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| {{#Wiki_filter:PR.IC)R.I"EV1ACCELERATEDRIDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9504060190,DOC.DATE:95/03/31NOTARIZED:YESDOCKETgFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316,AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk) | | {{#Wiki_filter:PR.IC)R.I"EV1ACCELERATED RIDSPROCESSING) |
| | REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9504060190, DOC.DATE: |
| | 95/03/31NOTARIZED: |
| | YESDOCKETgFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316, AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E. |
| | IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ApplicationforamendstolicensesDPR-58&DPR-74.AmendswouldmodifyTS3.9.4toprovideflexibilityinoperationofcontainmentpersonnel.airlocksduringcorealterations.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:.LTRtENCLJSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNAL:LECENTE01NRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS2'XTERNAL:NOACCOPIESLTTRENCL111111111110RECIPIENTIDCODE/NAMEPD3-1PDNMSS/DWM/LLDPNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL1122111111NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELI!vIINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTS'YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL12 R
| | Application foramendstolicensesDPR-58&DPR-74.Amends wouldmodifyTS3.9.4toprovideflexibility inoperation ofcontainment personnel. |
| IndianaMichiganPowerCompany'P.O.Box16631Columbus,OH43216FIMarch31,1995AEP:NRC'1220DocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENTTOTECHNICALSPECIFICATIONSECTION3/4.9.4FORCONTAINMENTPERSONNELAIRLOCKREQUIREMENTSThisletteranditsattachmentsconstituteanapplicationfor,amendmenttothetechnicalspecifications(T/Ss)forDonaldC.CookNuclearPlantUnits1and2.Specifically,weareproposingtomodifyT/Ss3.9.4entitledRefuelingOperations,.ContainmentBuildingPenetrations,toprovideflexibilityintheoperationofthecontainmentpersonnelairlocksduringCOREALTERATIONSbyexpandingtheexistinglimitingconditionforoperationtoincludetheestablishmentofcontainmentclosurecapabilityrequirements.ThisproposedamendmentisconsistentwithAmendments194(DPR-53)and171(DPR-69)approvedforuseattheCalvertCliffsNuclearPowerPlantintheNRC'stransmittalofAugust31,1994.TheCalvertCliffsamendmentallowsthepersonnelairlockdoorstobeopenduringCOREALTERATIONSprovidedcertainadministrativecontrolsareinplace.Attachment1providesadetaileddescriptionoftheproposedchanges,thejustificationforthechanges,andourdeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92.Attachment2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.I.GC03>95040601'PO950331PDRADOCK05000315~,.P'PDR | | airlocksduringcorealterations. |
| | DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:.LTR tENCLJSIZE:TITLE:ORSubmittal: |
| | GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL: |
| | LECENTE01NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2'XTERNAL: |
| | NOACCOPIESLTTRENCL111111111110RECIPIENT IDCODE/NAME PD3-1PDNMSS/DWM/LLDP NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1122111111NOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELI!vIINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS'YOU DON'TNEED!TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR13ENCL12 R |
| | IndianaMichiganPowerCompany'P.O.Box16631Columbus, OH43216FIMarch31,1995AEP:NRC'1220 DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen: |
| | DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENT TOTECHNICAL SPECIFICATION SECTION3/4.9.4FORCONTAINMENT PERSONNEL AIRLOCKREQUIREMENTS Thisletteranditsattachments constitute anapplication for,amendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing tomodifyT/Ss3.9.4entitledRefueling Operations,. |
