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==SUBJECT:==
==SUBJECT:==
ForwardsTS,supportingoperationofplantatincreasedcoreratedthermalpowerof3588MWt.DISTRIBUTIONCODE:00010COPIESRECEIVED:LTR(ENCL(SIZE:2ITITLE:ORSubmittal:GeneralDistr'.'butionNOTES:RECIPIENTCOPIESCOPIESIDCODE/NAMELTTRENCLLTTRENCLPD3-1LA1111HICKMAN,J11RECIPIENTIDCODE/NAMEPD3-1PDCATEGORYj.REGULATOINFORMATIONDISTRIBUTIONYSTEM(RIDS)ACCESSION'NBR:9607150008'OC.DATE:96/07/11NOTARIZED:YESDOCKETFACIL:50-315Donald'C.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPower-Co.(formerlyIndianaaMichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)0INTERNAL:FILECDRCH/HICBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOAC1111111011NRCPDR11NRR/DE/EMCB11NRR/DSSA/SPLB11NUDOCS-ABSTRACT11D0UNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!tTOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11 I
ForwardsTS,supporting operation ofplantatincreased coreratedthermalpowerof3588MWt.DISTRIBUTION CODE:00010COPIESRECEIVED:LTR (ENCL(SIZE:2ITITLE:ORSubmittal:
AmericanElectric~r1RiversidePlaza~Columbus,OH4321523736142231000July11,1996DocketNos.50-31550-316AEP:NRC:1223U.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Gentlemen:DONALDC.COOKNUCLEARPLANTUNITS1AND2LICENSENOS.DPR-58ANDDPR-74PROPOSEDLICENSEANDTECHNICALSPECIFICATIONCHANGESSUPPORTEDBYANALYSESTOINCREASEUNIT2RATEDTHERMALPOWERANDCERTAINPROPOSEDCHANGESFORUNIT1SUPPORTEDBYRELATEDANALYSESThisletteranditsattachmentsconstituteanapplicationforamendmentoftheDonaldC.CookNuclearPlantunit2facilityoperatinglicense,foramendmentoftheDonaldC.CookNuclearPlantunit2technicalspecificat:ions(T/S),andforsomerelatedchangestotheunit1technicalspecifications.ChangesareproposedprimarilytosupportoperationofCookNuclearPlantunit2at:anincreasedcoreratedthermalpowerof3588MWt.Inaddition,analysesandevaluationshavebeenperformedtosupportincreasedoperatingmarginsforunit2.ChangestotheT/Ssbasedonthoseanalysesandevaluationsareproposed.Someoftheproposedchangesareproposedforbothunit1andunit2.Thesmallbreaklossofcoolantaccidentanalysis,whichissubmittedwiththisletter,wasperformedusingnewWestinghouseElectricCorporationmodels.Thesemodelsemploynewmethodsformodelingsafetyinjectiontothebrokenloopandanimprovedsteamcondensationmodel.ThesemodelsweresubmittedforNRCreviewbyWestinghouseElectricCorporationunderaletterdatedDecember14,1994,identifiedasNTD-NRC-94-4278,totheDocumentControlDeskfromN.J.Liparulo.Tobeimplemented,thissubmittalrequirestheapprovalofprevioussubmittals.ThefirstoftheseisidentifiedasAEP:NRC:1207.Itproposes"TechnicalSpecificat:ionChangesSupportedbyAnalysestoIncreaseUnit1SteamGeneratorTube96071500081I960711PDRADOCK<"050003f5tPPDR' U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1223PluggingLimitandCertainProposedChangesforUnit2SupportedbyAnalyses."The'submittalisdatedMay26,1995,fromE.E.FitzpatricktotheUSNRCDocumentControlDesk.AEP:NRC:1207includesthemostrecentsteamlinemassandenergyreleasetocontainmentanalysiswhichboundsbothunitsatacorepowerof3588MWt.Thatanalysis,inpart,providessupportfortheproposaltouprateunit2toacorepowerof3588MWt.Adescriptionoftheproposedchangesandananalysisconcerningsignificanthazardsconsiderationpursuantto10CFR50.92iscontainedinAttachment1.Attachment2containstheproposed,revisedT/Spages.Attachment3containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment4isasummarydescriptionoftheproposedT/Schanges.Itcontainsabriefsummaryofeachproposedchangeanddirectsthereviewertothesupportingdocumentation.Attachment5isadiscussionofearlierrelatedsubmittals.Theanalysesdescribedintheearliersubmittalssupportfutureoperationattheproposed,increasedratedthermalpower.Theseanalyses,togetherwithevaluationsandanalysesdescribedintheattachmentstothissubmittal,providethenecessarysupportfortheproposedincreaseinratedthermalpower.Attachment5alsoaddressespreviouslysubmittedanalysesforunit1thatsupporttheproposedchangestobothunits.Attachment6isadescriptionofanalysesperformedbyWestinghouseElectricCorporationtosupportthepoweruprateofCookNuclearPlantunit2.Attachment7describestheeffectoftheproposedupratedpoweronbalanceofplantsystemsandtheresultofmiscellaneoussafetyevaluations.Plantradiationprotectionfeaturesaredesignedtolimittheradiationexposuretoplantpersonnelandthegeneralpublicto10CFR20limitsundernormalconditions.Whilecertainisotopesarepresentingreaterconcentrationinthefuelgapduetotheupratedpowerlevel,theactualincreasesinoccupationaldoseareexpectedtobeminimal.Thefuelhasbeendesignedtooperateatthehigherpowerlevelwithoutanydamage,whichwouldnegateanyincreasesinradioactivitytrappedwithinanintactfuelrod.Also,ourtechnicalspecificationslimittheconcentrationofradioactivitywithinthereactorcoolantsystem(seeT/S3.4.8).Nevertheless,accidentoffsitedoseshavebeenrecalculatedbasedontheupratedsourcetermandotheranalysisassumptionsusedintheUpratingProgram.Insomecases,theresultingthyroidoffsitedoseconsequencesincreaseslightlyabovethevaluespresentlyintheUFSAR.ThenewcalculatedwholebodydosesareboundedbytheUFSARvalues.Forbothtypesofcalculations,thechangesintheoffsiteradiationdoseforeachaccidentarenotsignificantandarewithintheacceptancecriteriaasdefinedin10CFR100~
GeneralDistr'.'bution NOTES:RECIPIENT COPIESCOPIESIDCODE/NAME LTTRENCLLTTRENCLPD3-1LA1111HICKMAN,J 11RECIPIENT IDCODE/NAME PD3-1PDCATEGORYj.REGULATOINFORMATION DISTRIBUTION YSTEM(RIDS)ACCESSION'NBR:9607150008
U.S.NuclearRegulatoryCommissionPage3AEP:NRC:1223Becausesystemsandprocedurescontrollingnormalradioactivereleasesarebasedonlimitingplanteffluentstoasmallfractionofregulatorylimits,theproposedupratingofunit2willnotexceed10CFR20or10CFR100limits'asedonthisinformation,therewillbenosignificantincreaseinthetypesoramountsofeffluentsthatmaybereleasedoffsiteandnosignificantincreaseinindividualorcumulativeoccupationalradiationexposure.Someofthechangesproposedforunit2arealsoproposedforunit1.Thefirstproposestwofootnotesthatrequiretheasleftmagnitudeofthepressurizersafetyvalvetolerancebe1X.ThesecondaffectstheTechnicalSpecificationBasesforcontainmentinternalpressureandairtemperature.Thefinalchangeaffectingbothunitsinvolvesaclarificationoftherequiredvolumeforthecondensatestoragetank.Ourfinalreviewoftwoissuesremainsincompleteatthistime.Theseissuesare(1)theimpactofpoweruprateonblowdownforcesonductingandcabletraysinthecontainmentand(2)theresidualheatremovalcooldowncapability.Weanticipatethefinalreviewswillshowthattheseissuescanbesafelyaddressedandwillnotadverselyimpactoperationandlicensingofunit2atanupratedcorepowerlevelof3588MWt.Uponresolutionoftheseissues,wewillnotifytheNRCstaffoftheresults.ApprovalofthechangesinthissubmittalisneededbyAugust1,1997,tosupportunit2,cycle12operation.WebelievetheproposedT/Schangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountofeffluentthatmightbereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedT/SchangeshavebeenreviewedandapprovedbythePlantNuclearSafetyReviewCommitteeandbytheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtheMichiganDepartmentofPublicHealth.Sincerely,p~E.E.FitzpatrickVicePresidentTHISQ~DAYOF1996NotaryPublicMyCommissionExpires:~Q-'~SWORNTOANDSUBSCRIBEDBEFOREME U.S.NuclearRegulatoryCommissionPage4AEP:NRC:1223Attachmentscc:A.A.BlindH.J.MillerNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett U.S.NuclearRegulatoryCommissionPage5AEP:NRC:1223bc:S.J.Brewer/D.H.Malin/M.S.AckermanJ.A.Kobyra/K.R.Baker/D.R.HaferJ.B.Kingseed/V.D.Vanderburg/S.L.Colvisw/attachmentsD.F.Powell/S.K.Farlow/D.P.SchmaderB.B.Bradley-w/attachments(exceptattachment6)J.B.ShinnockJ.S.WiebeJ.B.Hickman,NRC-Washington,D.C.-w/attachmentsM.E.Eberhardt-w/attachments(exceptattachment6)M.E.Barfelz-w/attachments(exceptattachment6)G.P.Arent-w/attachmentsPRONET-w/attachmentDC-N-6015.1  
'OC.DATE:
-ATTACHMENT1TOAEP:NRC:1223REASONSAND10CFR50.92ANALYSISFORCHANGESTOTHECOOKNUCLEARPLANTUNITNO.2LICENSEANDTECHNICALSPECIFICATIONSANDCOOKNUCLEARPLANTUNITNO~1TECHNICALSPECIFICATIONS96P715PPPS Attachment1toAEP:NRC:1223Page1INTRODUCTIONTheprimarypurposeofthissubmittalistorequestapprovaltooperateCookNuclearPlantunit2atanupratedcoreratedthermalpowerof3588MWt.Theanalysesneededtosupportthisrequestincludereanalysis,evaluation,orreviewoftheeventsdiscussedinChapter14oftheUpdatedFinalSafetyAnalysisReport(UFSAR)andtheevaluationofthecapabilityofvarioussystemsandcomponents.AsdiscussedinAttachment5,DiscussionofPreviousRelatedSubmissions,previouslysubmittedanalysesforCookNuclearPlantunit2were,forthemostpart,performedataratedthermalpowerof3588MWt.Thiswasdonetopositionunit2foroperationatanupratedpower.AsdiscussedinAttachment6,WCAP14489,thepreviouslyanalyzedeventswerereviewedtoensurethatnoevaluationswereperformedoranyothereventhadoccurredthatwouldinvalidatetheanalyzedcorepower.Eventspreviouslyanalyzedatacorepowerlowerthan3588MWtwerereanalyzedorpowersensitivitycasesruntosupporttheproposedupratedpower.AnalysesinthiscategoryareLOCAcontainmentintegrityanalysis,largebreakLOCAwithresidualheatremoval(RHR)crosstiesclosed,andsmallbreakLOCAwithhighheadsafetyinjection(HHSI)crosstiesclosed.TheeffectofoperationattheupratedcorepoweronNSSSsystemsandcomponentsisalsoaddressedinAttachment6andtheeffectonbalanceofplantsystemsisaddressedinAttachment7.MiscellaneoussafetyevaluationshavebeenincludedinAttachment7.BecausetheworkneededtosupporttheproposedincreaseincorepowerinvolvedreanalysisorreviewoftheeventsdiscussedinChapter14oftheUFSAR,analysesandevaluationswereperformedsothatadditionaloperatingmargincouldbeachievedinsomeareas.Thissubmittalcontainsproposalsbasedontheseanalysesandevaluations.Furthermore,thecurrentlyapprovedunit2technicalspecifications(T/Ss)arebasedonanalysesforamixedcoreofWestinghouseVantage5andAdvancedNuclearFuel.BecausetheCookNuclearPlantunit2corenowconsiststotallyofWestinghouseVantage5fuel,thepenaltiesassociatedwiththemixedcoreanalysisarenolongerappropriate.Therefore,anumberofchangesrelatedtothecompletionofthetransitiontoafullVantage5coreareproposedinthissubmission.AfewoftheproposedchangestotheT/Ssareapplicabletobothunits.ThesechangesrelatetotheLOCAcontainmentintegrityanalysisthatboundsbothunitsandthecorrectionofanomissionintheproposedunit1T/Ssforrelaxedpressurizersafetyvalveliftpointtolerance.Theunit1submissionwasmadeinAEP:NRC:1207,datedMay26,1995.Thecorrespondingproposalforunit2isincludedinthegroupofchangesproposedtoincrease lili Attachment1toAEP:NRC:1223Page2unit2operatingmargin.Itisapartofthissubmission.Also,thedescriptionoftherequiredvolumeofthecondensatestoragetankhasbeenchangedfrom"contained"to"useable".Finally,anadministrativechangeisproposed.InTable2.2-1,thedesignflowhasbeenredefinedasafractionofthereactorcoolantsystemtotalflowrate.TheadministrativechangeisdiscussedinmoredetailundertheheadingforGroup6.TheproposedchangesarediscussedingreaterdetailbelowandinAttachment4,SummaryDescriptionofProposedUnit2PowerUprateTechnicalSpecifications.Attachment4isprovidedtoassistthereviewer.Itcontainsabriefsummaryofeachchangeanddirectsthereviewertothesupportingdocumentation.Attachment2containstheproposedT/Schanges.Attachment3containsthecurrentT/Spagesmarkedtoreflecttheproposedchanges.ThesummaryinAttachment4providesabriefdescriptionofeachproposedchangeandacrossreferencetospecificanalyseswhereappropriate.Thechangeincorepowerdependsonthefactthatallanalysesneededtosupporttheupratedcorepowerhavebeencompletedattheupratedpower;therefore,thereferencesprovidedinAttachment4aregeneralinnature.DESCRIPTIONORCHANGESTheproposedchangesarediscussedinrelatedgroups.Groupl:ChangesDirectlyRelatedtoIncreasedRatedThermalPowerTheGroupIproposedchangesarefoundintheoperatinglicenseandtheT/Sslistedbelow:OperatingLicenseSection2.C(l)currentlystates,"IndianaandMichiganElectricCompanyisauthorizedtooperatethefacilityatsteadystatereactorcorepowerlevelsnotinexcessof3411megawattsthermalinaccordancewiththeconditionsspecifiedhereinandinAttachment1tothislicense."Iftheproposaltoincreasecoreratedthermalpowerisapproved,thestatementneedstobechangedto,"IndianaandMichiganElectricCompanyisauthorizedtooperatethefacilityatsteadystatereactorcorepowerlevelsnotinexcessof3588megawattsthermalinaccordancewiththeconditionsspecifiedhereinandinAttachment1tothislicense."
96/07/11NOTARIZED:
Attachment1toAEP:NRC:1223Page3TechnicalSpecificationsIncreaseratedthermalpower1.3ReducetheapplicabilityoftheheatupandcooldowncurvesFigure3.4-2Figure3.4-3B3/4.4.9LowerthemaximumallowablepowerrangeneutronhighfluxsetpointwithinoperablesteamlinesafetyvalvesTable3.7-1Thefirstgroupofthesechangesisdirectlyrelatedtotheproposedincreaseincoreratedthermalpower.TheanalysesthatsupporttheproposedupratingofCookNuclearPlantunit2havebeenperformedoveraperiodofyearsinseveralcontexts.IncludingthenewanalysesdescribedinAttachment6(WCAP14489)andtheevaluationsdescribedinAttachment7(BalanceofPlantEvaluationsandMiscellaneousSafetyEvaluations),allthenecessaryanalysesandevaluationshavebeencompletedtosupportanuprateofunit2toacorepowerof3588MWt.ExceptforthesteammassandenergyreleasetocontainmentsubmittedwithsubmittalAEP:NRC:1207(reference30ofAttachment5),thespentfuelpoolthermalhydraulicanalysessubmittedwithsubmittalsAEP:NRC:1202andAEP:NRC:1202A(asidentifiedinthecoverletter),andAttachments6and7ofthissubmittal,alltheanalyseshavebeenpreviouslysubmittedandreviewed.AbriefhistoryofthedevelopmentoftheanalysessupportingtheupratedpowerisprovidedinAttachment5.Itsummarizesthepreviousanalysesthatprovidepartofthesupportforupratedpowerandtheirassociatedsubmittals.Attachment6,WCAP14489,describesthemostrecentanalysesandsensitivitystudies.Newanalyseshavebeenperformedtoreplaceorsupplementthoseanalysesformerlyperformedatthecurrentlyapprovedmaximumpowerlevel.ThenewanalysesyieldedacceptableresultsattheproposedupratedcorepowerasdescribedinAttachment6.TheWestinghousemodelandtheplantinputassumptionswerereviewedforthenewlongtermcontainmentanalysis.Therevisedinputassumptionwiththegreatestimpactontheresultwasanewlyrevisedstructuralheatsinkmodel.Theheatsinkmodelwascompletelyrevisedtoreconstructitsbasis.Theanalysisperformedafterthisreviewwassatisfactory.  
YESDOCKETFACIL:50-315 Donald'C.
CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichiganPower-Co.(formerly IndianaaMichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)0INTERNAL:
FILECDRCH/HICB NRR/DSSA/SRXB OGC/HDS2EXTERNAL:
NOAC1111111011NRCPDR11NRR/DE/EMCB 11NRR/DSSA/SPLB 11NUDOCS-ABSTRACT 11D0UNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!tTOTALNUMBEROFCOPIESREQUIRED:
LTTR12ENCL11 I
AmericanElectric~r 1RiversidePlaza
~Columbus, OH4321523736142231000July11,1996DocketNos.50-31550-316AEP:NRC:1223 U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen:
DONALDC.COOKNUCLEARPLANTUNITS1AND2LICENSENOS.DPR-58ANDDPR-74PROPOSEDLICENSEANDTECHNICAL SPECIFICATION CHANGESSUPPORTED BYANALYSESTOINCREASEUNIT2RATEDTHERMALPOWERANDCERTAINPROPOSEDCHANGESFORUNIT1SUPPORTED BYRELATEDANALYSESThisletteranditsattachments constitute anapplication foramendment oftheDonaldC.CookNuclearPlantunit2facilityoperating license,foramendment oftheDonaldC.CookNuclearPlantunit2technical specificat:ions (T/S),andforsomerelatedchangestotheunit1technical specifications.
Changesareproposedprimarily tosupportoperation ofCookNuclearPlantunit2at:anincreased coreratedthermalpowerof3588MWt.Inaddition, analysesandevaluations havebeenperformed tosupportincreased operating marginsforunit2.ChangestotheT/Ssbasedonthoseanalysesandevaluations areproposed.
Someoftheproposedchangesareproposedforbothunit1andunit2.Thesmallbreaklossofcoolantaccidentanalysis, whichissubmitted withthisletter,wasperformed usingnewWestinghouse ElectricCorporation models.Thesemodelsemploynewmethodsformodelingsafetyinjection tothebrokenloopandanimprovedsteamcondensation model.Thesemodelsweresubmitted forNRCreviewbyWestinghouse ElectricCorporation underaletterdatedDecember14,1994,identified asNTD-NRC-94-4278, totheDocumentControlDeskfromN.J.Liparulo.
Tobeimplemented, thissubmittal requirestheapprovalofprevioussubmittals.
Thefirstoftheseisidentified asAEP:NRC:1207.
Itproposes"Technical Specificat:ion ChangesSupported byAnalysestoIncreaseUnit1SteamGenerator Tube96071500081I960711PDRADOCK<"050003f5tPPDR' U.S.NuclearRegulatory Commission Page2AEP:NRC:1223 PluggingLimitandCertainProposedChangesforUnit2Supported byAnalyses."
The'submittal isdatedMay26,1995,fromE.E.Fitzpatrick totheUSNRCDocumentControlDesk.AEP:NRC:1207 includesthemostrecentsteamlinemassandenergyreleasetocontainment analysiswhichboundsbothunitsatacorepowerof3588MWt.Thatanalysis, inpart,providessupportfortheproposaltouprateunit2toacorepowerof3588MWt.Adescription oftheproposedchangesandananalysisconcerning significant hazardsconsideration pursuantto10CFR50.92iscontained inAttachment 1.Attachment 2containstheproposed, revisedT/Spages.Attachment 3containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 4isasummarydescription oftheproposedT/Schanges.Itcontainsabriefsummaryofeachproposedchangeanddirectsthereviewertothesupporting documentation.
Attachment 5isadiscussion ofearlierrelatedsubmittals.
Theanalysesdescribed intheearliersubmittals supportfutureoperation attheproposed, increased ratedthermalpower.Theseanalyses, togetherwithevaluations andanalysesdescribed intheattachments tothissubmittal, providethenecessary supportfortheproposedincreaseinratedthermalpower.Attachment 5alsoaddresses previously submitted analysesforunit1thatsupporttheproposedchangestobothunits.Attachment 6isadescription ofanalysesperformed byWestinghouse ElectricCorporation tosupportthepoweruprateofCookNuclearPlantunit2.Attachment 7describes theeffectoftheproposedupratedpoweronbalanceofplantsystemsandtheresultofmiscellaneous safetyevaluations.
Plantradiation protection featuresaredesignedtolimittheradiation exposuretoplantpersonnel andthegeneralpublicto10CFR20limitsundernormalconditions.
Whilecertainisotopesarepresentingreaterconcentration inthefuelgapduetotheupratedpowerlevel,theactualincreases inoccupational doseareexpectedtobeminimal.Thefuelhasbeendesignedtooperateatthehigherpowerlevelwithoutanydamage,whichwouldnegateanyincreases inradioactivity trappedwithinanintactfuelrod.Also,ourtechnical specifications limittheconcentration ofradioactivity withinthereactorcoolantsystem(seeT/S3.4.8).Nevertheless, accidentoffsitedoseshavebeenrecalculated basedontheupratedsourcetermandotheranalysisassumptions usedintheUpratingProgram.Insomecases,theresulting thyroidoffsitedoseconsequences increaseslightlyabovethevaluespresently intheUFSAR.Thenewcalculated wholebodydosesareboundedbytheUFSARvalues.Forbothtypesofcalculations, thechangesintheoffsiteradiation doseforeachaccidentarenotsignificant andarewithintheacceptance criteriaasdefinedin10CFR100~
U.S.NuclearRegulatory Commission Page3AEP:NRC:1223 Becausesystemsandprocedures controlling normalradioactive releasesarebasedonlimitingplanteffluents toasmallfractionofregulatory limits,theproposedupratingofunit2willnotexceed10CFR20or10CFR100limits'ased onthisinformation, therewillbenosignificant increaseinthetypesoramountsofeffluents thatmaybereleasedoffsiteandnosignificant increaseinindividual orcumulative occupational radiation exposure.
Someofthechangesproposedforunit2arealsoproposedforunit1.Thefirstproposestwofootnotes thatrequiretheasleftmagnitude ofthepressurizer safetyvalvetolerance be1X.ThesecondaffectstheTechnical Specification Basesforcontainment internalpressureandairtemperature.
Thefinalchangeaffecting bothunitsinvolvesaclarification oftherequiredvolumeforthecondensate storagetank.Ourfinalreviewoftwoissuesremainsincomplete atthistime.Theseissuesare(1)theimpactofpoweruprateonblowdownforcesonductingandcabletraysinthecontainment and(2)theresidualheatremovalcooldowncapability.
Weanticipate thefinalreviewswillshowthattheseissuescanbesafelyaddressed andwillnotadversely impactoperation andlicensing ofunit2atanupratedcorepowerlevelof3588MWt.Uponresolution oftheseissues,wewillnotifytheNRCstaffoftheresults.Approvalofthechangesinthissubmittal isneededbyAugust1,1997,tosupportunit2,cycle12operation.
WebelievetheproposedT/Schangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountofeffluentthatmightbereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedT/SchangeshavebeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee.
Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.Sincerely, p~E.E.Fitzpatrick VicePresident THISQ~DAYOF1996NotaryPublicMyCommission Expires:~Q-'~
SWORNTOANDSUBSCRIBED BEFOREME U.S.NuclearRegulatory Commission Page4AEP:NRC:1223 Attachments cc:A.A.BlindH.J.MillerNFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett U.S.NuclearRegulatory Commission Page5AEP:NRC:1223 bc:S.J.Brewer/D.
H.Malin/M.S.AckermanJ.A.Kobyra/K.
R.Baker/D.R.HaferJ.B.Kingseed/V.
D.Vanderburg/S.
L.Colvisw/attachments D.F.Powell/S.
K.Farlow/D.
P.SchmaderB.B.Bradley-w/attachments (exceptattachment 6)J.B.ShinnockJ.S.WiebeJ.B.Hickman,NRC-Washington, D.C.-w/attachments M.E.Eberhardt
-w/attachments (exceptattachment 6)M.E.Barfelz-w/attachments (exceptattachment 6)G.P.Arent-w/attachments PRONET-w/attachment DC-N-6015.1  
-ATTACHMENT 1TOAEP:NRC:1223REASONSAND10CFR50.92 ANALYSISFORCHANGESTOTHECOOKNUCLEARPLANTUNITNO.2LICENSEANDTECHNICAL SPECIFICATIONS ANDCOOKNUCLEARPLANTUNITNO~1TECHNICAL SPECIFICATIONS 96P715PPPS Attachment 1toAEP:NRC:1223 Page1INTRODUCTION Theprimarypurposeofthissubmittal istorequestapprovaltooperateCookNuclearPlantunit2atanupratedcoreratedthermalpowerof3588MWt.Theanalysesneededtosupportthisrequestincludereanalysis, evaluation, orreviewoftheeventsdiscussed inChapter14oftheUpdatedFinalSafetyAnalysisReport(UFSAR)andtheevaluation ofthecapability ofvarioussystemsandcomponents.
Asdiscussed inAttachment 5,Discussion ofPreviousRelatedSubmissions, previously submitted analysesforCookNuclearPlantunit2were,forthemostpart,performed ataratedthermalpowerof3588MWt.Thiswasdonetopositionunit2foroperation atanupratedpower.Asdiscussed inAttachment 6,WCAP14489,thepreviously analyzedeventswerereviewedtoensurethatnoevaluations wereperformed oranyothereventhadoccurredthatwouldinvalidate theanalyzedcorepower.Eventspreviously analyzedatacorepowerlowerthan3588MWtwerereanalyzed orpowersensitivity casesruntosupporttheproposedupratedpower.AnalysesinthiscategoryareLOCAcontainment integrity
: analysis, largebreakLOCAwithresidualheatremoval(RHR)crossties closed,andsmallbreakLOCAwithhighheadsafetyinjection (HHSI)crossties closed.Theeffectofoperation attheupratedcorepoweronNSSSsystemsandcomponents isalsoaddressed inAttachment 6andtheeffectonbalanceofplantsystemsisaddressed inAttachment 7.Miscellaneous safetyevaluations havebeenincludedinAttachment 7.Becausetheworkneededtosupporttheproposedincreaseincorepowerinvolvedreanalysis orreviewoftheeventsdiscussed inChapter14oftheUFSAR,analysesandevaluations wereperformed sothatadditional operating margincouldbeachievedinsomeareas.Thissubmittal containsproposals basedontheseanalysesandevaluations.
Furthermore, thecurrently approvedunit2technical specifications (T/Ss)arebasedonanalysesforamixedcoreofWestinghouse Vantage5andAdvancedNuclearFuel.BecausetheCookNuclearPlantunit2corenowconsiststotallyofWestinghouse Vantage5fuel,thepenalties associated withthemixedcoreanalysisarenolongerappropriate.
Therefore, anumberofchangesrelatedtothecompletion ofthetransition toafullVantage5coreareproposedinthissubmission.
AfewoftheproposedchangestotheT/Ssareapplicable tobothunits.ThesechangesrelatetotheLOCAcontainment integrity analysisthatboundsbothunitsandthecorrection ofanomissionintheproposedunit1T/Ssforrelaxedpressurizer safetyvalveliftpoint tolerance.
Theunit1submission wasmadeinAEP:NRC:1207, datedMay26,1995.Thecorresponding proposalforunit2isincludedinthegroupofchangesproposedtoincrease lili Attachment 1toAEP:NRC:1223 Page2unit2operating margin.Itisapartofthissubmission.
Also,thedescription oftherequiredvolumeofthecondensate storagetankhasbeenchangedfrom"contained" to"useable".
Finally,anadministrative changeisproposed.
InTable2.2-1,thedesignflowhasbeenredefined asafractionofthereactorcoolantsystemtotalflowrate.Theadministrative changeisdiscussed inmoredetailundertheheadingforGroup6.Theproposedchangesarediscussed ingreaterdetailbelowandinAttachment 4,SummaryDescription ofProposedUnit2PowerUprateTechnical Specifications.
Attachment 4isprovidedtoassistthereviewer.
Itcontainsabriefsummaryofeachchangeanddirectsthereviewertothesupporting documentation.
Attachment 2containstheproposedT/Schanges.Attachment 3containsthecurrentT/Spagesmarkedtoreflecttheproposedchanges.ThesummaryinAttachment 4providesabriefdescription ofeachproposedchangeandacrossreference tospecificanalyseswhereappropriate.
Thechangeincorepowerdependsonthefactthatallanalysesneededtosupporttheupratedcorepowerhavebeencompleted attheupratedpower;therefore, thereferences providedinAttachment 4aregeneralinnature.DESCRIPTION ORCHANGESTheproposedchangesarediscussed inrelatedgroups.Groupl:ChangesDirectlyRelatedtoIncreased RatedThermalPowerTheGroupIproposedchangesarefoundintheoperating licenseandtheT/Sslistedbelow:Operating LicenseSection2.C(l)currently states,"IndianaandMichiganElectricCompanyisauthorized tooperatethefacilityatsteadystatereactorcorepowerlevelsnotinexcessof3411megawatts thermalinaccordance withtheconditions specified hereinandinAttachment 1tothislicense."
Iftheproposaltoincreasecoreratedthermalpowerisapproved, thestatement needstobechangedto,"IndianaandMichiganElectricCompanyisauthorized tooperatethefacilityatsteadystatereactorcorepowerlevelsnotinexcessof3588megawatts thermalinaccordance withtheconditions specified hereinandinAttachment 1tothislicense."
Attachment 1toAEP:NRC:1223 Page3Technical Specifications Increaseratedthermalpower1.3Reducetheapplicability oftheheatupandcooldowncurvesFigure3.4-2Figure3.4-3B3/4.4.9Lowerthemaximumallowable powerrangeneutronhighfluxsetpointwithinoperable steamlinesafetyvalvesTable3.7-1Thefirstgroupofthesechangesisdirectlyrelatedtotheproposedincreaseincoreratedthermalpower.TheanalysesthatsupporttheproposedupratingofCookNuclearPlantunit2havebeenperformed overaperiodofyearsinseveralcontexts.
Including thenewanalysesdescribed inAttachment 6(WCAP14489)andtheevaluations described inAttachment 7(BalanceofPlantEvaluations andMiscellaneous SafetyEvaluations),
allthenecessary analysesandevaluations havebeencompleted tosupportanuprateofunit2toacorepowerof3588MWt.Exceptforthesteammassandenergyreleasetocontainment submitted withsubmittal AEP:NRC:1207 (reference 30ofAttachment 5),thespentfuelpoolthermalhydraulic analysessubmitted withsubmittals AEP:NRC:1202 andAEP:NRC:1202A (asidentified inthecoverletter),andAttachments 6and7ofthissubmittal, alltheanalyseshavebeenpreviously submitted andreviewed.
Abriefhistoryofthedevelopment oftheanalysessupporting theupratedpowerisprovidedinAttachment 5.Itsummarizes thepreviousanalysesthatprovidepartofthesupportforupratedpowerandtheirassociated submittals.
Attachment 6,WCAP14489,describes themostrecentanalysesandsensitivity studies.Newanalyseshavebeenperformed toreplaceorsupplement thoseanalysesformerlyperformed atthecurrently approvedmaximumpowerlevel.Thenewanalysesyieldedacceptable resultsattheproposedupratedcorepowerasdescribed inAttachment 6.TheWestinghouse modelandtheplantinputassumptions werereviewedforthenewlongtermcontainment analysis.
Therevisedinputassumption withthegreatestimpactontheresultwasanewlyrevisedstructural heatsinkmodel.Theheatsinkmodelwascompletely revisedtoreconstruct itsbasis.Theanalysisperformed afterthisreviewwassatisfactory.  


