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| {{#Wiki_filter:ACCESSIONNBR:FACIL:50-31550-31mAUTH.NAI]EALEXICH.N'RECIP.NANEDENTQNpH.R.REGULATORYIFQRNATIONDISTRIBUTIONSYel't(RIDS)8612300253DQC.DATE:86/12/22NOTARIZED:NODOCKET¹DonaldC.CookNuclearPowerPlant.Unit1>Indiana505000315DonaldC.CookNuclearPowerPlantiUnit2>Indiana00500031bAUTHORAFFILIATIONIndiana8cNichiganElectricCo.RECIPIENTAFFILIATIONOfficeofNuclearReactorRegulationtDirector(post851125 | | {{#Wiki_filter:ACCESSION NBR:FACIL:50-31550-31mAUTH.NAI]EALEXICH.N'RECIP.NANEDENTQNpH.R.REGULATORY IFQRNATION DISTRIBUTION SYel't(RIDS)8612300253 DQC.DATE:86/12/22NOTARIZED: |
| | NODOCKET¹DonaldC.CookNuclearPowerPlant.Unit1>Indiana505000315DonaldC.CookNuclearPowerPlantiUnit2>Indiana00500031bAUTHORAFFILIATION Indiana8cNichiganElectricCo.RECIPIENT AFFILIATION OfficeofNuclearReactorRegulationt Director(post851125 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ApplicationtoamendLicensesDPR-58ZcDPR-74>modifgingTechSpec5.3.1todeletereftomaxUweightperassembly0tocorrectminoreditorialchanges.Feepaid.DIBTRIBUTIONCODE:AOCIDCOPTERRECEIVED:LTR)ENCLQSIZE:l+(TITLE:QRSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAl'lEPWR-AEBPWR-AFOBPWR-APD4PD01PWR-APSBINTERNAL:ADN/LFNBNRR/DHFT/TSCB04COPIESLTTRENCL1115511101111RECIPIENTIDCODE/NANEPWR-AEICSBPWR-APD4LAWIQQINQTONiDPWR-ARSB1EELD/HDS3NRR/GRASRQN3COPIESLTTRENCL22101111101011EXTERNAL:E('@('RUSKE,SNRCPDR02111LPDRNSIC030522148'R(P~gg-g)lyg<5aATOTALNUl'tBEROFCOPIESREQUIRED:LTTR.2+ENCL
| | Application toamendLicensesDPR-58ZcDPR-74>modifgingTechSpec5.3.1todeletereftomaxUweightperassembly0tocorrectminoreditorial changes.Feepaid.DIBTRIBUTION CODE:AOCIDCOPTERRECEIVED: |
| | LTR)ENCLQSIZE:l+(TITLE:QRSubmittal: |
| | GeneralDistribution NOTES:RECIPIENT IDCODE/NAl'lE PWR-AEBPWR-AFOBPWR-APD4PD01PWR-APSBINTERNAL: |
| | ADN/LFNBNRR/DHFT/TSCB 04COPIESLTTRENCL1115511101111RECIPIENT IDCODE/NANE PWR-AEICSBPWR-APD4LAWIQQINQTONi DPWR-ARSB1EELD/HDS3NRR/GRASRQN3COPIESLTTRENCL22101111101011EXTERNAL: |
| | E('@('RUSKE, SNRCPDR02111LPDRNSIC030522148'R(P~gg-g)lyg<5aATOTALNUl'tBEROFCOPIESREQUIRED: |
| | LTTR.2+ENCL |
| *thI4I~H-t'KIh'I'l>>)~IHI>>,Hlh4If>>HKI<<1,HhtI'Hdghgfh/1lh'41fl"WHHHJll~,I44IIWIh', | | *thI4I~H-t'KIh'I'l>>)~IHI>>,Hlh4If>>HKI<<1,HhtI'Hdghgfh/1lh'41fl"WHHHJll~,I44IIWIh', |
| INDIANA8MICHIGANELECTRICCOMPANYP,O.BOX16631COLUMBUS,OHIO43216December22,1986AEP:NRC:1016DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74FUELASSEMBLYURANIUMMASSTECHNICALSPECIFICATIONCHANGEMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555 | | INDIANA8MICHIGANELECTRICCOMPANYP,O.BOX16631COLUMBUS, OHIO43216December22,1986AEP:NRC:1016 DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74FUELASSEMBLYURANIUMMASSTECHNICAL SPECIFICATION CHANGEMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555 |
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| ==DearMr.Denton:== | | ==DearMr.Denton:== |