| | Containment BuildingPenetrations, toprovideflexibility intheoperation ofthecontainment personnel airlocksduringCOREALTERATIONS byexpanding theexistinglimitingcondition foroperation toincludetheestablishment ofcontainment closurecapability requirements. |
| | Thisproposedamendment isconsistent withAmendments 194(DPR-53)and171(DPR-69)approvedforuseattheCalvertCliffsNuclearPowerPlantintheNRC'stransmittal ofAugust31,1994.TheCalvertCliffsamendment allowsthepersonnel airlockdoorstobeopenduringCOREALTERATIONS providedcertainadministrative controlsareinplace.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. |
| | I.GC03>95040601'PO 950331PDRADOCK05000315~,.P'PDR |
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| U.S.NuclearRegulatoryCommissionPage2AEP:NRC'1220TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(l),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Sincerely,qg'E9r(~E.E.FitzpatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMETHIS8/n/DAYOF~A1995No,aryPubiicMyCommissionExpires:-M-5'5'hAttachmentsCC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett | | U.S.NuclearRegulatory Commission Page2AEP:NRC'1220 TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee. |
| 'I ATTACHMENT1TOAEP:NRC:1220DESCRIPTIONANDJUSTIFICATIONOFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICALSPECIFICATIONS | | Incompliance withtherequirements of10CFR50.91(b)(l), |
| ~~E, Attachment1toAEP:NRC:1220Page1I.DESCRIPTIONOFCHANGESTheproposedamendmenttotechnicalspecification(T/S)3.9.4makesthefollowingspecificchangestotheCookNuclearPlantUnits1and2T/Ss:S394A.ExpandLimitingConditionForOperation3.9.4,item"b"(page3/49-4)toincludetheabilitytoleavebothpersonnelairlockdoorsinthe"open"positionduringCOREALTERATIONS.Asaresult,closurecapabilityofthecontainmentairlockdoorswillbeassuredinoneoftwoways;1)oneairlockdoorwillbemaintainedclosedduringCOREALTERATIONS,or2)bothairlocksmayremainopenprovidedcertainrestrictionsaresatisfiedincludingthepositioningofdedicatedpersonnelattheairlocktofacilitateclosure.,B.AfootnotehasalsobeenaddedtodefinewhatconstitutesanOPERABLEairlockdoorwhenimplementingthe"bothairlockdoorsopen"optionofthespecification.C.RevisetheBasesforspecification3/4.9.4(pageB3/49-1)toincludetherestrictionsassociatedwiththe"bothairlockdoorsopen"option.II.JUSTIFICATIONFORCHANGESTechnicalspecification3.9.4requiresthataminimumofonepersonnelairlockdoor,aswellasothercontainmentpenetrationsbeclosedduringCOREALTERATIONSandmovementofirradiatedfuelwithinthecontainment.Althoughthepresenttechnicalspecificationrequiresaminimumofoneairlockdoortobeclosedduringrefueling,theUFSARanalysisofaradioactivereleaseresultingfromafuelhandlingaccidentinsidecontainment,takesnocreditforcontainmentisolation.Duringarefuelingoutage,otherworkinthecontainmentdoesnotstopduringfuelmovementandCOREALTERATIONS.Thisrequiresthatpersonneloperatetheairlockdoorstoenterandexitthecontainment.StudiesofairlockdooroperationandmaintenanceatCookNuclearPlanthaveidentifiedthefollowingtrends.Airlockusage,duringthe1994refuelingoutage,fortheperiodsboundingCOREALTERATIONS(Sept.16th-20thandOct.18th-25th)totalled10,200entriesandexits.Assumingfourtofiveindividualsenteredthecontainmentperairlockcycle,theaveragenumberofairlockcyclesduringCOREALTERATIONSisconservativelyestimatedtobegreaterthan200perday.Suchheavyuseoftheairlockdoorswasnotanticipatedduringitsdesign.Asaresultofthisunexpectedlyheavyuse,failuresofthedoorhavemanifestedthemselvesas