ML18026A260

Forwards Response to 931123 RAI Re Personnel Access Questions Resulting from Postulated Loss of Spent Fuel Pool Cooling Events

ML18026A260
Person / Time
Site:	Susquehanna
Issue date:	01/04/1994
From:	BYRAM R G PENNSYLVANIA POWER & LIGHT CO.
To:	MILLER C L Office of Nuclear Reactor Regulation
References
PLA-4069, NUDOCS 9401110318
Download: ML18026A260 (103)

Text

ACCELERATEDDITRIBUTIONDEMONSTQWTIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9401110318DOC.DATE:94/01/04NOTARIZED:NOFACIL:50-387SusquehannaSteamElectricStation,Unit1,Pennsylva50-388SusquehannaSteamElectricStation,Unit2,PennsylvaAUTH.NAMEAUTHORAFFILIATIONBYRAM,R.G.PennsylvaniaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONMILLER,C.L.ProjectDirectorateI-2

SUBJECT:

Forwardsresponseto931123RAIrepersonnelaccessquestionsresultingfrompostulatedlossofspentfuelpoolcoolingevents.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:DOCKET0500038705000388DARECIPIENTIDCODE/NAMEPD1-2LACLARK,RINTERNAL:ACRSNRR/DORS/OTSBNRR/DRPWNRR/DSSA/SRXB01EXTERNAL:NRCPDRCOPIESLTTRENCL112266111111101111RECIPIENTIDCODE/NAMEPD1-2PDNRR/DE/EELBNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTOGC/HDS2NSICCOPIESLTTRENCL11111111111011DDRDNOTETOALL"RIDS"RECIPIENTS:DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLIS15FORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR22ENCL20 PennsylvaniaPower8LightCompanyTwoNorthNinthStreet~Alientown,PA18101-1179~215/774-5151RobertG.ByramSeniorVicePresident-Nuclear215/774-7502PANyDirectorofNuclearReactorRegulationAttention:Mr.C.L.Miller,ProjectDirectorProjectDirectorateI-2DivisionofReactorProjectsU.S.NuclearRegulatoryCommissionWashington,D.C.20555SUSQUEHANNASTEAMELECTRICSTATIONREQUESTFORADDITIONALINFORMATIONONLOSSOFSPENTFUELPOOLCOOLINGEVENTSPLA-4069FILER41-2DocketNos.50-387and50-388

DearMr.Miller:

AttachedisPP8rL'sresponsetoyourNovember23,1993RequestforAdditionalInformationconcerningpersonnelaccessquestionsresultingfrompostulatedlossofspentfuelpoolcoolingevents.PleasecontactMr.JamesM.Kennyat(215)774-7914shouldyourrequireadditionalinformation.Verytrulyyours,R..ByAttachmentcc:%RCDocumellt=Control-Desk=(original)ttNRCRegionIMr.G.S.Barber,NRCSr.ResidentInspector-SSESMr.R.J.Clark,NRCSr.ProjectManager-Rockville0700tfa.9401110318940104,PDRADOCK05000387S.,'..PDR

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ATTACHMENT1toPLA-4069ATTACHMENT1RESPONSETOQUESTION1OFNRC11/23/93RAIPage1 0h,I.

ATTACHMENT1toPLA<069QIIEHTIONIProvideadetaileddescriptionofthemodelingtechniquesusedtogeneratethe4.22RemcitedintheAugust16,1993submittalasthedosereceivedduringtheoperationofthespentfuelpoolemergencyservicewatersupplyvalves.Describeindetailthetime-motionanalysisperformedtodetermineexposuretimeassociatedwithrequiredoperatoractions.Includetheparametersandassumptionsusedtogeneratethecontainedandairbornesourcetermsandcalculatetherespectivedosecomponentsassociatedwitheachsegmentofthetime-motionanalysis.RESPONSE1Thefollowingprovidesacompleteresponsetoquestion1oftheNovember23,1993NRCRAIconcerningradiologicalevaluationsfortheLossofSFPCoolingissue.AsdiscussedinPPkL'sMay24andAugust16,1993submittals,restorationofthenormalSFPcoolingsystempriortoboilingisexpected.Consequently,PPALwouldnotexpectittobenecessarytouseESWformake-upsincethenormalsystemscouldbeusedormake-upfromthenon-accidentunitcouldbeprovided.Thisresponseisseparatedintotwoparts.Section1.0providesadescriptionofthemodelingtechniquesandassumptionsusedforevaluatingoperatoraccesstotheESWmake-upvalves.Alsoincludedinthissection,isadiscussionofhowtheresultstime-motionstudywerefactoredintotheanalysis.Section2.0providessummarytablesofthedoses(bothairborneandcontained)foreachofthesegmentsassumedinthecalculation.ThesetablesshowdosesforaDBALOCAwith1%claddamage,100%claddamage,and100%fuelmelt(i.e.,Reg.Guide1.3sourceterm).1.0DetailedDescritionofModelinTechniues1.1OverviewTheTACT5computercodeisusedtoevaluatepost-LOCAradiationsourcesinsidethereactorbuildingusingtheFSARChapter15.6.5DBA-LOCAactivityflowpathmodelwithrealisticestimatesofcontainmentleakagerates.Airborneactivityconcentrationsinthereactorbuildingandactivityconcentrationsinthesuppressionpoolwaterareevaluatedforpostulatedcladdingfailure(NUREG-1465)andfuelmelt(RegulatoryGuide1.3)sourceterms.Usingthesepost-LOCAsourceterms,radiationdoseratesinsidethereactorbuildingfromairborneactivityandfromsuppressionpoolwatercontainedsourcesareevaluatedusingtheMICROSHIELDcomputercode.OperatoraccessrequirementsinsidethereactorbuildingweredeterminedforestablishingESWmakeuptothespentfuelpoolunderpost-LOCAconditions.OperatoraccessroutesandmissionswereidentifiedanddividedintosequentialsegmentsforthepurposeofevaluatingoperatoraccessPage2 ATTACHMENT1toPLA%069doses.Operatoraccessdosesarecomputedbymultiplyingtheradiationdoseratesfrombothairborneandcontainedsourcesinagivenmissionsegmentbythetimespentbytheoperatorinthatmissionsegment.Thesumoftheradiationdosesforallsegmentsofthemissionprovidesthetotalmissiondose.1.2DetailedDescritionThisanalysisevaluatespersonnelaccessdosesinsidethereactorbuildingforthefollowingpostulatedLOCAinitiatedcoredamagecases:1%claddamage,100%claddamage,and100%fuelmelt.ThecladdamagecasesareevaluatedusingassumptionsconsistentwiththeaccidentsourcetermsdescribedinNUREG-1465.ThefuelmeltcaseisconservativelyevaluatedusingaccidentsourcetermsconsistentwithUSNRCRegulatoryGuide1.3andtheFSARChapter15.6.5DBA-LOCAlicensingbasisevaluation.Forallcases,realisticestimatesofthecontainmentleakagerateareused.Fortheactivityflowpathmodelusedinthisanalysis,theactivityconcentrationsinsidethenodalvolumesarecalculatedbydividingtheactivityinthenodeatthetimeofinterestbythenodalvolumeandthereforearedirectlyproportionaltotheactivitysourcetermreleasedfromthefuelintothecontainmentandsuppressionpool.ForthepostulatedLOCA'sthatassumecladdamage,theamountofactivityreleasedisdirectlyproportionaltotheamountofcladdamage.Therefore,acompletesourcetermanddoseanalysisisperformedforthe100%claddamagecaseandsourcetermsanddoseresultsforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamageresultsby0.01.NUREG-1465wasusedtosupplyreleasedataforthecladdamagecases.SincenospecificnumericalguidanceisprovidedinNUREG-1465,theamountofcladactivityreleasedfromthecorewhichbecomesairborneinsidecontainmentorremainsinthesuppressionpoolwaterisbasedontakingcreditforfissionproductscrubbingandretentioninaccordancewithStandardReviewPlan6.5.5.Inaddition,forthecladdamagecases,anaerosolremovalrateof0.73hr'orparticulateiodineandcesiumisassumedbasedoninformationprovidedinNUREG-1465,Table5.6fortheLaSalleNuclearPowerPlantwhichisalsoaBWRMarkIIcontainmentdesign.Nocreditforaerosolremovalwastakeninthe100%fuelmeltcase.CoreactivityreleasefractionsforaLOCAwith100%fuelmeltarebasedontherequirementsofRegulatoryGuide1.3andNUREG-0737andarethat25%oftheiodinesand100%ofthenoblegasesareinstantaneouslyairborneinprimarycontainmentandavailableforleakageand50%ofthecoreinventoryofiodinesand1%oftheparticulatearereleasedtothesuppressionpoolwater.Duetothenumberofparticulateisotopesinthecoreandthenumberofdosecalculationsrequired,theparticulateactivityreleasefromthecorewasnotexplicitlyincludedinthesuppressionpoolactivitysourcetermforthe100%fuelmeltcase.Instead,boundingdosecalculationsusingpost-LOCAsuppressionpoolcontainedsourceswithandwithoutparticulatePage3 