Attachment1toAEP:NRC:1223Page4ThelargebreakLOCA(LBLOCA)reanalysiswithRHRcrosstiesclosedwasalsosatisfactoryusingthecurrentmodel.AsdescribedinSection3.1.1.3ofWCAP14489,thenewreanalysisincorporatesmodelchangesthatresultedfromtheresolutionofissuesidentifiedinlOCFR50.46reportsandinWestinghousereportstotheNRC.Thesemodelchangeswereasignificantbenefitto-aCookNuclearPlantunit2specificanalysis.ThesmallbreakLOCA(SBLOCA)reanalysisalsowassatisfactory.Asindicatedinthecoverletterofthissubmittal,theSBLOCAreanalysiswasperformedusingtheimprovedsteamcondensationmodelthatresultsinasignificantbenefittoaCookNuclearPlantunit2specificanalysis.Thisnewanalysissupportsourproposal,describedinGroup2,todeletetherequirementinEmergencyCoreCoolingSystemTechnicalSpecificationthatpowerbereducedwhentheHHSIcrosstiesareclosed.Attachment6alsosummarizesanalysesandevaluationspreviouslyperformedbyWestinghouseElectricCorporationtosupporttheupratedcorepowerforunit2.Section2.0ofWCAP14489referencestheearlierwork.TheevaluationsdescribedinWCAP14489arebasedontheseearlieranalyses.TheearlieranalysesaredescribedinReratingProgramWCAP's11902and11902Supplement1,references3and10ofAttachment5,'ndintheVantage5ReloadTransitionSafetyReportforDonaldC.CookNuclearPlantUnit2,Revision1,March1990(RTSR),referencellofAttachment5.TheSteamGeneratorTubePluggingProgramsteamlinemassandenergyrelease(SGTPSM&E)tocontainmentanalysisisdescribedinWCAP14285,reference29ofAttachment5.WCAP11902anditssupplementarereferredtoasthe"ReratingProgram"inWCAP14489.Thereloadtransitionsafetyreportisreferredtoas"RTSR"inWCAP14489.Theincreaseinthepermittedlevelofsteamgeneratortubepluggingprogramisreferredtoas"SGTPProgram"inWCAP14489.Attachment6,togetherwithearlierworkreferencedinAttachments5and6,andAttachment7supporttheupratedcorepowerforunit2.Group2:ChangetoRemovePowerRestrictionforHighHeadSafetyInjectionCrossTiesClosedOperationThisgroupofproposedchangesisfoundinthefollowingT/Ss:Deletepowerreductionrequirementwhenthehighheadsafetyinjectioncrosstiesareclosed3.5.2B3/4.5.2andB3/4.5.3ThesecondgroupofchangesconsistsofasinglechangetoT/S3.5.2,EmergencyCoreCoolingSystems.ThecurrentlyapprovedLimitingConditionforOperation(LCO)requiresthat"allsafety  
Attachment 1toAEP:NRC:1223 Page4ThelargebreakLOCA(LBLOCA)reanalysis withRHRcrosstiesclosedwasalsosatisfactory usingthecurrentmodel.Asdescribed inSection3.1.1.3ofWCAP14489,thenewreanalysis incorporates modelchangesthatresultedfromtheresolution ofissuesidentified inlOCFR50.46 reportsandinWestinghouse reportstotheNRC.Thesemodelchangeswereasignificant benefitto-aCookNuclearPlantunit2specificanalysis.
ThesmallbreakLOCA(SBLOCA)reanalysis alsowassatisfactory.
Asindicated inthecoverletterofthissubmittal, theSBLOCAreanalysis wasperformed usingtheimprovedsteamcondensation modelthatresultsinasignificant benefittoaCookNuclearPlantunit2specificanalysis.
Thisnewanalysissupportsourproposal, described inGroup2,todeletetherequirement inEmergency CoreCoolingSystemTechnical Specification thatpowerbereducedwhentheHHSIcrossties areclosed.Attachment 6alsosummarizes analysesandevaluations previously performed byWestinghouse ElectricCorporation tosupporttheupratedcorepowerforunit2.Section2.0ofWCAP14489references theearlierwork.Theevaluations described inWCAP14489arebasedontheseearlieranalyses.
Theearlieranalysesaredescribed inReratingProgramWCAP's11902and11902Supplement 1,references 3and10ofAttachment 5,'ndintheVantage5ReloadTransition SafetyReportforDonaldC.CookNuclearPlantUnit2,Revision1,March1990(RTSR),reference llofAttachment 5.TheSteamGenerator TubePluggingProgramsteamline massandenergyrelease(SGTPSM&E)tocontainment analysisisdescribed inWCAP14285,reference 29ofAttachment 5.WCAP11902anditssupplement arereferredtoasthe"Rerating Program"inWCAP14489.Thereloadtransition safetyreportisreferredtoas"RTSR"inWCAP14489.Theincreaseinthepermitted levelofsteamgenerator tubepluggingprogramisreferredtoas"SGTPProgram"inWCAP14489.Attachment 6,togetherwithearlierworkreferenced inAttachments 5and6,andAttachment 7supporttheupratedcorepowerforunit2.Group2:ChangetoRemovePowerRestriction forHighHeadSafetyInjection CrossTiesClosedOperation Thisgroupofproposedchangesisfoundinthefollowing T/Ss:Deletepowerreduction requirement whenthehighheadsafetyinjection crosstiesareclosed3.5.2B3/4.5.2andB3/4.5.3ThesecondgroupofchangesconsistsofasinglechangetoT/S3.5.2,Emergency CoreCoolingSystems.Thecurrently approvedLimitingCondition forOperation (LCO)requiresthat"allsafety  


