ML17264A849

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Proposed Tech Specs 3.7.12 Re Spent Fuel Pool Boron Concentration
ML17264A849
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Issue date: 03/31/1997
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SFPBoronConcentration 3.7.123.7PLANTSYSTEMS3.7.12SpentFuelPool(SFP)BoronConcentration c,-t.)LCO3.7.12TheSFPboronconcentration shallbea0ppm.APPLICABILITY:

Whenfuelassemblies arestoredintheSFPandaSFPverification hasnotbeenperformed sincethelastmovementoffuelassemblies intheSFP.ACTIONSCONDITION RE(UIREDACTIONCOMPLETION TIME-A.SFPboronconcentration notwithinlimit.------------NOTE-------------

LCO3.0.3isnotapplicable.

A.IANDA.2.1ORSuspendmovementoffuelassemblies intheSFP.InitiateactiontorestoreSFPboronconcentration towithinlimit.Immediately Immediately A.2.2InitiateactiontoperformSFPverification.

Immediately 9704070040 97033iPDRADOCK05000244PPDRR.E.GinnaNuclearPowerPlant30727Amendment No.61 o.n<a&a33.ho.voi~i&o3~me%~~S.Wrwup~)~i~3.'7PLANTSYSTEMS~a.~+a.hi~

o.~o'37.13SpentFuelPool(SFP)StorageSFPStorage3.7.13LCO3.7.13Fuelassemblystorageinthespentfuelpoolshallbemaintained asfollows:C~X~'L-:a.Fuelassemblies inRegion1shallhaveaK-infinity of~1.458.and"b.Fuelassemblies inRegion2shallhaveinitial'enrichment andburnupwithintheacceptable areaoftheFigure3.7.13l.~APPLICASILITY:

Wheneveranyfuelassemblyisstoredinthespentfuelpool.ACTIONSCONDITION REQUIREDACTIONCOMPLETION TIME"-A.Requirements oftheA.1LCOnotmetforeitherregion.--------NOTE---------

LCO3.0.3isnot'applicable.

Q.X~1Initiateactiontomovethenoncomplying ueasseromapp>cableregion.Immediately

+o~~~~~<X'4~QAiR.E.GinnaNuclearPowerPlant3.7-29Amendment No.61' SFPStorage3.7.13SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

.SR3.7.13.1NOTENotrequiredtobeperformed whentransferring afuelassemblyfromRegion2toRegion.l.