ATTACHMENT1toPlA-4069wereusedtodetermineadosemultiplierwhichwasusedtoaccountforthedosecontributionfrom1%particulateinthesuppressionpoolwater.Theiodineandnoblegasactivitiesreleasedforthe100%fuelmeltcaseareobtainedfromtheFSARDBA-LOCAanalysisgiveninPP&LcalculationFX-C-DAM-014.Theboundinganalysisforthedosecontributionfromparticulateisbasedonpost-LOCAsuppressionpoolliquidactivitysourcetermsgiveninSusquehannaProjectBechtelCalculation200-201.Forallcladdamageandfuelmeltcases,theisotopicchemicalformoftheactivityreleasedfromthecoreisassumedtobeasfollows:Iodines=91%elemental=4%organic=5%particulateCesiums=100%particulateNobleGases=100%elementalThisassumptionisconsistentwithUSNRCRegulatoryGuide1.3forcorefueldamage.Forthecladdamagecases,NUREG-1465indicatesthatthechemicalformforiodineenteringcontainmentis95%particulateand5%elemental,butwithoutPhcontrolofthesuppressionpoolwater,arelativelylargefractionoftheparticulateiodinedissolvedinsuppressionpoolwaterwillbeconvertedtoelementaliodine.Therefore,theabovechemicalformsassumedforthisanalysisareconservativeforthecladdamagecases.Theprimarycontainmentdesignbasisleakagerateis1%/day.FortheFSARlicensingbasisDBA-LOCAanalysisthisleakagerateisassumedforthedurationoftheaccident.Forthisevaluation,atimedependentrealisticcontainmentleakageratebasedoncontainmentIntegratedLeakageRateTesting(ILRT)resultsandthecalculatedcontainmentpost-LOCApressureresponseisusedforboththecladdamageand100%fuelmeltcases.TheILRTtestpressurecorrespondstothemaximumcalculatedcontainmentpost-LOCApressurewithadesignmarginapplied.TherealisticcontainmentleakageratewascalculatedbyreducingtheILRTmeasuredleakagerateproportionatelytotheILRTtestpressureandthecalculatedcontainmentpressureresponseforaLOCA.Forthisanalysis,themostup-to-dateleakageratedataisusedsothatthedoseestimatesreflectthemostup-to-datecontainmentleakageconditions.Therefore,themeasuredleakagerateof0.606%/dayfromtheUnit1ILRTperformed5/5/92isassumedforthisanalysis.Aleakagerateof0.606%/dayisalsorepresentativeoftypicalmeasuredleakageratesatSSESUnits1&2.NUREG-0737providesguidanceforevaluatingoperatoraccesstovitalplantareasforpost-accidentoperations.ItstatesunderItem(2)SystemsContainingTheSourcethatforpost-LOCAaccidentoperations,"Radiationfromleakageofsystemslocatedoutsideofcontainmentneednotbeconsideredforthisanalysis".Therefore,itisassumedforthisevaluationthattheleakageofpost-LOCAcontainmentairborneactivitythroughcontainmentpenetrationsthatarewatersealedPage4 ATTACHMENT1toPLA<069neednotbeconsidered.Therealisticcontainmentleakagerateusedforboththecladandfueldamagecasesarebasedonthemeasuredleakageratesthroughcontainmentpenetrationsthatarenotwatersealed.Basedontheaboveactivityflowpathways,theTACT5codeprovidestotalactivityinthereactorbuildingandsuppressionpoolasafunctionoftimepostaccident.Attherequiredevaluationtime(24hourspostaccident),isotopicactivitiesweretakenfromtheTACT5outputeditanddividedbytheappropriatedispersalvolumetogiveactivityconcentrations.Radiationdosesinsidethereactorbuildingareevaluatedforboth"airborneactivityandforsuppressionpoolwatercontainedsources.OperatoraccessdosesorarearadiationdoseratesareevaluatedineachoftheareasthatrequireaccesstoprovideESWmakeup.RadiationdosesareevaluatedusingtheMICROSHIELDcomputercodewiththeTACT5generatedactivityconcentrationsourceterms.Thedoseratefromairborneactivityinsidethereactorbuildingisactuallyanimmersiondose.However,sincetheMICROSHIELDcomputercodecannotcalculatedoseratesinternaltothesource,slabgeometryisused.Onehalfofthesourcevolumeismodeledasarectangularvolumesourceandadoserateonthesurfaceofthisvolumeiscalculated.Theimmersiondoseisthencalculatedbymultiplyingthecontactdoseratefromhalfofthesourcevolumebyafactorof2.Allimmersiondoseratesareconservativelycalculatedatthecenterlineoftheroom.Doseratesfromthecontainedsuppressionpoolliquidpipingsourcesarecalculatedusingcylindricalsourcegeometrywithreceiveratside.Inordertoevaluateoperatoraccessdoses,operatorwalkingratesandstairclimbingratesarerequired.AtimemotionstudywasperformedtoverifyoperatoraccesstraveltimesinsidethereactorbuildingunderLOCAconditions.AnoperatorwasdressedinprotectiveclothingandworeaSelfContainedBreathingApparatusandactualtransittimestovalveslocatedonelevations670'nd749'fthereactorbuildingweremeasured.AccesstothesevalvesisrequiredtoprovideESWmakeuptothespentfuelpool.Basedupontheresultsofthistimemotionstudy,anoperatorwalkingrateof200ft/minandastairclimbingrateof50.ft/minareconservativelyassumedforoperatoringress/egressdosecalculationsforaccesstothereactorbuildingunderLOCAconditions.Alsoaspartofthisstudy,usingsparevalves,thevalveopeningtimeforthe2inchvalvesusedforESWsystemtie-inandflowcontrolwasmeasuredtobe10to15seconds,butforcalculationalconservatism,avalveopeningtimeof1minutewasused.Theincorporationofthetime-motionstudyintothefinalcalculationresultedinthepreliminarydosetotheoperatorincreasingfrom4.22Rem.to4.57Rem.,foraccesstothevalvesonelevations670.The4.22RemvaluewasreportedinPPkL'sAugust16,1993submittal.OperatoraccessdosesareonlyevaluatedforUnit1~TheoperatoraccessarealocationsforUnits1and2areidenticalexceptfortheareacontainingthevalvesrequiredfortie-inoftheESWsystemformakeup(ValveNos.153500,153501and253500,253501).Basedonthepost-accidentradiationlevelsgiveninFigures18.1-3and18.1-4oftheSSESFSAR,theareacontainingtheUnit1valvesforESWsystemtie-inhashigherdoseratesthantheUnit2area.Page5 ATTACHMENT1toPLA-4069ThereforedoseratescalculatedfortheUnit1areawillbeconservativefortheUnit2area.Therefore,allofthecalculatedoperatoraccessdosesforUnit1areapplicabletoUnit2.Operatoraccessdosesareevaluatedat24hourspost-LOCA.Forlossofspentfuelpoolcooling,thefuelpoolbeginstoboilinapproximately48hours.FortheconditionwhereaLossofOffsitePower(LOOP)isalsopostulated,powerisexpectedtoberestoredwithin24hours.Therefore,24hourswaschosenasthelatesttimeoperatoractioncouldbetakentorestorecoolingand/ormake-uptothepullandassurethoseactionswouldbecompletedpriortoSFPboilingSomedoseratesarealsocalculatedatothertimespost-LOCAandtoshowthatpost-LOCAdoseratesaredecreasingfortimeperiodsgreaterthan24hours.Forthe100%fuelmeltcase,adosefactorisusedtotakeintoaccountthedosecontributionfromparticulateinthesuppressionpoolliquid(seeSection5.1,Assumption5).Theparticulatedosefactorisdefinedastheratioofthedosefromsuppressionpoolliquidsourcescontainingcoreiodineandparticulateactivitytothedosefromsuppressionpoolliquidsourcescontainingiodineactivityonly.Alldosesfromcontainedsourcesforthe100%fuelmeltcasearecalculatedusingtheMICROSHIELDcomputercodewithasuppressionpoolsourcetermthatcontainsiodinesonly.TheMICROSHIELDresultsforcontainedsourcesforthe100%fuelmeltcasearethenmultipliedbytheparticulatedosefactortotakeintoaccountthedosecontributionfromparticulate.Thisdosefactoriscalculatedat24hourspost-LOCAandcanonlybeappliedtooperatoraccessdosesfromsuppressionpoolliquidsourcesevaluatedatthissametimeperiodpost-accident.Page6 