| ThisletteranditsattachmentsconstituteanapplicationforamendmenttotheTechnicalSpecifications(T/Ss)fortheDonaldC.CookNuclearPlantUnitNos.1and2.Specifically,weproposetomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies)todeletereferencetoamaximumuraniumweightperassemblyandtocorrectminoreditorialchanges'hereasonsfortheproposedchangesandouranalysesconcerningsignificanthazardsconsiderationsarecontainedinAttachment1tothisletter.TheproposedrevisedT/SpagesarecontainedinAttachment2.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee(PNSRC)andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee(NSDRC)attheirnextregularlyscheduledmeeting.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.R.C.CallenoftheMichiganPublicServiceCommissionandMr.G.BruchmannoftheMichiganDepartmentofPublicHealth.Pursuantto10CFR170.12(c),wehaveenclosedanapplicationfeeof$150.00fortheproposedamendments.86i2300253861222~PDR*DOCK05000315('PDR~I, L~~~CI Mr.HaroldR.Denton-2-AEP:NRC:1016ThisdocumenthasbeenpreparedfollowingCorporateprocedureswhichincorporateareasonablesetofcontrolstoinsureitsaccuracyandcompletenesspriortosignaturebytheundersigned.Verytrulyyours,MPA/cmAttachmentsM..AleichVicePresidentIply'll>>cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.BruchmannG.CharnoffNRCResidentInspector-Bridgman Attachment1toAEP:NRC:1016Reasonsand10CFR50.92AnalysesforChangestotheDonaldC.CookNuclearPlantUnitNos.1and2TechnicalSpecifications Attachment1toAEP:RC:1016Page1ThislicenseamendmentrequestproposestomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies)forUnits1and2todeletereferencetoamaximumuraniumweightperassembly.BackroundByletterdatedSeptember4,1986(Attachment3),WestinghouseElectricCorporation(Westinghouse)officiallynotifiedusofadiscrepancyinvolvingthemaximumuraniumweightperassemblyspecifiedinT/S5.3.1'orUnit1.Specifically,Westinghouseinformedusthatrecentimprovementstotheirfueldesign(includingchamferedpelletswithareduceddishandanominaldensityincrease)haveincreasedfuelweightslightly.Theweightincreaseshavecausedthemaximumfuelrodweighttoexceedthemaximumvalueof2236gramsspecifiedinUnit1DesignFeaturesT/S5.3.1.WestinghousealsoprovideduswithproposedwordingandjustificationforaT/Schange,aswell,asajustificationforcontinuedoperation.WestinghousehadnotifiedusoftheconditioninformallyinAprilofthisyear.Atthattime,theissuewasdiscussedwithyourstaff,whoinformedustheissuecouldberesolvedbysubmittingrevisedT/Ss.TheapplicabilityofthisissuetoUnit2oftheD.C.CookPlantwasdiscussedwithExxonNuclearCompany(ENC),ourUnit2fuelsupplier.AlthoughtheENCfuelinUnit2doesnotexceedthemaximumuraniumweightperrodspecifiedinUnit2T/S5.3.1,ENCinformedusbyletterdatedOctober15,1986(Attachment4)thatthey"concurwiththegenericWestinghouseevaluationoftheproposedremovalofthemaximumrodweightfromT/S5.3.1."EvaluationTheproposedchangeofTechnicalSpecificationDesignFeaturesSection5.3.1isgiveninAttachment2.ThisistheonlyreferencetofuelroduraniumweightintheTechnicalSpecifications.AsdescribedbyWestinghouseinAttachment3,Althoughanumberofsafetyanalysesareaffectedindirectlybyfuelweight,theanalysesaremoresensitivetofuelconfiguration,length,enrichmentandphysicaldesignwhicharealsospecifiedintheplantTechnicalSpecifications.TheTechnicalSpecificationslimitpowerandpowerdistribution,thuscontrollingthefissionrateandtherateofdecayheatproduction.Fuelrodweightdoesnothaveanydirectbearingonthepowerlimits,poweroperatinglevel,ordecayheatrate.Thecompositionofthefueliscloselymonitoredtoassureacceptablefuelperformance.ThefuelweightchangesthatcouldbemadewithoutaTechnicalSpecificationlimitarenotofsufficientmagnitudetocauseasignificantdifferenceinfuelperformanceasanalyzedbyWestinghouse.Therearenoexpectedobservablechangesinnormaloperationduetothenotedfuelrodweightchanges,andtheremainingfuelparameterslistedintheTechnicalSpecificationsareconsideredintheReloadSafetyEvaluation.
| | Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnitNos.1and2.Specifically, weproposetomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies) todeletereference toamaximumuraniumweightperassemblyandtocorrectminoreditorial changes'he reasonsfortheproposedchangesandouranalysesconcerning significant hazardsconsiderations arecontained inAttachment 1tothisletter.TheproposedrevisedT/Spagesarecontained inAttachment 2.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. |
| | TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee (PNSRC)andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee (NSDRC)attheirnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1), |
| | copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.G.Bruchmann oftheMichiganDepartment ofPublicHealth.Pursuantto10CFR170.12(c), |
| | wehaveenclosedanapplication feeof$150.00fortheproposedamendments. |
| | 86i2300253 861222~PDR*DOCK05000315(' |
| | PDR~I, L~~~CI Mr.HaroldR.Denton-2-AEP:NRC:1016 Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned. |
| | Verytrulyyours,MPA/cmAttachments M..AleichVicePresident Iply'll>>cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.Bruchmann G.CharnoffNRCResidentInspector |
| | -Bridgman Attachment 1toAEP:NRC:1016 Reasonsand10CFR50.92AnalysesforChangestotheDonaldC.CookNuclearPlantUnitNos.1and2Technical Specifications Attachment 1toAEP:RC:1016Page1Thislicenseamendment requestproposestomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies) forUnits1and2todeletereference toamaximumuraniumweightperassembly. |
| | BackroundByletterdatedSeptember 4,1986(Attachment 3),Westinghouse ElectricCorporation (Westinghouse) officially notifiedusofadiscrepancy involving themaximumuraniumweightperassemblyspecified inT/S5.3.1'orUnit1.Specifically, Westinghouse informedusthatrecentimprovements totheirfueldesign(including chamfered pelletswithareduceddishandanominaldensityincrease) haveincreased fuelweightslightly. |
| | Theweightincreases havecausedthemaximumfuelrodweighttoexceedthemaximumvalueof2236gramsspecified inUnit1DesignFeaturesT/S5.3.1.Westinghouse alsoprovideduswithproposedwordingandjustification foraT/Schange,aswell,asajustification forcontinued operation. |
| | Westinghouse hadnotifiedusofthecondition informally inAprilofthisyear.Atthattime,theissuewasdiscussed withyourstaff,whoinformedustheissuecouldberesolvedbysubmitting revisedT/Ss.Theapplicability ofthisissuetoUnit2oftheD.C.CookPlantwasdiscussed withExxonNuclearCompany(ENC),ourUnit2fuelsupplier. |
| | AlthoughtheENCfuelinUnit2doesnotexceedthemaximumuraniumweightperrodspecified inUnit2T/S5.3.1,ENCinformedusbyletterdatedOctober15,1986(Attachment 4)thatthey"concurwiththegenericWestinghouse evaluation oftheproposedremovalofthemaximumrodweightfromT/S5.3.1."Evaluation TheproposedchangeofTechnical Specification DesignFeaturesSection5.3.1isgiveninAttachment 2.Thisistheonlyreference tofuelroduraniumweightintheTechnical Specifications. |