Verifybyadministrative meanstheK-infinity ofthefuelassemblyis~1.458.Priorto.storingthefuelassemblyinRegion1SR3.7.13.2Verifybyadministrative meanstheinitialenrichment andburnupofthefuelassemblyisinaccordance withFigure3.7.13~,2.PriortostoringthefuelassemblyinRegion,:2 R.E.GinnaNuclearPowerPlant3.7-30Amendment No.61 SFPStorage3.7.1340000ACCEPTABLE 30000O.=ErD-m20000P"fC5CJ'.l5"EUNACCEPTABLE 10000-OFAFuel6ExmnFuel----5'1DFuel1.82.63.03.43.84.2NominalUEnrichment(w/o) 6.0Figure3.7.13~FuelAssemblyBurnupLimitsinRegion2R.f.GinnaNuclearPowerPlant3.7-31Amendment No.61 M<58Jf+SFPStorage3.7;13I!!II~I~0~I~0I-415000I"4Q=81OOOO)~~;i)Ii~')I0IIiI'I)!II)I~I~II!I!II!II'!!!I.I:I'!I~~IIi!I~~~->>00611$2XS"33S445"5AssemblyInitial'Enrichment, VA%'Figure3.7.13-1FuelAssemblyBurnupLimitsinRegionIA~as-bX~aw~up~~oi~4r-clara~xma.~K~~~~~i~~~gus~.A~+rae4)QurmmP~ki~~fSI)I~g)',W

~~~2~~~~9.-ivR.E.GinnaNuclearPowerPlant3.7-a<~

!IA1-AcceptabrnupdomainforstorageinanylocationinRegion2.A2.-AcceptableMurnup domainforstorage.face-adjacent toypeA1orA2assembly, orawatercell.B-Acceptable burnupdomainforstorageface-adjacent toaTypeA1assemblyorawatercell.C-Acceptable-burnup domainforstorage:face-adjacent,to awatercellonly.Storage3.7.13,Region2.Loading,Ciuve.

cateM300008=CO-"K8=-0'0000VJCO>>II'!!!I;:IiI;II~!~,::I!I!'!!~~~~lllII;e!!lI!!llIIlIl!!>>,!l!!IlI;0%Oi.LS=1~ISs2~..sD",sW.4+.4$>>5%.AssemblyInitial=.Enrichment,-.Wt%-

Figure3.7:13-2IuelAssemblyBurnupLimitsinRegion2"RK..Ginna.Nuclear..Power Plant3.7-3gQ DesignFeatures4.04.0DESIGNFEATURES4.2ReactorCore(continued)

-4.2.2ControlRodAssemblies Thereactorcoreshallcontain29controlrodassemblies.

Thecontrolmaterialshallbesilverindiumcadmium.-4.3FuelStorage4:3.14:3.l.IThespentfuelstorageracksaredesignedandshallbe-maintained with:>>a.Fuelassemblies havingamaximumU-235enrichment of5.05weightpercent;..b.k,<<s0.95iffullyfloodedwithunborated water,whichincludesanallowance foruncertainties asdescribed inSection9.1oftheUFSAR;C,a.ac~Consolidated-rod storagecanisters maybestoredinthespentfuelstorageracksprovidedthatthefuelassemblies fromwhichtherodswereremovedmeetalltherequirements ofLCO3.7.13fortereioninwhichtheanisteristobestoreHowevereconsolaterostoragecanisterlocatediRegionRGAF2mayexeedthesereu'.Theaerageecayeaotheueassemblyfromwhichtherodswereremovedforallconsolidated fuelassemblies mustalsobes2150BTU/hr.4.3.1.2Thenew-fuelstoragedryracksare'esigned andshallbemaintained with:a.Fuelassemblies havingamaximumU-235enrichment of5.05weightpercent;b;-k,<<z0.95iffullyfloodedwithunborated water,whichincludes.anallowance foruncertainties asdescribed inSection9.1oftheUFSAR;andc.k,<<s0.98ifmoderated byaqueousfoam,whichincludesanallowance foruncertainties asdescribed inSection9.1oftheUFSAR.(continued)

R.E.GinnaNuclearPowerPlant4;0-2Amendment No.61 DesignFeatures4.0(4.0DESIGNFEATURES(continued)

-4.3FuelStorage(continued)

.4.3.2~DnainaeThespentfuelpoolisdesignedandshallbemaintained topreventinadvertent drainingofthepoolbelowelevation 257'0"(meansealevel)..4.3.3~Caacit"Thespentfuelpoolisdesignedandshallbemaintained with-astoragecapacitylimitedto.nomorethanQggfuelassemblies.

la~a~4R.E.GinnaNuclearPowerPlant4.0-3Amendment No.61 PBoron'oncentration B3.7;12'ASES(continued)

APPLICABLE SAFETYANALYSESThepostulated accidents intheSFPcanbedividedintotwobasiccategories (Ref.3and4).Thefirstcategoryareeventswhichcause.alossofcoolinginthe.SFP.ChangesintheSFPtemperature couldresultinanincreaseinpositivereactivity.

However,thepositivereactivity isultimately limitedbyvoiding(whichwouldresultin'theadditionofnegativereactivity) andtheSFPgeometrywhichisdesignedassuminguseofunborated watereventhoughsolubleboronisavailable (seeSpecification 4.3.1.1).Thesecondcategoryisrelatedtothemovementoffuelassemblies in.theSFP(i:e,afuelhandlingaccident) andisthemostlimitingaccidentscenariowithrespecttoreactivity.

Thetypesofaccidents withinthiscategoryincludeanincorrectly transferred fuelassembly(e.g.,transferfromRegion1toRegion2of.anunirradiated oraninsufficiently depletedfuelassembly) andadroppedfuelassembly.

