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| {{#Wiki_filter:CATEGORY1REGULATOROINFORMATZONDISTRIBUTIONTEM(RIDE)ACCESSIONNBR:9612270111DOC.DATE:96/12/20NOTARIZED:YESFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.EAmericanElectricPowerCo.,Inc.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk) | | {{#Wiki_filter:CATEGORY1REGULATOROINFORMATZON DISTRIBUTION TEM(RIDE)ACCESSION NBR:9612270111 DOC.DATE: |
| | 96/12/20NOTARIZED: |
| | YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E AmericanElectricPowerCo.,Inc.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) |
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| ApplicationforamendstolicensesDPR-58!'PR-74,requestingrevofreactorcoolantpumpflywheelinspfrequency.DISTRIBUTIONCODE:AOOZDCOPIESRECEIVED:LTR1ENCLiSIZE:4I4TITLE:ORSubmittal:GeneralDistributionNOTES:DOCKET0500031505000316ERECIPIENTIDCODE/NAMEPD3-3LAHICKMAN,JINTERNA:MLECENTE0.RDEEMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTEXTERNAL:NOACCOPIESLTTRENCL111111111111RECIPIENTIDCODE/NAMEPD3-3PDNRR/DE/ECGB/ANRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL.'12 IndianaMichiganPowerCompany500CircleDriveBuchanan,Ml491071395INQMNANICNESANPQWMDecember20,1996DocketNo:50-31550-316AEP:NRC:124510CFR50.90U.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR"74PROPOSEDLICENSEANDTECHNICALSPECIFICATIONCHANGESOFREACTORCOOLANTPUMPFLYWHEELINSPECTIONFREQUENCYThisletteranditsattachmentsconstituteanapplicationforamendmentofthetechnicalspecifications(T/S)forCookNuclearPlantunits1and2.Changesareproposedtoreducethefrequencyandscopeofreactorcoolantpumpflywheelinspectionsconsistentwithyourstaff'sevaluationofWCAP-14535,"TopicalReportonReactorCoolantPumpFlywheelInspectionElimination."Adescriptionoftheproposedchangesandananalysisconcerningsignificanthazardsconsiderationpursuantto10CFR50.92iscontainedinattachment1.Attachment2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment.3containstheproposed,revisedT/Spages.WebelievetheproposedT/Schangeswillnotresultinasignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountofeffluentthatmightbereleasedoffsite,orasignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee~.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtheMichiganDepartment.ofPublicHealth.Sincerely,SWORNTOANDSUBSCRIBEDBEFOREMEITHIS~ODAYOF~~Mt1996E.E.Fitpatrick96OO3VicePresidentAttachmentsNotaryPublicMyCommissionExpires:JANWATSONNOTARYPUBUC,BERRIENCOUNTY,MIIMYCOMMISSIONEXPIRESFEB101999'Pbi2270iii9hi220PDRADQCK050003l5PPDR J1';C.1Wtq'ae4~Ia,<<W*<<i~u~""C U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1245cc:A.A.BlindA.B.BeachMDEQ"DWEcRPDNRCResidentInspectorJ.R.Padgett ATTACHMENT1TOAEP:NRC:124S10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICALSPECIFICATIONS Attachment1toAEP:NRC:1245Page11.0SECTIONTOBECHANGED1.Unit1technicalspecification(T/S)4.4.10.12.Unit2T/S4.4.10.12.0EXTENTOFCHANGES1.Weareproposingtochangeunit1T/S4.4.10.1torequirereactorcoolantpump(RCP)flywheelinspectionsonceevery10yearsinthemannerdescribedbelow.Weareproposingtochangeunit2T/S4.4.10.1torequireRCPflywheelinspectionsonceevery10yearsinthemannerdescribedbelow.3.0CHANGESREUESTEDWeareproposingtomakethefollowingchangetotheunit1andunit2T/Ss.CurrentlyT/Ssection4.4.10.1requiresthateachreactorcoolantpumpflywheelbeinspectedpertherecommendationsofregulatorypositionC.4.bofRegulatoryGuide(RG)1.14,Revision1,August1975.TheregulatorypositionofRG1.14concerningISIcallsforanin-placeultrasonicvolumetricexaminationoftheareasofhigherstressconcentrationattheboreandkeywayatapproximately3-yearintervalsandasurfaceexaminationofallexposedsurfacesandcompleteultrasonicvolumetricexaminationatapproximately10-yearintervals.TheproposedT/Srequiresthateitheraqualifiedin-placeUTexaminationoverthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination(MTand/orPT)ofexposedsurfacesdefinedbythevolumeofthedisassembledflywheelsbeconductedonceevery10years.4.0DISCUSSIONTechnicalSecification4.4.10.1BasesT/S4.4.10.1ensuresthatthestructuralintegrityofthereactorcoolantpumpflywheelswillbemaintainedatanacceptablelevelthroughoutthelifeoftheplant.JustificationforProosedTechnicalSecificationChanesTheproposedT/SamendmentrequesttoreducethefrequencyandscopeofsurveillanceoftheRCPflywheelsisjustifiedforseveralreasons.ThischangeisconsistentwithMr.Sheron's(DirectorDivisionofEngineering,OfficeofNuclearReactorRegulation)letterentitled"AcceptanceforReferencingofTopicalReportWCAP-14535,'TopicalReportonReactorCoolantPumpFlywheelInspectionElimination'andrelatedattachments.Pertherequirementofthisletter,wehaveconfirmedthattheRCPflywheelsinplaceatCookNuclearPlantarecomposedofSA533Bmaterial.ThoughWestinghouseElectricCorporationreportWCAP-14535,entitled"TopicalReportonReactorCoolantPumpFlywheelInspectionElimination",seekseliminationofflywheelinspections,weonly