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{{#Wiki_filter:ACCELERATEDDITRJBUTIONDEMONSATIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:8910310003DOC.DATE:89/10/17NOTARIZED:NODOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,Indiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATIONALEXICH,M.P.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)SUBZECT:ApplicationforamendstoLicensesDPR-58&DPR-74,revisingTechSpecsrecontrolledleakage.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTESRDRECIPIENTIDCODE/NAMEPD3-1LAGIITTER,Z'NTERNAL:NRR/DEST/ADS7ENRR/DEST/ICSBNRR/DEST/RSB8ENUDOCS-ABSTRACTOGC/HDS1RES/DSIR/EIBEXTERNAL:LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENTIDCODE/NAMEPD3-1PDNRR/DEST/ESB8DNRR/DEST/MTB9HNRR/DOEA/TSB11OC/~GFILOlNRCPDRCOPIESLTTRENCL111111111'1111DDSDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR21ENCL19Dp8, IndianaMichiganPowerCompanyP.O.Box16631Columbus,OH43216RSNSIAMAMCNSIMNPQHfMAEP'NRC:107010CFR50.90DonaldC.CookNuclearPlantUnits1and2LicenseNos.DPR-58andDPR-74DocketNos.50-315and50-316CONTROLLEDLEAKAGETECHNICALSPECIFICATIONCHANGEU.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyOctober17,1989
{{#Wiki_filter:ACCELERATED DITRJBUTION DEMONSATIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:8910310003 DOC.DATE:
89/10/17NOTARIZED:
NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,Indiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)SUBZECT:Application foramendstoLicensesDPR-58&DPR-74,revising TechSpecsrecontrolled leakage.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
GeneralDistribution NOTESRDRECIPIENT IDCODE/NAME PD3-1LAGIITTER,Z'NTERNAL:
NRR/DEST/ADS 7ENRR/DEST/ICSB NRR/DEST/RSB 8ENUDOCS-ABSTRACT OGC/HDS1RES/DSIR/EIB EXTERNAL:
LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DEST/ESB 8DNRR/DEST/MTB 9HNRR/DOEA/TS B11OC/~GFILOlNRCPDRCOPIESLTTRENCL111111111'1111DDSDNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR21ENCL19Dp8, IndianaMichiganPowerCompanyP.O.Box16631Columbus, OH43216RSNSIAMAMCNSIMNPQHfMAEP'NRC:1070 10CFR50.90DonaldC.CookNuclearPlantUnits1and2LicenseNos.DPR-58andDPR-74DocketNos.50-315and50-316CONTROLLED LEAKAGETECHNICAL SPECIFICATION CHANGEU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyOctober17,1989