| | Asdescribed byWestinghouse inAttachment 3,Althoughanumberofsafetyanalysesareaffectedindirectly byfuelweight,theanalysesaremoresensitive tofuelconfiguration, length,enrichment andphysicaldesignwhicharealsospecified intheplantTechnical Specifications. |
| | TheTechnical Specifications limitpowerandpowerdistribution, thuscontrolling thefissionrateandtherateofdecayheatproduction. |
| | Fuelrodweightdoesnothaveanydirectbearingonthepowerlimits,poweroperating level,ordecayheatrate.Thecomposition ofthefueliscloselymonitored toassureacceptable fuelperformance. |
| | ThefuelweightchangesthatcouldbemadewithoutaTechnical Specification limitarenotofsufficient magnitude tocauseasignificant difference infuelperformance asanalyzedbyWestinghouse. |
| | Therearenoexpectedobservable changesinnormaloperation duetothenotedfuelrodweightchanges,andtheremaining fuelparameters listedintheTechnical Specifications areconsidered intheReloadSafetyEvaluation. |
| 1f~~ | | 1f~~ |
| Attachment1toAEP.RC:1016Page2OtherDesignBasisEventswereexaminedtoassesstheeffectsofpossiblechangesinfuelrodweight.Fuelrodweightwillonlychangeasaresultofaspecificchangeinthephysicaldesign,whichisaddressedintheReloadSafetyEvaluation,orwithinthemanufacturingtolerances,inwhichcasethechangesinfuelrodweightarerelativelyinsignificant.Changesinnucleardesignresultingfromfuelrodweightchangesarecontrolledasdiscussedabove.Forthesechanges,theeffectonnewandspentfuelcriticalityandfuel-handlinganalysesremainboundedbytheexistinganalysesandTechnicalSpecificationDesignFeaturelimits.Fuel-handlingequipmentandproceduresarenotaffectedbytheseweightchanges.Seismic/LOCAanalysescontainsufficientconservatismtoboundtheseweightchanges.Otheraccidentanalysesarenotaffectedbyrodweightasadirectparameter,andtheexistinganalysesremainbounding.Asstatedearlier,ENChas(inAttachment4)concurredwiththeWestinghouseevaluationwithregardtoD.C.CookUnit2.BasisforNoSinificantHazardsDeterminationPer10CFR50.92,aproposedamendmentwillinvolveanosignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.OurevaluationoftheabovecriteriaisbasedoninformationsuppliedtousbyWestinghouse(seeAttachment3).Criterion1Thedeletionofthefuelroduraniumweightlimitdoesnotsignificantlyincreasetheprobabilityorconsequencesofpreviouslyevaluatedaccidents.ThevariationinfuelrodweightthatcanoccurevenwithoutaTechnicalSpecificationlimitissmallbasedonotherfueldesignconstraints,e.g.,roddiameter,gapsize,UO-2densityandactivefuellength,allofwhichprovidesomelimitonthevariationinrodweight.Thecurrentsafetyanalysesarenotbaseddirectlyonfuelrodweight,abutratherondesignparameterssuchaspower-andfueldimensions.Theseparametersareeither(1)notaffectedatallbyfuelrodweight,or(2)areonlyslightlyaffected.However,areviewofdesignparameterswhichmaybeaffectedindicatesthatachangeinfuelweightdoesnotcauseotherdesignparameterstoexceedthevaluesassumedinthevarioussafetyanalyses,ortocauseacceptancecriteriatobeexceeded.Theeffectsarenotsignificantwithrespecttomeasurednuclearparameters(power,powerdistribution,nuclearcoefficients),i.e.,theyremainwithintheirT/Slimits.Thus,itisconcludedthattheT/Smodificationdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident.