Attachment1toAEP:NRC:1245Page2seektoreducethefrequencyoftheseinspectionstoonceevery10years.WCAP-14535-concludesthefollowing.1.Flywheelsarecarefullydesignedandmanufacturedfromexcellentqualitysteel,whichhasahighfracturetoughness.2.Flywheeloverspeedisthecriticalloading,butleakbeforebreakhaslimitedthemaximumspeedtolessthan1500rpm.6.7.Flywheelinspectionshavebeenperformedfor2Cyears,withnoindicationsofserviceinducedflaws.Flywheelintegrityevaluationsshowveryhighflawtolerancefortheflywheels.Crackextensionovera60yearservicelifeisnegligible.Structuralreliabilitystudieshaveshownthateliminatinginspectionsafter10yearsofplantlifewillnotsignificantlychangetheprobabilityoffailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreserviceinspectionoratworstearlyinplantlife,andcrackgrowthoverplantlifeisnegligible.AsstatedintheSERassociatedwithWCAP-14535,assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintainedduringthe10-yearinspectionperiod.Inspectionsresultinmanremexposureandthepotentialforflywheeldamageduringdisassemblyandreassembly.Basedontheaboveconclusions,inspectionsofRCPflywheelswitha10-yearfrequencyandmodifiedscopearejustified.5.0NOSIGNIFICANTHAZARDSCONSIDERATIONWehaveevaluatedtheproposedT/Schangesandhavedeterminedthey'onotrepresentasignificanthazardsconsiderationbasedonthecriteriaestablishedin10CFR50.92(c).OperationofCookNuclearPlantinaccordancewiththeproposedamendmentwillnot:1.InvolveasinificantincreaseintherobabilitorconseenceofanaccidentreviouslevaluatedThischangewillreducetnefrequencyandscopeofthesurveillancetestingonthereactorcoolantpumpflywheels.Operatingpowerplantshavebeeninspectingtheirflywheelsforover20yearswithnoflawsidentifiedwhichaffectflywheelintegrity.PastexaminationsperformedtosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextensionovera60yearservicelifeisnegligible.Structuralreliabilitystudieshaveshownthateliminatinginspectionsafter10yearsofplantlifewillnotsignificantlychange'heprobabilityoffailure.Mostflawswhichcouldleadto Attachment1toAEP:NRC:1245Page3failurewouldbedetectedduringpreserviceinspectionor,atworst,earlyinplantlife,andcrackgrowthoverplantlifeisnegligible.AsstatedintheSERassociatedwithWCAP-14535,assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintainedduringthe10-yearinspectionperiod.Therefore,thechangeintestfrequencywillnotendangerpublichealthorsafety.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident.Createtheossibilitofanewordifferentkindofaccidentfromanaccidentreviouslevaluated.Thechangeswillnotintroduceanynewmodesofplantoperation,norwillanyphysicalchangestotheplantberequired.Thus,thechangeswillnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated.3.InvolveasinificantreductioninamarinofaafetThischangewillreducethefrequencyandscopeofthesurveillancetestingonthereactorcoolantpumpflywheels.Operatingpowerplantshavebeeninspectingtheirflywheelsforover20yearswithnoflawsidentifiedwhichaffectflywheelintegrity.PastexaminationsperformedtosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextensionovera60yearservicelifeisnegligible.Structuralreliabilitystudieshaveshownthateliminatinginspectionsafter10yearsofplantlifewillnotsignificantlychangetheprobabilityoffailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreserviceirepectionoratw'orstearlyinplantlife,andcrackgr.~thoverplantlifeisnegligible.AsstatedintheSERassociatedwithWCAP-,14535,assuminganinitialcrackof10%ofthedistancef'romthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgiowth,ASMEmarginswouldbemaintainedduringthe10-yearinspectionperiod.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificantreductioninamarginofsafety.6.0PENDINGTSPROPOSALSIMPACTINGTHISSUBMITTALTherearenootherT/Sproposalsunderreviewthatimpactthissubmittal~.}}
| | Application foramendstolicensesDPR-58!'PR-74,requesting revofreactorcoolantpumpflywheelinspfrequency. |