Attachment1toAEP:NRC:1223Page5injectioncross-tievalves(be)open."Ifahighheadsafetyinjectioncross-tievalveisclosed,theACTIONstatementsmustbeenteredandthecorepowerreducedto3250MWt.Theproposedchangedeletestheserequirements.Thecurrentlyapprovedrestrictioninpowerwithsafetyinjectioncross-tiesclosedistheresultoftheSBLOCAanalysisperformedinsupportofrelaxingthemainsteamsafetyvalve(MSSV)setpointtolerance.TheMSSVsubmittalandtheassociatedSERarereferences26and28ofAttachment5,respectively.TheapprovedWestinghouseSBLOCAmodelatthetimeoftheMSSVsubmittalrequiredapowerreductiontogetanacceptableresult.Forthispowerupratingprogram,animprovedSBLOCAmodelincorporatingtheCOSIcondensationmodelwasused.Theresultswereacceptableattheproposedupratedcorepowerof3588MWt.TheMSSVanalysisandthenewanalysiswiththeCOSIcondensationmodelarediscussedinmoredetailinSections3.1.2.3and3.1.2.4ofWCAP14489,Attachment6.ThecoverlettertothissubmittaladdressesthefactthattheSBLOCAanalysiswasperformedusingthenew,improvedmodelandprovidesareferencetotheWestinghousesubmittalforthenewmodel.Group3:ChangesProposedtoIncreaseUnitZOperatingHarginThisgroupofproposedchangesarefoundinthefollowingT/S:ReviseSafetyLimitsandOPhT/OThTReactorTripSetpointFigure2.1-1Table2.2-1B2'.1OverpowerDeltaTIncreaseUnit1PressurizerSafetyValveTolerance3.4.23.4.3Thethirdgroupofchangesresultsfromanalysesandevaluationsdesignedtoincreaseoperatingmargin.BecausemostoftheeventsdescribedinChapter14oftheUFSARhadtobereanalyzed,evaluated,orreviewedtoensurecurrencyinordertosupporttheincreaseincoreratedthermalpower,theefforttoincreasesomemarginswasperformedatthesametime.ThefirstproposedchangesinthisgrouparechangestotheovertemperaturedeltaT(OThT)andoverpowerdeltaT(OPAT)reactortripsetpoints.ThenewsetpointsarebasedoncorethermalsafetylimitsforanallVantage5coreat3588MWt.ThesafetylimitsarethosewhichwerecalculatedforanallVantage5coreatthetimeoftransitionfromAdvancedNuclearFueltoWestinghousefuel.TheproposedsafetylimitscouldhavebeenincludedwiththechangeseitherinthisgrouporinGroup4 Attachment1toAEP:NRC:1223Page6below.They'reincludedhereinGroup3becauseoftheirrelationship.totheproposedOT~TandOPaTreactortripsetpoints.Asaresultoftemperaturestreaminginthereactorcoolanthotlegs,thereisaninaccuracyinthemeasurementofTintheresistancetemperaturedetector(RTD)bypasslines'hisstreamingisafunctionofthecorepowerdistribution.DriftintheDeltaTmeasurementsatfullpowerasafunctionofburnupresultsfromthisphenomenon.Whenthedeviationsexceedtheinstrumentallowancesforhotlegstreaming,itisnecessarytorecalibratetheOT~TandOP~Tsystem.TheOTnTandOP~Treactortripfunctionsprovideprimaryprotectionagainstfuelcenterlinemelting,amongotherconcerns(e.g.,DNBandhot-legboiling).RevisedOT~TandOP~Treactortripsetpointsfortheincreasedreactorcorepowerof3588MWtwerecalculatedtoaccommodateanincreaseintheallowancebetweenthesafetyanalysislimitsandthetechnicalspecificationsetpoints.Thechangesproposedinthissubmittalarebaseduponanalysesperformedbybothusandourcontractor,WestinghouseElectricCorporation.Westinghouseperformedcalculationstoensurethatthesafetyanalysisvaluesfort'eOT~TandOP~Tsetpointsprovidethenecessaryprotectionwithrespecttofuelcenterlinemelting,theapplicablecorethermallimits,andthatacceptableresultsareobtainedfortheaffectedtransients.WeperformedthecalculationstoensureadequatemarginexistsbetweenthesafetyanalysisvaluesandtheT/SnominalvaluesoftheOT~TandOP~Treactortrip,setpoints.Theassociatedallowablevaluesproposedfornotes3and4ofT/STable2.2-1inAttachments2and3arebasedonourcalculations.Thepressurizersafetyvalveliftpointtolerancewasincreasedto+3X.-AsindicatedinSection3.3.2.2ofAttachment6,theappropriateeventshavebeenshowntosupportthisincreasedtolerance.TheanalysesandevaluationsdescribedinWCAP14489,Attachment6,supporttheproposedT/Schangestoincreaseoperatingmargindescribedabove.  
Attachment 1toAEP:NRC:1223 Page5injection cross-tie valves(be)open."Ifahighheadsafetyinjection cross-tie valveisclosed,theACTIONstatements mustbeenteredandthecorepowerreducedto3250MWt.Theproposedchangedeletestheserequirements.
Thecurrently approvedrestriction inpowerwithsafetyinjection cross-ties closedistheresultoftheSBLOCAanalysisperformed insupportofrelaxingthemainsteamsafetyvalve(MSSV)setpointtolerance.
TheMSSVsubmittal andtheassociated SERarereferences 26and28ofAttachment 5,respectively.
TheapprovedWestinghouse SBLOCAmodelatthetimeoftheMSSVsubmittal requiredapowerreduction togetanacceptable result.Forthispowerupratingprogram,animprovedSBLOCAmodelincorporating theCOSIcondensation modelwasused.Theresultswereacceptable attheproposedupratedcorepowerof3588MWt.TheMSSVanalysisandthenewanalysiswiththeCOSIcondensation modelarediscussed inmoredetailinSections3.1.2.3and3.1.2.4ofWCAP14489,Attachment 6.Thecoverlettertothissubmittal addresses thefactthattheSBLOCAanalysiswasperformed usingthenew,improvedmodelandprovidesareference totheWestinghouse submittal forthenewmodel.Group3:ChangesProposedtoIncreaseUnitZOperating HarginThisgroupofproposedchangesarefoundinthefollowing T/S:ReviseSafetyLimitsandOPhT/OThT ReactorTripSetpointFigure2.1-1Table2.2-1B2'.1Overpower DeltaTIncreaseUnit1Pressurizer SafetyValveTolerance 3.4.23.4.3Thethirdgroupofchangesresultsfromanalysesandevaluations designedtoincreaseoperating margin.Becausemostoftheeventsdescribed inChapter14oftheUFSARhadtobereanalyzed, evaluated, orreviewedtoensurecurrencyinordertosupporttheincreaseincoreratedthermalpower,theefforttoincreasesomemarginswasperformed atthesametime.Thefirstproposedchangesinthisgrouparechangestotheovertemperature deltaT(OThT)andoverpower deltaT(OPAT)reactortripsetpoints.
Thenewsetpoints arebasedoncorethermalsafetylimitsforanallVantage5coreat3588MWt.Thesafetylimitsarethosewhichwerecalculated foranallVantage5coreatthetimeoftransition fromAdvancedNuclearFueltoWestinghouse fuel.TheproposedsafetylimitscouldhavebeenincludedwiththechangeseitherinthisgrouporinGroup4 Attachment 1toAEP:NRC:1223 Page6below.They'reincludedhereinGroup3becauseoftheirrelationship.
totheproposedOT~TandOPaTreactortripsetpoints.
Asaresultoftemperature streaming inthereactorcoolanthotlegs,thereisaninaccuracy inthemeasurement ofTintheresistance temperature detector(RTD)bypasslines'his streaming isafunctionofthecorepowerdistribution.
DriftintheDeltaTmeasurements atfullpowerasafunctionofburnupresultsfromthisphenomenon.
Whenthedeviations exceedtheinstrument allowances forhotlegstreaming, itisnecessary torecalibrate theOT~TandOP~Tsystem.TheOTnTandOP~Treactortripfunctions provideprimaryprotection againstfuelcenterline melting,amongotherconcerns(e.g.,DNBandhot-legboiling).
RevisedOT~TandOP~Treactortripsetpoints fortheincreased reactorcorepowerof3588MWtwerecalculated toaccommodate anincreaseintheallowance betweenthesafetyanalysislimitsandthetechnical specification setpoints.
Thechangesproposedinthissubmittal arebaseduponanalysesperformed bybothusandourcontractor, Westinghouse ElectricCorporation.
Westinghouse performed calculations toensurethatthesafetyanalysisvaluesfort'eOT~TandOP~Tsetpoints providethenecessary protection withrespecttofuelcenterline melting,theapplicable corethermallimits,andthatacceptable resultsareobtainedfortheaffectedtransients.
Weperformed thecalculations toensureadequatemarginexistsbetweenthesafetyanalysisvaluesandtheT/SnominalvaluesoftheOT~TandOP~Treactortrip,setpoints.
Theassociated allowable valuesproposedfornotes3and4ofT/STable2.2-1inAttachments 2and3arebasedonourcalculations.
Thepressurizer safetyvalveliftpoint tolerance wasincreased to+3X.-Asindicated inSection3.3.2.2ofAttachment 6,theappropriate eventshavebeenshowntosupportthisincreased tolerance.
Theanalysesandevaluations described inWCAP14489,Attachment 6,supporttheproposedT/Schangestoincreaseoperating margindescribed above.  


