOperation:

Theproposedchangesreflectthechangessubmitted insupportofCycle2operation (reference proposedamendment 52toLicenseNo.NPF-22,datedJune30,1987),whichisstillpendingwiththeNRC.Theonlychangenotexplicitly evaluated inthatsubmittal wasthecycle-specific singleloopMCPRlimit,andanadministrative changetotheSingleLoopOperation

.(SLO)figureonThermalPowerLimitations.

I.No.ThenewMCPRlimitisaresultoftheSLOanalysisdiscussed intheattachedANFreport,ANF-87-125.

The0.01MCPRpenaltyduringSLOisstillproposed.

Thechangetothefigurenumberisentirelyeditorial innatureandtherefore hasnoimpactonsafety.II.No.SeeIabove.III.No.SeeIabove.

e'pv'IP'ga