ATTACHMENT1toPLA-40692.0Summof0eratorDosesforESWMake-uValvesTABLE2.1SUMMARYOFCALCULATEDOPERATORACCESSDOSESTOPROVIDEESWMAKEUPTOSPENTFUELPOOL--REACTORBUILDINGUNIT1-ACCESSTOVALVES153500AND153501-ELEV.670'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToValves153500&153501OperatorStayTimeAtValves153500Ec153501TotalsDoseFromAirborneActivity7.22-37.45-30.0147DoseFromContainedSources0.4764.21-30.480DoseFromAirborneActivity7.22-57.45-51.47-4DoseFromContainedSources4.76-34.21-54.80-3DoseFromAirborneActivity0.1980.2040.402DoseFromContainedSources4.120.04764.168TotalIngress/EgressTotalOperatorStayTime0.48330.01174.83-31.17-44.3180.252TOTALACCESSDOSE0.494.90-34.57NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page7 ATTACHMENT1toPLA-4069-TABLE2.2SUMMARYOFCALCULATEDOPERATORACCESSDOSESTOCONTROLESWMAKEUPFLOW-REACTORBUILDINGUNIT2-ACCESSTOHEATEXCHANGERPUMPROOM(1-514)-ELEV.749'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToHeatExchangerPumpRoom(11-514)OperatorStayTimeInHeatExchangerPumpRoom(11-514)TotalsDoseFromAirborneActivity0.0280.02250.0505DoseFromContainedSources0.02882.77-40.0291DoseFromAirborneActivity2.80-42.25-45.05-4DoseFromContainedSources2.88-42.77-62.91-4DoseFromAirborneActivity0.7040.6151.319DoseFromContainedSources0.2922.65-30.295TotalIngress/EgressTotalOperatorStayTime0.05700.02285.70-42.28-40.9960.618TOTALACCESSDOSE0.07987.98-41.61NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.PageS ATTACHMENT2toPLA-4069ATTACHMENT2RESPONSETOQUESTION2OFNRC11/23/93RAIPage9 ATTACHMENT2toPLA-4069OVVONProvideoperatordoseestimatesforthoseoperatoractionsneededtomaintainthenormalspentfuelpoolcoolingfunctionunderDBAaccidentconditions,assumingthenormalspentfuelpoolcoolingsystemisoperationalfollowinganaccident.Considerthoseactionsneededtorestorenormalspentfuelfollowingautomaticormanualloadshedofthespentfuelpoolcoolingsystem.Includethesamelevelofdetailasinyourresponsetoquestion1.RE<SPONSK2Thefollowingprovidesacompleteresponsetoquestion2oftheNovember23,1993NRCRAIconcerningradiologicalevaluationsfortheLossofSFPCoolingissue.Forthisevaluation,ESWwasevaluatedasthesourceofmake-upwatersinceitissafety-related.Othersourcesofnon-safetyrelatedwatercouldbeusedbutwerenotevaluatedinordertominimizetheamountofcalculationsperformed.Asnotedintheresponsetoquestion1,restorationofnormalSFPcoolingistheexpectedcourseofactionforrespondingtoaLossofSFPcoolingevent.Thisresponseisbrokenintothreeparts.Section1.0providesadescriptionofthemodelingtechniquesandassumptionsusedforevaluatingoperatoraccesstorestorenormalSpentFuelPool(SFP)Cooling.Section2.0adescriptionoftheactionsrequiredtorestoreandmaintainnormalSFPCooling.Itisimportanttonotethatnotime-motionstudywasperformedfortheseactions.Thetimingisbasedonoperatorexperiencesincetheseactionsareperformedonaregularbasis.Section3.0providessummarytablesofthedoses(bothairborneandcontained)foreachofthesegments/actionsassumedinthecalculation.Itshouldbenotedthatseveralseparateactions,atdifferentlocationsarerequiredtorestoreandmaintainnormalSFPcooling.ThesetablesshowdosesforaDBALOCAwith1%claddamage,100%claddamage,and100%fuelmelt(i.e.,Reg.Guide1.3sourceterm).1.0DetailedDescritionofModelinTechniuesThecalculationperformedtodeterminetheoperatordosesforrestorationofnormalSFPcoolingisbasedonthecalculationperformedfortheresponsetoquestion1.Theonlydifferencesareassociatedwiththestaytimesandlocationoftheoperatorswithregardtodistancefromcontainedsources.Theresultsofthetime-motionstudyperformedforquestion1wereusedtodetermineoperatortransittimes,whileoperatorexperience.was.usedtodeterminethetimetoperformtheactions.Page10 ATTACHMENT2toPLA-40692.0ActionsforRestorationofNormalSFPCoolinTheactionsarebasedonthefollowingsequencesofeventsandplantconfiguration':TIMEDESCRIPTION0hrs.FuelPoolsareisolated;Botharefilled;U2poolheatload=8.2MBTU/HR(justcompleteda40dayoutage);U1poolheatload=6.27MBTU/HR(lastoutagebegan135daysago);PoolTemp=110'F.U2LOCA/LOOPoccurs;Lossoffuelpoolcoolingoccurstobothpools;ReactorbuildingHVACrecirculationsystemstarts;SGTSstarts.24Hrs.ON-135(235)-001LOSSOFFUELPOOLCOOLING/COOLANTINVENTORYentered.U1controlledshutdownbeginsduetotheLOOPcondition.AccessavailabletoESWinbothUnits.Offsitepowerisrestored.ImplementOffNormalProcedures(LOSSOFFUELPOOLCOOLING)tocheckthatthesystemcanbeoperatedandthenimplementOP-135(235)-001toplacefuelpoolcoolingintooperation.TheON-135(235)-001(LOSSOFFUELPOOLCOOLING)wouldhavebeenenteredattime0oftheeventandwouldhavebeenimplementedtocheckthatthesystemcanbeoperated.ItwouldhavebeendeterminedthatitcouldnotduetoaLOOP.Oncepowerisrestored(assumedtooccuratnolaterthan24hoursaftereventinitiation)theONprovisionswouldguidetheoperatortodeterminethatthesystemandthenecessarysupportsystemsareavailable.ImplementationoftheON'swillassurethesupportsystemsareoperableandfunctionasrequiredtosupportfuelpoolcoolingsystemoperation.Theseproceduresrequireachecktoassurenosystembreachhasoccurred.Whenentranceismadetorestorethesystem,itwillbeassumedthatatthistimeanybreachwouldbeobviousandthatnospecial.entrancetolookforasystembreachisnecessary.Thedemineralizerportionofthesystemwillnothavetobeinspectedasitwillbeisolatedfromthecoolingportionofthesystembyvalves15406/25406/05406and15444/25444/05444.Thesevalvesgoclosedonthelossofpowerattime0oftheevent.NoneoftheotherONactionsrequireentrancetothereactorbuilding(exceptforthanfuelpoolcoolingsystemstart-upandfuelpoollevelmakeupwhichwillbediscussedbelow)~AUNIT2LOCAISASSUMEDFORTHISCONDITIONSINCEITRESULTSINTHEWORSTCASERADIOLOGICALCONDITIONS~Page11

~~ATTACHMENT2toPLA%069Oncethesupportsystemsareassuredfunctioningandavailable,thefuelpoolcoolingsystemoperationwillberestored.Thedemineralizerfunctionwillnotberestoreduntilsometimelaterwhenconditionshaveimprovedsuchthatitcanbeinspectedforpossiblesystembreach.ItwillbeassumedhoweverthatanoperatorwillgotothedemineralizerpanelOC207onelevation779'odeterminethatthefuelpoolfilterdemineralizersubsystemisappropriatelyisolated.Itisconservativelyestimatedthattheoperatorwillspend10minutesatthepanel.Theskimmersurgetankandfuelpoollevelwillbemorethanadequatetosupportsystemoperationasthepoolswellduetoheatup(includingevaporativelosses)willcauseaslightincreaseinSFPlevel.Ithasbeencalculatedthatitwillatmosttake20minutestomakeupthevolumeofwaterlostduetoevaporationduringthe24hoursinwhichitisassumedcoolingislost.ThisassumesoneloopofESWat35gpmmake-uprate.Thusthepumpsmaybestartedoncethebypassvalve153013isclosed,whichtakesatmost2minutes(assumingthevalvewasfullopenattime0oftheevent).Thisvalveisamanuallyoperatedvalveandwouldnotchangepositionattime0oftheevent.Also,ittakesapproximately5minutestoturnonthethreepumpsandadjustthebypassvalve153013opentopassthe1800GPMfiow.Oncethebypassvalveisproperlyadjustedandthethreepumpsareoperating,nootheractionsarerequired.ThusforUnit1inwhichthe153013valveisnexttothe1C206panel,itwilltakeoneoperatoramaximumof7minutestoplacethesysteminoperationwiththreepumpsexcludingingressandegresstimes.Thedoseassociatedwithaningressandegresstimeof=6minutesiscalculatedandreflectedinthetablesinsection3.0.OnUnit2,oneoperatorwillhavetooperatethe253013valve(approximate4minuteoperation)andonewillhavetooperatethepumpcontrolbuttons(2minuteoperation)asthevalveisnotinthevicinityofthepanel.Page12 ATIACHMENT2toPLA-40693.0Summaof0eratorDosesforRestorationofNormalSFPCoolinTABLE3.1SUMMARYOFCALCULATEDOPERATORACCESSDOSESTORESTORETHESPENTFUELPOOLCOOLINGSYSTEM-REACTORBUILDINGUNIT1-ACCESSTOCONTROLPANEL1C206/VALVE153013-ELEV.749'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToControlPanel1C206/Valve153013OperatorStayTimeAtControlPanel1C206/Valve153013TotalsDoseFromAirborneActivity0.02720.0400.0672DoseFromContainedSources0.04710.4450.492DoseFromAirborneActivity2.72-44.0-46.72-4DoseFromContainedSources4.71-44.45-34.92-3DoseFromAirborneActivity0.6891.0791.768DoseFromContainedSources0.504.9145.414TotalIngress/EgressTotalOperatorStayTime0.07430.4857.43-44.85-31.1895.993TOTALACCESSDOSE0.5595.59-37.182NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page13