| | Attachment 1toAEP.RC:1016Page2OtherDesignBasisEventswereexaminedtoassesstheeffectsofpossiblechangesinfuelrodweight.Fuelrodweightwillonlychangeasaresultofaspecificchangeinthephysicaldesign,whichisaddressed intheReloadSafetyEvaluation, orwithinthemanufacturing tolerances, inwhichcasethechangesinfuelrodweightarerelatively insignificant. |
| P Attachment1toAEP.C:1016Page3Criterion2Thecreationofanewordifferentkindofaccidentfromanypreviouslyevaluatedaccidentisnotconsideredapossibility.Allofthefuelcontainedinthefuelrodissimilartoanddesignedtofunctionsimilartopreviousfuel.Thus,theexistingnewandspentfuelstoragecriticalityanalysesboundthechangesobserved.Thischangeisconsideredasadministrativeinnatureanddoesnotcreatethepossibilityofanewordifferentkindofaccident.Criterion3Themarginofsafetyismaintainedbyadherencetootherfuel-relatedTechnicalSpecificationlimitsandtheFSARdesignbases.ThedeletionoffuelrodweightlimitsintheTechnicalSpecificationsDesignFeaturesSection5.3.1doesnotdirectlyaffectanysafetysystemorthesafetylimits,andthereforewillnotreducethemarginofsafety.Lastly,wenotethattheNRChasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityofoccurrenceorconsequencesofapreviouslyanalyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofwhicharewithinacceptablecriteria.DeletingtheT/Slimitformaximumfuelroduraniumweightmaybeperceivedasreducingmarginofsafetyorincreasingtheprobabilityorconsequencesofpreviouslyanalyzedaccidents.However,evaluationsoftheproposedchangeperformedbyWestinghouseandENChavedemonstratedthatapplicablecriteriawithregardstonuclearsafetywouldcontinuetobesatisfied.AdditionalChanesInadditiontothechangesdescribedabove,wealsomadeseveralminoreditorialchangestocorrecttypographicalerrorsintheT/Stext.Specifically,wecorrectedthespellingof"Zircaloy-4"inUnit1T/S5.3.1,andthespellingof"control"inUnit2T/S5.3.2.Thesechangesarepurelyadministrativeinnatureandthereforedonotreduceamarginofsafety,donotincreasetheprobabilityorconsequencesofapreviouslyanalyzedaccident,anddonotintroducethepossibilityofanewaccident.Therefore,webelievethatthesechangesdonotinvolveasignificanthazardsconsiderationasdefinedby10CFR50.92. | | Changesinnucleardesignresulting fromfuelrodweightchangesarecontrolled asdiscussed above.Forthesechanges,theeffectonnewandspentfuelcriticality andfuel-handling analysesremainboundedbytheexistinganalysesandTechnical Specification DesignFeaturelimits.Fuel-handling equipment andprocedures arenotaffectedbytheseweightchanges.Seismic/LOCA analysescontainsufficient conservatism toboundtheseweightchanges.Otheraccidentanalysesarenotaffectedbyrodweightasadirectparameter, andtheexistinganalysesremainbounding. |
| Attachment2toAEP:NRC:1016ProposedRevisedTechnicalSpecificationPages}}
| | Asstatedearlier,ENChas(inAttachment 4)concurred withtheWestinghouse evaluation withregardtoD.C.CookUnit2.BasisforNoSinificantHazardsDetermination Per10CFR50.92,aproposedamendment willinvolveanosignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, or(3)involveasignificant reduction inamarginofsafety.Ourevaluation oftheabovecriteriaisbasedoninformation suppliedtousbyWestinghouse (seeAttachment 3).Criterion 1Thedeletionofthefuelroduraniumweightlimitdoesnotsignificantly increasetheprobability orconsequences ofpreviously evaluated accidents. |
| | Thevariation infuelrodweightthatcanoccurevenwithoutaTechnical Specification limitissmallbasedonotherfueldesignconstraints, e.g.,roddiameter, gapsize,UO-2densityandactivefuellength,allofwhichprovidesomelimitonthevariation inrodweight.Thecurrentsafetyanalysesarenotbaseddirectlyonfuelrodweight,abutratherondesignparameters suchaspower-andfueldimensions. |
| | Theseparameters areeither(1)notaffectedatallbyfuelrodweight,or(2)areonlyslightlyaffected. |
| | However,areviewofdesignparameters whichmaybeaffectedindicates thatachangeinfuelweightdoesnotcauseotherdesignparameters toexceedthevaluesassumedinthevarioussafetyanalyses, ortocauseacceptance criteriatobeexceeded. |
| | Theeffectsarenotsignificant withrespecttomeasurednuclearparameters (power,powerdistribution, nuclearcoefficients), |
| | i.e.,theyremainwithintheirT/Slimits.Thus,itisconcluded thattheT/Smodification doesnotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated accident. |
| | P Attachment 1toAEP.C:1016Page3Criterion 2Thecreationofanewordifferent kindofaccidentfromanypreviously evaluated accidentisnotconsidered apossibility. |