However,forbothoftheseaccidents, thenegativereactivity effectofthesolubleboroncompensates fortheincreased reactivity.

Bycloselycontrolling themovementofeachassemblyandbycheckingthelocationofeachassemblyaftermovement, thetimeperiodforpotential accidents whichcredituseofthesolubleboronmaybelimitedtoasmallfractionofthetotaloperating time.Theconcentration ofdissolved boronintheSFPsatisfies Criterion 2oftheNRCPolicyStatement.

LCO+5~TheSFPboronconcentration isrequiredtobea00ppm.-Thespecified concentration ofdissolved boronintheSFPpreserves theassumptions usedintheanalysesofthepotential criticalaccidentscenarios asdescribed inReferences 3and4(i.e.,afuelhandlingaccident).

Thisconcentration.

ofdissolved boronistheminimumrequiredconcentration forfuelassemblystorageandmovementwithintheSFPuntilthefuelassemblies havebeenverifiedtobestoredcorrectly.

R.E.GinnaNuclearPowerPlantB3.7-'87(continued)

Revision0 FPBoronConcentration B3.7.12BASES(continued)

SURVEILLANCE REQUIREMENTS SR3.7.12.1This.SRverifiesthattheconcentration ofboronintheSFPiswithinthelimit.-'AslongasthisSRismet,theanalyzedaccidents arefullyaddressed.

The31day.Frequency isappropriate becausethevolumeandboronconcentration inthepoolisnormallystableandallwaterlevelchangesandboronconcentration changesarecontrolled

,byplantprocedures.

ThisSRisrequiredtobeperformed priortofuelassemblymovementintoRegion1orRegion2andmustcontinue-to;be performed

.untilthenecessary SFPverification isaccomplished (i.-e.,SR3.7.13.1and3;7.13:2).

'EFERENCES I.ANSIN16.1-1975, "American NationalStandardforNuclearCriticality SafetyinOperations withFissionable Materials OutsideReactors."

"2.LetterfromB.K.Grimes,NRC,toAll'PowerReactorLicensees,

Subject:

"OTPositionforReview.andAcceptance ofSpentFuelStorageandHandlingApplications,"

datedApril14,1978..3.Westinghouse, "Criticality AnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidated RodStorageCanisters,"

datedJune1994.4.UFSAR,Section15.7.3.3.Framatome Technologies, Inc.,""R:E.

GinnaNuclearPowerPlant,~SpentFuelPoolRe-racking Licensing Report,"Section4,February1997.R.E.GinnaNuclearPowerPlantB3.7-89Revision0 SFPStorageB3.7.13B3.7PLANTSYSTEMSB3.7.13SpentFuelPool(SFP)Storage&h'LR8.CLh~hss4cS MmQwsrtAQtM,L~wM~o,'g-t~h,z,~~~

<"a<+~BASESBACKGROUND

~hdup4ches~~.'K-a~Wet~%t'Nhast-10'1'7'Thespentfuelpool(SFP)isdividedintotwoseparateanddistinctregions(seeFigureB3.7.13-1) which,forthepurposeofcriticality considerations, areconsidered asseparatepools(Ref.I).Region1,withgsWagstora epositions, isd'oaccommodate neworspenfuelutilizing acheckerboard arranementfuel.assemianenric~-.w.canbestoredatanyavailable locationinRegion1sincetheaccidentanalyseswereperformed assumingthatRegion1wasfilled,withfuelassemblies ofthisenrichment.

Afuelassemblywithanenrichment

>4.05wt%U-235canalsobestored-in Region1providedthatintegralburnablepoisonsareresentintheassemblies suchthatk-infinity is.s1.458.heexisingesignusesntegraueBurnaesorbersIFBAsthepoisonforfuelassemblies withenrichments

>4.05wt%.IFBAsconsistofneutronabsorbing materialwhichprovidesequivalencing reactivity holddown(i:e.,neutronpoison)thatallowsstorageofhigherenrichment fuel.Theneutronabsorbing materialisanon-removable orintegralpartof'hefuelassemblyonceitisapplied.Theinfinitemultiplication factor,K-infinity, isareference criticality pointofeachfuelassemblythatifmaintained s1.458,willresultinak,<<z0.95forRegion1.'TheK-infinity limitisderivedforconstantconditions ofnormalreactorcoreconfiguration (i.e.,typicalgeometryoffuelassemblies inverticalpositionarrangedinaninfinitearray)atcoldconditions (i.e.,68'Fand14.7-psia).egion2,wi840soragepositions, isdesignedtoaccommodate fueofvariousinitialenrichments whichhaveaccumulated minimumburnupsihintheacceptable domainaccording toFigure3.7.1,intheaccompanying LCO..The~$~sorageouehicharewithintheacceptaberaneofFigure3.7.13inRegion2ensuresaK,<<s0.95inthisregion.F~aQa.S~%4m~i~nntesaaWW~

