ML17334A816
| ML17334A816 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/23/1984 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17334A815 | List: |
| References | |
| NUDOCS 8409050174 | |
| Download: ML17334A816 (18) | |
Text
Mr.HaroldR.DentonAEP:NRC:0745M Attachment AProposedRevisedTechnical Specifications PagesforD.C.CookUnitC090100g7gy08R>
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POWEROISTRIBUTION LIMITSLIMITINGCONOITION FOROPERATION (Cont1nued) 2.ReduceTHERMALPOWERasnecessary tomeetthelimitsofSpecfffcatfon 3.2.6usfngtheAPOMSwiththelatestfncoremapandupdatedR.b.Identffyandcorrectthecauseoftheout,oflimitcond1t,fon pr1ortafncreasfng THERMALPOWER;THERMALPOWERmaythenbefncreased providedF~fsdemonstrated thorough1ncoremappingtobew1thfnftslfmft.SURVEILLANCE REUIREHENM4.2.2.1Theprovfsfons ofSpecification 4.0.4arenotapplicable.
4.2.2.2F~(Z,i)shallbedetermined tobewithinftslimitby:a.Usfngthemovablefncoredetectors toobtainapowerd1stributfon mapatanyTHERMALPOWERgreaterthanSXofRATEDTHERMALPOWER.b.Increasing themeasuredF~(Z,t)component ofthepo~erdistribution mapby3Xtoaccountformanufacturing talerancesandfurtherincreasing thevaluebySXtoaccountformeasurement uncertafntfes.
ThisproductfsdefinedasF~(Z).c.Satisfying thefollowfng relationships atthetimeofthetargetfl.uxdetermination.
WestfnhouseFuelExxonNuclearCa.FuelFq(Z)~2.10PxE(Z~KZV(Z)F<(Z)<LF,(Z)~xvZ)P>0.5V(X)Fq(Z)4.20E(Z)K(Z)vvv'<O.SD.C.CookUnit13/42-6Attendant "o
POWEROISfRIBUTIOH LIMITSSURVEILLANCE REgUIREMEHTS (Continued) whereF~(z)=F~(z,a)attforwhichF(Z,x)3samaximumT(E)F<(Z)=F<(E,)attforwhich~F(z,a)T(E)isamaximumF~(Z)andF~(Z)arefunctions ofcoreheiaht,Z,andF(Z,a)correspond ateachZtotherod4forwhichT(Eisamaximu'matthatZV(Z)isacycledependent, functionand.isprovidedinthePeakingFactorLimitReport.QZ)isdefinedinFigure3.2-2forExxonNuclearCompanyfuel'andinFigure3.2-3forWestinghouse fuel.T(E<)isdefinedin~Figures3.2-4and3.2-5.E(Z)isanuncertainty factortoaccountpforthereduction intheF~(E)curveduetoaccumulation ofLexposurepriortothenextfluxmap.I,/l<estinqhouse FuelExxonNuclearCo.FuelE,(z)=l.oE(Z)=1.0E,(z)=l.oD.C.CookUnit1E,(z)=l.oE(Z)=1.0+I.0040xPE(Z)=1.0+[.0093xE(Z)=1.0+L.0060x3/42-70.0F(Z)]17.62FO(Z)]34.5F<(Z)]42.2Amendment No.EE<17.62<ER<'34.5<ER<422<ER<48.0
'~H~~~IIi~~~~~~~~~~~,~~~I~~~~I~I~IV~~~~I~Ilt~~I~I~~~~~~~~.~~~~~~~~II~~~'I 121.0(0.0,1.0)
(6.0,1.0)
[~~~~I1~LLiI(11.183,0.935) 0.812.0,0.714) 0.60'.4I~~~~~~~~i'~~I&02I~I~~[~~L0.004l~'46CoreHeight(FT)10I~12FIGURE3.2-3K(Z)-Normalized F(Z)AsAFunction'fCoreHeightForWestinghouse Fuel0.C.Cook-Unit13/42-11Amendment No.
~~~~~~~~'~~~~~~'~~'Dl~~Q~~~~~~~~~~~~~~~~~~~~~~~
~~I':~~~IIliiiI~'~~~~~~~~~~~~0l~,~~~~'~~~~~I~.~~~I~.~~~~~~~~~~~~~~~\~~~~~~I~I'~~ll~I~~~~~~~~~~'~~~~I 2.22'0204)(17.62,2.04) 2.0{34.5,1.95) 1.9u1.81.71.6L=-FqLFq--FLgL.=-gFq(Ea)=2.0400<Ea<1762(Ea)=2.134-.005333 ER17.62<Ea<34.5(ER)=2.353-.01169 ER34.5<ER<42.2{Ea)=2.151-.006897 ER42.2<Ea<48.0(42.2,1.86)
=.'."(48.0,1.82)
~~~151.094J.8~~~Ic~~-p~'I~~~4I~~~~~~.17.62,1.0)34.5,.956)t-(42.2~912)(480,.892).7.6.0=1.046-.002614 ER=1.154-.00573 ER=1.054-.003381 Ea0.0<Ea<17.17.62<ER<34.345<ER<42.42.2<ER<48.62=--52':0I*4~~'-k>>~~II1020304050PeakPelletExposureinHklD/KGFjGURE3.2-4ExposureDependent F~Limit,F0{Ea),andNormalized LimitT(Ea)asafunctionofPeakPelletBurnupforExxonNuclearCompanyFuelD.C.Cook-Unit13/42-23Amendment No.