| | Allofthefuelcontained inthefuelrodissimilartoanddesignedtofunctionsimilartopreviousfuel.Thus,theexistingnewandspentfuelstoragecriticality analysesboundthechangesobserved. |
| | Thischangeisconsidered asadministrative innatureanddoesnotcreatethepossibility ofanewordifferent kindofaccident. |
| | Criterion 3Themarginofsafetyismaintained byadherence tootherfuel-related Technical Specification limitsandtheFSARdesignbases.ThedeletionoffuelrodweightlimitsintheTechnical Specifications DesignFeaturesSection5.3.1doesnotdirectlyaffectanysafetysystemorthesafetylimits,andtherefore willnotreducethemarginofsafety.Lastly,wenotethattheNRChasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration. |
| | Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobability ofoccurrence orconsequences ofapreviously analyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofwhicharewithinacceptable criteria. |
| | DeletingtheT/Slimitformaximumfuelroduraniumweightmaybeperceived asreducingmarginofsafetyorincreasing theprobability orconsequences ofpreviously analyzedaccidents. |
| | However,evaluations oftheproposedchangeperformed byWestinghouse andENChavedemonstrated thatapplicable criteriawithregardstonuclearsafetywouldcontinuetobesatisfied. |
| | Additional ChanesInadditiontothechangesdescribed above,wealsomadeseveralminoreditorial changestocorrecttypographical errorsintheT/Stext.Specifically, wecorrected thespellingof"Zircaloy-4" inUnit1T/S5.3.1,andthespellingof"control" inUnit2T/S5.3.2.Thesechangesarepurelyadministrative innatureandtherefore donotreduceamarginofsafety,donotincreasetheprobability orconsequences ofapreviously analyzedaccident, anddonotintroduce thepossibility ofanewaccident. |
| | Therefore, webelievethatthesechangesdonotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92. |
| | Attachment 2toAEP:NRC:1016 ProposedRevisedTechnical Specification Pages}} |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 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 ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 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 ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
ACCESSION NBR:FACIL:50-31550-31mAUTH.NAI]EALEXICH.N'RECIP.NANEDENTQNpH.R.REGULATORY IFQRNATION DISTRIBUTION SYel't(RIDS)8612300253 DQC.DATE:86/12/22NOTARIZED:
NODOCKET¹DonaldC.CookNuclearPowerPlant.Unit1>Indiana505000315DonaldC.CookNuclearPowerPlantiUnit2>Indiana00500031bAUTHORAFFILIATION Indiana8cNichiganElectricCo.RECIPIENT AFFILIATION OfficeofNuclearReactorRegulationt Director(post851125
SUBJECT:
Application toamendLicensesDPR-58ZcDPR-74>modifgingTechSpec5.3.1todeletereftomaxUweightperassembly0tocorrectminoreditorial changes.Feepaid.DIBTRIBUTION CODE:AOCIDCOPTERRECEIVED:
LTR)ENCLQSIZE:l+(TITLE:QRSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAl'lE PWR-AEBPWR-AFOBPWR-APD4PD01PWR-APSBINTERNAL:
ADN/LFNBNRR/DHFT/TSCB 04COPIESLTTRENCL1115511101111RECIPIENT IDCODE/NANE PWR-AEICSBPWR-APD4LAWIQQINQTONi DPWR-ARSB1EELD/HDS3NRR/GRASRQN3COPIESLTTRENCL22101111101011EXTERNAL:
E('@('RUSKE, SNRCPDR02111LPDRNSIC030522148'R(P~gg-g)lyg<5aATOTALNUl'tBEROFCOPIESREQUIRED:
LTTR.2+ENCL
- thI4I~H-t'KIh'I'l>>)~IHI>>,Hlh4If>>HKI<<1,HhtI'Hdghgfh/1lh'41fl"WHHHJll~,I44IIWIh',
INDIANA8MICHIGANELECTRICCOMPANYP,O.BOX16631COLUMBUS, OHIO43216December22,1986AEP:NRC:1016 DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74FUELASSEMBLYURANIUMMASSTECHNICAL SPECIFICATION CHANGEMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555
DearMr.Denton:
Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnitNos.1and2.Specifically, weproposetomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies) todeletereference toamaximumuraniumweightperassemblyandtocorrectminoreditorial changes'he reasonsfortheproposedchangesandouranalysesconcerning significant hazardsconsiderations arecontained inAttachment 1tothisletter.TheproposedrevisedT/Spagesarecontained inAttachment 2.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee (PNSRC)andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee (NSDRC)attheirnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.G.Bruchmann oftheMichiganDepartment ofPublicHealth.Pursuantto10CFR170.12(c),
wehaveenclosedanapplication feeof$150.00fortheproposedamendments.