==DearDr.Murley:==
==DearDr.Murley:==
ThisletteranditsattachmentsconstituteanapplicationforamendmenttotheTechnicalSpecifications(T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2,Specifically,weareproposingtomodifyT/S3/4.4.6.2(OperationalLeakage)anditsassociatedBasessuchthattherequirementsforcontrolledleakagearemademorerestrictive.Thereasonforthechangeandour10CFR50.92significanthazardsanalysisarefoundinAttachmentl.Attachment2containstheproposedrevisedT/Spages,Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.ThisT/SchangeisintendedtocorrectadeficiencyinourpresentT/Sssothattheassumptionsoftheapplicableaccidentanalysisareadequatel'yprotected.AsdescribedinAttachment1tothisletter,wehaveadministrativelyimplementedrestrictionsabovethepresentT/Srequirementsthatareprotectingtheaccidentanalysisassumptions.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandbytheNuclearSafetyandDesignReviewCommittee,Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.R.C.CallenoftheMichiganPublicServiceCommissionandtheMichiganDepartmentofPublicHealth.85'i03i000S'8'yl-017----~PDRADGCK05000315PPQCIJ Dr.T.E.Murley-2-AEP:NRC:1070Attachment1tothisletterincludesAEPdrawingsOP-2-5129andOP-2-5128A.InaccordancewiththerestrictionsastousesetforthontheAEPdrawings,AEPherebyreleasesthesedocumentstotheNRCforitsinformationanduseinconnectionwiththissubmittal.AEPalsopermitstheNRCtoreproducethedrawingsasnecessarytofacilitatereviewanddistributionofthedrawingstomeetNRCrequirements.ThisdocumenthasbeenpreparedfollowingCorporateproceduresthatincorporateareasonablesetofcontrolstoensureitsaccuracyandcompletenesspriortosignaturebytheundersigned.Sincerely,M..AlechVicePresidentldpAttachmentscc:D.H.Vi.lliams,Jr.A.A.Blind-BridgmanR.C.CallenG.CharnoffA.B.DavisNRCResidentInspector-BridgmanNFEMSectionChief ATTACHMENT1TOAEP;NRC:1070REASONSAND10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTTECHNICALSPECIFICATIONS Attachment1toAEP:NRC:1070Page1IntroductionTheTechnicalSpecification(T/S)changeproposedinthisletterisintendedtoensuretheT/Ssaccuratelyreflecttherequirementsofthesafetyanalysiswithregardstocontrolledleakage.Tofacilitatethereview,wehaveincludedthefollowingflowdiagrams:1)OP-2-5129CVCSReactorLetdownandCharging2)OP-2-5128AReactorCoolantDescritionofChaneAscurrentlywritten,T/S3,4.6.2.e(OperationalLeakage)limitscontrolledleakageto52gpm.Surveillancerequirement4.4.6.2.1.requiresmeasurementofcontrolledleakageatleastonceper31days.ControlledleakageisdefinedinSection1oftheT/Ssas"thatsealwaterflowsuppliedtothereactorcoolantpumpseals."VeareproposingtoamendthesubjectT/Ssuchthatthecontrolledleakagelimitisexpressedasalineresistance,illratherthanaspecificflowrate.Theseallineresistancewbemeasuredatleastonceper31dayswhenthepressurizerpressureiswithin20psiofitsnominalfullpressure~alue.Theseallineresistancemeasuredduring2thesurveillancemustbbegreaterthanorequalto2.27E-1ft/gpm.TheseallineSL'sistanceRisdeterminedfromthefollowingexpression:R~2.31(P-P)SLQ2where:Pchargingpumpheaderpressure,psigCHPP2112psig(Unit1lowpressureoperation)SX2262psig(Unit1highpressureoperation)2262psig(Unit2operation)232.31conversionfactor(12in/ft)/(62.3lb/ft)totalsealinjectionflow,gpmAdditionally,wehaveaddedanexemptionfromtherequirementsofT/S4.0.4forentryintoModes3and4,deletedafootnotefromT/S3.4.6.2Action(c)involvingreportingrequirementsforreactorcoolantpressureboundaryleakage,andmodifiedtheBasessectiontoreflect'thecontrolledleakagerequirementchange, Attachment1toAEP:NRC:1070Page2ReasonforChaneThechangetothecontrolledleakagerequirementsresultsfromourconclusionthatthepresentlimitof52gpmcannotbyitselfensurecompliancewiththeassumptionsofthesafetyanalysis.FortheLOCAanalyseswithminimumsafeguardsassumptions,thefuelvendorsassumethatalloftheflowthatisdivertedfromtheboroninjectiontank(BIT)linebythesealinjectionlineisunavailableforcorecooling.(Althoughaportionofthesealwaterisinjectedintothereactorcoolantsystem,thereisnoT/Slimitonthisflowandthereforeallofthesealflowisassumedunavailableforcorecooling,)Thefuelvendoranalysesassumeaseallinehydraulicresistanceof0.227ft/gpm.Surveillancerequirement4.4.6.2.l,cisintendedtoverifythattheactualseallineresistanceisgreaterthanorequaltothisvalue.ItiscomplementedbyT/S4.5.2.h(ECCSSubsystems),which,asdiscussedinT/SBases3/4.5,2and3/4.5.3,assuresthattheBITthrottlevalvesareadjustedsuchthat:a)totalpumpflowdoesnotexceedrunoutconditionswhenthesystemisinitsminimumresistanceconfiguration,b)theproperflowsplitexistsbetweeninjectionpointsinaccordancewiththeassumptionsusedintheECCS-LOCAanalyses,andc)thetotalECCSflowtoallinjectionpointsisequaltoorabovethatassumedintheECCS-LOCAanalyses.Thenominaldevelopedheadofthechargingpumpatrunout(550gpm)isapproximately1431feet.Therefore,theflowdivertedthroughtheseallineunderEmergencyCoreCoolingSystem(ECCS)operationat0psigis:(1431ft/0'27ft/gpm)21/279gpmAsaresult,T/S4.5.2.hspecifiesanominalpumprunoutflowrateof550gpmwithasimulatedsealflowof80gpmandamaximumof470gpmthroughtheBIT.Duringnormaloperation,theUnit2pressurizerpressureismaintainedatanominalpressureof2235psig.Theresultingpressureatthesealinjectionpointinthereactorcoolantpumpisapproximately2260psig.Assumingnormalletdown(75gpm),thechargingpumpdischargepressureshouldbeatleast2413psig.Thecorrespondingsealinjectionflowrateis:((2413-2260)psi/(0.227ft/gpm)2+(12in/ft)/(62lb/ft))40gpm Attachment1toAEP:NRC:1070Page3ThecurrentT/Sonlyspecifiesamaximumflowrate.TheT/SdoesnotprovideanylimitsonRCSorpumpdischargepressurethatcorrespondtotheflowlimit.Asseenintheexampleabove,the52gpmlimitwouldbenonconservativewiththechargingpumpheadassumedintheexample.TheWestinghouseStandardT/Ssspecifyacontrolledleakagelimitingpm.TheStandardT/Ssurveillancerequirementspecifiesthatthemodulatingvalve(correspondingtoCookNuclearPlantvalveQRV-251,shownatlocationJ-5ondrawingOP-2-5129)mustbefullyopen.AlthoughthisisanenhancementoverthepresentCookNuclearPlantT/S,itpresentsoperationaldifficultiessinceitrequiresvalveQRV-251tobefullyopenedinordertoperformthetest.SinceQRV-251isthemainvalveusedtothrottlechargingflowduringnormaloperations,itisnotgenerallyfullyopen.TheoperatormustcarefullyadjustQRV-200(shownatlocationH-3ondrawingOP-2-5129)tomaintainthenecessarychargingflowandpressurizerlevelduringthetest.SincewehaverecognizedthatthepresentT/Sisinadequate,wehaveimplementedadministrativecontrolstoensurethatthecontrolledleakagesurveillanceaccuratelyreflectsthesafetyanalysisassumptions.Controlledleakage,asmeasuredduringthesurveillance,isadministrativelylimitedto40gpm,WearepresentlyperformingthesurveillanceoutlinedbytheStandardT/S,exceptthatwemeasurethechargingpumpheaderpressuretoensureitisconsistentwiththe40gpmcontrolledleakagelimitandtheresistanceassumedintheWestinghouseanalysis.OurproposedT/SchangeensuresthattheaccidentanalysisassumptionsareprotectedwhileeliminatingthedifficultyassociatedwiththeStandardT/Ssurveillance.Theactuallineresistanceisdeterminedratherthanasimpleflowrate.Inperformingthesurveillance,wearecurrentlyplanningtomeasurepumpdischargepressureusingpressureinstrumentQPI-250,sinceitreadsoutinthe'controlroom.TheinstrumentisinthepumpdischargeheaderdownstreamofQRV-251.Thisisconservativesinceitpredictsalowersystemresistanceandthereforewillmakeitmoredifficulttopassthetest.Also,sincepumpdischargepressureismeasureddownstreamofQRV-251,thereisnoneedtofullyopenthevalve,asthestandardT/Srequires,(TheinstrumentisshownatlocationK-4ondrawingOP-2-5129).SeallineflowwillbedeterminedbysummingtheflowindicatedinthecontrolroombyinstrumentsQFI210,220,230,and240,thatindicatethesealflowtoreactorcoolantpumps1through4,respectively.(TheinstrumentsareshownatlocationB-4ondrawingOP-2-5128A.)Theconversionfrompressurizerpressuretosealinjectionpointpressure(P)wascalculatedusingamethodologyprovidedtousbyWeshinghouse.Thismethodologyaccountsforpressureeffectssuchasthedifferenceinelevationbetweenpressurizerprogrammedlevelandtheseal-injection Attachment1toAEP:NRC:1070Page4points.TheWestinghouseequationswereappliedtoprogrammedRCSconditions(temperatureandpressurizerlevel)forbothunitsatvariouspowerlevels.ThevaluesforPIspecifiedintheproposedT/Sscorrespondto100%poweroperationsincethisconservativelyresultsinthelargestvalueofP.TwovaluesforP>arespecifiedforUnit1,correspondingtothetwodiscretepressurizerpressurevalues(2235psigand2085psig)SIwhicharesupportedbytheUnit1reducedtemperatureandpressureprogram(ReferenceUnit1T/SAmendment126).Theseallineresistance,asdeterminedbytheproposedsurveillancerequirement,isapplicableatfullpressure'onditions.Thisisbecausethepressureatthesealin]ectionpoint,whichcannotbedirectlymeasured,hasbeencalculatedassumingfullpressureoperation,ThisisrecognizedbytheStandardT/S,whichspecifiestheLCOandthesurveillancerequirementatapressurizerpressureof2235+20psig,(Inpractice,fullpressureoperationisthemostlimitingbecauseitrequiresthelowestlineresistancetoprovideadequateflowtothereactorcoolantpumpseals.)WehaveaddedafootnotetotheLCOandwordedtheproposedsurveillancerequirementsuchthatitisclearthattheT/Sisapplicablewithaveragepressurizerpressureatitsfullpressurevalue.(Wehavemaintainedthe20psitolerancefromtheStandardT/S,sincepressurizerpressuremayfluctuateslightlyarounditsnominalvalue.)WehavealsoaddedaT/S4.0.4exemptionforT/S4.4.6.2.1forentryintoModes3and4.The4.0.4exemptionwillallowentryintoModes3and4beforethecontrolledleakagesurveillanceiscompleted,ThischangeisconsistentwiththeStandardT/S.Asdiscussedabove,thesurveillanceistobeperformedwiththeRCSfullypressurized.ThisconditionistypicallyestablishedinMode3.WhiletheRCSpressureischanging,itmaybenecessarytoad]ustsealflowtothereactorcoolantpumpsusingneedlevalvesCS-438-1,-2,-3,and-4,(Thesevalvesareshownondrawing2-5128AatB-4.)Achangeinneedlevalvepositionaltersthesystemresistance,renderingobsoleteanyresistancemeasurementstakenbeforehand.WearealsoproposingtodeleteafootnoteassociatedwithT/S3,4.6.2Action(c)thatinvolvesreportingofreactorcoolantpressureboundaryleakagepursuanttoT/S6.9.1~ThereportabilityrequirementsofT/S6,9,1havebeenmodifiedbecauseofchangestotheLERrule(10CFR50.73),andT/S6.9.1nolongercontainsrequirementsrelatedtoreportingofpressureboundaryleakage.Thischangeisthereforepurelyadministrativeinnature,intendedonlytoremoveasupersededreferencefromtheT/Ss.
Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2,Specifically, weareproposing tomodifyT/S3/4.4.6.2 (Operational Leakage)anditsassociated Basessuchthattherequirements forcontrolled leakagearemademorerestrictive.
Attachment1toAEP:NRC:1070Page510CFR50.92CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:1)Involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,2)"Createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluate'd,or3)Involveasignificantreductioninamarginofsafety.Criterion1WeareproposingtomodifytheT/SsurveillancerequirementforcontrolledleakagesuchthatitaccuratelyreflectstheassumptionsoftheLOCAanalysis.ThepresentT/Swordingisvague,anddoesnotbyitselfensureconsistencywiththeanalysis,Therevisedsurveillancerequirementplacesadditionalrestrictionsontheplant,andwouldbeexpectedtoincrease,ratherthandecrease,safety.TheproposedadditionofaT/S4.0.4exemptionforModes3and4andtheclarificationsthatthespecificationisapplicablewiththeRCSfullypressurizedareareductiontothecurrentrequirements,butareconsistentwithperformingthesurveillancewiththeRCSfullypressurized,andaresimilartotheStandardT/Srequirements.SincetherearenosubstantivedifferencesbetweentheCookNuclearPlantcontrolledleakageconfigurationandthatreflectedbytheStandardT/S,thechangewouldnotbeexpectedtodecreasesafety,Forthesereasons,webelievethechangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofapreviouslyanalyzedaccident,norshoulditinvolveasignificantreductioninamarginofsafety.Criterion2Theonlychangetoplantoperationsisthemethodofmeasuringcontrolledleakage.Theproposedmethodrequiresnochangesinplantequipmentlineups.Dataisrecordedfromexistinginstrumentation,andthenismathematicallymanipulatedtoensuretheresistanceisincompliancewiththeaccidentanalysisassumptions.Sincethechangeinvolvesnonewmodesofplantoperation,noranyphysicalchangestotheplant,thechangeshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated, Attachment1toAEP:NRC:1070Page6Criterion3SeeCriterion1above.Lastly,wenotethattheCommissionhaspiovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thefirstexamplereferstochangesthatarepurelyadministrativeinnature.ThisexampleisapplicabletothedeletionofthefootnotereferringtothereportingrequirementsofT/S6.9,1,Thesecondexamplerefer'stochangesthat,constituteanadditionallimi.tation,restriction,orcontrolnotpresentlyincludedintheT/Ss:forexample,morestringentsurveillancerequirements.Theproposedsurveillancerequirement,asdescribedabove,ismorerestrictivethanthepresentsurveillancerequirement.Theadditionalrestrictionsareintendedtoensurecompliancewiththeaccidentanalysisassumptions.ThesixthFederalRegisterexamplereferstochangesthatmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyanalyzedaccident,buttheresultsofwhicharewithinclearlyestablishedacceptancelimits.TheT/S4.0,4exemptionandlimitingofapplicabilitytoafullypressurizedRCSwehavep'roposedaresimilartotheStandardT/Ss,andthereforefitthestatedexample.}}