Attachment1toAEP:NRC:1223Page7Group4:ChangesRelatedtoTransitionCoreorTransitiontoTemperatureWindow/DualPressureTechnicalSpeciecationsThisgroupofproposedchangesisfoundinthefollowingT/Ss:IncreaseDNBTemperatureLimit,IncludeLimitsforBothAnalyzedPressures,DeleteLowTemperatureLimit3'.5B3/4.2.5ReduceSetpointandAllowableValueforSIonLowPressurizerPressureTable3.3-4ReduceSetpointandAllowableValueforSIonLowSteamlinePressureTable3.3-4ReduceSetpointandAllowableValueforSteamlineIsolationonLowSteamlinePressureTable3.3-4IncludePressureCriteriaforBothAnalyzed,NominalPressures4.4.6.2.1RemoveReferencestoAdvancedNuclearFuelB2.1.1B3/4.2.2andB3/4.2.3ThefourthgroupofproposedchangesarechangesthatremoverestrictionsrelatedtooperationofCookNuclearPlantunit2withamixedcoreofWestinghouseVantage.5fuelandAdvancedNuclearFuel.ThefirstfullVantage5corewascycle10.Theproposedchangesareplannedforimplementationincycle12.TheproposalsexpandthetemperaturewindowtothatanalyzedforafullVantage5core,identifybothanalyzedpressures,changeengineeredsafetyfeaturesactuationsetpoints,deletethelowtemperaturelimitfromtheDNBT/S,anddeletereferencestoAdvancedNuclearFuelfromthebases.ExceptfortheproposaltolowerthesafetyinjectionactuationsetpointonlowpressurizerpressureandtheproposaltodeletethelowtemperaturelimitfromtheDNBT/S,theunderlyinganalysesfortheproposedchangesinthisgrouphavebeenreviewedandapprovedasapartofprevioussubmittals.However,thesteammassandenergyrelease(SM&E)tocontainmentanalysisthatdirectlysupportsthesetpointforlowsteampressurewasrecentlyreanalyzedtoboundbothunitsat,theunit2upratedpower.Thiswasdonetocorrectsomeinaccurateanalysis Attachment1toAEP:NRC:1223Page8assumptions.Asindicatedin.thecoverletterandAttachment5,thisnewanalysiswassubmittedaspartofourproposaltoincreasethelimitofpluggedsteamgeneratortubesforunit1(SGTP),reference30ofAttachment5.TheanalysesincludedintheVantage5ReloadTransitionSafetyReportforCookNuclearPlantunit2,revision1,March1990(RTSR)generallyaddressedtwosituations,amixedcoreofAdvancedNuclearFuelandWestinghouseVantage5fuelandacoreofallVantage5fuel.OperationwithanallVantage5coresupportedanoperatingtemperaturewindowandtheoptionofoperatingattwoprimarypressures.TheanalysesforthemixedcoreusedtheW-3DNBcorrelationfortheAdvancedNuclearFuel.UseoftheW-3correlationwasasignificantDNBpenalty.Toobtainacceptableresultsforamixedcore,thehightemperaturesideofthetemperaturewindowwasrestrictedtoaTavgof576.0'Fandoperationwaspermittedonlyatthehighnominalpressureof2250psia.TheselimitationsaredocumentedintheRTSR,reference11ofAttachment5.Operationofunit2withallWestinghousefuelwasapprovedbyreference17ofAttachment5.Changestosupportoperationinthefulltemperaturewindowandatbothoperatingpressuresareproposedinthissubmittal.TheproposedT/SchangesincludeanewupperlimitonreactorcoolantsystemTavg.Theproposeddeparturefromnucleateboiling(DNB)uppertemperaturelimitwascalculatedfromtheupperlimitofthetemperaturewindowforafullVantage5coreatacorepowerof3588MWt.TheDNBtemperaturelimitisobtainedbyaddingthecontrollerallowancetothehighnominalTavgusedintheanalysisandthensubtractingthereadabilityallowance.ThehighnominalTavgis581.3'Fandthecontrollerallowanceis4,14F.ThesevaluesarefoundinTable3.3-1andSection3.3.3.1ofWCAP14489,respectively.Thereadabilityallowance,calculatedbyAEPSC,is2.1~F.TheresultingDNBtemperaturelimitis583.34F.TheproposedchangesincludeaddingtheDNBpressurelimitforlowpressureoperation.TheDNBpressurelimitisobtainedbysubtractingthetotalpressureallowanceusedintheanalysisfromthenominaloperatingpressureusedintheanalysisandthenaddingthereadabilityallowance.ThenominalpressuresandthetotalallowancearefoundinSection3.3.1and3.3.3.1ofWCAP14489,respectively.Thereadabilityallowance,calculatedbyAEPSC,is18.9psi.ThepressurelimitcurrentlyintheT/Ssforhighpressureoperationisconservativelyhigherthanthecalculatedvalueof2191psig.Theproposedlimitof2050'psigfor'lowpressureoperationisanaddition.Itisconservativelyhigherthanthecalculatedvalueof2041psig,Theproposedvalueforthelowpressurelimitisthesameastheunit1limit.  
Attachment 1toAEP:NRC:1223 Page7Group4:ChangesRelatedtoTransition CoreorTransition toTemperature Window/Dual PressureTechnicalSpeciecationsThisgroupofproposedchangesisfoundinthefollowing T/Ss:IncreaseDNBTemperature Limit,IncludeLimitsforBothAnalyzedPressures, DeleteLowTemperature Limit3'.5B3/4.2.5ReduceSetpointandAllowable ValueforSIonLowPressurizer PressureTable3.3-4ReduceSetpointandAllowable ValueforSIonLowSteamline PressureTable3.3-4ReduceSetpointandAllowable ValueforSteamline Isolation onLowSteamline PressureTable3.3-4IncludePressureCriteriaforBothAnalyzed, NominalPressures 4.4.6.2.1 RemoveReferences toAdvancedNuclearFuelB2.1.1B3/4.2.2andB3/4.2.3Thefourthgroupofproposedchangesarechangesthatremoverestrictions relatedtooperation ofCookNuclearPlantunit2withamixedcoreofWestinghouse Vantage.5fuelandAdvancedNuclearFuel.ThefirstfullVantage5corewascycle10.Theproposedchangesareplannedforimplementation incycle12.Theproposals expandthetemperature windowtothatanalyzedforafullVantage5core,identifybothanalyzedpressures, changeengineered safetyfeaturesactuation setpoints, deletethelowtemperature limitfromtheDNBT/S,anddeletereferences toAdvancedNuclearFuelfromthebases.Exceptfortheproposaltolowerthesafetyinjection actuation setpointonlowpressurizer pressureandtheproposaltodeletethelowtemperature limitfromtheDNBT/S,theunderlying analysesfortheproposedchangesinthisgrouphavebeenreviewedandapprovedasapartofprevioussubmittals.
However,thesteammassandenergyrelease(SM&E)tocontainment analysisthatdirectlysupportsthesetpointforlowsteampressurewasrecentlyreanalyzed toboundbothunitsat,theunit2upratedpower.Thiswasdonetocorrectsomeinaccurate analysis Attachment 1toAEP:NRC:1223 Page8assumptions.
Asindicated in.thecoverletterandAttachment 5,thisnewanalysiswassubmitted aspartofourproposaltoincreasethelimitofpluggedsteamgenerator tubesforunit1(SGTP),reference 30ofAttachment 5.TheanalysesincludedintheVantage5ReloadTransition SafetyReportforCookNuclearPlantunit2,revision1,March1990(RTSR)generally addressed twosituations, amixedcoreofAdvancedNuclearFuelandWestinghouse Vantage5fuelandacoreofallVantage5fuel.Operation withanallVantage5coresupported anoperating temperature windowandtheoptionofoperating attwoprimarypressures.
TheanalysesforthemixedcoreusedtheW-3DNBcorrelation fortheAdvancedNuclearFuel.UseoftheW-3correlation wasasignificant DNBpenalty.Toobtainacceptable resultsforamixedcore,thehightemperature sideofthetemperature windowwasrestricted toaTavgof576.0'Fandoperation waspermitted onlyatthehighnominalpressureof2250psia.Theselimitations aredocumented intheRTSR,reference 11ofAttachment 5.Operation ofunit2withallWestinghouse fuelwasapprovedbyreference 17ofAttachment 5.Changestosupportoperation inthefulltemperature windowandatbothoperating pressures areproposedinthissubmittal.
TheproposedT/SchangesincludeanewupperlimitonreactorcoolantsystemTavg.Theproposeddeparture fromnucleateboiling(DNB)uppertemperature limitwascalculated fromtheupperlimitofthetemperature windowforafullVantage5coreatacorepowerof3588MWt.TheDNBtemperature limitisobtainedbyaddingthecontroller allowance tothehighnominalTavgusedintheanalysisandthensubtracting thereadability allowance.
ThehighnominalTavgis581.3'Fandthecontroller allowance is4,14F.ThesevaluesarefoundinTable3.3-1andSection3.3.3.1ofWCAP14489,respectively.
Thereadability allowance, calculated byAEPSC,is2.1~F.Theresulting DNBtemperature limitis583.34F.TheproposedchangesincludeaddingtheDNBpressurelimitforlowpressureoperation.
TheDNBpressurelimitisobtainedbysubtracting thetotalpressureallowance usedintheanalysisfromthenominaloperating pressureusedintheanalysisandthenaddingthereadability allowance.
Thenominalpressures andthetotalallowance arefoundinSection3.3.1and3.3.3.1ofWCAP14489,respectively.
Thereadability allowance, calculated byAEPSC,is18.9psi.Thepressurelimitcurrently intheT/Ssforhighpressureoperation isconservatively higherthanthecalculated valueof2191psig.Theproposedlimitof2050'psig for'lowpressureoperation isanaddition.
Itisconservatively higherthanthecalculated valueof2041psig,Theproposedvalueforthelowpressurelimitisthesameastheunit1limit.  


Attachment1toAEP:NRC:1223Page9Otherlimitationsofthetransitionanalysisaffecttheengineeredsafetyfeaturesactuationsetpoints.Atthetimeofthefueltransition,thereanalysisofSMSEoutsidecontainmentforreratingandreducedtemperature/reducedpressureoperationwasnotcomplete.TheevaluationofthethenapplicableanalysisassumedanNSSSpowerof3425MWtandalowsteamlinepressuresetpointnolowerthan520psig.ThislimitationisdocumentedinRTSR,referencellofAttachment5.TherevisedSMGEreleaseanalysisoutsidecontainmentneededtosupportthereductioninsafeguardsactuationsetpointonlowsteamlinepressurewassubmittedinsupportofourproposaltolowertheboronconcentrationintheboroninjectiontank(BIT),reference24ofAttachment5.AsdiscussedinAttachment5,thisproposalwasapprovedbyreference25ofAttachment5.ThenewSM&Einsidecontainment,whichwassubmittedwiththeunit1increasedSGTPProgram,andthecoreresponsesteamlineandfeedwaterlinebreakssubmittedwiththeRTSRalsosupporttheproposaltolowertheengineeredsafetyfeaturessetpointonlowsecondarypressureanditsassociatedallowablevalue.EvaluationsofthecoreresponseanalysesarediscussedinSections3.3.4.6and3.3.4.7ofWCAP14489.TheRTSR,itsassociatedsubmittalandapprovalarereferences11,13,and17ofAttachment5.TheSGTPsubmittalwasaddressedinthecoverlettertothissubmittalandisreference30toAttachment5.Aspartofthe"ReratingProgram",anevaluationofmargintosafetyinjectiononturbine/reactortriptransientswasperformed.Forunit2operatingatTavgabove570'Fandatthelownominalpressure,itwasdeterminedthatitwouldbenecessarytoreducethesafetyinjectionactuationsetpointonlowpressurizerpressure.Sincethischangeisassociatedwithoperationatthelowerof'thetwoanalyzedprimarypressures,theproposaltolowerthissetpointanditsassociatedallowablevaluewasincludedinthisgroupofchanges.TheevaluationsthatsupportloweringthesafetyinjectionactuationsetpointonlowpressurizerpressurearedocumentedinSections3.3.4.5and3.3.4.6ofWCAP14489.Otheranalysesaffectedbysafetyinjectiononlowpressurizerpressureassumedasetpointsufficientlylowtoaccommodatetheloweredsetpoint.Theproposedchangesdeletethelowtemperaturelimitthatcurrentlyappearsintheunit2DNBspecification.Thisproposalisincludedwiththetransitiongroup(Group4)becausethelowtemperaturelimitisrelatedtotheanalyzedtemperaturewindow.TheproposedchangeconvertstheDNBspecificationbacktoapurelyDNBspecification.ThisisconsistentwithboththenewandoldstandardT/S,NUREG-1431,Rev.1andNUREG-0452,Rev4,respectively.Theproposalwillalsomaketheunit1andunit2T/Ssmorenearlyalike.Thecyclespecificneutronicsdesignimposestemperaturelimitsthataremorerestrictivethaneither
Attachment 1toAEP:NRC:1223 Page9Otherlimitations ofthetransition analysisaffecttheengineered safetyfeaturesactuation setpoints.
Atthetimeofthefueltransition, thereanalysis ofSMSEoutsidecontainment forreratingandreducedtemperature/reduced pressureoperation wasnotcomplete.
Theevaluation ofthethenapplicable analysisassumedanNSSSpowerof3425MWtandalowsteamlinepressuresetpointnolowerthan520psig.Thislimitation isdocumented inRTSR,reference llofAttachment 5.TherevisedSMGEreleaseanalysisoutsidecontainment neededtosupportthereduction insafeguards actuation setpointonlowsteamlinepressurewassubmitted insupportofourproposaltolowertheboronconcentration intheboroninjection tank(BIT),reference 24ofAttachment 5.Asdiscussed inAttachment 5,thisproposalwasapprovedbyreference 25ofAttachment 5.ThenewSM&Einsidecontainment, whichwassubmitted withtheunit1increased SGTPProgram,andthecoreresponsesteamlineandfeedwater linebreakssubmitted withtheRTSRalsosupporttheproposaltolowertheengineered safetyfeaturessetpointonlowsecondary pressureanditsassociated allowable value.Evaluations ofthecoreresponseanalysesarediscussed inSections3.3.4.6and3.3.4.7ofWCAP14489.TheRTSR,itsassociated submittal andapprovalarereferences 11,13,and17ofAttachment 5.TheSGTPsubmittal wasaddressed inthecoverlettertothissubmittal andisreference 30toAttachment 5.Aspartofthe"Rerating Program",
anevaluation ofmargintosafetyinjection onturbine/reactor triptransients wasperformed.
Forunit2operating atTavgabove570'Fandatthelownominalpressure, itwasdetermined thatitwouldbenecessary toreducethesafetyinjection actuation setpointonlowpressurizer pressure.
Sincethischangeisassociated withoperation atthelowerof'thetwoanalyzedprimarypressures, theproposaltolowerthissetpointanditsassociated allowable valuewasincludedinthisgroupofchanges.Theevaluations thatsupportloweringthesafetyinjection actuation setpointonlowpressurizer pressurearedocumented inSections3.3.4.5and3.3.4.6ofWCAP14489.Otheranalysesaffectedbysafetyinjection onlowpressurizer pressureassumedasetpointsufficiently lowtoaccommodate theloweredsetpoint.
Theproposedchangesdeletethelowtemperature limitthatcurrently appearsintheunit2DNBspecification.
Thisproposalisincludedwiththetransition group(Group4)becausethelowtemperature limitisrelatedtotheanalyzedtemperature window.TheproposedchangeconvertstheDNBspecification backtoapurelyDNBspecification.
Thisisconsistent withboththenewandoldstandardT/S,NUREG-1431, Rev.1andNUREG-0452, Rev4,respectively.
Theproposalwillalsomaketheunit1andunit2T/Ssmorenearlyalike.Thecyclespecificneutronics designimposestemperature limitsthataremorerestrictive thaneither