| | DISTRIBUTION CODE:AOOZDCOPIESRECEIVED:LTR 1ENCLiSIZE:4I4TITLE:ORSubmittal: |
| | GeneralDistribution NOTES:DOCKET0500031505000316ERECIPIENT IDCODE/NAME PD3-3LAHICKMAN,J INTERNA:MLECENTE0.RDEEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: |
| | NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-3PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT. |
| | 415-2083) |
| | TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR13ENCL.'12 IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071395 INQMNANICNESANPQWMDecember20,1996DocketNo:50-31550-316AEP:NRC:1245 10CFR50.90U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen: |
| | DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR"74PROPOSEDLICENSEANDTECHNICAL SPECIFICATION CHANGESOFREACTORCOOLANTPUMPFLYWHEELINSPECTION FREQUENCY Thisletteranditsattachments constitute anapplication foramendment ofthetechnical specifications (T/S)forCookNuclearPlantunits1and2.Changesareproposedtoreducethefrequency andscopeofreactorcoolantpumpflywheelinspections consistent withyourstaff'sevaluation ofWCAP-14535, "TopicalReportonReactorCoolantPumpFlywheelInspection Elimination." |
| | Adescription oftheproposedchangesandananalysisconcerning significant hazardsconsideration pursuantto10CFR50.92iscontained inattachment 1.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment |
| | .3containstheproposed, revisedT/Spages.WebelievetheproposedT/Schangeswillnotresultinasignificant changeinthetypesofeffluents orasignificant increaseintheamountofeffluentthatmightbereleasedoffsite,orasignificant increaseinindividual orcumulative occupational radiation exposure. |
| | TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee~ |
| | .Incompliance withtherequirements of10CFR50.91(b)(1), |
| | copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment. |
| | ofPublicHealth.Sincerely, SWORNTOANDSUBSCRIBED BEFOREMEITHIS~ODAYOF~~Mt1996E.E.Fitpatrick96OO3VicePresident Attachments NotaryPublicMyCommission Expires:JANWATSONNOTARYPUBUC,BERRIENCOUNTY,MIIMYCOMMISSION EXPIRESFEB101999'Pbi2270iii 9hi220PDRADQCK050003l5PPDR J1';C.1Wtq'ae4~Ia,<<W*<<i~u~""C U.S.NuclearRegulatory Commission Page2AEP:NRC:1245cc:A.A.BlindA.B.BeachMDEQ"DWEcRPDNRCResidentInspector J.R.Padgett ATTACHMENT 1TOAEP:NRC:124S 10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1245 Page11.0SECTIONTOBECHANGED1.Unit1technical specification (T/S)4.4.10.12.Unit2T/S4.4.10.12.0EXTENTOFCHANGES1.Weareproposing tochangeunit1T/S4.4.10.1torequirereactorcoolantpump(RCP)flywheelinspections onceevery10yearsinthemannerdescribed below.Weareproposing tochangeunit2T/S4.4.10.1torequireRCPflywheelinspections onceevery10yearsinthemannerdescribed below.3.0CHANGESREUESTEDWeareproposing tomakethefollowing changetotheunit1andunit2T/Ss.Currently T/Ssection4.4.10.1requiresthateachreactorcoolantpumpflywheelbeinspected pertherecommendations ofregulatory positionC.4.bofRegulatory Guide(RG)1.14,Revision1,August1975.Theregulatory positionofRG1.14concerning ISIcallsforanin-placeultrasonic volumetric examination oftheareasofhigherstressconcentration attheboreandkeywayatapproximately 3-yearintervals andasurfaceexamination ofallexposedsurfacesandcompleteultrasonic volumetric examination atapproximately 10-yearintervals. |
| | TheproposedT/Srequiresthateitheraqualified in-placeUTexamination overthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (MTand/orPT)ofexposedsurfacesdefinedbythevolumeofthedisassembled flywheels beconducted onceevery10years.4.0DISCUSSION Technical Secification 4.4.10.1BasesT/S4.4.10.1ensuresthatthestructural integrity ofthereactorcoolantpumpflywheels willbemaintained atanacceptable levelthroughout thelifeoftheplant.Justification forProosedTechnical Secification ChanesTheproposedT/Samendment requesttoreducethefrequency andscopeofsurveillance oftheRCPflywheels isjustified forseveralreasons.Thischangeisconsistent withMr.Sheron's(Director DivisionofEngineering, OfficeofNuclearReactorRegulation) letterentitled"Acceptance forReferencing ofTopicalReportWCAP-14535,'TopicalReportonReactorCoolantPumpFlywheelInspection Elimination' andrelatedattachments. |
| | Pertherequirement ofthisletter,wehaveconfirmed thattheRCPflywheels inplaceatCookNuclearPlantarecomposedofSA533Bmaterial. |