~~N ATTACHMENT2toPLA-4069.i<TABLE3.2SUMMARYOFCALCULATEDOPERATORACCESSDOSESTORESTORETHESPENTFUELPOOLCOOLING'.SYSTEM-REACTORBUILDINGUNIT2-MISSION1,ACCESSTOCONTROLPANEL2C206-ELEV.749'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToControlPanel2C206OperatorStayTimeAtControlPanel2C206TotalsDoseFromAirborneActivity0.02720.0400.0672DoseFromContainedSources0.04710.4450.492DoseFromAirborneActivity2.72-44.0-46.72-4DoseFromContainedSources4.71-44.45-34.92-3DoseFromAirborneActivity0.6891.0791.768DoseFromContainedSources0.504.9145.414TotalIngress/EgressTotalOperatorStayTime0.07430.4857.43-44.85-31.1895.993TOTALACCESSDOSE0.5595.59-37.182NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page14 ATIACHMENT2toPLA-4069.TABLE3.3SUMMARYOFCALCULATEDOPERATORACCESSDOSESTORESTORETHESPENTFUELPOOLCOOLING'YSTEM-REACTORBUILDINGUNIT2-MISSION2,ACCESSTOVALVE253013-PLATFORMELEV.762'-10"OPERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToValve253013OperatorStayTimeAtValve253013TotalsDoseFromAirborneActivity0.02720.03960.0668DoseFromContainedSources0.1420.5380.68DoseFromAirborneActivity2.72-43.96-46.68-4DoseFromContainedSources1.42-35.38-36.80-3DoseFromAirborneActivity0.7461.0791.825DoseFromContainedSources1.5696.087.649TotalIngress/EgressTotalOperatorStayTime0.1690.5781.69-35.78-32.3157.159TOTALACCESSDOSE0.757.50-39.47NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page15 ATTACHMENT2toPLA-4069.TABLE3.4SUMMARYOFCALCULATEDOPERATORACCESSDOSESTOCHECK.DEMNERALIZERPANELOC207REACTORBUILDINGUNIT1-ACCESSTOPANELOC207-ELEV.779'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToControlPanelOC207OperatorStayTimeAtControlPanelOC207TotalsDoseFromAirborneActivity0.02430.05640.0807DoseFromContainedSources0.02880.0288DoseFromAirborneActivity2.43-45.64-48.07-4DoseFromContainedSources2.88-42.88-4DoseFromAirborneActivity0.6681.542.208DoseFromContainedSources0.2920.292TotalIngress/EgressTotalOperatorStayTime0.05310.05645.31-45.64-40.9601.54TOTALACCESSDOSE0.111.10-32.5NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page16 ATTACHMENT2toPLA-4069.TABLE3.5SUMMARYOFCALCULATEDOPERATORACCESSTOPROVIDEMAKE-UPWATERTOTHESPENTFUELPOOL-'REACTORBUILDINGUNIT1-ACCESSTOROOMI-514ANDPANEL1C206-ELEV.749'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/SOURCEIngress/EgressToRoomI-514DoseToCheckWaterLevelAtPanel1C206DoseInsideRoomI-514TotalsDoseFromAirborneActivity0.02410.006810.1010.132DoseFromContainedSources0.03260.05671.24-30.0905DoseFromAirborneActivity2.41-46.81-51.01-31.32-3DoseFromContainedSources3.26-45.67-41.24-59.05-4DoseFromAirborneActivity0.6620.1862.7493.597DoseFromContainedSources0.3340.6320.01180.978TotalIngress/EgressTotalOperatorStayTime0.05670.1665.67-41.66-30.9963.579TOTALACCESSDOSE0.2232.23-34.58NOTES:(1)Post-LOCAradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page17

~~44.~'

ATTACKMfNT3toPLA-4069ATTACHMENT3RESPONSETOQUESTION3OFNRC11/23/93RAIPage18

~~~

ATTACHMENT3toPLA-4069SQUESIQNPiovideoperatordoseestimatesforthoseoperatoractionsneededtomaintainalternativespentfuelpoolcoolingfunctionsunderDBAaccidentconditions(i.e.useofaccidentandnon-accidentunitspentfuelpoolcoolingsystemtocooltheaccidentunitfuelpool,etc.)assumingtheaccidentunitnormalspentfuelpoolcoolingsystemhasfailedasaresultofaLOCA.Includethesamelevelofdetailasinyourresponsetoquestion1~RESPONSE1Thefollowingprovidesacompleteresponsetoquestion3oftheNovember23,1993NRCRAIconcerningradiologicalevaluationsfortheLossofSFPCoolingissue.Thisresponseisbrokenintotwoparts.Section1.0providesa'discussestheavailabilityofalternativeSFPcoolingunderDBA(Reg.Guide1.3)LOCAconditions.Section2.0providesasummarytableofthedoses(bothairborneandcontained)forRHRSFPcoolinginthenon-accidentunit.ThistableshowsdosesforaDBALOCAwith1%claddamage,100%claddamage,and100%fuelmelt(i.e.,Reg.Guide1.3sourceterm).1.0AvailabiliofAlternativeSentFuelPoolCoolinAsdiscussedinPP&L'sMay24andAugust16,1993submittals,RHRSFPCoolingintheaccidentunitandtheRefuelingfloorareinaccessibleforaDBALOCAwithanassumedReg.Guide1.3sourceterm.PP&LhasnotperformedacalculationforaReg.Guide1.3sourcetermforRHRSFPcoolingmode,however,thedoseratesfor100%claddamageareontheorderof50to440Rem/hour.Basedontheseresults,thedoseratesforafuelmelt(Reg.Guide1.3)wouldprohibitoperatoraccess.UnderDBALOCAconditions(i.e.1%claddamage)operatoraccesswouldbepossiblesincethedoserateswouldbeontheorderof0.5to4.4Rem/hour.Therefore,useoftheaccidentunit'sRHRsystemforalternativeSFPcoolingisnotanoptionifaReg.Guide1.3sourcetermisassumed,butispossiblefortheconditionsexpectedinaDBALOCA.AsreportedinPP&L'sMay24,1993submittal,thedoserateontheRefuelingfloorat24hoursafteraReg.Guide1.3DBALOCAis79.8Rem/hour.Thedosesforthe100%and1%claddamageconditionswerereportedtobe3.8and0.038Rem/hour,respectively.Sincethetimetopullthecaskpitgatesisontheorderofashift,itisnotpossibletoaccomplishthisactivityandincuranacceptabledosetotheoperatorforunderRegGuide1.3conditionswithairborneradiation.Therefore,useofthenon-accidentunit'ssystems(normalSFPcoolingandRHR)tocooltheaccidentunit'sSFPisnotanoptionifthecaskstoragepitgatesareinstalledandaReg.Guide1.3sourcetermispresent.TheseactionscouldbeperformedfortheDBALOCAforthe100%and1%claddamageconditions.Thecalculationusedtodeterminetheabovedoseratesisthesamecalculationdescribedintheresponsetoquestion1.Page19 ATTACHMENT3toPLA<0692.0Summaof0eratorDosesfortheNon-AccidentUnit'sRHRSFPCoolinThefollowingtablesummarizesthedosethatanoperatorwouldexperienceestablishingRHRSFPcoolingtothenon-accidentunit.WhilethisisnotspecificallyrequestedintheRAI,PP&Lisprovidingthisinformationtoestablishtheaccessibilityofthenon-accidentuniteveniftheventilationisnotisolatedfromtheaccidentunit.Non-isolationofnon-accidentunitisassumedforthiscaseinordertomaximizethedoseinthenon-accidentunit.AsnotedinPP&L'sAugust16,1993submittal,thenon-accidentunitcanbeisolatedfromthereactorbuildingHVACrecirculationplenum,therebypreventingthespreadofradiationtothenon-accidentunit.Thedosesarebasedonthesamecalculationusedtoobtainthedosesfortheanswertoquestion2.ThetimetostroketheRHRvalvesfromfullclosedtofullopenis2minutespervalveandaseparateoperatorwouldbesenttomanipulateeachvalve.Page20 