Attachment1toAEP:NRC:1223Page10theDNBlimitorthelowtemperaturelimitproposedforremoval.Compliancewiththecyclespecifictemperaturelimitsiscontrolledadministratively.TheotherchangesinthisgrouparetheremovalofreferencestoAdvancedNuclearFuel.ThereferencestoAdvancedNuclearFuelarenotneededbecauseunit2coresarenowallWestinghouseVantage5fuel.Group5:ChangesProposedforBothUnitsThisgroupofproposedchangesisfoundinthefollowingT/S's:AddFootnotetoPressurizerSafetyLCORequiring1/asLeftTolerance3.4.23.4.3ChangePeakContainmentPressuretoReflectNewAnalysis,BothunitsB3/4.6.1.4B3/46.1.5ChangeRequiredCondensateStorageContainedtoUseable.3.7.1.34.7.1.3.1B3/4.7.1.3TankfromGroup5proposeschangesapplicabletobothunits.Thesechangesareinthreecategories.Thefirstproposesafootnoterequiringtheaslefttoleranceofthepressurizersafetyvalvetolerancebe.1X.Thisrequirementisconsistentwithasimilarrequirementapprovedforthemainsteamsafetyvalves.ItisbeingsubmittedforbothunitsbecauseitwasinadvertentlyomittedinoursubmittalAEP:NRC:1207,datedMay26,1995,whichincludedtheanalyticaljustificationforanincreaseinpressurizersafetyvalvesetpointtoleranceforunitl.ThesecondchangeinthisgroupaffectstheT/Sbases.Thepeakpressureofthelongtermcontainmentintegrityanalysisisnowbeingreportedasbeingbelowthelimitof12psiginsteadofreportingthespecificvaluecalculatedintheanalysis.ThenewanalysisreportedinWCAP14489,Attachment6,boundsbothunitsatacorepowerof3588MWt.TheproposedchangetotheT/Sbasesboundsthevaluecalculatedinthenewanalysis.ThethirdproposalchangesthecontainedvolumeofthecondensatestoragetanktouseablevolumeinTechnicalSpecifications3.7.1.3and4'.1.3.1.TheproposedBasisSection3/4.7.1.3is
Attachment 1toAEP:NRC:1223 Page10theDNBlimitorthelowtemperature limitproposedforremoval.Compliance withthecyclespecifictemperature limitsiscontrolled administratively.
Theotherchangesinthisgrouparetheremovalofreferences toAdvancedNuclearFuel.Thereferences toAdvancedNuclearFuelarenotneededbecauseunit2coresarenowallWestinghouse Vantage5fuel.Group5:ChangesProposedforBothUnitsThisgroupofproposedchangesisfoundinthefollowing T/S's:AddFootnotetoPressurizer SafetyLCORequiring 1/asLeftTolerance 3.4.23.4.3ChangePeakContainment PressuretoReflectNewAnalysis, BothunitsB3/4.6.1.4 B3/46.1.5ChangeRequiredCondensate StorageContained toUseable.3.7.1.34.7.1.3.1 B3/4.7.1.3 TankfromGroup5proposeschangesapplicable tobothunits.Thesechangesareinthreecategories.
Thefirstproposesafootnoterequiring theaslefttolerance ofthepressurizer safetyvalvetolerance be.1X.Thisrequirement isconsistent withasimilarrequirement approvedforthemainsteamsafetyvalves.Itisbeingsubmitted forbothunitsbecauseitwasinadvertently omittedinoursubmittal AEP:NRC:1207, datedMay26,1995,whichincludedtheanalytical justification foranincreaseinpressurizer safetyvalvesetpointtolerance forunitl.ThesecondchangeinthisgroupaffectstheT/Sbases.Thepeakpressureofthelongtermcontainment integrity analysisisnowbeingreportedasbeingbelowthelimitof12psiginsteadofreporting thespecificvaluecalculated intheanalysis.
ThenewanalysisreportedinWCAP14489,Attachment 6,boundsbothunitsatacorepowerof3588MWt.TheproposedchangetotheT/Sbasesboundsthevaluecalculated inthenewanalysis.
Thethirdproposalchangesthecontained volumeofthecondensate storagetanktouseablevolumeinTechnical Specifications 3.7.1.3and4'.1.3.1.TheproposedBasisSection3/4.7.1.3 is


Attachment1toAEP:NRC:1223Pagellalsorevisedtoaddresswhyuseablevolumeisappropriate.Duetothefactthatthezeroofthelevelinstrumentationislocatedatthecenterlineofthedischargepipe,abovethelevelforrequiredNPSH,alltheindicatedvolumeisuseable.Therefore,thereisnoneedtoaddressanyallowanceforwaternotuseable.Group6:Administ'rativeChangeThisgroupof,proposedchangesisfoundinthefollowingT/S's:RedefineDesignFlowtobe1/4ofReactorCoolantSystemTotalFlowRateTable2.2-1Thefinalgroupconsistsofanadministrativechange.TheproposalchangesthedesignflowfootnoteinTable2.2-1toareferencetoReactorCoolantSystemTotalFlowRateofSpecification3.2.5.Designflowis1/4ofReactorCoolantSystemTotalFlowRate.ThischangeensuresthatthereisonlyoneplaceintheT/S'stochangethisparameter.Theproposedchangehasnosubstantiveimpact.10CFR50.92SIGNIFICANTHAZARDSCONSIDERATIONANALYSIS10CFR50.92specifiesthattheholderofanoperatinglicenseorconstructionpermitofanuclearpowerfacilityparticipateindeterminingwhetherachangetotheT/S'sorlicenseinvolvesasignificanthazardsconsideration.PriortoimplementationofachangetotheT/S'sorlicense,theNuclearRegulatoryCommissionmustreviewandmakeafinaldetermination,pursuanttotheproceduresin10CFR50.91,thataproposedamendmentinvolvesnosignificanthazardsconsiderations.Tosatisfactorilycompletethereview,theproposedamendmentmustnot:l.involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3."involveasignificantreductioninamarginofsafety.Forthepurposeofperformingasignificanthazardsconsiderationanalysis,thesixgroupsofT/SandoperatinglicensechangesdiscussedunderDescriptionofChangescanbereducedtothreegroups.Inevaluatingsignificanthazards,thosechangessupportedbyanalyses,essentiallyallofthefirstfivegroups il'tI(Il' Attachment1toAEP:NRC:1223Page12ofproposedT/Sandoperatinglicense,willbeconsideredtogether.TheremovalofthelowtemperaturelimitfromtheDNBT/Sandtheadministrativechangewilleachbeconsideredseparately.DETERMINATIONOFNOSIGNIFICANTHAZARDSFORCHANGESBASEDONANALYSESANDEVALUATIONS[Groups1,2,3,4(exceptdeletionofDNBlowtemperaturelimit),and5(exceptcondensatestoragetankuseablevolume)]Criterion1Dotheproposedchangesinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated?No.Theanalysesperformedtosupportthefirstfivegroupsofproposedchangesdemonstratethatplantequipmentwilloperateacceptablyattheupratedconditionsandapplicableacceptancecriteriaaremet.TheproposedT/Sandoperatinglicensechangesdonotinvolvepostulatedinitiatorsforanalyzedevents;therefore,theprobabilityofaccidentscannot,beaffected.Theanalysesandevaluationsperformedallmetapplicableacceptancecriteria;therefore,theconsequencesofaccidentspreviouslyevaluatedareunaffected.Criterion2Dotheproposedchangescreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated?No.Thefirstgroupofproposedchangesincreasesthecorepoweratwhichunit2maybeoperated.Operationattheproposednewpowerhasbeenanalyzed.ThesecondgroupofchangesproposestoremovethepowerrestrictionwhentheHHSIcrosstiesareclosed.HHSIisanaccidentmitigator.Theproposedchangesinthisgrouparebasedonanewanalysisusinganimprovedmodel.Theanalysesperformedtosupportthethird,fourth,andfifthgroupsofproposedchangesaddressincreasesinoperatingmarginforaccidentmitigators,Nonewaccidentisinvolvedinthisproposal.
Attachment 1toAEP:NRC:1223 Pagellalsorevisedtoaddresswhyuseablevolumeisappropriate.
0 Attachment1toAEP:NRC:1223Page13Criterion3Dotheproposedchangesinvolveasignificantreductioninamarginofsafety2No.Themarginofsafetyisprovidedfortheprimarypressureboundaryandothercomponentsinpartbyapplicabledesigncodes.Themarginofsafetyforthevariousaccidentsandtransientsismaintainedbytheanalysisacceptancecriteria.BecausethecomponentsremainincompliancewiththecodesandstandardsineffectwhenCookNuclearPlantwaslicensedandapplicableacceptancecriteriaaremet,themarginofsafetyisnotreducedbytheproposalsinthisunit2uprateprogram.DETERMINATIONOFNOSIGNIFICANTHAZARDSFORDELETIONOFTHELOWTEMPERATURELIMITFROMTHEDNBTECHNICALSPECIFICATION(WithinGroup4)Criterion1Dotheproposedchangesinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated'o.TheproposaltodeletethelowtemperaturelimitfromtheDNBT/Schangedoesnotinvolveaphysicalchangetotheplant.Theproceduresandadministrativecontrolsfortheplantdescribedabovewilleitherremaininplaceorbereplacedbycontrolsofcomparableeffectiveness.Therefore,theproposedT/Schangewillnotresultinasignificantincreaseintheprobabilityorconsequencesofanyaccidentpreviouslyanalyzed.Criterion2Dotheproposedchangescreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated?No.TheproposedchangetotheDNBT/Sdoesnotinvolveaphysicalchangetotheplant.Theproceduresandadministrativecontrolsfortheplantdescribedabovewilleitherremaininplaceorbereplacedbycontrolsofcomparableeffectiveness.Therefore,theproposedchangewillnotcreatethepossibilityofanewordifferentaccidentfromanypreviouslyevaluated.rCriterion3Dotheproposedchangesinvolveasignificantreductioninamarginofsafety'o.TheproposedchangetotheDNBT/Sdoesnotinvolveaphysicalchangetotheplant.Theproceduresandadministrative Attachment1toAEP:NRC:1223Page14controlsfortheplantdescribedabovewilleitherremaininplaceorbereplacedbycontrolsofcomparableeffectiveness.Therefore,theproposedT/Schangewillnotinvolveasignificant,reductioninanymarginofsafety.DETERMINATIONOFNOSIGNIFICANTHAZARDSFORADMINISTRATIVECHANGES[Group5(CondensateStorageTankUseableVolumeonly)andGroup6)Criterion1DoestheproposedchangeinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluatedfNo.TheproposedchangesinvolvereferencinganotherT/Sratherthanincorporatingaspecificvalueintoasecondspecificationandachangeinterminologyreflectingtheexistinginstrument.configuration.Thesechangesareforconvenienceandhavenosubstantiveimpact.Theseproposalshavenoimpactonprobability.Theproposedchangesalsohavenoimpactontheconsequencesofanaccidentbecausetheyhavenosubstantiveimpactonplantoperationoroperatinglimits.Criterion2Doestheproposedchangecreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated2No.Nothingischangedwithregardtoaccidentinitiators.Thereisnosubstantivechange;therefore,theproposedchangescanhavenoimpactonaccidentinitiators.Criterion3Doestheproposalinvolveasignificantreductioninamarginofsafety'o.Theproposaldoesnotchangeanyrequirements;therefore,thereisnochangeinthemarginofsafety.CONCLUSIONItisconcludedthatoperationofCookNuclearPlantunits1and2,withthechangesproposedabove,doesnotinvolveanysignificanthazardsconsiderationasdefinedin10CFR50.92.  
Duetothefactthatthezeroofthelevelinstrumentation islocatedatthecenterline ofthedischarge pipe,abovethelevelforrequiredNPSH,alltheindicated volumeisuseable.Therefore, thereisnoneedtoaddressanyallowance forwaternotuseable.Group6:Administ'rative ChangeThisgroupof,proposedchangesisfoundinthefollowing T/S's:RedefineDesignFlowtobe1/4ofReactorCoolantSystemTotalFlowRateTable2.2-1Thefinalgroupconsistsofanadministrative change.TheproposalchangesthedesignflowfootnoteinTable2.2-1toareference toReactorCoolantSystemTotalFlowRateofSpecification 3.2.5.Designflowis1/4ofReactorCoolantSystemTotalFlowRate.ThischangeensuresthatthereisonlyoneplaceintheT/S'stochangethisparameter.
Theproposedchangehasnosubstantive impact.10CFR50.92SIGNIFICANT HAZARDSCONSIDERATION ANALYSIS10CFR50.92specifies thattheholderofanoperating licenseorconstruction permitofanuclearpowerfacilityparticipate indetermining whetherachangetotheT/S'sorlicenseinvolvesasignificant hazardsconsideration.
Priortoimplementation ofachangetotheT/S'sorlicense,theNuclearRegulatory Commission mustreviewandmakeafinaldetermination, pursuanttotheprocedures in10CFR50.91,thataproposedamendment involvesnosignificant hazardsconsiderations.
Tosatisfactorily completethereview,theproposedamendment mustnot:l.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3."involveasignificant reduction inamarginofsafety.Forthepurposeofperforming asignificant hazardsconsideration
: analysis, thesixgroupsofT/Sandoperating licensechangesdiscussed underDescription ofChangescanbereducedtothreegroups.Inevaluating significant hazards,thosechangessupported byanalyses, essentially allofthefirstfivegroups il'tI(Il' Attachment 1toAEP:NRC:1223 Page12ofproposedT/Sandoperating license,willbeconsidered together.
Theremovalofthelowtemperature limitfromtheDNBT/Sandtheadministrative changewilleachbeconsidered separately.
DETERMINATION OFNOSIGNIFICANT HAZARDSFORCHANGESBASEDONANALYSESANDEVALUATIONS
[Groups1,2,3,4(exceptdeletionofDNBlowtemperature limit),and5(exceptcondensate storagetankuseablevolume)]Criterion 1Dotheproposedchangesinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated?
No.Theanalysesperformed tosupportthefirstfivegroupsofproposedchangesdemonstrate thatplantequipment willoperateacceptably attheupratedconditions andapplicable acceptance criteriaaremet.TheproposedT/Sandoperating licensechangesdonotinvolvepostulated initiators foranalyzedevents;therefore, theprobability ofaccidents cannot,beaffected.
Theanalysesandevaluations performed allmetapplicable acceptance criteria; therefore, theconsequences ofaccidents previously evaluated areunaffected.
Criterion 2Dotheproposedchangescreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated?
No.Thefirstgroupofproposedchangesincreases thecorepoweratwhichunit2maybeoperated.
Operation attheproposednewpowerhasbeenanalyzed.
Thesecondgroupofchangesproposestoremovethepowerrestriction whentheHHSIcrosstiesareclosed.HHSIisanaccidentmitigator.
Theproposedchangesinthisgrouparebasedonanewanalysisusinganimprovedmodel.Theanalysesperformed tosupportthethird,fourth,andfifthgroupsofproposedchangesaddressincreases inoperating marginforaccidentmitigators, Nonewaccidentisinvolvedinthisproposal.
0 Attachment 1toAEP:NRC:1223 Page13Criterion 3Dotheproposedchangesinvolveasignificant reduction inamarginofsafety2No.Themarginofsafetyisprovidedfortheprimarypressureboundaryandothercomponents inpartbyapplicable designcodes.Themarginofsafetyforthevariousaccidents andtransients ismaintained bytheanalysisacceptance criteria.
Becausethecomponents remainincompliance withthecodesandstandards ineffectwhenCookNuclearPlantwaslicensedandapplicable acceptance criteriaaremet,themarginofsafetyisnotreducedbytheproposals inthisunit2uprateprogram.DETERMINATION OFNOSIGNIFICANT HAZARDSFORDELETIONOFTHELOWTEMPERATURE LIMITFROMTHEDNBTECHNICAL SPECIFICATION (WithinGroup4)Criterion 1Dotheproposedchangesinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated'o.
Theproposaltodeletethelowtemperature limitfromtheDNBT/Schangedoesnotinvolveaphysicalchangetotheplant.Theprocedures andadministrative controlsfortheplantdescribed abovewilleitherremaininplaceorbereplacedbycontrolsofcomparable effectiveness.
Therefore, theproposedT/Schangewillnotresultinasignificant increaseintheprobability orconsequences ofanyaccidentpreviously analyzed.
Criterion 2Dotheproposedchangescreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated?
No.TheproposedchangetotheDNBT/Sdoesnotinvolveaphysicalchangetotheplant.Theprocedures andadministrative controlsfortheplantdescribed abovewilleitherremaininplaceorbereplacedbycontrolsofcomparable effectiveness.
Therefore, theproposedchangewillnotcreatethepossibility ofanewordifferent accidentfromanypreviously evaluated.
rCriterion 3Dotheproposedchangesinvolveasignificant reduction inamarginofsafety'o.
TheproposedchangetotheDNBT/Sdoesnotinvolveaphysicalchangetotheplant.Theprocedures andadministrative Attachment 1toAEP:NRC:1223 Page14controlsfortheplantdescribed abovewilleitherremaininplaceorbereplacedbycontrolsofcomparable effectiveness.
Therefore, theproposedT/Schangewillnotinvolveasignificant, reduction inanymarginofsafety.DETERMINATION OFNOSIGNIFICANT HAZARDSFORADMINISTRATIVE CHANGES[Group5(Condensate StorageTankUseableVolumeonly)andGroup6)Criterion 1Doestheproposedchangeinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluatedf No.Theproposedchangesinvolvereferencing anotherT/Sratherthanincorporating aspecificvalueintoasecondspecification andachangeinterminology reflecting theexistinginstrument.
configuration.
Thesechangesareforconvenience andhavenosubstantive impact.Theseproposals havenoimpactonprobability.
Theproposedchangesalsohavenoimpactontheconsequences ofanaccidentbecausetheyhavenosubstantive impactonplantoperation oroperating limits.Criterion 2Doestheproposedchangecreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated2 No.Nothingischangedwithregardtoaccidentinitiators.
Thereisnosubstantive change;therefore, theproposedchangescanhavenoimpactonaccidentinitiators.
Criterion 3Doestheproposalinvolveasignificant reduction inamarginofsafety'o.
Theproposaldoesnotchangeanyrequirements; therefore, thereisnochangeinthemarginofsafety.CONCLUSION Itisconcluded thatoperation ofCookNuclearPlantunits1and2,withthechangesproposedabove,doesnotinvolveanysignificant hazardsconsideration asdefinedin10CFR50.92.  