Thereasonforthechangeandour10CFR50.92significant hazardsanalysisarefoundinAttachment l.Attachment 2containstheproposedrevisedT/Spages,Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
ThisT/Schangeisintendedtocorrectadeficiency inourpresentT/Sssothattheassumptions oftheapplicable accidentanalysisareadequatel'y protected.
Asdescribed inAttachment 1tothisletter,wehaveadministratively implemented restrictions abovethepresentT/Srequirements thatareprotecting theaccidentanalysisassumptions.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee, Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.85'i03i000S
'8'yl-017
----~PDRADGCK05000315PPQCIJ Dr.T.E.Murley-2-AEP:NRC:1070 Attachment 1tothisletterincludesAEPdrawingsOP-2-5129 andOP-2-5128A.
Inaccordance withtherestrictions astousesetforthontheAEPdrawings, AEPherebyreleasesthesedocuments totheNRCforitsinformation anduseinconnection withthissubmittal.
AEPalsopermitstheNRCtoreproduce thedrawingsasnecessary tofacilitate reviewanddistribution ofthedrawingstomeetNRCrequirements.
Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
Sincerely, M..AlechVicePresident ldpAttachments cc:D.H.Vi.lliams, Jr.A.A.Blind-BridgmanR.C.CallenG.CharnoffA.B.DavisNRCResidentInspector
-BridgmanNFEMSectionChief ATTACHMENT 1TOAEP;NRC:1070 REASONSAND10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTTECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1070 Page1Introduction TheTechnical Specification (T/S)changeproposedinthisletterisintendedtoensuretheT/Ssaccurately reflecttherequirements ofthesafetyanalysiswithregardstocontrolled leakage.Tofacilitate thereview,wehaveincludedthefollowing flowdiagrams:
1)OP-2-5129 CVCSReactorLetdownandCharging2)OP-2-5128A ReactorCoolantDescritionofChaneAscurrently written,T/S3,4.6.2.e (Operational Leakage)limitscontrolled leakageto52gpm.Surveillance requirement 4.4.6.2.1.
requiresmeasurement ofcontrolled leakageatleastonceper31days.Controlled leakageisdefinedinSection1oftheT/Ssas"thatsealwaterflowsuppliedtothereactorcoolantpumpseals."Veareproposing toamendthesubjectT/Ssuchthatthecontrolled leakagelimitisexpressed asalineresistance, illratherthanaspecificflowrate.Theseallineresistance wbemeasuredatleastonceper31dayswhenthepressurizer pressureiswithin20psiofitsnominalfullpressure~alue.Theseallineresistance measuredduring2the surveillance mustbbegreaterthanorequalto2.27E-1ft/gpm.TheseallineSL'sistance Risdetermined fromthefollowing expression:
R~2.31(P-P)SLQ2where:Pchargingpumpheaderpressure, psigCHPP2112psig(Unit1lowpressureoperation)
SX2262psig(Unit1highpressureoperation) 2262psig(Unit2operation) 232.31conversion factor(12in/ft)/(62.3lb/ft)totalsealinjection flow,gpmAdditionally, wehaveaddedanexemption fromtherequirements ofT/S4.0.4forentryintoModes3and4,deletedafootnotefromT/S3.4.6.2Action(c)involving reporting requirements forreactorcoolantpressureboundaryleakage,andmodifiedtheBasessectiontoreflect'the controlled leakagerequirement
: change, Attachment 1toAEP:NRC:1070 Page2ReasonforChaneThechangetothecontrolled leakagerequirements resultsfromourconclusion thatthepresentlimitof52gpmcannotbyitselfensurecompliance withtheassumptions ofthesafetyanalysis.
FortheLOCAanalyseswithminimumsafeguards assumptions, thefuelvendorsassumethatalloftheflowthatisdivertedfromtheboroninjection tank(BIT)linebythesealinjection lineisunavailable forcorecooling.(Although aportionofthesealwaterisinjectedintothereactorcoolantsystem,thereisnoT/Slimitonthisflowandtherefore allofthesealflowisassumedunavailable forcorecooling,)
Thefuelvendoranalysesassumeaseallinehydraulic resistance of0.227ft/gpm.Surveillance requirement 4.4.6.2.l,c isintendedtoverifythattheactualseallineresistance isgreaterthanorequaltothisvalue.Itiscomplemented byT/S4.5.2.h(ECCSSubsystems),
which,asdiscussed inT/SBases3/4.5,2and3/4.5.3,assuresthattheBITthrottlevalvesareadjustedsuchthat:a)totalpumpflowdoesnotexceedrunoutconditions whenthesystemisinitsminimumresistance configuration, b)theproperflowsplitexistsbetweeninjection pointsinaccordance withtheassumptions usedintheECCS-LOCA
: analyses, andc)thetotalECCSflowtoallinjection pointsisequaltoorabovethatassumedintheECCS-LOCA analyses.
Thenominaldeveloped headofthechargingpumpatrunout(550gpm)isapproximately 1431feet.Therefore, theflowdivertedthroughtheseallineunderEmergency CoreCoolingSystem(ECCS)operation at0psigis:(1431ft/0'27ft/gpm)21/279gpmAsaresult,T/S4.5.2.hspecifies anominalpumprunoutflowrateof550gpmwithasimulated sealflowof80gpmandamaximumof470gpmthroughtheBIT.Duringnormaloperation, theUnit2pressurizer pressureismaintained atanominalpressureof2235psig.Theresulting pressureatthesealinjection pointinthereactorcoolantpumpisapproximately 2260psig.Assumingnormalletdown(75gpm),thechargingpumpdischarge pressureshouldbeatleast2413psig.Thecorresponding sealinjection flowrateis:((2413-2260)psi/(0.227 ft/gpm)2+(12in/ft)/(62lb/ft))40gpm Attachment 1toAEP:NRC:1070 Page3ThecurrentT/Sonlyspecifies amaximumflowrate.TheT/SdoesnotprovideanylimitsonRCSorpumpdischarge pressurethatcorrespond totheflowlimit.Asseenintheexampleabove,the52gpmlimitwouldbenonconservative withthechargingpumpheadassumedintheexample.TheWestinghouse StandardT/Ssspecifyacontrolled leakagelimitingpm.TheStandardT/Ssurveillance requirement specifies thatthemodulating valve(corresponding toCookNuclearPlantvalveQRV-251,shownatlocationJ-5ondrawingOP-2-5129) mustbefullyopen.Althoughthisisanenhancement overthepresentCookNuclearPlantT/S,itpresentsoperational difficulties sinceitrequiresvalveQRV-251tobefullyopenedinordertoperformthetest.SinceQRV-251isthemainvalveusedtothrottlechargingflowduringnormaloperations, itisnotgenerally fullyopen.Theoperatormustcarefully adjustQRV-200(shownatlocationH-3ondrawingOP-2-5129) tomaintainthenecessary chargingflowandpressurizer levelduringthetest.Sincewehaverecognized thatthepresentT/Sisinadequate, wehaveimplemented administrative controlstoensurethatthecontrolled leakagesurveillance accurately reflectsthesafetyanalysisassumptions.
Controlled leakage,asmeasuredduringthesurveillance, isadministratively limitedto40gpm,Wearepresently performing thesurveillance outlinedbytheStandardT/S,exceptthatwemeasurethechargingpumpheaderpressuretoensureitisconsistent withthe40gpmcontrolled leakagelimitandtheresistance assumedintheWestinghouse analysis.