ATTACHMENT3toPLA-4069TABLE2.1SUMMARYOFCALCULATEDOPERATORACCESSDOSESFORRHRFUELPOOLCOOLINGASSISTFROMNON-ACCIDENTUNIT-,REACTORBUILDINGUNIT1-ACCESSTOVALVES151060AND151070PLATFORMELEV.705'PERATORACCESSDOSESAT24HOURSPOST-LOCA(R)100%CLADDAMAGE1%CLADDAMAGE100%FUELMELTDOSELOCATION/SOURCEDoseFromAirborneActivityDoseFromContainedSourcesDoseFromAirborneActivityDoseFromContainedSourcesDoseFromAirborneActivityDoseFromContainedSourcesIngress/EgressToValves151060&151070OperatorStayTimeAtValves151060&151070Totals0.0260.02310.04915.17-36.67-30.01182.60-42.31-44.91-45.17-36.67-30.01180.7140.6341.3485.17-36.67-30.0118TotalIngress/EgressTotalOperatorStayTime0.03120.02975.43-36.91-30.7190.641TOTALACCESSDOSE0.06090.01231.36NOTES:(1)Post-LOCAairborneradiationdosesforthe1%claddamagecaseareobtainedbymultiplyingthe100%claddamagedosesbyafactorof0.01.Page21 il 01~4-198414(G~rP.O2ENCLOSURE1PennsylvaniaPowerRLightCompanyVeONOrthNinthStreeihllentOWn,PAtbtct.ttreoStb/7744151Robert0.Syrem2$IM74-7502DirectorofNuclearReactorRegulationAttention:Mr.C,L.Miller,ProjectDirectorProjectDirectorate1-2DivisionofReactorProjectsU.S.NuclearRegulatoryCommissionWashington,D.C.20555CrSUSQUEHhNNhSTEAMBLBCTRICSThTIONREQUESTFORADDITIONALINPORMATIONONLO55OtStENTWELtOOLCOOLINQEVENTSQodcatNo@504tlandSMSI

DearMr.Miller.AttachedisPP&?.'areayonaatayourNovember23.1993RequestforAdditionalInfortnationconcctttingpersonnelaccesstiwsthnstisultingfloepostulatedlossofspentfuelpoolcoolingevents.PlasscontactMr.JamesM.Kennyat(215)774-7914shouMyourrequiteadditionalinfomtation.Vctytrulyyours,

I9<pllsppp6Attachmentcc:NRCDocumentControlDesk(oriiinal)NRCRegionlMr.G,S,Barber,NRCSr.ResidentInspector-SSSSMr,R.J.Clek,NRCSr,ProjectManager-.Rockvtlle AlThCHMENT1topLA~ATTACHMENT1RESPONSETOQUESTION1OFNRC11/23/93RAIPage1 AlTACHMENT1toPLA~Provideadetaileddescriptionofthemodelingtechniquesusedtogeneratethe4,22RemcitedintheAugus!16,1993submittalssthedosereceiveddWngtbaaerationofthespentSuelpoolemergencyservicewatersupplyvalves.Describeindetailthetime-motionanalysisperformedtodetermineexposuretimeeeoclatedwithrequiredoperatoractions.1ncludctheparametersandassumptionsusedtoSeneratcthecontainedandairbornesourcetermsandcalculatetherespectivedosecomponentsassociatedwitheachsegmentofthethne-motionanalysis.ThefollowingprovidesacompleteresponsetoquestionIoftheNovember23,1993NRCRAIconcsrainsradiologicalevaluationsfortheLossofSFPCoolingissue.AsdiscussedinPP&L'sMay24andAugust16,1993submittals,restorationofthenormalSFPcoolingsystempriortoboQingisexpccld.Consequently,PALwouldnotexpectittobcaccessarytousaE8Wformake-upsincethenoanalsystetnscouldbeusedormake-upfhmthenon-accidentunitcouldbeprovided,Thisresponseisseparatedintotwoparts.Section1.0providesadescriptionofthemodelingtechniquesandassumptionauasdforevaluatingoperatoraccesstothcESWmake-upvalves,Alsoincludedinthissection,isadiscussionofhowtheresultstimemotionstudywerefactoredintotheanalysis.Section2,0providessununarytablesofthedoses(bothairbotnaandcontained)foreachofthcsegmentsassumedlnthecalculatioLThesetablesshowdosesforaDBALOCAwith19ocladdamage,1N%claddaautgc,and10%tMtnelt{i,e.,Reg.Guide1.3sourcetarn).1.011QzmimTheTACT5computercodeisusedtoevaluatepost.LOCAradiationsourcesinsidethereactorbuildingusingtheCESARChsytcr15.6.5DBA-LOCAactivityQowpathmodelwithrealisticestimatesofcontainmentl<<akagerateaAirborneactivityconcentrationsinthereactorbuilding!bNtf~!U!!Ip!Ihd!!!Nlhd%Id!failure(NURE&14N)andhealmolt(RegulatoryGuide1.3)sourceterms,Usingthesepost-LOCAsourceterms,radiationdoseratesinsidethereactorbuildinghornairborneaotivityand&unsuppressionpoolwatercontainedsourcesaeevaluatedusingtheMICROSHIELDcomputercodaOperatoraccessrequirementsinsidethemactbrbuildingwaredeterminedforestablishingESVmahruptothespentfbe1poolunderpost-LOCAconditions.OperatoraccusroutesandmisaomwercidentKedanddlvidafintos<<quentialsegmentsforth<<purposeofevaluatingoperatoraccessPage2 ATTACHMENT1toPEA~9doses.Operatoraccessdosesarccomputedbymultiplyingihcradiationdoseratesfromboihairborneandcontainedsourcesinagivenmissionsegmentbythetimespentbytheoperatorinthatmissionscgmcnt,Thesumoftheradiationdosesforallsegmentsofthemissionprovidesthetotalmissiondose.1,2ThisanalysisevaluatespersonnelaccessdosesinsidethereactorbuildingfnrthefollowingpostulatedLOCAinitiatedcoredamagecases:1%claddamage,100%claddamage,and100%fueliuclt.ThecladdamagecasesareevaluatedusingassumptionsconsistentwiththeaccidentsourcetermsdescribedinVUREG-1465,ThefuelmeltcaseiscnnservativelyevaluatedusingaccidentsourcetermsconsistentwithUSNRCRegulatoryGuide1.3andthePSARChapter15.6.5DBA-LOCAlicensingbasisevaluation.Forallcases,realisticcstimatosofthccontainmcntIcekegorateareused.FortheactivityRnwpathmadelusedinthisanalysis,theactivityconcentrationsinsidethenodalvolumesarecalculatedbydividing'theactivityinthenodeatthetimeofinterestbythenodal~volumeandthereforearedirectlyproportionaltotheactivitysourcetermrclcascd&omthefuelintothccontainmentandsuppressionpool,ForthepostulatedLOCA'sthatassumecladdamage,theamountofactivityreleasedisdirectlyproportionaltotheamountofcladdamage,Therefore,acompletesourcetermanddoseanalysisisperfozmcdforthclOONcladdamagecaseandsourcetcrznsanddoseresultsforthcI/ocladdamagecaseazcobtainedbymultiplyingthe100%claddamageresultsby0,01,hKGKG-1465wasusedtosupplyreleasedataforthecladdamagecases.SincenospeciQcnumericalguidanceisprovidedinNURE6-1465,theamountofcladactivityreleased&omthecorewhichbecomesairbornemsidccontainmentorrenudnsinthcsupprcoionpoolwaterisbasedontakingcreditfor55atonproductscrubMngandretentioninaccordancewithStandardReviewPlhn6,5,5.Inaddition,forthecladdamagecases,anaerosolremovalrateof0.73hz"'orparticulateiodineandcesiumisassumedbasedoninfozznatioaprovidedinNUREG-1465,TableS,6fortheLaSalleNuclearPowerPlantwhichisalsoaBWRMarkIIcontainmentdesign,Nocreditforaerosolremovalwastakeninthe18%fhclmeltcase.Cozeactivityrelease&actionsforaLOCAwith15%fuelmeltarebasedonthcrequirementsofRegulatoryGuide1.3stndNURBO-0737andazcth¹25%oftheiodincsand100%ofthenoblegasesareinstantaneouslyairborneinpriniarycontainznentandavailableforleakageand50%ofthecoreinventoryofiodizlsand1%oftheparticulatearereleasedtothesupprcssioepoolwater,Ductothenumberofparticulateisotopesintbccoreandthenumberofdosecalculationsrequired,theparticul¹eectivityreleasekhanthecorewasnotexplicitlyincludedinthcsuppressionpoolactivitysourcetennforthe100%fbelmeltcase.Instead,boundingdosecalculationsusingpost-LOCANipyxessionpoolcontainedsourceswithandwithoutparticulatePage3 