| | ThoughWestinghouse ElectricCorporation reportWCAP-14535, entitled"TopicalReportonReactorCoolantPumpFlywheelInspection Elimination", |
| | seekselimination offlywheelinspections, weonly Attachment 1toAEP:NRC:1245 Page2seektoreducethefrequency oftheseinspections toonceevery10years.WCAP-14535-concludes thefollowing. |
| | 1.Flywheels arecarefully designedandmanufactured fromexcellent qualitysteel,whichhasahighfracturetoughness. |
| | 2.Flywheeloverspeed isthecriticalloading,butleakbeforebreakhaslimitedthemaximumspeedtolessthan1500rpm.6.7.Flywheelinspections havebeenperformed for2Cyears,withnoindications ofserviceinducedflaws.Flywheelintegrity evaluations showveryhighflawtolerance fortheflywheels. |
| | Crackextension overa60yearservicelifeisnegligible. |
| | Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlife willnotsignificantly changetheprobability offailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreservice inspection oratworstearlyinplantlife,andcrackgrowthoverplantlifeisnegligible. |
| | AsstatedintheSERassociated withWCAP-14535, assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Inspections resultinmanremexposureandthepotential forflywheeldamageduringdisassembly andreassembly. |
| | Basedontheaboveconclusions, inspections ofRCPflywheels witha10-yearfrequency andmodifiedscopearejustified. |
| | |
| | ==5.0 NOSIGNIFICANT== |
| | HAZARDSCONSIDERATION Wehaveevaluated theproposedT/Schangesandhavedetermined they'onotrepresent asignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c).Operation ofCookNuclearPlantinaccordance withtheproposedamendment willnot:1.Involveasinificantincreaseintherobabilit orconseenceofanaccidentreviouslevaluated Thischangewillreducetnefrequency andscopeofthesurveillance testingonthereactorcoolantpumpflywheels. |
| | Operating powerplantshavebeeninspecting theirflywheels forover20yearswithnoflawsidentified whichaffectflywheelintegrity. |
| | Pastexaminations performed tosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextension overa60yearservicelifeisnegligible. |
| | Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlifewillnotsignificantly change'he probability offailure.Mostflawswhichcouldleadto Attachment 1toAEP:NRC:1245 Page3failurewouldbedetectedduringpreservice inspection or,atworst,earlyinplantlife,andcrackgrowthoverplantlifeisnegligible. |
| | AsstatedintheSERassociated withWCAP-14535, assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Therefore, thechangeintestfrequency willnotendangerpublichealthorsafety.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated accident. |
| | Createtheossibilit ofanewordifferent kindofaccidentfromanaccidentreviouslevaluated. |
| | Thechangeswillnotintroduce anynewmodesofplantoperation, norwillanyphysicalchangestotheplantberequired. |
| | Thus,thechangeswillnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated. |
| | 3.Involveasinificantreduction inamarinofaafetThischangewillreducethefrequency andscopeofthesurveillance testingonthereactorcoolantpumpflywheels. |
| | Operating powerplantshavebeeninspecting theirflywheels forover20yearswithnoflawsidentified whichaffectflywheelintegrity. |
| | Pastexaminations performed tosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextension overa60yearservicelifeisnegligible. |
| | Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlifewillnotsignificantly changetheprobability offailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreservice irepection oratw'orstearlyinplantlife,andcrackgr.~thoverplantlifeisnegligible. |
| | AsstatedintheSERassociated withWCAP-,14535,assuminganinitialcrackof10%ofthedistancef'romthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgiowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificant reduction inamarginofsafety.6.0PENDINGTSPROPOSALS IMPACTING THISSUBMITTAL TherearenootherT/Sproposals underreviewthatimpactthissubmittal~ |
| | .}} |
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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
CATEGORY1REGULATOROINFORMATZON DISTRIBUTION TEM(RIDE)ACCESSION NBR:9612270111 DOC.DATE:
96/12/20NOTARIZED:
YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E AmericanElectricPowerCo.,Inc.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
SUBJECT:
Application foramendstolicensesDPR-58!'PR-74,requesting revofreactorcoolantpumpflywheelinspfrequency.