Attachment1toAEP:NRC:1220Page2problemsinthegearandinterlockalignmentsofthedoorslockingmechanismandhandwheelfailures.Inadditiontothewearandmaintenanceconcernsdescribedabove,theCalvertCliffssubmittalraisedconcernsregardingworkersafetyandthepracticalrealityoftheairlock'sabilitytopreventthereleaseofradioactivematerialfollowingafuelhandlingaccident.CalvertCliffsprovidedthefollowingargumentwhichwebelievetobeaccurate,realisticandapplicabletoCookNuclearPlant:"Therearealargenumberofpeopleinthecontainmentduringarefuelingoutage,evenduringfuelmovementandCOREALTERATIONS.Shouldafuelhandlingaccidentoccur,itwouldtakeanumberofcyclesoftheairlocktoevacuatepersonnelfromcontainment.Witheachairlockcycle,morecontainmentairwouldbereleased.Whilewaitingfortheirturntoexit,the"workerswouldbeexposedtothereleasedactivity."Toaddressthepotentialforworkerexposureandtoincreasetheavailability/maintainabilityofthepersonnelairlockdooratCookNuclearPlant,weproposetoallowbothairlockstobeopenduringCOREALTERATIONSprovidedthefollowingadministrativecontrolsareestablished.Theairlockdoorsshallbecontrolledinthefollowingmanner:1.aminimumofonedoorineachairlockisclosed,or2.bothairlockdoorsmaybeopenprovided:a.onedoorineachairlockisOPERABLE,b.refuelingcavitylevelisgreaterthan23feet,andc.adesignatedindividualisavailableatalltimestoclosetheairlockifrequired.Whenconsideringtheproposedamendment,thedoseconsequencesofafuelhandlingaccidentwerereviewed.TwocasesarediscussedintheUFSAR,oneforafuelhandlingaccidentintheauxiliarybuilding,theotherforasimilaraccidentinsidecontainment.Thedesignbasisaccidentisthecompleteruptureofthehighestratedspentfuelassembly.Whenconsideringthetwoaccidentanalysesthecontainmenteventwasconsideredtoprovidetheboundingconditions.Thiswasbasedonthefactthatnoreductioninthepotentialthyroiddoeswasassumedsincecharcoalfiltrationwasnotconsideredandnocreditwastakenforcontainmentisolation.Theaccidentinsidecontainment(assuming3588MWTpoweroperation)gave | | copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Sincerely, qg'E9r(~E.E.Fitzpatrick VicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS8/n/DAYOF~A1995No,aryPubiicMyCommission Expires:-M-5'5'hAttachments CC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector |
| | -BridgmanJ.R.Padgett |
| | 'I ATTACHMENT 1TOAEP:NRC:1220 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS |
| | ~~E, Attachment 1toAEP:NRC:1220 Page1I.DESCRIPTION OFCHANGESTheproposedamendment totechnical specification (T/S)3.9.4makesthefollowing specificchangestotheCookNuclearPlantUnits1and2T/Ss:S394A.ExpandLimitingCondition ForOperation 3.9.4,item"b"(page3/49-4)toincludetheabilitytoleavebothpersonnel airlockdoorsinthe"open"positionduringCOREALTERATIONS. |
| | Asaresult,closurecapability ofthecontainment airlockdoorswillbeassuredinoneoftwoways;1)oneairlockdoorwillbemaintained closedduringCOREALTERATIONS, or2)bothairlocksmayremainopenprovidedcertainrestrictions aresatisfied including thepositioning ofdedicated personnel attheairlocktofacilitate closure., |
| | B.Afootnotehasalsobeenaddedtodefinewhatconstitutes anOPERABLEairlockdoorwhenimplementing the"bothairlockdoorsopen"optionofthespecification. |
| | C.RevisetheBasesforspecification 3/4.9.4(pageB3/49-1)toincludetherestrictions associated withthe"bothairlockdoorsopen"option.II.JUSTIFICATION FORCHANGESTechnical specification 3.9.4requiresthataminimumofonepersonnel airlockdoor,aswellasothercontainment penetrations beclosedduringCOREALTERATIONS andmovementofirradiated fuelwithinthecontainment. |
| | Althoughthepresenttechnical specification requiresaminimumofoneairlockdoortobeclosedduringrefueling, theUFSARanalysisofaradioactive releaseresulting fromafuelhandlingaccidentinsidecontainment, takesnocreditforcontainment isolation. |
| | Duringarefueling outage,otherworkinthecontainment doesnotstopduringfuelmovementandCOREALTERATIONS. |
| | Thisrequiresthatpersonnel operatetheairlockdoorstoenterandexitthecontainment. |