ATTACHJHENT0top~~wereusedtodetermineadosemultipliawhichwasusedtoaccountforthedosecontributionfrom198particulateinthesuppressionpoolwater,Theiodineandnoblegasactivitiesreleasedfortbe100%Smlmeltcaseareobtained&amtheFSARDBA.LOCAanalysisgiveninPP8Q.calculationFXMDAM<14.TheSoundinganalys'Iforthedosecoatributloabornperticulereisbasedonpost-LOCAsuppressionpoolliquidactivitysourcetermsgiveninSusquehannaProjootBechtclGdcuiation21M-201.Forailcladdamageandfbclmeltcases,theisotopicchemicalformoftheactivityreleasedfromthecoreisassumedtobeasallows:Iodincs~91%elemental~4%iorganic~5%particulateCesiums10N4particulateNobleGases~100%elenentalThisassumptionisconsistentwithUSNRCRegulatory&dde1,3forcorefueldamage.Forthecladdaaagecases,NUREQ-1465indicatesthatthechemicalformforiodineenteringcontainmcmtis95%particulatand5%elemental,butwitboutPhcontrolofthesuppressionpoolwater,arelativelylarge&actionoftheparticul¹eiodinedissolvedinsupIxelionyoolwaterwillbeconvertedtoeleInentaliodine.'Qierekre,theabovechemicalformsassumedforthisanaiyisalecohshrvativefortheclatdamagecases.Thoprimaryccntainmcntdesignbasisleakagerateis1&day.ForthePSARliccninsbasisDBA-LOCAanalysisthisleakagerateiaassumedforthedurationoftheaccident.Pocthisevaluation,aonedepmkntrealistsoontainaMsttleakageratabasedoacontainlnetttIntegr¹edLeakageRataTostinggLRT)jesuitsandthecalculasalcosttaheeatpoet-LOCAIeeaamreapolmiaueedScbeththecladdamageaatIQ%MddtornaTheILRTtestpressurecorrespondstothcmaxhnumcalcul¹cdcontainmentpoNLOCApressurewithadesignmarginapplied.TherealisticcoatainmentleakageratewaacalculatedbyreducingtheILRTmeasuredleakager¹eproportion¹elytotheILRTtestpressureandthecalculatedcontainmentpressureresponseforaLOCA.Foethhanalyda,themostuy-to~1eaksgeratedataiausedsothatthodoseestimate>>reQectthemostup-~latecontainmentleakagecoaditionaTbetefore,themeasuredIcakagorateat0.606&day5omtheUnit1ILRTperformed5/5/92iaaounedforthisanalyiaAleakager¹eofO.N6&dayisalsorepresentativeoftypicalmeasuredleakageratesatSSESUnita142.NUItE64737providesguidanceforevaluatingoperatoracceNtovitalplantmmforpost-accidentoperations,It!tiesunderItetn(2)SystemaContaininlTbeSourcetha!forpost-LOCAaccidentoperationa,"IbdMon&omleakageofsystetnslocatedoutsideofcontainmentbaaednotbeconsideredforthisanalysis".Tbaehx>>,itisammedScthiaevaluationth¹thelealageofpner-I,OCAo~aha~airborneactivitythoughoorltallanlttyeaetratiooathatmeveroeelodPage4 nssdzMstbeoeasidecod.Thercalilticcoeaiarnentleakagerateusedfbrboththecladandfueldamagecases<<rebasedonthemeasuredleakageratesQnaughcontainmentpenetrationsthatarenotwatersealsBasedontheaboveactivityflowpathways,.theTACTScodeprovidestotalactivityinthereactorbuildingandsuppresaianpoolasafunctionoftimepostaccident.Attherequiredevaluationtime(24hourspostaccident),isotopicactivitiesweretaken&omtheTACTSoutputeditanddividedbytheappropriatedispersalvolumetogiveactivityconcentrations,RadiationdosesinsMethereactorbuildingareevaluatedforbothairborneactivityandforsuppressionpoolwatercontainedsources.OperatoraccessdosesorarearadiationdoseratciareevaluatedineachoftheareasthatrequireaccesstoprovideBSWmakeup,RahstiondosesareevaluatedusingtheMIGROSKELDcoaqtutercodewiththeTACTSgeneratedactivityconcentrationsourceterms,Thedoserate&omairborneactivityinsidethereactorbuildingisactuallysnimmsrsiondose.However,sincetheMICROSHIELDcomputercodecatuxrtcalcuhrtedoserateshternaltothesource,slabgeometryisused.Onehalfofthesourcevolumeismodeledasarectangularvolumesourceandadoserateonthesurheeofthisvolumeiscalculated.Theinuncniondoseisthcalculatedbymultiplyingthecontactdoserate6amhalfofthesourcevolumebyafactorof2.AllimmersiondoseratesarcconservativelycalculatedatthecenterlineoCLho@xnan,Dose~&omthemntainedsuppressionpoollhiuidpipingsourcessrecalctdatedusingcylindricalsourcegeometryvdthreceiveratside.InordertoevaluateoperatoracceNdoses,operatorwalkhgratesandstirclimbingratesarerequired.AtabacmotionstudywaspcrfoanodtovmifyoperatoraccesetraveltimesinsidethereactorbuildingunderLOCAconditions.AnopetahewaadressedinpeNctivaclothingandworlaSelfCelledSrlathmgAIyardusandactualtransitthaeatovalveslocatedonelevationa670'nd749'fthetea~bi48ngweremeaseel.AnisetothesevalvesisrequiredtoprovideBSVmaIkauptoOwspentheipool.Baadupontberesultsofthistimemotionstudy,anoperatorwalkingrateof200ft/minandastairclhnbingrateot50.fthninareconservativelyammedforoperatorlngresa/egresadosscatcuistionaforaccesstothereactorbuiMingunderLOCAconditionLAlsoaspattofthisstudy,usingsparevalves,thevalveopeungthneforthe2inchvalvesusedforBS%systemtie-insadQowcoldrolwasmealuredtobe10ISdl,bafMldll~~%&~IIflTheincoqecadoaofthotime.motionstudyhtothefhalcalculationresultedinthepreliminarydosetotheoglerimeasing&om422Rem.to4,57Rem.,foracoesatothevalvesonelevations670.TheM2RccnvaluewasreportedinPPN'aAugust16,1993submittal.OIeratoraccasdosesareonlyevaluatedforUnit1.TheoperatoraccessarealocationsforUnits1and2areidccdcaleaceptlbrtheareacontainingthevalvesrcxpirN1ibrtie-inofdeESWsyltemfotmakeup(ValveNoL153500,153501anal253S00,2S3501).Buononthepost-accidentradiationlevelsgiveninFigures1$.1-3and11.14oftheSSESPSAR,theareacontainingtheUnit1valvesforRS%systemtieinhashigherdoseratesthandeUrtit2axea.Page5 ATTACHMENT1toPUAOHThereforedosoratescalculatedfortheUnit1areaw111beconservativefortheUnit2area.Therefore,allofthecalculatedoperatoraccessdosesforUnit1areapylicabletoUnit2,Operatoraces'osesareevaluatedat24hourspost-LOCA.FarloisofspentSwlpooloooHng,thefbelpoolbeiinstoboBinappoximately4Ihours,FortheconditionwhereaLouofCHMtePower(LOOP)isalsopost~i,povnclsoxpaMtoberestoredwithin24bours,Therefote,24hourswaschosenssthelatesttimeoperatoractioncouldbetakentorestorecoolingand/ormakeuptothepullandassurethoseactionswouldbecompletedpriortoSFPboiHngSomedoseratesareaiiocalculatedatothertimespost.LOCAandtoshowthatpoet-LOCAdoseratesaredecreasingfortimeperiodsyeaterthan24boaForthe1$%fidelmeltca+,adosefactorisusedtotakeintoaccountthedosecontribution&ompsrticulateinthesuppressionpoolliquid(secSection5.1,Assumption5).TheparticulatedosefactorisdefinedastheratioofthednsaRemsuppceaaionpoolliquidsourcescontainingcoream~~~~poolliqtnd~~contaSactivityonly.Alldoses&emcontainedsourcesforthe18%fbolmeltcasearecalculatedushgthehQCROSHIELDcomputercodewithasuppressionpoolsourcetermthcontainsiodinesonly.TheMICROSHIELDresultsforcontainedsourcesSrthe18%healmeltceoarethenmultiyHedbytheparticulatedosefctnrtotakeinto~untthedosecontributionCromparticulate,Thisdosefactoriscalculatedat24hourspost-LOCAandcanonlybeappliedtooperatoraccessdoseskomsuppressionpoolliquidsourcesevaluatedatNssatnethneperiodpost~acctdent

ThBLE2.1SUMMARYOFChLCULATKDOPERATORAUChSSDOSESTOPROVIDEESWMAKEUPToSPECI'UELPOOL-REACTORBUILDINGUNITI-AOCIXS1QVALVES153500AND153501-ELEV.670'PERATORACCESSDOSESAT24HOURSPOST-I.OCA(R)IM%CXADDAMAGEHCCLADDAMAGE(1)~'TVd1535004153501DoseFambib'ctivity722-3DoseFmaDoseFmraCaaimxlAirborneSourceshctivityOA7672?5DnaFamDoseFamCoaamalhiramScxxecsActivity4.76-3O.1911DoseFaxaCoataijsadSources4.12OleraltaStayTmehtValves153500A153501T0447.45-30.0147heal-3OASO7.45-S1.47-4heal-54.80-3O.402O.N764.16$TealTotalQpaatorQayTmc0.01174.83-31.17-443]802520.494.9D-3QQ~:(I)poat4A)CAtahatioadosesfortbcI<chddamageca+meobtaiaxlbyaadtiplyiagthe1095ciadogedosesbyo~yofOOI8 ThBLE22SUMMhRYOFChJAULLEDOPERATORhCCESSBOSFATOOONTROLESWMAKEOPFLAY-REA~RBUILIXNGUNIT2-AOCKSS'IQHEATEXCHANGERPUMPROOM(I-514)-ELEV.749'PERATOR.hOCESSDOSEShT24HOURSMST-LCICA(R)iN%CLhDDhhhLGE1%CLaDOhMAGE(1)1W%FUELMELT~TogaeleheapIaogtgI-SI4)QietatnrstayTimelnHeatEacbmgerPmyIpaaa(H-Sl4)DoseFaanhirbcxmActivity0.0225DoaeFrcmDateFnrnCocancdAirboraeSoiacxaActivity0.02882.854DoseFxocnCo&aiaedSourcesDoseFromhirbaea:herky0.7040.615DoseFernCoatauxxlSources02922.65-30.9291S.Q5-42.91-419190.295TotalTotalOy~rQayT~S.7040.9960.61$0.079$7.9@41.61NOH%.(I)post-L0CAradistioadoecgfmtbe1%daddamagecareaxeobtainedbYmultiplVinSthe100Yechddaaaagedosesbyafactorof0.01.