~~~('4~40~~R~~~3.7.t3-L(~a-~)hO~Owes.mt~&~~~Fm@th.C~MGW3,~tRt<~4s~~Q,~~s~'~NmQ.-'w~~o~.(continued)

R.E.GinnaNuclearPowerPlantB3.7-90Revision0

'Fuelassemblies withinitialenrichments andburnupswithindomainA1.ofFigure3.7.13-2maybestoredinanylocationinRegion.2.

Fuelassemblies withinitialenrichments andburnupswithindomainA2ofFigure3.7.13-2shallbestoredface-adjacent toa'TypeA1orA2assembly, orawatercell(emptycell).Fuelassemblies withinitialenrichments andburnupswithindomainBofFigure'.7.13-2shallbestoredface-adjacent toa'TypeA1assemblyorawatercell(emptycell).Fuelassemblies withinitialenrichments andburnupswithindomainCofFigure3.7.13-2shallbestoredface-adjacent toawatercell(emptycell)only.'Theword"face-adjacent" onFigure3.7.13-2isdefinedtomeanthattheflatsurfaceofafuelassemblyinonecellfacestheBatsurfaceoftheassemblyinthenextcell.///40!:caeno.vp;

/IS/Ã SFPStorageB3.7:13BASESBACKGROUND (continued)

OConsolidated rodtorgenisterscanalsobestoredineither-region itroviburnuofFigure3:7.13-1et.Inaddition, allcanisters pacenoserviceaer1994musthave-z144rodsora256ro(Ref.'.2).ecanisers.aresanessseeconainerscontainthefuelrodsofamaximum-of twofuelassemblies (i;e.,358rods).Allbowed,broken,orotherwise.

failedfuelrods.arefirststoredin;a.stainless steeltubeof0.75inchouterdiameterbeforebeingplacedin:acanister.

Eachcanisterwillaccommodate 110failedfuelrod~tubes.

Thewaterinthe'SFPnormallycontainssolubleboron,which"resultsinlargesubcriticality marginsunderactualoperating conditions.

However,theNRCguidelines, basedupontheaccident.condition inwhichall.solublepoisonisassumedtohavebeenlost,specifythat.alimitingk,<<of0;95bemaintained intheabs'enceofsolubleboron.Hence,thedesignofbothregionsisbasedontheuseofunborated water.suchthatconfiguration control(i..e.,controlling themovement.ofthefuel'ssembly andcheckingthelocation.

of.eachassemblyaftermovement) maintains eachregionin.asubcritical condition duringnormaloperation withtheregionsfullyloaded.Thedoublecontingency principle discussed inANSIN16.1-1975 (Ref.,3)andReference 4allowscreditforsolubleboronunderabnormaloraccidentconditions, sinceonlyasingleaccidentneedbeconsidered atonetime.Forexample,themostsevereaccidentscenarios areassociated withthemovementof'fuelfromRegion1toRegion2,andaccidental misloading ofafuelassemblyinRegion2.Eitherscenariocouldpotentially increasethereactivity ofRegion'2.

To-mitigate thesepostulated criticality relatedaccidents, boronisdissolved inthepoolwater.Safeoperation ofthestorage.rackswithnomovementof-assemblies maytherefore beachievedbycontrolling thelocationofeachassemblyin-accordance withthisLCO.Within7daysprior-tomovementofanassemblyintoaSFPregion,itisnecessary toperformSR3.7.12.1.

PriortomovinganassemblyintoaSFPregion,itisalsonecessary toperformSR3.7.13.1or3.7.13.2asapplicable.

R.E.GinnaNuclearPowerPlantB:3.7-91(continued)

ReVision0 SFPStor'ageB3.7.13BASES(continued)

APPLICABLE SAFETYANALYSESThepostulated accidents intheSFPcanbedividedintotwobasiccategories (Refs.2and5).Thefirstcategoryareevents-which causealossofcoolingintheSFP.ChangesintheSFPtemperature couldresultinanincreaseinpositivereactivity.

However,-the positivereactivity isultimately limited-by voiding(whichwouldresultintheadditionofnegativereactivity) andtheSFPgeometrywhichisdesignedassuminguseofunborated watereventhoughsoluble..boron isavailable (seeSpecification 4.'3.1.1).Thesecondcategoryi'srelated.tothemovementoffuelassemblies intheSFP(i;e,afuelhandlingaccident) andisthemostlimiting.accident scenariowithrespecttoreactivity.