OurproposedT/Schangeensuresthattheaccidentanalysisassumptions areprotected whileeliminating thedifficulty associated withtheStandardT/Ssurveillance.
Theactuallineresistance isdetermined ratherthanasimpleflowrate.Inperforming thesurveillance, wearecurrently planningtomeasurepumpdischarge pressureusingpressureinstrument QPI-250,sinceitreadsoutinthe'controlroom.Theinstrument isinthepumpdischarge headerdownstream ofQRV-251.Thisisconservative sinceitpredictsalowersystemresistance andtherefore willmakeitmoredifficult topassthetest.Also,sincepumpdischarge pressureismeasureddownstream ofQRV-251,thereisnoneedtofullyopenthevalve,asthestandardT/Srequires, (Theinstrument isshownatlocationK-4ondrawingOP-2-5129).
Seallineflowwillbedetermined bysummingtheflowindicated inthecontrolroombyinstruments QFI210,220,230,and240,thatindicatethesealflowtoreactorcoolantpumps1through4,respectively.
(Theinstruments areshownatlocationB-4ondrawingOP-2-5128A.)
Theconversion frompressurizer pressuretosealinjection pointpressure(P)wascalculated usingamethodology providedtousbyWeshinghouse.
Thismethodology accountsforpressureeffectssuchasthedifference inelevation betweenpressurizer programmed levelandtheseal-injection Attachment 1toAEP:NRC:1070 Page4points.TheWestinghouse equations wereappliedtoprogrammed RCSconditions (temperature andpressurizer level)forbothunitsatvariouspowerlevels.ThevaluesforPIspecified intheproposedT/Sscorrespond to100%poweroperation sincethisconservatively resultsinthelargestvalueofP.TwovaluesforP>arespecified forUnit1,corresponding tothetwodiscretepressurizer pressurevalues(2235psigand2085psig)SIwhicharesupported bytheUnit1reducedtemperature andpressureprogram(Reference Unit1T/SAmendment 126).Theseallineresistance, asdetermined bytheproposedsurveillance requirement, isapplicable atfullpressure'onditions.
Thisisbecausethepressureatthesealin]ection point,whichcannotbedirectlymeasured, hasbeencalculated assumingfullpressureoperation, Thisisrecognized bytheStandardT/S,whichspecifies theLCOandthesurveillance requirement atapressurizer pressureof2235+20psig,(Inpractice, fullpressureoperation isthemostlimitingbecauseitrequiresthelowestlineresistance toprovideadequateflowtothereactorcoolantpumpseals.)WehaveaddedafootnotetotheLCOandwordedtheproposedsurveillance requirement suchthatitisclearthattheT/Sisapplicable withaveragepressurizer pressureatitsfullpressurevalue.(Wehavemaintained the20psitolerance fromtheStandardT/S,sincepressurizer pressuremayfluctuate slightlyarounditsnominalvalue.)WehavealsoaddedaT/S4.0.4exemption forT/S4.4.6.2.1 forentryintoModes3and4.The4.0.4exemption willallowentryintoModes3and4beforethecontrolled leakagesurveillance iscompleted, Thischangeisconsistent withtheStandardT/S.Asdiscussed above,thesurveillance istobeperformed withtheRCSfullypressurized.
Thiscondition istypically established inMode3.WhiletheRCSpressureischanging, itmaybenecessary toad]ustsealflowtothereactorcoolantpumpsusingneedlevalvesCS-438-1,-2,-3,and-4,(Thesevalvesareshownondrawing2-5128AatB-4.)Achangeinneedlevalvepositionaltersthesystemresistance, rendering obsoleteanyresistance measurements takenbeforehand.
Wearealsoproposing todeleteafootnoteassociated withT/S3,4.6.2Action(c)thatinvolvesreporting ofreactorcoolantpressureboundaryleakagepursuanttoT/S6.9.1~Thereportability requirements ofT/S6,9,1havebeenmodifiedbecauseofchangestotheLERrule(10CFR50.73),andT/S6.9.1nolongercontainsrequirements relatedtoreporting ofpressureboundaryleakage.Thischangeistherefore purelyadministrative innature,intendedonlytoremoveasuperseded reference fromtheT/Ss.
Attachment 1toAEP:NRC:1070 Page510CFR50.92CriteriaPer10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:1)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously
: analyzed, 2)"Createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluate'd, or3)Involveasignificant reduction inamarginofsafety.Criterion 1Weareproposing tomodifytheT/Ssurveillance requirement forcontrolled leakagesuchthatitaccurately reflectstheassumptions oftheLOCAanalysis.
ThepresentT/Swordingisvague,anddoesnotbyitselfensureconsistency withtheanalysis, Therevisedsurveillance requirement placesadditional restrictions ontheplant,andwouldbeexpectedtoincrease, ratherthandecrease, safety.TheproposedadditionofaT/S4.0.4exemption forModes3and4andtheclarifications thatthespecification isapplicable withtheRCSfullypressurized areareduction tothecurrentrequirements, butareconsistent withperforming thesurveillance withtheRCSfullypressurized, andaresimilartotheStandardT/Srequirements.
Sincetherearenosubstantive differences betweentheCookNuclearPlantcontrolled leakageconfiguration andthatreflected bytheStandardT/S,thechangewouldnotbeexpectedtodecreasesafety,Forthesereasons,webelievethechangedoesnotinvolveasignificant increaseintheprobability orconsequences ofapreviously analyzedaccident, norshoulditinvolveasignificant reduction inamarginofsafety.Criterion 2Theonlychangetoplantoperations isthemethodofmeasuring controlled leakage.Theproposedmethodrequiresnochangesinplantequipment lineups.Dataisrecordedfromexistinginstrumentation, andthenismathematically manipulated toensuretheresistance isincompliance withtheaccidentanalysisassumptions.
Sincethechangeinvolvesnonewmodesofplantoperation, noranyphysicalchangestotheplant,thechangeshouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, Attachment 1toAEP:NRC:1070 Page6Criterion 3SeeCriterion 1above.Lastly,wenotethattheCommission haspiovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding examples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.
Thefirstexamplereferstochangesthatarepurelyadministrative innature.Thisexampleisapplicable tothedeletionofthefootnotereferring tothereporting requirements ofT/S6.9,1,Thesecondexamplerefer'stochangesthat,constitute anadditional limi.tation, restriction, orcontrolnotpresently includedintheT/Ss:forexample,morestringent surveillance requirements.
Theproposedsurveillance requirement, asdescribed above,ismorerestrictive thanthepresentsurveillance requirement.
Theadditional restrictions areintendedtoensurecompliance withtheaccidentanalysisassumptions.
ThesixthFederalRegisterexamplereferstochangesthatmayresultinsomeincreasetotheprobability orconsequences ofapreviously analyzedaccident, buttheresultsofwhicharewithinclearlyestablished acceptance limits.TheT/S4.0,4exemption andlimitingofapplicability toafullypressurized RCSwehavep'roposed aresimilartotheStandardT/Ss,andtherefore fitthestatedexample.}}