01-04-199411'0ATTACHMENT2toPLA~ATTACHMENT2RESPONSETOQUESTION2OFNRCi1/23/93RAIPage9 GX-04-198411I<0ProvideoperatordoseestnnatesforthoseoperatoractionsneededtomaintainthenormalspentgaelpoolcoolingfbncdonunderDBAaccidentconditions,assumingthenortnalspentfuelpoolcoolingsystetnisoperationalfoHowinganaccident.Considerthoseactionsneededtorestorenormalspentfbelfollowingautomaticormanuallpadshedofthespentfuelpoolcoolingsystczn,Includethesamelevelofdetailasinyourresponsetoquestionl.Thefollowingprovidesacompleteresponsetoquestion2oftheNovember23,1993NRCRAIconcerningradiologicalevaluationsfortheLossofSFPCoolingissue.Forthisevaluation,BSWwasevaluatedasthesourceofnuke.upwatersinceitissafetyrelated.Othersourcesofnon-safetyrelatedwatercouldbeusedbutwerenotevaluatedinordertomInimizetheamountofcalculationsperformed.Asnotedintheresponsetoquestion1,restorationofnormalSPPcoolingIstbeexpectedcourseofactinforresponding'toaLossofSFPcoolingevent.Thisresponseisbrokenintothreeparts.Section1.0providesadescriptionofthemodelingtechniquesandassumptionsusedforevaluatingoperateaccesstorestorenormalSpentFuelPool(SPP)CooHng.Section2.0adescriptionoftheactionsrequiredtorestoreandmaintainnortnalSFPCooling,ItIsImponaatonotethatggtime.motionstudywaspccformodfotthoseao6ans,Thetiaungisbasedonoperatoreqertencesincetheseactionsareperformedonaregulabasis.Section3,0providessudsytablesofthedoses{bothairborneandcontahml)foreachofthesegnNnlactionsassumedinthecalculation.Itshouldbenotedthatseveralseparateactions,atdifferentlocationsarerequiredtorestoreandmaintaintNnaalSFFcooling,ThesetablesshowdosesforaDBhLOCAwitb1%cled*mage,1554claddamage,and1$%&elmelt(i.e.,Reg.Guidel.3so+entean).1.0ThecalculationperfornodtodeterminetheoperatordosesforrestorationofnormalSFPcoolingisbasedoathecalculationperfortnedfortheresponsetoquestionl.TheonlydifferencesareassociatedwiththestaytimesandlocationoftheoIeratorswithregardtodistancefromcontaittedsoureeLTbeIeltltsoftbetimemotionstudy~Nrfosmedforquestion1wereusedtodetertnIMop~&tN5&~%hQ0operatoreaq)aicaaowasusedtodeterminethetimetoparianthe'IctioeaPagelo OL04189411148AlTAcHMENT2toplJwoaeTheactionsarebasedonthefollowingsequencesofeventsandplantconfiguration'.DESCRIPTION0hrs.FuelPoolsareisolated;Betharefilled,'2poolheatload$,2MBTU/HR(Iustcompleteda40dayoutage);Ulpoolheatload6.27MBTU/HR(lastoutagebegan135daysago);PoolTemp1104F.24Hr!.UZLOCA/LOOFoccurs;Lossoffbelpvvlcvotinloccurstobothpools;ReactorbuildingHVACrecirculationsystemstarts;SGTSstartLON<<13S(23$)M1LOSSOFFUELPOOLCOOLINO/COOLANTINVENTORYentered,UlcontrolledshutdownbeginsduetotheLOOPcondition.AccusavailabletoES%inbothUnitaat&topowerisrestored,QttylornentOffNonrtalProcedures(LOSSOFFUELPOOLCOOLINQ)tocheckthatthesystemcanbeoperatedandthenimplementOP-135(235)401toplacefidelpoolcooHngintooperation.TheON-l3S(23001g088OFFUELPOOLCOOLING)wouldhavebeenenteredattime0oftheeventandwouldhavebeenimpletnentedtocheckthatthesystetncanbeoperated.Itwouldhavebeendetacminedthatit.couldnotduetoaLOOP.Oncepowerisrestored(assumedtooccurataolaterthan24boursaftereventinititttion)tbeONprovisionswouMguidetheoperatortodetertrtinethatthosystemandtbottocessarysupportsystemsateavailable.ItnplementationoftheON'swillassurethettupportsystetnsareoperabloandSmctionasrequiredtosupportfho1poolcoolingsystetnoperation.Thoseproceduresrequireachecktoassurenosystetnbreachhasoccurred.Wbeaetttranceistnadotorestorethesystetrt,it<villbeassuntedthatatthistheargrbreachwouldbeobviousandthataospecialeatrancetolookforasysuanbrcachm.Ih~INffNINISI0'hfIfmltisolatedhemthecoolingportionofthosystambyvalva15406/254ki/05406andNN044II00444.IhMII~ltIf~I0fhNoftheotherONactionsteyireantrartcetothoreactorbuHdhg(exceptStthanfidelpoolcooling,systemstartupandSetpoollevelmake@whichvrNbediscusecdbc4ow).aasm2md2!aseam~mzacNsozTLMa~zTaeattscsm~caaIRMzaserlcM,cclrtzmMs~Pagell 819419&4'icOP.CUATTAt:HMEMT2toP~HOncethosupportsystemsarcassuredfunctioningandavailablo,thofuelpoolcoolingsystemoperationwiHbcrcstorlxLThedcmincralizerfunctionwillnotbcrestoreduntilsometimelaterwhenconditionshaveimprovedsuchthatitcanbeinspectedforpossiblesystembrcach.ItwillbessaunecLbe+evertharIaoperatorwillIotothedeminaraliieeyanelOC2MonelevarioetWFtodeterminethatthohNlpooL61terdcclrecralisersubsystemisappro1RICCLyisolated.Itisconservgivelyestimatedthattheopenerwillspend10minutesatthepanel.Thoskimuersurgetankandfuelpoollevelwillbemorethanadequatetosupportsystemoperationasthcpoolswellduetoheatup(includingevaporativelosses)wiHcauseasHghtmxaasoinSFPleveLIthasbeencalculatedthititwilletmoattaloe2Dminutestnmsheq)thevolumeofwaterlostduotoevaporationduringthe24hoursinwhichitisassurMdcoolingislost.ThisassumesoncloopofRSVPat3Sgpmmako.uprute.Thusthopumpsmaybostartedoncetbobypassvalve153013isclosed,whichtalesatmost2minutes(assumingtbevalvewasfullopenattime0ofthcevent),Thisvalveisamanuallyoperatedvalveandwouldnotchangepositionattime0oftheevent.Ahe,ittakesapproximately5minutestoturnontbethreepumpsandadustthcbypassvalve1S3013opentopassthc1800GPMQow,Oncethebypassvalveisproperlya(ustedandthethroepumpsareoperating,motheractionsarerequired,ThusforUnit1inwhichthe193013valveisnexttotheIC206panel,itwilltaleoneoperatoramaxitnumof7minutestoplacethesysteminoperationwiththreepumpscxciudiniingressandcycsstimes.Thedoseassoc}atsdwithaningresssadegresstimeofe6minutesiacalculatedandrcQcctodinthetablesinscctioa3.0.OnUnit2,oneoperatorwillhavetooperatethe2S3013valve(approximate4minuteoperation)endonewillhavetooperatethepuapcontrolbuttons(2minutooyoration)asthevalveisnotinthevicinityoftbepaneLPage12 h1ThcHA4ENfg~~anyTABLE3.1SIJMMARYOPCAIZUIATEDOPERATORh1X.'KSSDOSESTORESTORETHESPENTFUELPOOLCOOINGSYFHiM-RBhCIORKKlLDKNGUNlI'-hCCESS1Q69NROLPANEL)C206AALVEl53013-KLEV.74KOPERATORhGC)%SDOSESAT24HOURSPOST-LOCA(R)1N%CXhDSAMhGE1%CLADSAMhGE()j1&%HRLMELTDOSELOCA'DON/SOURCETC)C206/YaIve1530)3QgecgrQayTiaeAtG~mlPand)C206NaheI530I3DoseFramhxboroeActivity0.040DoseFaxaDoseFredCoecaimxlAirbrea:SocaccsActivity0.0471Z72WOA45DoseFroriCoatainedSources4.71-44.45-3OaocFranAiR~Activity0.6&9I.079'.761DoseFromG0QltslBcdSources4.9145.414TagaIOpa~QIyT~0.07437.43-44.$5-3).)89$9930559$39-37.1N2~~f0rQx:1%claddsmagcceeereoblainedbymaltiptyhgrhcl00$daddaaagcdasesbyaD'oruf0.0l.3Pagel3 AlTAClgmr2sa~~yapThe%32SUMMARYOFAQXXJLAVEDOPERATORACCESSDOSESTORESIORETHESPENTFUELPOOLCOGUNGSVSHQ4-REACMRBO1LD&IQUMT2-MISSIGbll,Al3~8TOCONTROLPANEL2CM6-ELEV.749'PERATORhCCESSDOSEShT24HOURSPOST-LOCh(R)l%CLADSkhfAGK1%CLADDhMAGE(I)lM%FllKLMELTDOSELOCATEÃ/SOURCEToGyraltiead2C206DoseFmahihxmhctbrkgDoseFramCoataiuedSources.0.0411DmeFamhatbo~ActivityDoeeFramContainedSouces4.71-44.4$-3DoseFromAirboca:Activity0.6$9I079DoseFnlrrCarrtamxlSnxcea0.504.9I44.92-35410.4854.85-3l.ls95993TOYALACCIESSDOSE5.59-3V.II2NOIES:(1)FMO-LOChrttrhilborrdosesRcthe1%daddamneecaseareobtaimxibyaulgj8yjggtbe19'laddarxggpdosesbya~afOAI.Page14 ATtACH~Zw~~ThBLB33SMAMllkYOFCALCULATEDOPERATORhCCESSDOSESTORESTORETHESPENfFUELPOOLC0OLPg)SYSTEM-REhCMRBUILDINGUMT2-MISSION2,ACCF~TOVALVE253013-PLATFORhfELEV.762'-10"OPERATORACCESSDOSESAT24HOURSPOST-LOCA(R)1N%CLADQkb%AGR1%CLADDAMlCE(I)1%E%ELMELTDOSELCXMTION/SOURCEToVahe253013Ope~St¹yTmeAtValve2530)3DogeFamAirbriaeActhityBoaeFnmCoettlirredSasacsO.l42OMS0.68DoseFmnAil&ma:ActivityDoleFaxaDoseFnlnCo&anedAirbr'M:SomxaActivityIAZ-30.746538-3).0796.$0-31.125BoeeFmraContaaedSauces).5697.649Total0.1691.69-35.78-32.3157.1590.757~39.47~&@:(I)Pbo¹tgAKAagleamdosesfoethe1%c)addamagecan:areobtiiceclbymultiplyagtheIONt'ladr)ramagedosclbya~oE0.O).Page15O TABLE3.1SUMMARYOFCALCULATEDOPEgATQRA@CESSDOSESTO~~@~M;IONIZERPANEL0C207REhClORBUILDS'TI-AOCESSTOPANELOC207-FLED.779'2'ERhTORACCESSDOSEShT24HO%KMST-LOCA(R)QIQ1N%CLADShMAGEl%Cl~ShMACE(I)II0%PIIM.MELTDOSELOCA'HONJ'OURCEToCaaelPandOC?07DoseFramhiahmmhctiviiyQ.92430.0564SoleFamDoseFmnCoaCaiaedAItboaaeSmaoeeActivitytklMS2.43-405.64-4DoseFax'oaCaincdSoaxces2.N-4DoseFamAirboatAcciviy0.66&DoIeFreya.CoasaiaedSoarces0.2921.0740.292T~~ToIsl01~QayT~0.6531531-4ITALNX~SDOSS0.11I.I0-3,NQ'lpga:(I)~LOChzafwda)dosesRtAe1%cMdaalge~mtobasinaibyIrnsICiplymgdaIONAoh'srnll@~ga~oftkOI.Page160

ATFhCiaE~g~ABLE3.5StjMMhRYOFCMCULATEDQPBRATORAOCESSTOPROVlljEMA1~-UPly'AppalTOTESP~FUHPOO1-RFM!TQR.$81LIMNOUNIT1-hCCESSTO1INM1-514hNDPANELIC206-EL'.749'%RA&lRAOCBSSDOSESAT24HOURSNKI'-IANNAgt)IIMCCLADDhhklCR1%CLADQA59LGE(1)IM%FllELMIXTDOSELOCATION/SOURCE~Tm1-5NDaceFmcahirhxmhcIIivity06241DaceFromDaceFaxnGoahIinedhirbarrs:SonreelAcuity0.03262A1%DoseFmmDoseFromCoIeaitljdhirborneSoaxccsActbity32640.662DoseFranCtmainedSouaxmDoseToEback.%~LcvdhIPand1C206DamhaikRoau1-5140.006810.1011.24-36.81-51.01-3132-35.67%1.Z4-59.~0.156OBIIITotalOp~aRayT~0.0567$47%1.66-30.9963.$79NOTES:(l)~LOChgad~idosee5g'be1%cad<eml8~cameareobtamas14xn14~iagthelOMCeh@d~p4ba4'O.OI.Bsge1?