| | Studiesofairlockdooroperation andmaintenance atCookNuclearPlanthaveidentified thefollowing trends.Airlockusage,duringthe1994refueling outage,fortheperiodsboundingCOREALTERATIONS (Sept.16th-20thandOct.18th-25th)totalled10,200entriesandexits.Assumingfourtofiveindividuals enteredthecontainment perairlockcycle,theaveragenumberofairlockcyclesduringCOREALTERATIONS isconservatively estimated tobegreaterthan200perday.Suchheavyuseoftheairlockdoorswasnotanticipated duringitsdesign.Asaresultofthisunexpectedly heavyuse,failuresofthedoorhavemanifested themselves as Attachment 1toAEP:NRC:1220 Page2problemsinthegearandinterlock alignments ofthedoorslockingmechanism andhandwheel failures. |
| | Inadditiontothewearandmaintenance concernsdescribed above,theCalvertCliffssubmittal raisedconcernsregarding workersafetyandthepractical realityoftheairlock's abilitytopreventthereleaseofradioactive materialfollowing afuelhandlingaccident. |
| | CalvertCliffsprovidedthefollowing argumentwhichwebelievetobeaccurate, realistic andapplicable toCookNuclearPlant:"Therearealargenumberofpeopleinthecontainment duringarefueling outage,evenduringfuelmovementandCOREALTERATIONS. |
| | Shouldafuelhandlingaccidentoccur,itwouldtakeanumberofcyclesoftheairlocktoevacuatepersonnel fromcontainment. |
| | Witheachairlockcycle,morecontainment airwouldbereleased. |
| | Whilewaitingfortheirturntoexit,the"workerswouldbeexposedtothereleasedactivity." |
| | Toaddressthepotential forworkerexposureandtoincreasetheavailability/maintainability ofthepersonnel airlockdooratCookNuclearPlant,weproposetoallowbothairlockstobeopenduringCOREALTERATIONS providedthefollowing administrative controlsareestablished. |
| | Theairlockdoorsshallbecontrolled inthefollowing manner:1.aminimumofonedoorineachairlockisclosed,or2.bothairlockdoorsmaybeopenprovided: |
| | a.onedoorineachairlockisOPERABLE, b.refueling cavitylevelisgreaterthan23feet,andc.adesignated individual isavailable atalltimestoclosetheairlockifrequired. |
| | Whenconsidering theproposedamendment, thedoseconsequences ofafuelhandlingaccidentwerereviewed. |
| | Twocasesarediscussed intheUFSAR,oneforafuelhandlingaccidentintheauxiliary |
| | : building, theotherforasimilaraccidentinsidecontainment. |
| | Thedesignbasisaccidentisthecompleteruptureofthehighestratedspentfuelassembly. |
| | Whenconsidering thetwoaccidentanalysesthecontainment eventwasconsidered toprovidetheboundingconditions. |
| | Thiswasbasedonthefactthatnoreduction inthepotential thyroiddoeswasassumedsincecharcoalfiltration wasnotconsidered andnocreditwastakenforcontainment isolation. |
| | Theaccidentinsidecontainment (assuming 3588MWTpoweroperation) gave |
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| Attachment1to,AEP:NRC:1220Page3a0-2hoursiteboundarythyroiddoseofapproximately100rem,andawholebodydoseof1.4rem.Bothofthesevaluesremainsignificantlybelowthe300remthyroidand25remwholebodylimitsestablishedin10CFR100.Basedonthesefindings,itwasdeterminedthatallowingbothairlockdoorstoremainopenduringCOREALTERATIONSwouldnotincreasetheanalyzedsiteboundarydoseresultingfromafuelhandlingaccident.Comparedtotheanalyzedcase,thedoseconsequencesofareleasethroughanopenairlockmayevenbereducedbecauseofretentiontimeintheauxiliarybuildingandthepossibilityoffiltrationthroughtheauxiliarybuildingventilationsystem.III.0CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificanthazardsconsiderationifthechangedoesnot:involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3.involveasignificantreductioninamarginofsafety.Criterion1Thedesignbasisfuelhandlingaccidentistheruptureofthehighestratedfuelassembly.Asdiscussedpreviously,theconsequencesofanaccidentinsidecontainment(i.e.,siteboundarydose),withbothairlockdoorsareboundedbytheexistingfuelhandlingaccidentcurrentlypresentedinourUFSAR.Sincethecontainmentairlockdoorsdonotaffectthefailuremechanismofafuelassemblyduringafuelhandlingaccident,webelievethatthisamendmentrequestdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Additionally,nocreditwastakenforcontainmentclosureintheaccidentanalysis.Therefore,basedontheseconsiderations,itisconcludedthattheproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.