DISTRIBUTION CODE:AOOZDCOPIESRECEIVED:LTR 1ENCLiSIZE:4I4TITLE:ORSubmittal:
GeneralDistribution NOTES:DOCKET0500031505000316ERECIPIENT IDCODE/NAME PD3-3LAHICKMAN,J INTERNA:MLECENTE0.RDEEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL:
NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-3PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL.'12 IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071395 INQMNANICNESANPQWMDecember20,1996DocketNo:50-31550-316AEP:NRC:1245 10CFR50.90U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen:
DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR"74PROPOSEDLICENSEANDTECHNICAL SPECIFICATION CHANGESOFREACTORCOOLANTPUMPFLYWHEELINSPECTION FREQUENCY Thisletteranditsattachments constitute anapplication foramendment ofthetechnical specifications (T/S)forCookNuclearPlantunits1and2.Changesareproposedtoreducethefrequency andscopeofreactorcoolantpumpflywheelinspections consistent withyourstaff'sevaluation ofWCAP-14535, "TopicalReportonReactorCoolantPumpFlywheelInspection Elimination."
Adescription oftheproposedchangesandananalysisconcerning significant hazardsconsideration pursuantto10CFR50.92iscontained inattachment 1.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment
.3containstheproposed, revisedT/Spages.WebelievetheproposedT/Schangeswillnotresultinasignificant changeinthetypesofeffluents orasignificant increaseintheamountofeffluentthatmightbereleasedoffsite,orasignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee~
.Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment.
ofPublicHealth.Sincerely, SWORNTOANDSUBSCRIBED BEFOREMEITHIS~ODAYOF~~Mt1996E.E.Fitpatrick96OO3VicePresident Attachments NotaryPublicMyCommission Expires:JANWATSONNOTARYPUBUC,BERRIENCOUNTY,MIIMYCOMMISSION EXPIRESFEB101999'Pbi2270iii 9hi220PDRADQCK050003l5PPDR J1';C.1Wtq'ae4~Ia,<<W*<<i~u~""C U.S.NuclearRegulatory Commission Page2AEP:NRC:1245cc:A.A.BlindA.B.BeachMDEQ"DWEcRPDNRCResidentInspector J.R.Padgett ATTACHMENT 1TOAEP:NRC:124S 10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1245 Page11.0SECTIONTOBECHANGED1.Unit1technical specification (T/S)4.4.10.12.Unit2T/S4.4.10.12.0EXTENTOFCHANGES1.Weareproposing tochangeunit1T/S4.4.10.1torequirereactorcoolantpump(RCP)flywheelinspections onceevery10yearsinthemannerdescribed below.Weareproposing tochangeunit2T/S4.4.10.1torequireRCPflywheelinspections onceevery10yearsinthemannerdescribed below.3.0CHANGESREUESTEDWeareproposing tomakethefollowing changetotheunit1andunit2T/Ss.Currently T/Ssection4.4.10.1requiresthateachreactorcoolantpumpflywheelbeinspected pertherecommendations ofregulatory positionC.4.bofRegulatory Guide(RG)1.14,Revision1,August1975.Theregulatory positionofRG1.14concerning ISIcallsforanin-placeultrasonic volumetric examination oftheareasofhigherstressconcentration attheboreandkeywayatapproximately 3-yearintervals andasurfaceexamination ofallexposedsurfacesandcompleteultrasonic volumetric examination atapproximately 10-yearintervals.