2.22.12.0(0.0,2.10)
(42.2,2.10) 1.91.8t'1.71.6~~1.0~--~+-~I~~tL-:(O.o,l.no)
P~~(42.2,1.00)
=0.80.7~~I01020304050PEAKPELLETEXPOSUREINMLlD/KGFIGURE3.2-5.Exoosure Deoendent FOLimit;F~(ER),'"and Normalized.
LimitT(ER)asaFunctionofPeakPelletBurnuoforl<estinghouse FuelD.C.Cook-Unit13/42-24Amendment No.
Mr.HaroldR.BentonAEP:NRC0745MAttachment BEnvironmental and10CFR50.92justifications forthoseTechnical Specifications changes(enclosed inAttachment A)associated withtheextension ofthepeakpelletburnupallowedinfuelsuppliedbyExxonNuclearCompany.
Mr.HaroldR.DentonB-1AEP:NRC:0745MTheJustification foranincreaseintheallowedpeakpelletburnupinfuelsuppliedbyExxonNuclearCompany(ENC)from42,200MWD/MTU(42.2MWD/KG)to48,000MWD/MTU(48.0MWD/KG)isbasedonanalysesperformed onthemechanical design,LOCA-ECCS
- analysis, andreviewofsignificant hazardsandenvironmental considerations.
Mechanical designanalysesforextendedburnupto48,000MWD/MTU(48.0MWD/KG)wereperformed.
Theresultsoftheseanalysesarepresented inXN-NF-84-25(P),
April,1984.XN-NF-84-25(P),
April,1984,statesthatallcurrentENCdesigncriteriaaresatisfied.
Thesecriteriaarerepeatedbelow:oThemaximumend-of-life (EOL)steady-state claddingstrainwasdetermined tobenegative, thu'smeetingthe1.0$designlimit.Thecladdingstressandstrainduringpowerramps,calculated underdifferent overpower conditions, donotexceedthedesignstresscorrosion crackingthreshold orthe1.0$strainlimit.Thecladdingfatigueusagefactorof0.20iswithinthe0.67designlimit.Theend-of-life fuelrodinternalpressureislessthanthesystempressure.
Thecladdingdiameterreduction duetouniformcreepdown pluscreepovalityafterfueldensification islessthantheminimuminitialpellet/clad gap.Thiscriterion preventstheformation offuelcolumngapa.Themaximumcalculated EOLthickness oftheoxidecorrosion layerislessthan0.0007inch,andthemaximumcalculated concentration ofhydrogeninthecladdingis80ppm.Thesevaluesarewithinthedesignlimitsof0.002inchand300ppm,'espectively.
.Anevaluation ofthefuelassembly, growthand'thefuelrodgrowthindicates thatthefuelassemblydesignprovidesadequateclearances atthedesignburnup.
Mr.HaroldR.DentonB-2AEP:NRC:0745MDataontheperformance ofsimilarENCfuelathighburnupscanbefoundinXN-NF-82-06, "Qualification.
ofExxonNuclearFuelforExtendedBurnup",June,1982.Leadassemblies atH.B.Robinsonhavebeenburnedtoassemblyaverage'xposures of-approximately 48,000MWD/MTU(48.0MWD/KG).ALOCA/ECCS analysiswasperformedtoextendthepeakpelletexposurefrom42,200MWD/MTU(42.2MWD/KG)to48,000MWD/MTU(48.0MWD/KG).Theresultsoftheseanalysesarepresented inXN-NF-83-61, August,1983,whichextendstheanalysespresented inXN-NF-81-07,
- February, 1981.Theend-of-life calculated peakcladdingtemperature (PCT)is1736F,occurring 262secondsintotheaccidentatalocation$.25feetfromthebottomoftheactivecore.Assuminga42FincreaseinPCTfromanearliersensitivity studyforaconservative estimateofmaximumLPSIflow,thePCTwillbe1778F.TheanalysisofthelimitingbreakfortheD.C.CookUnit1reactorwiththeENCWREM-IIAandselectedEXEM/PWRECCSevaluation modelsshowsthatthereactorcanoperateatallowedtotalpeakingFof1.82andFHof1.55atapeakpelletburnupof48,000MWD/kTU(48.0MWD/KG)andcontinuetomeetthe10CFR50.46criteriawithanalysesperformed inconformance to10CFR50AppendixKrequirements.
InaDecember, 1982memofromL.G.Hulman,ChiefNRC-Accident Evaluation Branch,toCarlBerlinger, Chief,NRC-CorePerformance Branch,L.G.Hulmansuggested thattheAccidentEvaluation Branchneednotbeinvolvedinreloadanalysisaslongasbatchaverageburnuplevelsdonotexceed38,000MWD/MTU(38.0MWD/KG)atdischarge.