| | Attachment 1to,AEP:NRC:1220 Page3a0-2hoursiteboundarythyroiddoseofapproximately 100rem,andawholebodydoseof1.4rem.Bothofthesevaluesremainsignificantly belowthe300remthyroidand25remwholebodylimitsestablished in10CFR100.Basedonthesefindings, itwasdetermined thatallowingbothairlockdoorstoremainopenduringCOREALTERATIONS wouldnotincreasetheanalyzedsiteboundarydoseresulting fromafuelhandlingaccident. |
| | Comparedtotheanalyzedcase,thedoseconsequences ofareleasethroughanopenairlockmayevenbereducedbecauseofretention timeintheauxiliary buildingandthepossibility offiltration throughtheauxiliary buildingventilation system.III.0CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.Criterion 1Thedesignbasisfuelhandlingaccidentistheruptureofthehighestratedfuelassembly. |
| | Asdiscussed previously, theconsequences ofanaccidentinsidecontainment (i.e.,siteboundarydose),withbothairlockdoorsareboundedbytheexistingfuelhandlingaccidentcurrently presented inourUFSAR.Sincethecontainment airlockdoorsdonotaffectthefailuremechanism ofafuelassemblyduringafuelhandlingaccident, webelievethatthisamendment requestdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. |
| | Additionally, nocreditwastakenforcontainment closureintheaccidentanalysis. |
| | Therefore, basedontheseconsiderations, itisconcluded thattheproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. |
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| Attachment1toAEP:NRC:1220Page4Criterion2Asstatedinresponsetocriterionone,thepositionofthecontainmentairlockdoorsinnowayaffectsthemechanismbywhichaspentfuelassemblyisdamagedduringafuelhandlingaccident.Thus,itisconcludedthattheproposedchangesdonotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Criterion3Themarginforsafetyasdefinedin10CFR100hasnotbeenreduced.Asdiscussedpreviously,theexistingfuelhandlingaccidentanalysisforaneventinsidecontainmenttakesnocreditfortheisolationofcontainment.Asaresult,thepositionoftheairlockdoorshasnoimpactontheanalyzedsiteboundarydosesresultingfromsuchanaccident.Basedontheseconsiderations,itisconcludedthatthechangesdonotinvolveasignificantreductioninamarginofsafety.
| | Attachment 1toAEP:NRC:1220 Page4Criterion 2Asstatedinresponsetocriterion one,thepositionofthecontainment airlockdoorsinnowayaffectsthemechanism bywhichaspentfuelassemblyisdamagedduringafuelhandlingaccident. |
| ATTACHMENT2TOAEP:NRC:1220EXISTINGTECHNICALSPECIFICATIONPAGESMA%MDTOREFLECTPROPOSEDCHANGES e1~~}}
| | Thus,itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. |
| | Criterion 3Themarginforsafetyasdefinedin10CFR100hasnotbeenreduced.Asdiscussed previously, theexistingfuelhandlingaccidentanalysisforaneventinsidecontainment takesnocreditfortheisolation ofcontainment. |
| | Asaresult,thepositionoftheairlockdoorshasnoimpactontheanalyzedsiteboundarydosesresulting fromsuchanaccident. |
| | Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant reduction inamarginofsafety. |
| | ATTACHMENT 2TOAEP:NRC:1220 EXISTINGTECHNICAL SPECIFICATION PAGESMA%MDTOREFLECTPROPOSEDCHANGES e1~~}} |
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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
PR.IC)R.I"EV1ACCELERATED RIDSPROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9504060190, DOC.DATE:
95/03/31NOTARIZED:
YESDOCKETgFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316, AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
SUBJECT:
Application foramendstolicensesDPR-58&DPR-74.Amends wouldmodifyTS3.9.4toprovideflexibility inoperation ofcontainment personnel.
airlocksduringcorealterations.
DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:.LTR tENCLJSIZE:TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
LECENTE01NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2'XTERNAL:
NOACCOPIESLTTRENCL111111111110RECIPIENT IDCODE/NAME PD3-1PDNMSS/DWM/LLDP NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1122111111NOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELI!vIINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS'YOU DON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 R
IndianaMichiganPowerCompany'P.O.Box16631Columbus, OH43216FIMarch31,1995AEP:NRC'1220 DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENT TOTECHNICAL SPECIFICATION SECTION3/4.9.4FORCONTAINMENT PERSONNEL AIRLOCKREQUIREMENTS Thisletteranditsattachments constitute anapplication for,amendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing tomodifyT/Ss3.9.4entitledRefueling Operations,.