ATTACHMENT2TOAEP:NRC:1223PROPOSEDREVISEDTECHNICALSPECIFICATIONPAGES f}}
ATTACHMENT 2TOAEP:NRC:1223PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES f}}

Revision as of 06:17, 29 June 2018

Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl
ML17334B594
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/11/1996
From: FITZPATRICK E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A496 List:
References
AEP:NRC:1223, NUDOCS 9607150008
Download: ML17334B594 (34)
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Text

SUBJECT:

ForwardsTS,supporting operation ofplantatincreased coreratedthermalpowerof3588MWt.DISTRIBUTION CODE:00010COPIESRECEIVED:LTR (ENCL(SIZE:2ITITLE:ORSubmittal:

GeneralDistr'.'bution NOTES:RECIPIENT COPIESCOPIESIDCODE/NAME LTTRENCLLTTRENCLPD3-1LA1111HICKMAN,J 11RECIPIENT IDCODE/NAME PD3-1PDCATEGORYj.REGULATOINFORMATION DISTRIBUTION YSTEM(RIDS)ACCESSION'NBR:9607150008

'OC.DATE:

96/07/11NOTARIZED:

YESDOCKETFACIL:50-315 Donald'C.

CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.

IndianaMichiganPower-Co.(formerly IndianaaMichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)0INTERNAL:

FILECDRCH/HICB NRR/DSSA/SRXB OGC/HDS2EXTERNAL:

NOAC1111111011NRCPDR11NRR/DE/EMCB 11NRR/DSSA/SPLB 11NUDOCS-ABSTRACT 11D0UNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.

415-2083)

TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!tTOTALNUMBEROFCOPIESREQUIRED:

LTTR12ENCL11 I

AmericanElectric~r 1RiversidePlaza

~Columbus, OH4321523736142231000July11,1996DocketNos.50-31550-316AEP:NRC:1223 U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen:

DONALDC.COOKNUCLEARPLANTUNITS1AND2LICENSENOS.DPR-58ANDDPR-74PROPOSEDLICENSEANDTECHNICAL SPECIFICATION CHANGESSUPPORTED BYANALYSESTOINCREASEUNIT2RATEDTHERMALPOWERANDCERTAINPROPOSEDCHANGESFORUNIT1SUPPORTED BYRELATEDANALYSESThisletteranditsattachments constitute anapplication foramendment oftheDonaldC.CookNuclearPlantunit2facilityoperating license,foramendment oftheDonaldC.CookNuclearPlantunit2technical specificat:ions (T/S),andforsomerelatedchangestotheunit1technical specifications.

Changesareproposedprimarily tosupportoperation ofCookNuclearPlantunit2at:anincreased coreratedthermalpowerof3588MWt.Inaddition, analysesandevaluations havebeenperformed tosupportincreased operating marginsforunit2.ChangestotheT/Ssbasedonthoseanalysesandevaluations areproposed.

Someoftheproposedchangesareproposedforbothunit1andunit2.Thesmallbreaklossofcoolantaccidentanalysis, whichissubmitted withthisletter,wasperformed usingnewWestinghouse ElectricCorporation models.Thesemodelsemploynewmethodsformodelingsafetyinjection tothebrokenloopandanimprovedsteamcondensation model.Thesemodelsweresubmitted forNRCreviewbyWestinghouse ElectricCorporation underaletterdatedDecember14,1994,identified asNTD-NRC-94-4278, totheDocumentControlDeskfromN.J.Liparulo.

Tobeimplemented, thissubmittal requirestheapprovalofprevioussubmittals.

Thefirstoftheseisidentified asAEP:NRC:1207.

Itproposes"Technical Specificat:ion ChangesSupported byAnalysestoIncreaseUnit1SteamGenerator Tube96071500081I960711PDRADOCK<"050003f5tPPDR' U.S.NuclearRegulatory Commission Page2AEP:NRC:1223 PluggingLimitandCertainProposedChangesforUnit2Supported byAnalyses."

The'submittal isdatedMay26,1995,fromE.E.Fitzpatrick totheUSNRCDocumentControlDesk.AEP:NRC:1207 includesthemostrecentsteamlinemassandenergyreleasetocontainment analysiswhichboundsbothunitsatacorepowerof3588MWt.Thatanalysis, inpart,providessupportfortheproposaltouprateunit2toacorepowerof3588MWt.Adescription oftheproposedchangesandananalysisconcerning significant hazardsconsideration pursuantto10CFR50.92iscontained inAttachment 1.Attachment 2containstheproposed, revisedT/Spages.Attachment 3containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 4isasummarydescription oftheproposedT/Schanges.Itcontainsabriefsummaryofeachproposedchangeanddirectsthereviewertothesupporting documentation.

Attachment 5isadiscussion ofearlierrelatedsubmittals.

Theanalysesdescribed intheearliersubmittals supportfutureoperation attheproposed, increased ratedthermalpower.Theseanalyses, togetherwithevaluations andanalysesdescribed intheattachments tothissubmittal, providethenecessary supportfortheproposedincreaseinratedthermalpower.Attachment 5alsoaddresses previously submitted analysesforunit1thatsupporttheproposedchangestobothunits.Attachment 6isadescription ofanalysesperformed byWestinghouse ElectricCorporation tosupportthepoweruprateofCookNuclearPlantunit2.Attachment 7describes theeffectoftheproposedupratedpoweronbalanceofplantsystemsandtheresultofmiscellaneous safetyevaluations.

Plantradiation protection featuresaredesignedtolimittheradiation exposuretoplantpersonnel andthegeneralpublicto10CFR20limitsundernormalconditions.

Whilecertainisotopesarepresentingreaterconcentration inthefuelgapduetotheupratedpowerlevel,theactualincreases inoccupational doseareexpectedtobeminimal.Thefuelhasbeendesignedtooperateatthehigherpowerlevelwithoutanydamage,whichwouldnegateanyincreases inradioactivity trappedwithinanintactfuelrod.Also,ourtechnical specifications limittheconcentration ofradioactivity withinthereactorcoolantsystem(seeT/S3.4.8).Nevertheless, accidentoffsitedoseshavebeenrecalculated basedontheupratedsourcetermandotheranalysisassumptions usedintheUpratingProgram.Insomecases,theresulting thyroidoffsitedoseconsequences increaseslightlyabovethevaluespresently intheUFSAR.Thenewcalculated wholebodydosesareboundedbytheUFSARvalues.Forbothtypesofcalculations, thechangesintheoffsiteradiation doseforeachaccidentarenotsignificant andarewithintheacceptance criteriaasdefinedin10CFR100~

U.S.NuclearRegulatory Commission Page3AEP:NRC:1223 Becausesystemsandprocedures controlling normalradioactive releasesarebasedonlimitingplanteffluents toasmallfractionofregulatory limits,theproposedupratingofunit2willnotexceed10CFR20or10CFR100limits'ased onthisinformation, therewillbenosignificant increaseinthetypesoramountsofeffluents thatmaybereleasedoffsiteandnosignificant increaseinindividual orcumulative occupational radiation exposure.

Someofthechangesproposedforunit2arealsoproposedforunit1.Thefirstproposestwofootnotes thatrequiretheasleftmagnitude ofthepressurizer safetyvalvetolerance be1X.ThesecondaffectstheTechnical Specification Basesforcontainment internalpressureandairtemperature.

Thefinalchangeaffecting bothunitsinvolvesaclarification oftherequiredvolumeforthecondensate storagetank.Ourfinalreviewoftwoissuesremainsincomplete atthistime.Theseissuesare(1)theimpactofpoweruprateonblowdownforcesonductingandcabletraysinthecontainment and(2)theresidualheatremovalcooldowncapability.

Weanticipate thefinalreviewswillshowthattheseissuescanbesafelyaddressed andwillnotadversely impactoperation andlicensing ofunit2atanupratedcorepowerlevelof3588MWt.Uponresolution oftheseissues,wewillnotifytheNRCstaffoftheresults.Approvalofthechangesinthissubmittal isneededbyAugust1,1997,tosupportunit2,cycle12operation.

WebelievetheproposedT/Schangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountofeffluentthatmightbereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

TheseproposedT/SchangeshavebeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee.

Incompliance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.Sincerely, p~E.E.Fitzpatrick VicePresident THISQ~DAYOF1996NotaryPublicMyCommission Expires:~Q-'~

SWORNTOANDSUBSCRIBED BEFOREME U.S.NuclearRegulatory Commission Page4AEP:NRC:1223 Attachments cc:A.A.BlindH.J.MillerNFEMSectionChiefNRCResidentInspector

-BridgmanJ.R.Padgett U.S.NuclearRegulatory Commission Page5AEP:NRC:1223 bc:S.J.Brewer/D.

H.Malin/M.S.AckermanJ.A.Kobyra/K.

R.Baker/D.R.HaferJ.B.Kingseed/V.

D.Vanderburg/S.

L.Colvisw/attachments D.F.Powell/S.

K.Farlow/D.

P.SchmaderB.B.Bradley-w/attachments (exceptattachment 6)J.B.ShinnockJ.S.WiebeJ.B.Hickman,NRC-Washington, D.C.-w/attachments M.E.Eberhardt

-w/attachments (exceptattachment 6)M.E.Barfelz-w/attachments (exceptattachment 6)G.P.Arent-w/attachments PRONET-w/attachment DC-N-6015.1

-ATTACHMENT 1TOAEP:NRC:1223REASONSAND10CFR50.92 ANALYSISFORCHANGESTOTHECOOKNUCLEARPLANTUNITNO.2LICENSEANDTECHNICAL SPECIFICATIONS ANDCOOKNUCLEARPLANTUNITNO~1TECHNICAL SPECIFICATIONS 96P715PPPS Attachment 1toAEP:NRC:1223 Page1INTRODUCTION Theprimarypurposeofthissubmittal istorequestapprovaltooperateCookNuclearPlantunit2atanupratedcoreratedthermalpowerof3588MWt.Theanalysesneededtosupportthisrequestincludereanalysis, evaluation, orreviewoftheeventsdiscussed inChapter14oftheUpdatedFinalSafetyAnalysisReport(UFSAR)andtheevaluation ofthecapability ofvarioussystemsandcomponents.