Thetypes.ofaccidents-within thiscategoryincludeanincorrectly transferred fuelassembly(e.g.,transferfromRegion1toRegion2ofanunirradiated oraninsufficiently depletedfuelassembly) andadroppedfuelassembly.

However,forbothoftheseaccidents,"the negative-reactivity effectofthesolubleboroncompensates fortheincreased reactivity.

Bycloselycontrolling themovementofeachassemblyandbychecking'thelocationofeachassemblyaftermovement, thetimeperiodforpotential accidents whichcredituseofthesolubleboronmaybelimitedtoasmallfractionofthetotaloperating time.Theconfiguration, offuelassemblies inthespentfuelpoolsatisfies Criterion 2oftheNRCPolicyStatement.

LCOTherestrictions ontheplacement offuelassemblie's withintheSFPensurethek,<<oftheSFPwillalwaysremain<0.95,assumingthepooltobefloodedwithunborated.water (Specification 4.3.1.1).Forfuelassemblies storedinReion1,eachassemblmusthaveaK-infinity, ofs1.458.orfuelassemblies storedinRegion2,inssaenricmenandburnushallbewithintheaccetabeh~3.7.-.hex-axlesoisthenominalenrichment wt%whicdoesnotincludethe+0.05wt%tolerance thatisallowedforfuelmanufacturing andlistedinSpecification 4.3.1.1.ca~~-Mraugasst~'aha.~&4Aa~O>QW~~>>a<3-L.R.E.GinnaNuclearPowerPlantB3.7-92Revision0 SFPStorageB3.7.13.BASES(continued)

APPLICABILITY ThisLCOapplieswheneveranyfuelassemblyisstoredintheSFP.ACTIONSA.lWhentheconfiguration offuelassemblies storedin.eitherRegion1orRegion2oftheSFPisnotwithintheLCOlimits,theimmediate actionistoinitiateactiontomakethenecessary fuelassemblymovement(s) tobringt~r~PHcconfiguration intocompliance withSpecifn-4.3.1.1.Thiscompliance canbemadebyrelinthefuelassembltoadifferent regio~+RequiredActionA.lismodifiedbyaNoteindicating thatLCO3.0.3'doesnotapplysinceiftheLCOisnotmetwhilemovingirradiated fuelassemblies inMODE5or-6,LCO3.0.3wouldnotbeapplicable.

Ifmovingirradiated fuelassemblies whileinMODE1,2,3,or-4,theactionisindependent of'reactor operation.

Therefore, inability tomovefuelassemblies isnotsufficient reasontorequire.a reactorshutdown.

'SURVEILLANCE REQUIREMENTS SR3.7~13.1ThisSRverifiesbyadministrative meansthattheK-infinity ofeachfuelassemblyis~1.458priortostorageinRegionl.Iftheinitialenrichment ofafuelassemblyis~4.05wtl,aK-infinity ofs1.458isalwaysmaintained.

Forfuelas'semblies.with enrichment

>4.05wt%,aminimumnumberofIFBAsmustbepresentineachfuelassemblysuchthatk-infinity z1.458priortostorageinRegion1.Thisverification isonlyrequiredonceforeachfuelassemblysincetheburnablepoisons,ifrequired, areanintegralpartofthefuelassemblyandwillnotberemoved.Theinitialenrichment ofeachassemblywillalsonotchange(i.e.,increase) whilepartially burnedassemblies arelessreactivethanwhentheywerenew(i.e.,fresh).Performance ofthisSRensurescompliance withSpecification 4.3.1.1.(continued)

R.E.GinnaNuclearPowerPlantB3.7-93Revision0 SFPStorage83.7.13BASESSURVEILLANCE RE(UIREHENTS SR3.7.13.1(continued)

ThoughnotrequiredforthisLCO,this.SRmualsobeperformed aftercompletion offuelmovement-HAeRegion:exittheApplicability ofI.CO3.7.12,"SFPBoron~~'ta~Concentration."