',

ATI'ACHMENT3RESPONSE70QUESTION3OFNRC11/23/93RAI

81~1394P~12JATl'ACHMENT3toNAAOHProvideoperatordoseestimatesforthoseoperatoractionsneededtomaintainaltera<<&respentfidelpoolcooliaghmctionsunderDBhaccidentccnciitiens(i.e.useof<<ccideatautnon-accidentunitspentfuelpoolcoolingsystemtocooltheaccidentuaitfoolpool,etc.)assunungthe<<ccideatuaitaorjxllspoatfidelpoolcoolialsystemhefilledas<<resultofaLOCA.IncludeWsamelevelofdetailasinyourresponsetoquestion1.'Oefollowiagprovidesacompleteresporsetoquestion3oftheNovember23,1993NRCRAIcoacerniagradiologicalevaluationsfortheLossofSFPCoolingissue.Thisresponseisbrokenintotwoparts,Section1.0providesadiscussestheavailsMityofaltern<<tiveSFPcoolingundeDBA(Reg.Guide1.3)LOCAcotgiitioaLSection2.0providesaNaaamytableofthedoses0drb~~)faHRSFPthighd~Tl'lkdosesforaDBALOCAwith1%claddamage,105icladdamage,snd15%fbelmelt(i.e.,Reg.Quide1.3sourceterm).1,0AsdiscussedinPPM.'sMay24andAugust15,1993sabmittals,RHRSFPCoolingiatbeaccidcrrtunitandtheRefbeliagfhorareiaaeessibleforaDBALOCAwithanassumedReg,Guide13sourcetenn.PALh<<snotperformedacalculatioaforaRag.QuMe1.3pureetermforRHRSPPcoolingmode,however,thedoseratesfor100%claddamageNeoatheorderof$0to440Rcaulllur.S<<sadoatbcseresults,tbsjdoseratesforafbo1molt@Log.Guide1,$)wouldprohibitope~raccesLUaderDBALOCAconditions(i.e.1%claddamge)operatoracce<<awouldbepossiblesincethedoserateswouMbeoatheorderof0,5to4.4RNnthour.TherefoeeuseoftheaeidearunsRHRsystemfor<<ltern<<tiveSFPcaallnglsnotsnoptionifaReg.(halte1.3sousetermisassumed,butispossibleforthecosditioasexyectedinaDBALOCA.AsreportediaPPN,'sMay24,1993subraittal,thedoserateoetheReheUag5oarat24hours<<her~Res,(Idaho1.3MALOCAh%SReathea,VisedeeseAetheIONIC<<aL1%cl<<ddamageexxRCom~appedtoba34aalLNIRemlbaa,rasyeetiveiy.QaoethethnetepullSe~plCANietlr.theocdeofashat,ftis~poedbietoawomryiishthh<<ctivity<<ndiacutat'Nt8theoperltocforunderRegOuMe13ootMItiomwith<<irwin<<radhNadfuaofthememcMunit'ssystems(tlcmalSFPcooling<<ndRHR)tocoolthe<<ocidartunit'sSPPisnetmopt@aitthecaskstoragepitI<<te<<aremetall<<d<<adakeg.Gute1,3sourceternisimleaL'Hsaa:tioasoomph}bepe5xamdhrtheDSALOCAhctheIDOLasd1%cddaaNIeooa5thaarTbecalcuia8aausedtodetcemiaetheabovedoseratesisthesamecalculstioadescribedinthere<<yea<<etoyee&ml.Page19

AtThCRMENY3toI'~H2.0~efo]]owiagtableaummarinathedosethatanopcmtorwouldexperlEnceestablishingRHRSFPcoolingtothenoa~cidentunit.WhilethisisnotspcciQcaQyrequestedintheRAI,PPALispcevidinlthisinforamtiontoestablishtboeecelsibilityofthenon~dentuaitIteniftheventi&onisggisolatedBomtheaccidentunit.Non-isolationofaon-accidentunitisassumedforthiscaseiaordertotnsxindxethedoseiathenon~identunit,AsnotedinPPN.'sAugust1t41993subrnitta4thenoncidentunitumbe)solated&enthereactorbuildingHVACrecircubLtionplenum,therebypreveatialthespreadofradhtiontotheaoa-accidentuait,ThedosesarobasedoathesamecalcuMoausedtoobtainthedosesibr,theanswertoquestion'.Thetitaeto¹roketheRHRvalves6amMlcloaxltofbi'penis2minutespervalveandaseparateopentorwouldbeseattomanipuilteeachvalve.

ATTACHMENT'to~~ThSLE2.1SUMhQiRYOFChLCULATEDOPERATORhCXHSSDOSESFokRHRFUELPOOLGOOfINGhS8)STPR~MON-hQQIHKI'NIT-IEhCfORBUILKMsUNIT1-hGCKSSTOVALVES151060hND)5)070NA%0RMKLBV.705'PMh1QRACCESSDOSESAT24BOURSMST-DKA(R)HLCXADDhMAGRHMCFllBLMELTDOSELOCA'GON/SOURCEDoleFranhislxxaeActivhyDoseFaxnCoalmalSoars@DoseFryhirbanahctiviyfl)DoseFexnDoseFamOatma}Air@~84HIKcsActivityBoaeFernCaauaiaedSeesToVahesI51060A151070O.OZS5.17-35.17-3.0.714517-3Op~mSayThaAtVabel151060R0.02311510700.04916.67-30.0III49l-46.67-30.011I0.6346.67-30.011$TotalI0.03l25.43-36.91-30.7)90.641')OTALhCCEaSDOSE0.06090.0]23NOTES:())Post-LOCAadxrmradikioadoses6xthe)%daddamage~ageobtaig)edbyyzgg~ggyggtbeI~c)~d~~~bof0.01.Page21 FuelPoolCoolingIssueBackround~Issueraisedbytwocontractors~ContractorscontendthatalossofFPC,concurrentwithLOCAresultsin:-boilingSFPandfuelmeltoutsidecontainment-lossofallECCSandfailureofcontainmentintegrity~PP&LmaintainsthatadequatecapabilityexiststorespondtoalossofFPCevent FuelPoolCoolingIssueBackground~LossofnormalFPCsystemdueto:-Seismic-LOOP.-'LOCA~NormalFPCsystemisfirstlineofdefense~Othersystemsavailabletoprovide:-makeuptoSFP-coolingtoSFP FuelPoolCoolingIssueLA~HydrodynamicLoads~FPCnot.designedforhydrodynamicloads~PP&LassessmentconcludednormalEPCsystemmayremainfunctionalafterLOCA FuelPoolCoolingIssuePPLPosition~SSESLicensingBasisdoesnotconsiderlossofFPCforotherthanSeismicevents~Operatorshavetimetoreact(50to130hrs)~Safety-grademakeupsourcealwaysavailable~Safety-gradecoolingviaRHRFPCmode~Boilingenvironmentcanbemitigated e

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