Asdiscussed inAttachment 5,Discussion ofPreviousRelatedSubmissions, previously submitted analysesforCookNuclearPlantunit2were,forthemostpart,performed ataratedthermalpowerof3588MWt.Thiswasdonetopositionunit2foroperation atanupratedpower.Asdiscussed inAttachment 6,WCAP14489,thepreviously analyzedeventswerereviewedtoensurethatnoevaluations wereperformed oranyothereventhadoccurredthatwouldinvalidate theanalyzedcorepower.Eventspreviously analyzedatacorepowerlowerthan3588MWtwerereanalyzed orpowersensitivity casesruntosupporttheproposedupratedpower.AnalysesinthiscategoryareLOCAcontainment integrity

analysis, largebreakLOCAwithresidualheatremoval(RHR)crossties closed,andsmallbreakLOCAwithhighheadsafetyinjection (HHSI)crossties closed.Theeffectofoperation attheupratedcorepoweronNSSSsystemsandcomponents isalsoaddressed inAttachment 6andtheeffectonbalanceofplantsystemsisaddressed inAttachment 7.Miscellaneous safetyevaluations havebeenincludedinAttachment 7.Becausetheworkneededtosupporttheproposedincreaseincorepowerinvolvedreanalysis orreviewoftheeventsdiscussed inChapter14oftheUFSAR,analysesandevaluations wereperformed sothatadditional operating margincouldbeachievedinsomeareas.Thissubmittal containsproposals basedontheseanalysesandevaluations.

Furthermore, thecurrently approvedunit2technical specifications (T/Ss)arebasedonanalysesforamixedcoreofWestinghouse Vantage5andAdvancedNuclearFuel.BecausetheCookNuclearPlantunit2corenowconsiststotallyofWestinghouse Vantage5fuel,thepenalties associated withthemixedcoreanalysisarenolongerappropriate.

Therefore, anumberofchangesrelatedtothecompletion ofthetransition toafullVantage5coreareproposedinthissubmission.

AfewoftheproposedchangestotheT/Ssareapplicable tobothunits.ThesechangesrelatetotheLOCAcontainment integrity analysisthatboundsbothunitsandthecorrection ofanomissionintheproposedunit1T/Ssforrelaxedpressurizer safetyvalveliftpoint tolerance.

Theunit1submission wasmadeinAEP:NRC:1207, datedMay26,1995.Thecorresponding proposalforunit2isincludedinthegroupofchangesproposedtoincrease lili Attachment 1toAEP:NRC:1223 Page2unit2operating margin.Itisapartofthissubmission.

Also,thedescription oftherequiredvolumeofthecondensate storagetankhasbeenchangedfrom"contained" to"useable".

Finally,anadministrative changeisproposed.

InTable2.2-1,thedesignflowhasbeenredefined asafractionofthereactorcoolantsystemtotalflowrate.Theadministrative changeisdiscussed inmoredetailundertheheadingforGroup6.Theproposedchangesarediscussed ingreaterdetailbelowandinAttachment 4,SummaryDescription ofProposedUnit2PowerUprateTechnical Specifications.

Attachment 4isprovidedtoassistthereviewer.

Itcontainsabriefsummaryofeachchangeanddirectsthereviewertothesupporting documentation.

Attachment 2containstheproposedT/Schanges.Attachment 3containsthecurrentT/Spagesmarkedtoreflecttheproposedchanges.ThesummaryinAttachment 4providesabriefdescription ofeachproposedchangeandacrossreference tospecificanalyseswhereappropriate.

Thechangeincorepowerdependsonthefactthatallanalysesneededtosupporttheupratedcorepowerhavebeencompleted attheupratedpower;therefore, thereferences providedinAttachment 4aregeneralinnature.DESCRIPTION ORCHANGESTheproposedchangesarediscussed inrelatedgroups.Groupl:ChangesDirectlyRelatedtoIncreased RatedThermalPowerTheGroupIproposedchangesarefoundintheoperating licenseandtheT/Sslistedbelow:Operating LicenseSection2.C(l)currently states,"IndianaandMichiganElectricCompanyisauthorized tooperatethefacilityatsteadystatereactorcorepowerlevelsnotinexcessof3411megawatts thermalinaccordance withtheconditions specified hereinandinAttachment 1tothislicense."

Iftheproposaltoincreasecoreratedthermalpowerisapproved, thestatement needstobechangedto,"IndianaandMichiganElectricCompanyisauthorized tooperatethefacilityatsteadystatereactorcorepowerlevelsnotinexcessof3588megawatts thermalinaccordance withtheconditions specified hereinandinAttachment 1tothislicense."

Attachment 1toAEP:NRC:1223 Page3Technical Specifications Increaseratedthermalpower1.3Reducetheapplicability oftheheatupandcooldowncurvesFigure3.4-2Figure3.4-3B3/4.4.9Lowerthemaximumallowable powerrangeneutronhighfluxsetpointwithinoperable steamlinesafetyvalvesTable3.7-1Thefirstgroupofthesechangesisdirectlyrelatedtotheproposedincreaseincoreratedthermalpower.TheanalysesthatsupporttheproposedupratingofCookNuclearPlantunit2havebeenperformed overaperiodofyearsinseveralcontexts.

Including thenewanalysesdescribed inAttachment 6(WCAP14489)andtheevaluations described inAttachment 7(BalanceofPlantEvaluations andMiscellaneous SafetyEvaluations),

allthenecessary analysesandevaluations havebeencompleted tosupportanuprateofunit2toacorepowerof3588MWt.Exceptforthesteammassandenergyreleasetocontainment submitted withsubmittal AEP:NRC:1207 (reference 30ofAttachment 5),thespentfuelpoolthermalhydraulic analysessubmitted withsubmittals AEP:NRC:1202 andAEP:NRC:1202A (asidentified inthecoverletter),andAttachments 6and7ofthissubmittal, alltheanalyseshavebeenpreviously submitted andreviewed.

Abriefhistoryofthedevelopment oftheanalysessupporting theupratedpowerisprovidedinAttachment 5.Itsummarizes thepreviousanalysesthatprovidepartofthesupportforupratedpowerandtheirassociated submittals.

Attachment 6,WCAP14489,describes themostrecentanalysesandsensitivity studies.Newanalyseshavebeenperformed toreplaceorsupplement thoseanalysesformerlyperformed atthecurrently approvedmaximumpowerlevel.Thenewanalysesyieldedacceptable resultsattheproposedupratedcorepowerasdescribed inAttachment 6.TheWestinghouse modelandtheplantinputassumptions werereviewedforthenewlongtermcontainment analysis.

Therevisedinputassumption withthegreatestimpactontheresultwasanewlyrevisedstructural heatsinkmodel.Theheatsinkmodelwascompletely revisedtoreconstruct itsbasis.Theanalysisperformed afterthisreviewwassatisfactory.

Attachment 1toAEP:NRC:1223 Page4ThelargebreakLOCA(LBLOCA)reanalysis withRHRcrosstiesclosedwasalsosatisfactory usingthecurrentmodel.Asdescribed inSection3.1.1.3ofWCAP14489,thenewreanalysis incorporates modelchangesthatresultedfromtheresolution ofissuesidentified inlOCFR50.46 reportsandinWestinghouse reportstotheNRC.Thesemodelchangeswereasignificant benefitto-aCookNuclearPlantunit2specificanalysis.

ThesmallbreakLOCA(SBLOCA)reanalysis alsowassatisfactory.

Asindicated inthecoverletterofthissubmittal, theSBLOCAreanalysis wasperformed usingtheimprovedsteamcondensation modelthatresultsinasignificant benefittoaCookNuclearPlantunit2specificanalysis.

Thisnewanalysissupportsourproposal, described inGroup2,todeletetherequirement inEmergency CoreCoolingSystemTechnical Specification thatpowerbereducedwhentheHHSIcrossties areclosed.Attachment 6alsosummarizes analysesandevaluations previously performed byWestinghouse ElectricCorporation tosupporttheupratedcorepowerforunit2.Section2.0ofWCAP14489references theearlierwork.Theevaluations described inWCAP14489arebasedontheseearlieranalyses.

Theearlieranalysesaredescribed inReratingProgramWCAP's11902and11902Supplement 1,references 3and10ofAttachment 5,'ndintheVantage5ReloadTransition SafetyReportforDonaldC.CookNuclearPlantUnit2,Revision1,March1990(RTSR),reference llofAttachment 5.TheSteamGenerator TubePluggingProgramsteamline massandenergyrelease(SGTPSM&E)tocontainment analysisisdescribed inWCAP14285,reference 29ofAttachment 5.WCAP11902anditssupplement arereferredtoasthe"Rerating Program"inWCAP14489.Thereloadtransition safetyreportisreferredtoas"RTSR"inWCAP14489.Theincreaseinthepermitted levelofsteamgenerator tubepluggingprogramisreferredtoas"SGTPProgram"inWCAP14489.Attachment 6,togetherwithearlierworkreferenced inAttachments 5and6,andAttachment 7supporttheupratedcorepowerforunit2.Group2:ChangetoRemovePowerRestriction forHighHeadSafetyInjection CrossTiesClosedOperation Thisgroupofproposedchangesisfoundinthefollowing T/Ss:Deletepowerreduction requirement whenthehighheadsafetyinjection crosstiesareclosed3.5.2B3/4.5.2andB3/4.5.3ThesecondgroupofchangesconsistsofasinglechangetoT/S3.5.2,Emergency CoreCoolingSystems.Thecurrently approvedLimitingCondition forOperation (LCO)requiresthat"allsafety

Attachment 1toAEP:NRC:1223 Page5injection cross-tie valves(be)open."Ifahighheadsafetyinjection cross-tie valveisclosed,theACTIONstatements mustbeenteredandthecorepowerreducedto3250MWt.Theproposedchangedeletestheserequirements.

Thecurrently approvedrestriction inpowerwithsafetyinjection cross-ties closedistheresultoftheSBLOCAanalysisperformed insupportofrelaxingthemainsteamsafetyvalve(MSSV)setpointtolerance.

TheMSSVsubmittal andtheassociated SERarereferences 26and28ofAttachment 5,respectively.

TheapprovedWestinghouse SBLOCAmodelatthetimeoftheMSSVsubmittal requiredapowerreduction togetanacceptable result.Forthispowerupratingprogram,animprovedSBLOCAmodelincorporating theCOSIcondensation modelwasused.Theresultswereacceptable attheproposedupratedcorepowerof3588MWt.TheMSSVanalysisandthenewanalysiswiththeCOSIcondensation modelarediscussed inmoredetailinSections3.1.2.3and3.1.2.4ofWCAP14489,Attachment 6.Thecoverlettertothissubmittal addresses thefactthattheSBLOCAanalysiswasperformed usingthenew,improvedmodelandprovidesareference totheWestinghouse submittal forthenewmodel.Group3:ChangesProposedtoIncreaseUnitZOperating HarginThisgroupofproposedchangesarefoundinthefollowing T/S:ReviseSafetyLimitsandOPhT/OThT ReactorTripSetpointFigure2.1-1Table2.2-1B2'.1Overpower DeltaTIncreaseUnit1Pressurizer SafetyValveTolerance 3.4.23.4.3Thethirdgroupofchangesresultsfromanalysesandevaluations designedtoincreaseoperating margin.Becausemostoftheeventsdescribed inChapter14oftheUFSARhadtobereanalyzed, evaluated, orreviewedtoensurecurrencyinordertosupporttheincreaseincoreratedthermalpower,theefforttoincreasesomemarginswasperformed atthesametime.Thefirstproposedchangesinthisgrouparechangestotheovertemperature deltaT(OThT)andoverpower deltaT(OPAT)reactortripsetpoints.

Thenewsetpoints arebasedoncorethermalsafetylimitsforanallVantage5coreat3588MWt.Thesafetylimitsarethosewhichwerecalculated foranallVantage5coreatthetimeoftransition fromAdvancedNuclearFueltoWestinghouse fuel.TheproposedsafetylimitscouldhavebeenincludedwiththechangeseitherinthisgrouporinGroup4 Attachment 1toAEP:NRC:1223 Page6below.They'reincludedhereinGroup3becauseoftheirrelationship.

totheproposedOT~TandOPaTreactortripsetpoints.

Asaresultoftemperature streaming inthereactorcoolanthotlegs,thereisaninaccuracy inthemeasurement ofTintheresistance temperature detector(RTD)bypasslines'his streaming isafunctionofthecorepowerdistribution.

DriftintheDeltaTmeasurements atfullpowerasafunctionofburnupresultsfromthisphenomenon.

Whenthedeviations exceedtheinstrument allowances forhotlegstreaming, itisnecessary torecalibrate theOT~TandOP~Tsystem.TheOTnTandOP~Treactortripfunctions provideprimaryprotection againstfuelcenterline melting,amongotherconcerns(e.g.,DNBandhot-legboiling).

RevisedOT~TandOP~Treactortripsetpoints fortheincreased reactorcorepowerof3588MWtwerecalculated toaccommodate anincreaseintheallowance betweenthesafetyanalysislimitsandthetechnical specification setpoints.

Thechangesproposedinthissubmittal arebaseduponanalysesperformed bybothusandourcontractor, Westinghouse ElectricCorporation.

Westinghouse performed calculations toensurethatthesafetyanalysisvaluesfort'eOT~TandOP~Tsetpoints providethenecessary protection withrespecttofuelcenterline melting,theapplicable corethermallimits,andthatacceptable resultsareobtainedfortheaffectedtransients.

Weperformed thecalculations toensureadequatemarginexistsbetweenthesafetyanalysisvaluesandtheT/SnominalvaluesoftheOT~TandOP~Treactortrip,setpoints.

Theassociated allowable valuesproposedfornotes3and4ofT/STable2.2-1inAttachments 2and3arebasedonourcalculations.

Thepressurizer safetyvalveliftpoint tolerance wasincreased to+3X.-Asindicated inSection3.3.2.2ofAttachment 6,theappropriate eventshavebeenshowntosupportthisincreased tolerance.

Theanalysesandevaluations described inWCAP14489,Attachment 6,supporttheproposedT/Schangestoincreaseoperating margindescribed above.

Attachment 1toAEP:NRC:1223 Page7Group4:ChangesRelatedtoTransition CoreorTransition toTemperature Window/Dual PressureTechnicalSpeciecationsThisgroupofproposedchangesisfoundinthefollowing T/Ss:IncreaseDNBTemperature Limit,IncludeLimitsforBothAnalyzedPressures, DeleteLowTemperature Limit3'.5B3/4.2.5ReduceSetpointandAllowable ValueforSIonLowPressurizer PressureTable3.3-4ReduceSetpointandAllowable ValueforSIonLowSteamline PressureTable3.3-4ReduceSetpointandAllowable ValueforSteamline Isolation onLowSteamline PressureTable3.3-4IncludePressureCriteriaforBothAnalyzed, NominalPressures 4.4.6.2.1 RemoveReferences toAdvancedNuclearFuelB2.1.1B3/4.2.2andB3/4.2.3Thefourthgroupofproposedchangesarechangesthatremoverestrictions relatedtooperation ofCookNuclearPlantunit2withamixedcoreofWestinghouse Vantage.5fuelandAdvancedNuclearFuel.ThefirstfullVantage5corewascycle10.Theproposedchangesareplannedforimplementation incycle12.Theproposals expandthetemperature windowtothatanalyzedforafullVantage5core,identifybothanalyzedpressures, changeengineered safetyfeaturesactuation setpoints, deletethelowtemperature limitfromtheDNBT/S,anddeletereferences toAdvancedNuclearFuelfromthebases.Exceptfortheproposaltolowerthesafetyinjection actuation setpointonlowpressurizer pressureandtheproposaltodeletethelowtemperature limitfromtheDNBT/S,theunderlying analysesfortheproposedchangesinthisgrouphavebeenreviewedandapprovedasapartofprevioussubmittals.