86i2300253 861222~PDR*DOCK05000315('
PDR~I, L~~~CI Mr.HaroldR.Denton-2-AEP:NRC:1016 Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned.
Verytrulyyours,MPA/cmAttachments M..AleichVicePresident Iply'll>>cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.Bruchmann G.CharnoffNRCResidentInspector
-Bridgman Attachment 1toAEP:NRC:1016 Reasonsand10CFR50.92AnalysesforChangestotheDonaldC.CookNuclearPlantUnitNos.1and2Technical Specifications Attachment 1toAEP:RC:1016Page1Thislicenseamendment requestproposestomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies) forUnits1and2todeletereference toamaximumuraniumweightperassembly.
BackroundByletterdatedSeptember 4,1986(Attachment 3),Westinghouse ElectricCorporation (Westinghouse) officially notifiedusofadiscrepancy involving themaximumuraniumweightperassemblyspecified inT/S5.3.1'orUnit1.Specifically, Westinghouse informedusthatrecentimprovements totheirfueldesign(including chamfered pelletswithareduceddishandanominaldensityincrease) haveincreased fuelweightslightly.
Theweightincreases havecausedthemaximumfuelrodweighttoexceedthemaximumvalueof2236gramsspecified inUnit1DesignFeaturesT/S5.3.1.Westinghouse alsoprovideduswithproposedwordingandjustification foraT/Schange,aswell,asajustification forcontinued operation.
Westinghouse hadnotifiedusofthecondition informally inAprilofthisyear.Atthattime,theissuewasdiscussed withyourstaff,whoinformedustheissuecouldberesolvedbysubmitting revisedT/Ss.Theapplicability ofthisissuetoUnit2oftheD.C.CookPlantwasdiscussed withExxonNuclearCompany(ENC),ourUnit2fuelsupplier.
AlthoughtheENCfuelinUnit2doesnotexceedthemaximumuraniumweightperrodspecified inUnit2T/S5.3.1,ENCinformedusbyletterdatedOctober15,1986(Attachment 4)thatthey"concurwiththegenericWestinghouse evaluation oftheproposedremovalofthemaximumrodweightfromT/S5.3.1."Evaluation TheproposedchangeofTechnical Specification DesignFeaturesSection5.3.1isgiveninAttachment 2.Thisistheonlyreference tofuelroduraniumweightintheTechnical Specifications.
Asdescribed byWestinghouse inAttachment 3,Althoughanumberofsafetyanalysesareaffectedindirectly byfuelweight,theanalysesaremoresensitive tofuelconfiguration, length,enrichment andphysicaldesignwhicharealsospecified intheplantTechnical Specifications.
TheTechnical Specifications limitpowerandpowerdistribution, thuscontrolling thefissionrateandtherateofdecayheatproduction.
Fuelrodweightdoesnothaveanydirectbearingonthepowerlimits,poweroperating level,ordecayheatrate.Thecomposition ofthefueliscloselymonitored toassureacceptable fuelperformance.
ThefuelweightchangesthatcouldbemadewithoutaTechnical Specification limitarenotofsufficient magnitude tocauseasignificant difference infuelperformance asanalyzedbyWestinghouse.
Therearenoexpectedobservable changesinnormaloperation duetothenotedfuelrodweightchanges,andtheremaining fuelparameters listedintheTechnical Specifications areconsidered intheReloadSafetyEvaluation.
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Attachment 1toAEP.RC:1016Page2OtherDesignBasisEventswereexaminedtoassesstheeffectsofpossiblechangesinfuelrodweight.Fuelrodweightwillonlychangeasaresultofaspecificchangeinthephysicaldesign,whichisaddressed intheReloadSafetyEvaluation, orwithinthemanufacturing tolerances, inwhichcasethechangesinfuelrodweightarerelatively insignificant.