Containment BuildingPenetrations, toprovideflexibility intheoperation ofthecontainment personnel airlocksduringCOREALTERATIONS byexpanding theexistinglimitingcondition foroperation toincludetheestablishment ofcontainment closurecapability requirements.
Thisproposedamendment isconsistent withAmendments 194(DPR-53)and171(DPR-69)approvedforuseattheCalvertCliffsNuclearPowerPlantintheNRC'stransmittal ofAugust31,1994.TheCalvertCliffsamendment allowsthepersonnel airlockdoorstobeopenduringCOREALTERATIONS providedcertainadministrative controlsareinplace.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
I.GC03>95040601'PO 950331PDRADOCK05000315~,.P'PDR
U.S.NuclearRegulatory Commission Page2AEP:NRC'1220 TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.
Incompliance withtherequirements of10CFR50.91(b)(l),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Sincerely, qg'E9r(~E.E.Fitzpatrick VicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS8/n/DAYOF~A1995No,aryPubiicMyCommission Expires:-M-5'5'hAttachments CC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett
'I ATTACHMENT 1TOAEP:NRC:1220 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS
~~E, Attachment 1toAEP:NRC:1220 Page1I.DESCRIPTION OFCHANGESTheproposedamendment totechnical specification (T/S)3.9.4makesthefollowing specificchangestotheCookNuclearPlantUnits1and2T/Ss:S394A.ExpandLimitingCondition ForOperation 3.9.4,item"b"(page3/49-4)toincludetheabilitytoleavebothpersonnel airlockdoorsinthe"open"positionduringCOREALTERATIONS.
Asaresult,closurecapability ofthecontainment airlockdoorswillbeassuredinoneoftwoways;1)oneairlockdoorwillbemaintained closedduringCOREALTERATIONS, or2)bothairlocksmayremainopenprovidedcertainrestrictions aresatisfied including thepositioning ofdedicated personnel attheairlocktofacilitate closure.,
B.Afootnotehasalsobeenaddedtodefinewhatconstitutes anOPERABLEairlockdoorwhenimplementing the"bothairlockdoorsopen"optionofthespecification.
C.RevisetheBasesforspecification 3/4.9.4(pageB3/49-1)toincludetherestrictions associated withthe"bothairlockdoorsopen"option.II.JUSTIFICATION FORCHANGESTechnical specification 3.9.4requiresthataminimumofonepersonnel airlockdoor,aswellasothercontainment penetrations beclosedduringCOREALTERATIONS andmovementofirradiated fuelwithinthecontainment.
Althoughthepresenttechnical specification requiresaminimumofoneairlockdoortobeclosedduringrefueling, theUFSARanalysisofaradioactive releaseresulting fromafuelhandlingaccidentinsidecontainment, takesnocreditforcontainment isolation.
Duringarefueling outage,otherworkinthecontainment doesnotstopduringfuelmovementandCOREALTERATIONS.
Thisrequiresthatpersonnel operatetheairlockdoorstoenterandexitthecontainment.
Studiesofairlockdooroperation andmaintenance atCookNuclearPlanthaveidentified thefollowing trends.Airlockusage,duringthe1994refueling outage,fortheperiodsboundingCOREALTERATIONS (Sept.16th-20thandOct.18th-25th)totalled10,200entriesandexits.Assumingfourtofiveindividuals enteredthecontainment perairlockcycle,theaveragenumberofairlockcyclesduringCOREALTERATIONS isconservatively estimated tobegreaterthan200perday.Suchheavyuseoftheairlockdoorswasnotanticipated duringitsdesign.Asaresultofthisunexpectedly heavyuse,failuresofthedoorhavemanifested themselves as Attachment 1toAEP:NRC:1220 Page2problemsinthegearandinterlock alignments ofthedoorslockingmechanism andhandwheel failures.
Inadditiontothewearandmaintenance concernsdescribed above,theCalvertCliffssubmittal raisedconcernsregarding workersafetyandthepractical realityoftheairlock's abilitytopreventthereleaseofradioactive materialfollowing afuelhandlingaccident.
