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

ACCELERATED DITRIBUTION DEMONSTQWTION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9401110318 DOC.DATE:

94/01/04NOTARIZED:

NOFACIL:50-387 Susquehanna SteamElectricStation,Unit1,Pennsylva 50-388Susquehanna SteamElectricStation,Unit2,Pennsylva AUTH.NAMEAUTHORAFFILIATION BYRAM,R.G.

Pennsylvania Power&LightCo.RECIP.NAME RECIPIENT AFFILIATION MILLER,C.L.

ProjectDirectorate I-2

SUBJECT:

Forwardsresponseto931123RAIrepersonnel accessquestions resulting frompostulated lossofspentfuelpoolcoolingevents.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:DOCKET0500038705000388DARECIPIENT IDCODE/NAME PD1-2LACLARK,RINTERNAL:

ACRSNRR/DORS/OTSB NRR/DRPWNRR/DSSA/SRXB01EXTERNAL:

NRCPDRCOPIESLTTRENCL112266111111101111RECIPIENT IDCODE/NAME PD1-2PDNRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2NSICCOPIESLTTRENCL11111111111011DDRDNOTETOALL"RIDS"RECIPIENTS:

DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LIS15FORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR22ENCL20 Pennsylvania Power8LightCompanyTwoNorthNinthStreet~Alientown, PA18101-1179

~215/774-5151 RobertG.ByramSeniorVicePresident-Nuclear 215/774-7502 PANyDirectorofNuclearReactorRegulation Attention:

Mr.C.L.Miller,ProjectDirectorProjectDirectorate I-2DivisionofReactorProjectsU.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEHANNA STEAMELECTRICSTATIONREQUESTFORADDITIONAL INFORMATION ONLOSSOFSPENTFUELPOOLCOOLINGEVENTSPLA-4069FILER41-2DocketNos.50-387and50-388

DearMr.Miller:

AttachedisPP8rL'sresponsetoyourNovember23,1993RequestforAdditional Information concerning personnel accessquestions resulting frompostulated lossofspentfuelpoolcoolingevents.PleasecontactMr.JamesM.Kennyat(215)774-7914shouldyourrequireadditional information.

Verytrulyyours,R..ByAttachment cc:%RCDocumellt=Control-Desk=(original)tt NRCRegionIMr.G.S.Barber,NRCSr.ResidentInspector

-SSESMr.R.J.Clark,NRCSr.ProjectManager-Rockville 0700tfa.9401110318 940104,PDRADOCK05000387S.,'..PDR

~~

ATTACHMENT 1toPLA-4069ATTACHMENT 1RESPONSETOQUESTION1OFNRC11/23/93RAIPage1 0h,I.

ATTACHMENT 1toPLA<069QIIEHTIONIProvideadetaileddescription ofthemodelingtechniques usedtogeneratethe4.22RemcitedintheAugust16,1993submittal asthedosereceivedduringtheoperation ofthespentfuelpoolemergency servicewatersupplyvalves.Describeindetailthetime-motion analysisperformed todetermine exposuretimeassociated withrequiredoperatoractions.Includetheparameters andassumptions usedtogeneratethecontained andairbornesourcetermsandcalculate therespective dosecomponents associated witheachsegmentofthetime-motion analysis.

RESPONSE1Thefollowing providesacompleteresponsetoquestion1oftheNovember23,1993NRCRAIconcerning radiological evaluations fortheLossofSFPCoolingissue.Asdiscussed inPPkL'sMay24andAugust16,1993submittals, restoration ofthenormalSFPcoolingsystempriortoboilingisexpected.

Consequently, PPALwouldnotexpectittobenecessary touseESWformake-upsincethenormalsystemscouldbeusedormake-upfromthenon-accident unitcouldbeprovided.

Thisresponseisseparated intotwoparts.Section1.0providesadescription ofthemodelingtechniques andassumptions usedforevaluating operatoraccesstotheESWmake-upvalves.Alsoincludedinthissection,isadiscussion ofhowtheresultstime-motion studywerefactoredintotheanalysis.

Section2.0providessummarytablesofthedoses(bothairborneandcontained) foreachofthesegmentsassumedinthecalculation.