ThisSRismodifiedbyaNotewhichstatesthat,thisverification isnotrequiredwhentransferring afuelassemblyfromRegion2toRegion1.Theverification isnotrequiredsinceRegion2.isthelimitingSFPregion,andassuch,thefuelhasalreadybeenverifiedtobeacceptable forstorageinRegion.l..SR3.7.13.2ThisSRverifiesbyadministrative meansthattheinitialenrichment andburnupofthefuelassemblyisinaccordance withFiure3.7.13-intheaccompanying LCOprior.tosorageinRegion,.Onceafuelassemblyhasbeenver~fiedtobewithintheacceptable rangeofFigure3.7.13~furtherverifications arenolongerrequiredsincethe'initialenrichment orburnupwillnot,adversely change.Forfuelassemblies intheunacceptable r'angeofFigure3.7.13-1, performance ofthisSRwillensurecompliance with.Specification 4.3.1.1.ThoughnotrequiredforthisLCO,thisSRmuisobeperformed aftercompletion offuelmovement'egion2toexittheApplicability ofLCO3.7.12.REFERENCES

,1.UFSAR,Section9.1.2.2.Westinghouse, "Criticality AnalysisoftheR.E.Ginna.NuclearPowerPlantFreshandSpentFuelRacks,andConsolidated RodStorageCanisters,"

datedJune1994.3.ANSIN16.1-1975, "American NationalStandardforNuclearCriticality SafetyinOperations withFispionable Haterials OutsideReactors."

2.Framatome Technologies, Inc.,"R.E.GinnaNudearPowerPlant,SpentFuelPoolRe-racking.

Licensing Report,"Section4,February1997.(continued)

R.E.GinnaNuclearPowerPlant83.7-94Revision0

,SFPStorageB3.7.13SpentFuelStorageRacks3'wA1ERBOXEs QrroaNmczus RCKORAQSCAPhCtTYSN

~TOTALCAPACflYCN6FUELARKMBUES R.E.GinnaNuclearPowerPlantFigureB3.7.13-1SpentFuelPoolB3.7-96Revision0 SFPStorageB3.7.13Norfh-.FuelElevatorAreaReciion.2 1,075'Spent FuelCellsReceion-1 294'Spent'Fuel CellsCasAreafigureB3;7.13-1SpentFuelPoolR.E.GinnaNuclearPowerPlantB3.7-96aRevisionXX IncludedPages:Attachment IIIProposedTechnical Specifications 3.7-.273.7-'293.7-303.7-313.7-31a4.0-24.0-3 PBoronConcentration 3.7.123."7PLANTSYSTEMS3.7.12SpentFuelPool(SFP)BoronConcentration LCO.3:7.12TheSFPboronconcentration shallbea450ppm.APPLICABILITY:

Whenfuelassemblies arestoredinthe.SFPandaSFPverification hasnotbeenperformed sincethelastmovementoffuelassemblies intheSFP.-ACTIONSCONDITION REQUIREDACTIONCOMPLETION TIME~A..SFPboronconcentration not-withinlimit.------------NOTE-------------

LCO3.0.3isnotapplicable.

"A.'.1Suspendmovementoffuelassemblies intheSFP.ANDImmediately.A.2..1InitiateactiontorestoreSFPboronconcentration towithinlimit.Immediately

'ORA.2".2Initiateaction,to performSFPverification.

Immediately R.E.GinnaNuclearPowerPlant3.7-27Amendment No.Q (ga,.SFPStorage3.7.133'".7PLANTSYSTEMS3.7.13SpentFuelPool(SFP)StorageLCO.3.7.13Fuelassemblystorageinthespentfuelpoolshallbemaintained asfollows:-a.Fuelassemblies inRegion1shallhave.aK-infinity of~s1.458-and shallhaveinitialenrichment'and burnupwithintheacceptable area.ofFigure3.7.13-1; and-.b.Fuelassemblies inRegion2shallhaveinitialenrichment andburnupwithintheacceptable areaoftheFigure3";7.13=2.

APPLICABILITY:

Wheneveranyfuelassemblyisstoredinthespentfuelpool.ACTIONSCONDITION REQUIREDACTIONCOMPLETION TIME4A.Requirements oftheLCOnotmet-foreitherregion.-A:1--------NOTE---------

LCO3.0.3isnotapplicable.

Initiateactionto.movethenoncomplying fuelassembly.to an.acceptable storagelocation.