Revision as of 08:53, 29 June 2018

Application for Amends to Licenses DPR-58 & DPR-74,revising Tech Specs 3/4.4.6.2 Re Operational Leakage & Associated Bases.W/Two Oversize Drawings
ML17328A204
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/17/1989
From: ALEXICH M P
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17328A205 List:
References
AEP:NRC:1070, NUDOCS 8910310003
Download: ML17328A204 (10)
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Text

ACCELERATED DITRJBUTION DEMONSATIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:8910310003 DOC.DATE:

89/10/17NOTARIZED:

NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,Indiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.

IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)SUBZECT:Application foramendstoLicensesDPR-58&DPR-74,revising TechSpecsrecontrolled leakage.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTESRDRECIPIENT IDCODE/NAME PD3-1LAGIITTER,Z'NTERNAL:

NRR/DEST/ADS 7ENRR/DEST/ICSB NRR/DEST/RSB 8ENUDOCS-ABSTRACT OGC/HDS1RES/DSIR/EIB EXTERNAL:

LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DEST/ESB 8DNRR/DEST/MTB 9HNRR/DOEA/TS B11OC/~GFILOlNRCPDRCOPIESLTTRENCL111111111'1111DDSDNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR21ENCL19Dp8, IndianaMichiganPowerCompanyP.O.Box16631Columbus, OH43216RSNSIAMAMCNSIMNPQHfMAEP'NRC:1070 10CFR50.90DonaldC.CookNuclearPlantUnits1and2LicenseNos.DPR-58andDPR-74DocketNos.50-315and50-316CONTROLLED LEAKAGETECHNICAL SPECIFICATION CHANGEU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyOctober17,1989

DearDr.Murley:

Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2,Specifically, weareproposing tomodifyT/S3/4.4.6.2 (Operational Leakage)anditsassociated Basessuchthattherequirements forcontrolled leakagearemademorerestrictive.

Thereasonforthechangeandour10CFR50.92significant hazardsanalysisarefoundinAttachment l.Attachment 2containstheproposedrevisedT/Spages,Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

ThisT/Schangeisintendedtocorrectadeficiency inourpresentT/Sssothattheassumptions oftheapplicable accidentanalysisareadequatel'y protected.

Asdescribed inAttachment 1tothisletter,wehaveadministratively implemented restrictions abovethepresentT/Srequirements thatareprotecting theaccidentanalysisassumptions.

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

copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.85'i03i000S

'8'yl-017

~PDRADGCK05000315PPQCIJ Dr.T.E.Murley-2-AEP:NRC:1070 Attachment 1tothisletterincludesAEPdrawingsOP-2-5129 andOP-2-5128A.

Inaccordance withtherestrictions astousesetforthontheAEPdrawings, AEPherebyreleasesthesedocuments totheNRCforitsinformation anduseinconnection withthissubmittal.

AEPalsopermitstheNRCtoreproduce thedrawingsasnecessary tofacilitate reviewanddistribution ofthedrawingstomeetNRCrequirements.

Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.

Sincerely, M..AlechVicePresident ldpAttachments cc:D.H.Vi.lliams, Jr.A.A.Blind-BridgmanR.C.CallenG.CharnoffA.B.DavisNRCResidentInspector

-BridgmanNFEMSectionChief ATTACHMENT 1TOAEP;NRC:1070 REASONSAND10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTTECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1070 Page1Introduction TheTechnical Specification (T/S)changeproposedinthisletterisintendedtoensuretheT/Ssaccurately reflecttherequirements ofthesafetyanalysiswithregardstocontrolled leakage.Tofacilitate thereview,wehaveincludedthefollowing flowdiagrams:

1)OP-2-5129 CVCSReactorLetdownandCharging2)OP-2-5128A ReactorCoolantDescritionofChaneAscurrently written,T/S3,4.6.2.e (Operational Leakage)limitscontrolled leakageto52gpm.Surveillance requirement 4.4.6.2.1.