TheproposedT/Srequiresthateitheraqualified in-placeUTexamination overthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (MTand/orPT)ofexposedsurfacesdefinedbythevolumeofthedisassembled flywheels beconducted onceevery10years.4.0DISCUSSION Technical Secification 4.4.10.1BasesT/S4.4.10.1ensuresthatthestructural integrity ofthereactorcoolantpumpflywheels willbemaintained atanacceptable levelthroughout thelifeoftheplant.Justification forProosedTechnical Secification ChanesTheproposedT/Samendment requesttoreducethefrequency andscopeofsurveillance oftheRCPflywheels isjustified forseveralreasons.Thischangeisconsistent withMr.Sheron's(Director DivisionofEngineering, OfficeofNuclearReactorRegulation) letterentitled"Acceptance forReferencing ofTopicalReportWCAP-14535,'TopicalReportonReactorCoolantPumpFlywheelInspection Elimination' andrelatedattachments.
Pertherequirement ofthisletter,wehaveconfirmed thattheRCPflywheels inplaceatCookNuclearPlantarecomposedofSA533Bmaterial.
ThoughWestinghouse ElectricCorporation reportWCAP-14535, entitled"TopicalReportonReactorCoolantPumpFlywheelInspection Elimination",
seekselimination offlywheelinspections, weonly Attachment 1toAEP:NRC:1245 Page2seektoreducethefrequency oftheseinspections toonceevery10years.WCAP-14535-concludes thefollowing.
1.Flywheels arecarefully designedandmanufactured fromexcellent qualitysteel,whichhasahighfracturetoughness.
2.Flywheeloverspeed isthecriticalloading,butleakbeforebreakhaslimitedthemaximumspeedtolessthan1500rpm.6.7.Flywheelinspections havebeenperformed for2Cyears,withnoindications ofserviceinducedflaws.Flywheelintegrity evaluations showveryhighflawtolerance fortheflywheels.
Crackextension overa60yearservicelifeisnegligible.
Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlife willnotsignificantly changetheprobability offailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreservice inspection oratworstearlyinplantlife,andcrackgrowthoverplantlifeisnegligible.
AsstatedintheSERassociated withWCAP-14535, assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Inspections resultinmanremexposureandthepotential forflywheeldamageduringdisassembly andreassembly.
Basedontheaboveconclusions, inspections ofRCPflywheels witha10-yearfrequency andmodifiedscopearejustified.
5.0 NOSIGNIFICANT
HAZARDSCONSIDERATION Wehaveevaluated theproposedT/Schangesandhavedetermined they'onotrepresent asignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c).Operation ofCookNuclearPlantinaccordance withtheproposedamendment willnot:1.Involveasinificantincreaseintherobabilit orconseenceofanaccidentreviouslevaluated Thischangewillreducetnefrequency andscopeofthesurveillance testingonthereactorcoolantpumpflywheels.
Operating powerplantshavebeeninspecting theirflywheels forover20yearswithnoflawsidentified whichaffectflywheelintegrity.
Pastexaminations performed tosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextension overa60yearservicelifeisnegligible.
Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlifewillnotsignificantly change'he probability offailure.Mostflawswhichcouldleadto Attachment 1toAEP:NRC:1245 Page3failurewouldbedetectedduringpreservice inspection or,atworst,earlyinplantlife,andcrackgrowthoverplantlifeisnegligible.
AsstatedintheSERassociated withWCAP-14535, assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Therefore, thechangeintestfrequency willnotendangerpublichealthorsafety.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated accident.
Createtheossibilit ofanewordifferent kindofaccidentfromanaccidentreviouslevaluated.
Thechangeswillnotintroduce anynewmodesofplantoperation, norwillanyphysicalchangestotheplantberequired.
Thus,thechangeswillnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated.
3.Involveasinificantreduction inamarinofaafetThischangewillreducethefrequency andscopeofthesurveillance testingonthereactorcoolantpumpflywheels.
Operating powerplantshavebeeninspecting theirflywheels forover20yearswithnoflawsidentified whichaffectflywheelintegrity.
Pastexaminations performed tosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextension overa60yearservicelifeisnegligible.
Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlifewillnotsignificantly changetheprobability offailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreservice irepection oratw'orstearlyinplantlife,andcrackgr.~thoverplantlifeisnegligible.
AsstatedintheSERassociated withWCAP-,14535,assuminganinitialcrackof10%ofthedistancef'romthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgiowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificant reduction inamarginofsafety.6.0PENDINGTSPROPOSALS IMPACTING THISSUBMITTAL TherearenootherT/Sproposals underreviewthatimpactthissubmittal~
.