ThefuelsuppliedbyExxonNuclearCompanywhichiscurrently inDonaldC.CookNuclearPlantUnit1Cycle8isinRegion8andRegion9.ThefuelinRegion8whichwillbedischarged attheendofCycle8hasadesignbatchaverageburnupof32,600MWD/MTU(32.6MWD/KG).Theremaining Region8fuelwillbecompletely discharged attheendofCycle9withadesignaverageburnupof33,007MWD/MTU(33.007MWD/KG)forthatbatch.ThefuelinRegion9willbecompletely discharged atthe.endofCycle9withadesignbatchaverageburnupof34,061MWD/MTU(34.061MWD/KG).ReactorcoolantsystemactivitydataforUnit1Cycle8indicates thatsomefuelassemblies areleaking,whichwillresultinsomedesignchangesforUnit1'Cycle9,withminoreffectsonthedesignbatchaverageburnupsat'ischaige.-
Therefore',
thefuelsuppliedbyExxon'uclear Companywillnotexceed38,000MWD/MTU(38.0MWD/KG)batchaverageburnupsatdischarge, eventhoughthepeakpelletburnupmaybeupto48,000MWD/MTU(48.0MWD/KG).
Mr.HaroldR.DentonB-3AEP:NRC:0745M Onthebasisoftheaboveevaluations, webelievethattheTechnical Specifications changesassociated withextending thepeakpelletburnupfrom42,200MWD/MTU(42.2WD/KG)to48,000MMD/MTU(48.0MWD/KG)donotconstitute asignificant hazardsconsideration under10CFR50.92.Mehavefurtherconcluded thattheextendedburnupwillnotadversely.
affecttheenvironment since'twillnotresultinradiological consequences greaterthanthosepreviously analyzed.
Mr.HaroldR.DentonAEP:NRC:0745MAttachment CReasonsfortheincreaseinFforfuelsuppliedbyWestinghouse.
Mr.HaroldR.DentonC-1AEP:NRC:0745M TheJustification foranincreaseintheF<allowedinfuelsuppliedbyWestinghouse to2.10isbasedonalargebreakanalysiswhichwasperformed withtheDecember1981versionoftheEvaluation Modelmodifiedtoincorporate theBARTcomputercode.TheanalysisspecifictoDonaldC.CookNuclearPlant,Unit1isincludedasAttachment Dtothisletter.Themostlimitingsinglefailurewhenoffsitepowerisunavailable forD.C.CookUnit1isanalyzedwithmaximumsafeguards becausethecurrentAppendixKmodelsgivemorelimitingresultsassumingthemaximumpossibleECCSflowdelivery.
Inthatcase,maximumsafeguards whichassumeminimuminfection line.resistances, enhancedECCSpumpperformance, andnosinglefailure,resultinthehighestamountofflowdelivered totheRCS.Westinghouse ECCSanalysescurrently performed forsomeotherWestinghouse plantsassuneminimumsafeguards becausethatassumption ismorelimitingforthoseplantsthanthemaximumsafeguards assumption.
BasedonpreviousLOCAsensitivity studies,thelimitinglargebreakwasfoundtobethedoubleendedcoldlegguillotine (DECLG).Therefore, onlytheDECLGbreakisconsidered inthelargebreakECCSperformance analysis.
Calculations wereperformed forarangeofMoodybreakdischarge coefficients.
CurrentLOCAanalysisfortheD.C.CookUnit1hasdenanstrated thatmaximumsafeguards assumptions resultinthehighestpeakcladtemperature.
Therefore, theworstbreakforD.C.Cook(CD-0.6)wasre-analyzed, assumingmaximumsafeguards.
Theresultsoftheanalysespresented inAttachment Dshowthat1)themaximumcladtemperature calculated foralargebreakis2163F,2)themaximumlocalmetal-water reactionis9.65percent,and3)thetotalcoremetal-water reactionislessthan0.3percent.Thecladtemperature transientisterminated atatimewhenthecoregeometryisstillamenabletocooling.Asaresult,thecoretemperature willcontinuetodropandtheabilitytoremovedecayheatgenerated inthefuelforanextendedperiodoftimewillbeprovided.
Thesecalculations wereperformed at102$oftheDesignThermalPowerof3411MWTandapeakingfactorof2.10.~~
Mr.HaroldR.DentonC-2AEP:NRC:0745MOnthebasisoftheaboveevaluations, wheretheonlydifferences frompreviously analyzedresultsarethechangeinthepowerlevelfrom3250MWtto3411Wtandanincreased peakingfactorFfrom1.97to2.10,whichisbaseduponachangeinthemethodsusedtoperformtheanalysis; andsincetheresultsofsuchanalysisarewithintheguidelines specified in10CFR50.46,weconcludethatthechangewillnotinvolveasignificant hazardsconsiderations asdefinedby10CFR50.92.Alsosincetheaccidents analyzedwillnotresultinanincreaseintheradiological sourceterm,webelievethischangewillnothaveanadverseeffecttotheenvironment.