requiresmeasurement ofcontrolled leakageatleastonceper31days.Controlled leakageisdefinedinSection1oftheT/Ssas"thatsealwaterflowsuppliedtothereactorcoolantpumpseals."Veareproposing toamendthesubjectT/Ssuchthatthecontrolled leakagelimitisexpressed asalineresistance, illratherthanaspecificflowrate.Theseallineresistance wbemeasuredatleastonceper31dayswhenthepressurizer pressureiswithin20psiofitsnominalfullpressure~alue.Theseallineresistance measuredduring2the surveillance mustbbegreaterthanorequalto2.27E-1ft/gpm.TheseallineSL'sistance Risdetermined fromthefollowing expression:

R~2.31(P-P)SLQ2where:Pchargingpumpheaderpressure, psigCHPP2112psig(Unit1lowpressureoperation)

SX2262psig(Unit1highpressureoperation) 2262psig(Unit2operation) 232.31conversion factor(12in/ft)/(62.3lb/ft)totalsealinjection flow,gpmAdditionally, wehaveaddedanexemption fromtherequirements ofT/S4.0.4forentryintoModes3and4,deletedafootnotefromT/S3.4.6.2Action(c)involving reporting requirements forreactorcoolantpressureboundaryleakage,andmodifiedtheBasessectiontoreflect'the controlled leakagerequirement

change, Attachment 1toAEP:NRC:1070 Page2ReasonforChaneThechangetothecontrolled leakagerequirements resultsfromourconclusion thatthepresentlimitof52gpmcannotbyitselfensurecompliance withtheassumptions ofthesafetyanalysis.

FortheLOCAanalyseswithminimumsafeguards assumptions, thefuelvendorsassumethatalloftheflowthatisdivertedfromtheboroninjection tank(BIT)linebythesealinjection lineisunavailable forcorecooling.(Although aportionofthesealwaterisinjectedintothereactorcoolantsystem,thereisnoT/Slimitonthisflowandtherefore allofthesealflowisassumedunavailable forcorecooling,)

Thefuelvendoranalysesassumeaseallinehydraulic resistance of0.227ft/gpm.Surveillance requirement 4.4.6.2.l,c isintendedtoverifythattheactualseallineresistance isgreaterthanorequaltothisvalue.Itiscomplemented byT/S4.5.2.h(ECCSSubsystems),

which,asdiscussed inT/SBases3/4.5,2and3/4.5.3,assuresthattheBITthrottlevalvesareadjustedsuchthat:a)totalpumpflowdoesnotexceedrunoutconditions whenthesystemisinitsminimumresistance configuration, b)theproperflowsplitexistsbetweeninjection pointsinaccordance withtheassumptions usedintheECCS-LOCA

analyses, andc)thetotalECCSflowtoallinjection pointsisequaltoorabovethatassumedintheECCS-LOCA analyses.

Thenominaldeveloped headofthechargingpumpatrunout(550gpm)isapproximately 1431feet.Therefore, theflowdivertedthroughtheseallineunderEmergency CoreCoolingSystem(ECCS)operation at0psigis:(1431ft/0'27ft/gpm)21/279gpmAsaresult,T/S4.5.2.hspecifies anominalpumprunoutflowrateof550gpmwithasimulated sealflowof80gpmandamaximumof470gpmthroughtheBIT.Duringnormaloperation, theUnit2pressurizer pressureismaintained atanominalpressureof2235psig.Theresulting pressureatthesealinjection pointinthereactorcoolantpumpisapproximately 2260psig.Assumingnormalletdown(75gpm),thechargingpumpdischarge pressureshouldbeatleast2413psig.Thecorresponding sealinjection flowrateis:((2413-2260)psi/(0.227 ft/gpm)2+(12in/ft)/(62lb/ft))40gpm Attachment 1toAEP:NRC:1070 Page3ThecurrentT/Sonlyspecifies amaximumflowrate.TheT/SdoesnotprovideanylimitsonRCSorpumpdischarge pressurethatcorrespond totheflowlimit.Asseenintheexampleabove,the52gpmlimitwouldbenonconservative withthechargingpumpheadassumedintheexample.TheWestinghouse StandardT/Ssspecifyacontrolled leakagelimitingpm.TheStandardT/Ssurveillance requirement specifies thatthemodulating valve(corresponding toCookNuclearPlantvalveQRV-251,shownatlocationJ-5ondrawingOP-2-5129) mustbefullyopen.Althoughthisisanenhancement overthepresentCookNuclearPlantT/S,itpresentsoperational difficulties sinceitrequiresvalveQRV-251tobefullyopenedinordertoperformthetest.SinceQRV-251isthemainvalveusedtothrottlechargingflowduringnormaloperations, itisnotgenerally fullyopen.Theoperatormustcarefully adjustQRV-200(shownatlocationH-3ondrawingOP-2-5129) tomaintainthenecessary chargingflowandpressurizer levelduringthetest.Sincewehaverecognized thatthepresentT/Sisinadequate, wehaveimplemented administrative controlstoensurethatthecontrolled leakagesurveillance accurately reflectsthesafetyanalysisassumptions.

Controlled leakage,asmeasuredduringthesurveillance, isadministratively limitedto40gpm,Wearepresently performing thesurveillance outlinedbytheStandardT/S,exceptthatwemeasurethechargingpumpheaderpressuretoensureitisconsistent withthe40gpmcontrolled leakagelimitandtheresistance assumedintheWestinghouse analysis.

OurproposedT/Schangeensuresthattheaccidentanalysisassumptions areprotected whileeliminating thedifficulty associated withtheStandardT/Ssurveillance.

Theactuallineresistance isdetermined ratherthanasimpleflowrate.Inperforming thesurveillance, wearecurrently planningtomeasurepumpdischarge pressureusingpressureinstrument QPI-250,sinceitreadsoutinthe'controlroom.Theinstrument isinthepumpdischarge headerdownstream ofQRV-251.Thisisconservative sinceitpredictsalowersystemresistance andtherefore willmakeitmoredifficult topassthetest.Also,sincepumpdischarge pressureismeasureddownstream ofQRV-251,thereisnoneedtofullyopenthevalve,asthestandardT/Srequires, (Theinstrument isshownatlocationK-4ondrawingOP-2-5129).

Seallineflowwillbedetermined bysummingtheflowindicated inthecontrolroombyinstruments QFI210,220,230,and240,thatindicatethesealflowtoreactorcoolantpumps1through4,respectively.