ImmediatelyR.E.GinnaNuclearPowerPlant3.7-29Amendment No.Q V

(4SFPStorage3.7.13SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR3.7.13.1Verifybyadministrative meanstheK-infinity

-ofthefuelassemblyis~1.458andthattheinitialenrichment andburnupisinaccordance withFigure3.7.13-1.

PriortostoringthefuelassemblyinRegion.1SR'3.7.13:2 Verifybyadministrative meanstheinitialenrichment andburnupofthefuelassemblyisinaccordance withFigure'3;7.13=2.

PriortostoringthefuelassemblyinRegion.2R.E.GinnaNuclearPowerPlant3.7-30Amendment No.Q SFPStorage3.7.1330000tI~II,~I~I~~Ig20000'AII~I~'.:IiI~~I;I'II150004elIhg910000ASM~;;'~..'IIiIIIIjiiI:IIlljI~iiI'II~~I~~~~~00$1182,253.3S44S5AssemblyInitialEnrichment, Wt%A-Acceptable burnupdomainforstorageinanylocationwithinRegion1.B-Acceptable burnupdomainforstorageincellswithlead-infunnelsonly.Figure3.7.13-1FuelAssemblyBurnupLimitsinRegion1R.E.GinnaNuclearPowerPlant3.7-31Amendment No.Q SFPStorage3.7..13;jA-g450000CO+le+420000~I!iiII(III~!!III!!~~III'!l:'II!I!llIl'i,'I!1'.,

;,II!!I~I:'IIi0!.I81iS2~.55$~h45~5AssemblyInitialEnrichment, YVt%Al-Acceptable burnupdomainforstoragein,anylocation-within Region2.-A2-Acceptable burnupdomainforstorageface-adjacent toaTypeAlorA2assembly,-

or-awatercell.B-Assemblyburnupdomainforstorageface-adjacent toaTypeAlassemblyorawatercell.C-Acceptable burnupdomainforstorageface-adjacent toawatercellonly.Figure3.7.13-2FuelAssemblyBurnupLimitsinRegion2R.E.GinnaNuclearPowerPlant3.7-3laAmendment No.Q o.DesignFeatures4.04.0DESIGNFEATURES'-4:2ReactorCore(continued) 4.2.2ControlRodAssemblies Thereactorcoreshallcontain.29controlrodassemblies.

Thecontrolmaterialshallbesilverindiumcadmium.~4".3FuelStorage-4:3.1~CHti4;3.1.1Thespentfuelstorageracksaredesigned.

andshallbemaintained

-with:a.Fuelassemblies havingamaximumU-235enrichment of5.05-weightpercent;.b..k,<<s0;95iffullyfloodedwithunborated water,-whichincludes.

anallowance foruncertainties asdescribed in.Section9.1oftheUFSAR;-"c~Consolidated rodstoragecanisters may.bestoredinthespentfuelstorageracksprovidedthatthefuelassemblies fromwhichtherodswereremovedmeet.alltherequirements ofLCO3;7.13fortheregioninwhichthecanisteristobestored.Theaveragedecayheat,ofthefuelassemblyfromwhichtherodswereremovedforallconsolidated fuelassemblies mustalsobe-~2150BTU/hr.-4.3.1.2Thenewfuelstoragedryracksare:designed andshall;be-maintained with:'a."Fuel,assemblies havingamaximumU-235enrichment of5.05weightpercent;-b.k.<<w0;95iffullyflooded-with unborated water,*whichincludesanallowance foruncertainties as.described inSection9.1oftheUFSAR;andc.k,c0.98ifmoderated byaqueousfoam,=whichincludes-an allowance foruncertainties asdescribed inSection9.1oftheUFSAR.(continued)

R.E.GinnaNuclearPowerPlant4.0-2Amendment No.Pf DesignFeatures4.03'>-4.0DESIGNFEATURES(continued)

-4.'3FuelStorage(continued)

.4;3.2~DraieaeThespentfuelpoolisdesignedandshallbemaintained topreventinadvertent drainingofthepoolbelowelevation 257'0"(meansealevel).-4.3."3~CaacctThespentfuelpoolisdesignedand.shallbe-maintained with.astoragecapacitylimitedto.no-more than1879fuelassemblies and1369storage'locations.

R.E.GinnaNuclearPowerPlant4.0-3Amendment No.g Attachment IVR.E.GinnaNuclearPowerPlantSpentFuelPoolRe-racking Licensing ReportFebruary1997 0

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