CalvertCliffsprovidedthefollowing argumentwhichwebelievetobeaccurate, realistic andapplicable toCookNuclearPlant:"Therearealargenumberofpeopleinthecontainment duringarefueling outage,evenduringfuelmovementandCOREALTERATIONS.
Shouldafuelhandlingaccidentoccur,itwouldtakeanumberofcyclesoftheairlocktoevacuatepersonnel fromcontainment.
Witheachairlockcycle,morecontainment airwouldbereleased.
Whilewaitingfortheirturntoexit,the"workerswouldbeexposedtothereleasedactivity."
Toaddressthepotential forworkerexposureandtoincreasetheavailability/maintainability ofthepersonnel airlockdooratCookNuclearPlant,weproposetoallowbothairlockstobeopenduringCOREALTERATIONS providedthefollowing administrative controlsareestablished.
Theairlockdoorsshallbecontrolled inthefollowing manner:1.aminimumofonedoorineachairlockisclosed,or2.bothairlockdoorsmaybeopenprovided:
a.onedoorineachairlockisOPERABLE, b.refueling cavitylevelisgreaterthan23feet,andc.adesignated individual isavailable atalltimestoclosetheairlockifrequired.
Whenconsidering theproposedamendment, thedoseconsequences ofafuelhandlingaccidentwerereviewed.
Twocasesarediscussed intheUFSAR,oneforafuelhandlingaccidentintheauxiliary
- building, theotherforasimilaraccidentinsidecontainment.
Thedesignbasisaccidentisthecompleteruptureofthehighestratedspentfuelassembly.
Whenconsidering thetwoaccidentanalysesthecontainment eventwasconsidered toprovidetheboundingconditions.
Thiswasbasedonthefactthatnoreduction inthepotential thyroiddoeswasassumedsincecharcoalfiltration wasnotconsidered andnocreditwastakenforcontainment isolation.
Theaccidentinsidecontainment (assuming 3588MWTpoweroperation) gave
Attachment 1to,AEP:NRC:1220 Page3a0-2hoursiteboundarythyroiddoseofapproximately 100rem,andawholebodydoseof1.4rem.Bothofthesevaluesremainsignificantly belowthe300remthyroidand25remwholebodylimitsestablished in10CFR100.Basedonthesefindings, itwasdetermined thatallowingbothairlockdoorstoremainopenduringCOREALTERATIONS wouldnotincreasetheanalyzedsiteboundarydoseresulting fromafuelhandlingaccident.
Comparedtotheanalyzedcase,thedoseconsequences ofareleasethroughanopenairlockmayevenbereducedbecauseofretention timeintheauxiliary buildingandthepossibility offiltration throughtheauxiliary buildingventilation system.III.0CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.Criterion 1Thedesignbasisfuelhandlingaccidentistheruptureofthehighestratedfuelassembly.
Asdiscussed previously, theconsequences ofanaccidentinsidecontainment (i.e.,siteboundarydose),withbothairlockdoorsareboundedbytheexistingfuelhandlingaccidentcurrently presented inourUFSAR.Sincethecontainment airlockdoorsdonotaffectthefailuremechanism ofafuelassemblyduringafuelhandlingaccident, webelievethatthisamendment requestdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Additionally, nocreditwastakenforcontainment closureintheaccidentanalysis.
Therefore, basedontheseconsiderations, itisconcluded thattheproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Attachment 1toAEP:NRC:1220 Page4Criterion 2Asstatedinresponsetocriterion one,thepositionofthecontainment airlockdoorsinnowayaffectsthemechanism bywhichaspentfuelassemblyisdamagedduringafuelhandlingaccident.
Thus,itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Criterion 3Themarginforsafetyasdefinedin10CFR100hasnotbeenreduced.Asdiscussed previously, theexistingfuelhandlingaccidentanalysisforaneventinsidecontainment takesnocreditfortheisolation ofcontainment.
Asaresult,thepositionoftheairlockdoorshasnoimpactontheanalyzedsiteboundarydosesresulting fromsuchanaccident.
Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant reduction inamarginofsafety.
ATTACHMENT 2TOAEP:NRC:1220 EXISTINGTECHNICAL SPECIFICATION PAGESMA%MDTOREFLECTPROPOSEDCHANGES e1~~