However,thesteammassandenergyrelease(SM&E)tocontainment analysisthatdirectlysupportsthesetpointforlowsteampressurewasrecentlyreanalyzed toboundbothunitsat,theunit2upratedpower.Thiswasdonetocorrectsomeinaccurate analysis Attachment 1toAEP:NRC:1223 Page8assumptions.

Asindicated in.thecoverletterandAttachment 5,thisnewanalysiswassubmitted aspartofourproposaltoincreasethelimitofpluggedsteamgenerator tubesforunit1(SGTP),reference 30ofAttachment 5.TheanalysesincludedintheVantage5ReloadTransition SafetyReportforCookNuclearPlantunit2,revision1,March1990(RTSR)generally addressed twosituations, amixedcoreofAdvancedNuclearFuelandWestinghouse Vantage5fuelandacoreofallVantage5fuel.Operation withanallVantage5coresupported anoperating temperature windowandtheoptionofoperating attwoprimarypressures.

TheanalysesforthemixedcoreusedtheW-3DNBcorrelation fortheAdvancedNuclearFuel.UseoftheW-3correlation wasasignificant DNBpenalty.Toobtainacceptable resultsforamixedcore,thehightemperature sideofthetemperature windowwasrestricted toaTavgof576.0'Fandoperation waspermitted onlyatthehighnominalpressureof2250psia.Theselimitations aredocumented intheRTSR,reference 11ofAttachment 5.Operation ofunit2withallWestinghouse fuelwasapprovedbyreference 17ofAttachment 5.Changestosupportoperation inthefulltemperature windowandatbothoperating pressures areproposedinthissubmittal.

TheproposedT/SchangesincludeanewupperlimitonreactorcoolantsystemTavg.Theproposeddeparture fromnucleateboiling(DNB)uppertemperature limitwascalculated fromtheupperlimitofthetemperature windowforafullVantage5coreatacorepowerof3588MWt.TheDNBtemperature limitisobtainedbyaddingthecontroller allowance tothehighnominalTavgusedintheanalysisandthensubtracting thereadability allowance.

ThehighnominalTavgis581.3'Fandthecontroller allowance is4,14F.ThesevaluesarefoundinTable3.3-1andSection3.3.3.1ofWCAP14489,respectively.

Thereadability allowance, calculated byAEPSC,is2.1~F.Theresulting DNBtemperature limitis583.34F.TheproposedchangesincludeaddingtheDNBpressurelimitforlowpressureoperation.

TheDNBpressurelimitisobtainedbysubtracting thetotalpressureallowance usedintheanalysisfromthenominaloperating pressureusedintheanalysisandthenaddingthereadability allowance.

Thenominalpressures andthetotalallowance arefoundinSection3.3.1and3.3.3.1ofWCAP14489,respectively.

Thereadability allowance, calculated byAEPSC,is18.9psi.Thepressurelimitcurrently intheT/Ssforhighpressureoperation isconservatively higherthanthecalculated valueof2191psig.Theproposedlimitof2050'psig for'lowpressureoperation isanaddition.

Itisconservatively higherthanthecalculated valueof2041psig,Theproposedvalueforthelowpressurelimitisthesameastheunit1limit.

Attachment 1toAEP:NRC:1223 Page9Otherlimitations ofthetransition analysisaffecttheengineered safetyfeaturesactuation setpoints.

Atthetimeofthefueltransition, thereanalysis ofSMSEoutsidecontainment forreratingandreducedtemperature/reduced pressureoperation wasnotcomplete.

Theevaluation ofthethenapplicable analysisassumedanNSSSpowerof3425MWtandalowsteamlinepressuresetpointnolowerthan520psig.Thislimitation isdocumented inRTSR,reference llofAttachment 5.TherevisedSMGEreleaseanalysisoutsidecontainment neededtosupportthereduction insafeguards actuation setpointonlowsteamlinepressurewassubmitted insupportofourproposaltolowertheboronconcentration intheboroninjection tank(BIT),reference 24ofAttachment 5.Asdiscussed inAttachment 5,thisproposalwasapprovedbyreference 25ofAttachment 5.ThenewSM&Einsidecontainment, whichwassubmitted withtheunit1increased SGTPProgram,andthecoreresponsesteamlineandfeedwater linebreakssubmitted withtheRTSRalsosupporttheproposaltolowertheengineered safetyfeaturessetpointonlowsecondary pressureanditsassociated allowable value.Evaluations ofthecoreresponseanalysesarediscussed inSections3.3.4.6and3.3.4.7ofWCAP14489.TheRTSR,itsassociated submittal andapprovalarereferences 11,13,and17ofAttachment 5.TheSGTPsubmittal wasaddressed inthecoverlettertothissubmittal andisreference 30toAttachment 5.Aspartofthe"Rerating Program",

anevaluation ofmargintosafetyinjection onturbine/reactor triptransients wasperformed.

Forunit2operating atTavgabove570'Fandatthelownominalpressure, itwasdetermined thatitwouldbenecessary toreducethesafetyinjection actuation setpointonlowpressurizer pressure.

Sincethischangeisassociated withoperation atthelowerof'thetwoanalyzedprimarypressures, theproposaltolowerthissetpointanditsassociated allowable valuewasincludedinthisgroupofchanges.Theevaluations thatsupportloweringthesafetyinjection actuation setpointonlowpressurizer pressurearedocumented inSections3.3.4.5and3.3.4.6ofWCAP14489.Otheranalysesaffectedbysafetyinjection onlowpressurizer pressureassumedasetpointsufficiently lowtoaccommodate theloweredsetpoint.

Theproposedchangesdeletethelowtemperature limitthatcurrently appearsintheunit2DNBspecification.

Thisproposalisincludedwiththetransition group(Group4)becausethelowtemperature limitisrelatedtotheanalyzedtemperature window.TheproposedchangeconvertstheDNBspecification backtoapurelyDNBspecification.

Thisisconsistent withboththenewandoldstandardT/S,NUREG-1431, Rev.1andNUREG-0452, Rev4,respectively.

Theproposalwillalsomaketheunit1andunit2T/Ssmorenearlyalike.Thecyclespecificneutronics designimposestemperature limitsthataremorerestrictive thaneither

Attachment 1toAEP:NRC:1223 Page10theDNBlimitorthelowtemperature limitproposedforremoval.Compliance withthecyclespecifictemperature limitsiscontrolled administratively.

Theotherchangesinthisgrouparetheremovalofreferences toAdvancedNuclearFuel.Thereferences toAdvancedNuclearFuelarenotneededbecauseunit2coresarenowallWestinghouse Vantage5fuel.Group5:ChangesProposedforBothUnitsThisgroupofproposedchangesisfoundinthefollowing T/S's:AddFootnotetoPressurizer SafetyLCORequiring 1/asLeftTolerance 3.4.23.4.3ChangePeakContainment PressuretoReflectNewAnalysis, BothunitsB3/4.6.1.4 B3/46.1.5ChangeRequiredCondensate StorageContained toUseable.3.7.1.34.7.1.3.1 B3/4.7.1.3 TankfromGroup5proposeschangesapplicable tobothunits.Thesechangesareinthreecategories.

Thefirstproposesafootnoterequiring theaslefttolerance ofthepressurizer safetyvalvetolerance be.1X.Thisrequirement isconsistent withasimilarrequirement approvedforthemainsteamsafetyvalves.Itisbeingsubmitted forbothunitsbecauseitwasinadvertently omittedinoursubmittal AEP:NRC:1207, datedMay26,1995,whichincludedtheanalytical justification foranincreaseinpressurizer safetyvalvesetpointtolerance forunitl.ThesecondchangeinthisgroupaffectstheT/Sbases.Thepeakpressureofthelongtermcontainment integrity analysisisnowbeingreportedasbeingbelowthelimitof12psiginsteadofreporting thespecificvaluecalculated intheanalysis.

ThenewanalysisreportedinWCAP14489,Attachment 6,boundsbothunitsatacorepowerof3588MWt.TheproposedchangetotheT/Sbasesboundsthevaluecalculated inthenewanalysis.

Thethirdproposalchangesthecontained volumeofthecondensate storagetanktouseablevolumeinTechnical Specifications 3.7.1.3and4'.1.3.1.TheproposedBasisSection3/4.7.1.3 is

Attachment 1toAEP:NRC:1223 Pagellalsorevisedtoaddresswhyuseablevolumeisappropriate.

Duetothefactthatthezeroofthelevelinstrumentation islocatedatthecenterline ofthedischarge pipe,abovethelevelforrequiredNPSH,alltheindicated volumeisuseable.Therefore, thereisnoneedtoaddressanyallowance forwaternotuseable.Group6:Administ'rative ChangeThisgroupof,proposedchangesisfoundinthefollowing T/S's:RedefineDesignFlowtobe1/4ofReactorCoolantSystemTotalFlowRateTable2.2-1Thefinalgroupconsistsofanadministrative change.TheproposalchangesthedesignflowfootnoteinTable2.2-1toareference toReactorCoolantSystemTotalFlowRateofSpecification 3.2.5.Designflowis1/4ofReactorCoolantSystemTotalFlowRate.ThischangeensuresthatthereisonlyoneplaceintheT/S'stochangethisparameter.

Theproposedchangehasnosubstantive impact.10CFR50.92SIGNIFICANT HAZARDSCONSIDERATION ANALYSIS10CFR50.92specifies thattheholderofanoperating licenseorconstruction permitofanuclearpowerfacilityparticipate indetermining whetherachangetotheT/S'sorlicenseinvolvesasignificant hazardsconsideration.

Priortoimplementation ofachangetotheT/S'sorlicense,theNuclearRegulatory Commission mustreviewandmakeafinaldetermination, pursuanttotheprocedures in10CFR50.91,thataproposedamendment involvesnosignificant hazardsconsiderations.

Tosatisfactorily completethereview,theproposedamendment mustnot:l.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3."involveasignificant reduction inamarginofsafety.Forthepurposeofperforming asignificant hazardsconsideration

analysis, thesixgroupsofT/Sandoperating licensechangesdiscussed underDescription ofChangescanbereducedtothreegroups.Inevaluating significant hazards,thosechangessupported byanalyses, essentially allofthefirstfivegroups il'tI(Il' Attachment 1toAEP:NRC:1223 Page12ofproposedT/Sandoperating license,willbeconsidered together.

Theremovalofthelowtemperature limitfromtheDNBT/Sandtheadministrative changewilleachbeconsidered separately.

DETERMINATION OFNOSIGNIFICANT HAZARDSFORCHANGESBASEDONANALYSESANDEVALUATIONS

[Groups1,2,3,4(exceptdeletionofDNBlowtemperature limit),and5(exceptcondensate storagetankuseablevolume)]Criterion 1Dotheproposedchangesinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated?

No.Theanalysesperformed tosupportthefirstfivegroupsofproposedchangesdemonstrate thatplantequipment willoperateacceptably attheupratedconditions andapplicable acceptance criteriaaremet.TheproposedT/Sandoperating licensechangesdonotinvolvepostulated initiators foranalyzedevents;therefore, theprobability ofaccidents cannot,beaffected.

Theanalysesandevaluations performed allmetapplicable acceptance criteria; therefore, theconsequences ofaccidents previously evaluated areunaffected.

Criterion 2Dotheproposedchangescreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated?

No.Thefirstgroupofproposedchangesincreases thecorepoweratwhichunit2maybeoperated.

Operation attheproposednewpowerhasbeenanalyzed.

Thesecondgroupofchangesproposestoremovethepowerrestriction whentheHHSIcrosstiesareclosed.HHSIisanaccidentmitigator.

Theproposedchangesinthisgrouparebasedonanewanalysisusinganimprovedmodel.Theanalysesperformed tosupportthethird,fourth,andfifthgroupsofproposedchangesaddressincreases inoperating marginforaccidentmitigators, Nonewaccidentisinvolvedinthisproposal.

0 Attachment 1toAEP:NRC:1223 Page13Criterion 3Dotheproposedchangesinvolveasignificant reduction inamarginofsafety2No.Themarginofsafetyisprovidedfortheprimarypressureboundaryandothercomponents inpartbyapplicable designcodes.Themarginofsafetyforthevariousaccidents andtransients ismaintained bytheanalysisacceptance criteria.

Becausethecomponents remainincompliance withthecodesandstandards ineffectwhenCookNuclearPlantwaslicensedandapplicable acceptance criteriaaremet,themarginofsafetyisnotreducedbytheproposals inthisunit2uprateprogram.DETERMINATION OFNOSIGNIFICANT HAZARDSFORDELETIONOFTHELOWTEMPERATURE LIMITFROMTHEDNBTECHNICAL SPECIFICATION (WithinGroup4)Criterion 1Dotheproposedchangesinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated'o.

Theproposaltodeletethelowtemperature limitfromtheDNBT/Schangedoesnotinvolveaphysicalchangetotheplant.Theprocedures andadministrative controlsfortheplantdescribed abovewilleitherremaininplaceorbereplacedbycontrolsofcomparable effectiveness.

Therefore, theproposedT/Schangewillnotresultinasignificant increaseintheprobability orconsequences ofanyaccidentpreviously analyzed.

Criterion 2Dotheproposedchangescreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated?

No.TheproposedchangetotheDNBT/Sdoesnotinvolveaphysicalchangetotheplant.Theprocedures andadministrative controlsfortheplantdescribed abovewilleitherremaininplaceorbereplacedbycontrolsofcomparable effectiveness.

Therefore, theproposedchangewillnotcreatethepossibility ofanewordifferent accidentfromanypreviously evaluated.

rCriterion 3Dotheproposedchangesinvolveasignificant reduction inamarginofsafety'o.

TheproposedchangetotheDNBT/Sdoesnotinvolveaphysicalchangetotheplant.Theprocedures andadministrative Attachment 1toAEP:NRC:1223 Page14controlsfortheplantdescribed abovewilleitherremaininplaceorbereplacedbycontrolsofcomparable effectiveness.

Therefore, theproposedT/Schangewillnotinvolveasignificant, reduction inanymarginofsafety.DETERMINATION OFNOSIGNIFICANT HAZARDSFORADMINISTRATIVE CHANGES[Group5(Condensate StorageTankUseableVolumeonly)andGroup6)Criterion 1Doestheproposedchangeinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluatedf No.Theproposedchangesinvolvereferencing anotherT/Sratherthanincorporating aspecificvalueintoasecondspecification andachangeinterminology reflecting theexistinginstrument.

configuration.

Thesechangesareforconvenience andhavenosubstantive impact.Theseproposals havenoimpactonprobability.

Theproposedchangesalsohavenoimpactontheconsequences ofanaccidentbecausetheyhavenosubstantive impactonplantoperation oroperating limits.Criterion 2Doestheproposedchangecreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated2 No.Nothingischangedwithregardtoaccidentinitiators.

Thereisnosubstantive change;therefore, theproposedchangescanhavenoimpactonaccidentinitiators.

Criterion 3Doestheproposalinvolveasignificant reduction inamarginofsafety'o.

Theproposaldoesnotchangeanyrequirements; therefore, thereisnochangeinthemarginofsafety.CONCLUSION Itisconcluded thatoperation ofCookNuclearPlantunits1and2,withthechangesproposedabove,doesnotinvolveanysignificant hazardsconsideration asdefinedin10CFR50.92.

ATTACHMENT 2TOAEP:NRC:1223PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES f

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