(Theinstruments areshownatlocationB-4ondrawingOP-2-5128A.)

Theconversion frompressurizer pressuretosealinjection pointpressure(P)wascalculated usingamethodology providedtousbyWeshinghouse.

Thismethodology accountsforpressureeffectssuchasthedifference inelevation betweenpressurizer programmed levelandtheseal-injection Attachment 1toAEP:NRC:1070 Page4points.TheWestinghouse equations wereappliedtoprogrammed RCSconditions (temperature andpressurizer level)forbothunitsatvariouspowerlevels.ThevaluesforPIspecified intheproposedT/Sscorrespond to100%poweroperation sincethisconservatively resultsinthelargestvalueofP.TwovaluesforP>arespecified forUnit1,corresponding tothetwodiscretepressurizer pressurevalues(2235psigand2085psig)SIwhicharesupported bytheUnit1reducedtemperature andpressureprogram(Reference Unit1T/SAmendment 126).Theseallineresistance, asdetermined bytheproposedsurveillance requirement, isapplicable atfullpressure'onditions.

Thisisbecausethepressureatthesealin]ection point,whichcannotbedirectlymeasured, hasbeencalculated assumingfullpressureoperation, Thisisrecognized bytheStandardT/S,whichspecifies theLCOandthesurveillance requirement atapressurizer pressureof2235+20psig,(Inpractice, fullpressureoperation isthemostlimitingbecauseitrequiresthelowestlineresistance toprovideadequateflowtothereactorcoolantpumpseals.)WehaveaddedafootnotetotheLCOandwordedtheproposedsurveillance requirement suchthatitisclearthattheT/Sisapplicable withaveragepressurizer pressureatitsfullpressurevalue.(Wehavemaintained the20psitolerance fromtheStandardT/S,sincepressurizer pressuremayfluctuate slightlyarounditsnominalvalue.)WehavealsoaddedaT/S4.0.4exemption forT/S4.4.6.2.1 forentryintoModes3and4.The4.0.4exemption willallowentryintoModes3and4beforethecontrolled leakagesurveillance iscompleted, Thischangeisconsistent withtheStandardT/S.Asdiscussed above,thesurveillance istobeperformed withtheRCSfullypressurized.

Thiscondition istypically established inMode3.WhiletheRCSpressureischanging, itmaybenecessary toad]ustsealflowtothereactorcoolantpumpsusingneedlevalvesCS-438-1,-2,-3,and-4,(Thesevalvesareshownondrawing2-5128AatB-4.)Achangeinneedlevalvepositionaltersthesystemresistance, rendering obsoleteanyresistance measurements takenbeforehand.

Wearealsoproposing todeleteafootnoteassociated withT/S3,4.6.2Action(c)thatinvolvesreporting ofreactorcoolantpressureboundaryleakagepursuanttoT/S6.9.1~Thereportability requirements ofT/S6,9,1havebeenmodifiedbecauseofchangestotheLERrule(10CFR50.73),andT/S6.9.1nolongercontainsrequirements relatedtoreporting ofpressureboundaryleakage.Thischangeistherefore purelyadministrative innature,intendedonlytoremoveasuperseded reference fromtheT/Ss.

Attachment 1toAEP:NRC:1070 Page510CFR50.92CriteriaPer10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:1)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously

analyzed, 2)"Createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluate'd, or3)Involveasignificant reduction inamarginofsafety.Criterion 1Weareproposing tomodifytheT/Ssurveillance requirement forcontrolled leakagesuchthatitaccurately reflectstheassumptions oftheLOCAanalysis.

ThepresentT/Swordingisvague,anddoesnotbyitselfensureconsistency withtheanalysis, Therevisedsurveillance requirement placesadditional restrictions ontheplant,andwouldbeexpectedtoincrease, ratherthandecrease, safety.TheproposedadditionofaT/S4.0.4exemption forModes3and4andtheclarifications thatthespecification isapplicable withtheRCSfullypressurized areareduction tothecurrentrequirements, butareconsistent withperforming thesurveillance withtheRCSfullypressurized, andaresimilartotheStandardT/Srequirements.

Sincetherearenosubstantive differences betweentheCookNuclearPlantcontrolled leakageconfiguration andthatreflected bytheStandardT/S,thechangewouldnotbeexpectedtodecreasesafety,Forthesereasons,webelievethechangedoesnotinvolveasignificant increaseintheprobability orconsequences ofapreviously analyzedaccident, norshoulditinvolveasignificant reduction inamarginofsafety.Criterion 2Theonlychangetoplantoperations isthemethodofmeasuring controlled leakage.Theproposedmethodrequiresnochangesinplantequipment lineups.Dataisrecordedfromexistinginstrumentation, andthenismathematically manipulated toensuretheresistance isincompliance withtheaccidentanalysisassumptions.

Sincethechangeinvolvesnonewmodesofplantoperation, noranyphysicalchangestotheplant,thechangeshouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, Attachment 1toAEP:NRC:1070 Page6Criterion 3SeeCriterion 1above.Lastly,wenotethattheCommission haspiovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding examples(48FR14870)ofamendments considered notlikelytoinvolvesignificant hazardsconsideration.

Thefirstexamplereferstochangesthatarepurelyadministrative innature.Thisexampleisapplicable tothedeletionofthefootnotereferring tothereporting requirements ofT/S6.9,1,Thesecondexamplerefer'stochangesthat,constitute anadditional limi.tation, restriction, orcontrolnotpresently includedintheT/Ss:forexample,morestringent surveillance requirements.

Theproposedsurveillance requirement, asdescribed above,ismorerestrictive thanthepresentsurveillance requirement.

Theadditional restrictions areintendedtoensurecompliance withtheaccidentanalysisassumptions.

ThesixthFederalRegisterexamplereferstochangesthatmayresultinsomeincreasetotheprobability orconsequences ofapreviously analyzedaccident, buttheresultsofwhicharewithinclearlyestablished acceptance limits.TheT/S4.0,4exemption andlimitingofapplicability toafullypressurized RCSwehavep'roposed aresimilartotheStandardT/Ss,andtherefore fitthestatedexample.

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