Changesinnucleardesignresulting fromfuelrodweightchangesarecontrolled asdiscussed above.Forthesechanges,theeffectonnewandspentfuelcriticality andfuel-handling analysesremainboundedbytheexistinganalysesandTechnical Specification DesignFeaturelimits.Fuel-handling equipment andprocedures arenotaffectedbytheseweightchanges.Seismic/LOCA analysescontainsufficient conservatism toboundtheseweightchanges.Otheraccidentanalysesarenotaffectedbyrodweightasadirectparameter, andtheexistinganalysesremainbounding.
Asstatedearlier,ENChas(inAttachment 4)concurred withtheWestinghouse evaluation withregardtoD.C.CookUnit2.BasisforNoSinificantHazardsDetermination Per10CFR50.92,aproposedamendment willinvolveanosignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, or(3)involveasignificant reduction inamarginofsafety.Ourevaluation oftheabovecriteriaisbasedoninformation suppliedtousbyWestinghouse (seeAttachment 3).Criterion 1Thedeletionofthefuelroduraniumweightlimitdoesnotsignificantly increasetheprobability orconsequences ofpreviously evaluated accidents.
Thevariation infuelrodweightthatcanoccurevenwithoutaTechnical Specification limitissmallbasedonotherfueldesignconstraints, e.g.,roddiameter, gapsize,UO-2densityandactivefuellength,allofwhichprovidesomelimitonthevariation inrodweight.Thecurrentsafetyanalysesarenotbaseddirectlyonfuelrodweight,abutratherondesignparameters suchaspower-andfueldimensions.
Theseparameters areeither(1)notaffectedatallbyfuelrodweight,or(2)areonlyslightlyaffected.
However,areviewofdesignparameters whichmaybeaffectedindicates thatachangeinfuelweightdoesnotcauseotherdesignparameters toexceedthevaluesassumedinthevarioussafetyanalyses, ortocauseacceptance criteriatobeexceeded.
Theeffectsarenotsignificant withrespecttomeasurednuclearparameters (power,powerdistribution, nuclearcoefficients),
i.e.,theyremainwithintheirT/Slimits.Thus,itisconcluded thattheT/Smodification doesnotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated accident.
P Attachment 1toAEP.C:1016Page3Criterion 2Thecreationofanewordifferent kindofaccidentfromanypreviously evaluated accidentisnotconsidered apossibility.
Allofthefuelcontained inthefuelrodissimilartoanddesignedtofunctionsimilartopreviousfuel.Thus,theexistingnewandspentfuelstoragecriticality analysesboundthechangesobserved.
Thischangeisconsidered asadministrative innatureanddoesnotcreatethepossibility ofanewordifferent kindofaccident.
Criterion 3Themarginofsafetyismaintained byadherence tootherfuel-related Technical Specification limitsandtheFSARdesignbases.ThedeletionoffuelrodweightlimitsintheTechnical Specifications DesignFeaturesSection5.3.1doesnotdirectlyaffectanysafetysystemorthesafetylimits,andtherefore willnotreducethemarginofsafety.Lastly,wenotethattheNRChasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.
Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobability ofoccurrence orconsequences ofapreviously analyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofwhicharewithinacceptable criteria.
DeletingtheT/Slimitformaximumfuelroduraniumweightmaybeperceived asreducingmarginofsafetyorincreasing theprobability orconsequences ofpreviously analyzedaccidents.
However,evaluations oftheproposedchangeperformed byWestinghouse andENChavedemonstrated thatapplicable criteriawithregardstonuclearsafetywouldcontinuetobesatisfied.
Additional ChanesInadditiontothechangesdescribed above,wealsomadeseveralminoreditorial changestocorrecttypographical errorsintheT/Stext.Specifically, wecorrected thespellingof"Zircaloy-4" inUnit1T/S5.3.1,andthespellingof"control" inUnit2T/S5.3.2.Thesechangesarepurelyadministrative innatureandtherefore donotreduceamarginofsafety,donotincreasetheprobability orconsequences ofapreviously analyzedaccident, anddonotintroduce thepossibility ofanewaccident.
Therefore, webelievethatthesechangesdonotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.
Attachment 2toAEP:NRC:1016 ProposedRevisedTechnical Specification Pages