ThesetablesshowdosesforaDBALOCAwith1%claddamage,100%claddamage,and100%fuelmelt(i.e.,Reg.Guide1.3sourceterm).1.0DetailedDescritionofModelinTechniues1.1OverviewTheTACT5computercodeisusedtoevaluatepost-LOCA radiation sourcesinsidethereactorbuildingusingtheFSARChapter15.6.5DBA-LOCAactivityflowpathmodelwithrealistic estimates ofcontainment leakagerates.Airborneactivityconcentrations inthereactorbuildingandactivityconcentrations inthesuppression poolwaterareevaluated forpostulated claddingfailure(NUREG-1465) andfuelmelt(Regulatory Guide1.3)sourceterms.Usingthesepost-LOCA sourceterms,radiation doseratesinsidethereactorbuildingfromairborneactivityandfromsuppression poolwatercontained sourcesareevaluated usingtheMICROSHIELD computercode.Operatoraccessrequirements insidethereactorbuildingweredetermined forestablishing ESWmakeuptothespentfuelpoolunderpost-LOCA conditions.

Operatoraccessroutesandmissionswereidentified anddividedintosequential segmentsforthepurposeofevaluating operatoraccessPage2 ATTACHMENT 1toPLA%069doses.Operatoraccessdosesarecomputedbymultiplying theradiation doseratesfrombothairborneandcontained sourcesinagivenmissionsegmentbythetimespentbytheoperatorinthatmissionsegment.Thesumoftheradiation dosesforallsegmentsofthemissionprovidesthetotalmissiondose.1.2DetailedDescritionThisanalysisevaluates personnel accessdosesinsidethereactorbuildingforthefollowing postulated LOCAinitiated coredamagecases:1%claddamage,100%claddamage,and100%fuelmelt.Thecladdamagecasesareevaluated usingassumptions consistent withtheaccidentsourcetermsdescribed inNUREG-1465.

Thefuelmeltcaseisconservatively evaluated usingaccidentsourcetermsconsistent withUSNRCRegulatory Guide1.3andtheFSARChapter15.6.5DBA-LOCAlicensing basisevaluation.

Forallcases,realistic estimates ofthecontainment leakagerateareused.Fortheactivityflowpathmodelusedinthisanalysis, theactivityconcentrations insidethenodalvolumesarecalculated bydividingtheactivityinthenodeatthetimeofinterestbythenodalvolumeandtherefore aredirectlyproportional totheactivitysourcetermreleasedfromthefuelintothecontainment andsuppression pool.Forthepostulated LOCA'sthatassumecladdamage,theamountofactivityreleasedisdirectlyproportional totheamountofcladdamage.Therefore, acompletesourcetermanddoseanalysisisperformed forthe100%claddamagecaseandsourcetermsanddoseresultsforthe1%claddamagecaseareobtainedbymultiplying the100%claddamageresultsby0.01.NUREG-1465 wasusedtosupplyreleasedataforthecladdamagecases.Sincenospecificnumerical guidanceisprovidedinNUREG-1465, theamountofcladactivityreleasedfromthecorewhichbecomesairborneinsidecontainment orremainsinthesuppression poolwaterisbasedontakingcreditforfissionproductscrubbing andretention inaccordance withStandardReviewPlan6.5.5.Inaddition, forthecladdamagecases,anaerosolremovalrateof0.73hr'orparticulate iodineandcesiumisassumedbasedoninformation providedinNUREG-1465, Table5.6fortheLaSalleNuclearPowerPlantwhichisalsoaBWRMarkIIcontainment design.Nocreditforaerosolremovalwastakeninthe100%fuelmeltcase.Coreactivityreleasefractions foraLOCAwith100%fuelmeltarebasedontherequirements ofRegulatory Guide1.3andNUREG-0737 andarethat25%oftheiodinesand100%ofthenoblegasesareinstantaneously airborneinprimarycontainment andavailable forleakageand50%ofthecoreinventory ofiodinesand1%oftheparticulate arereleasedtothesuppression poolwater.Duetothenumberofparticulate isotopesinthecoreandthenumberofdosecalculations

required, theparticulate activityreleasefromthecorewasnotexplicitly includedinthesuppression poolactivitysourcetermforthe100%fuelmeltcase.Instead,boundingdosecalculations usingpost-LOCA suppression poolcontained sourceswithandwithoutparticulate Page3 ATTACHMENT 1toPlA-4069wereusedtodetermine adosemultiplier whichwasusedtoaccountforthedosecontribution from1%particulate inthesuppression poolwater.Theiodineandnoblegasactivities releasedforthe100%fuelmeltcaseareobtainedfromtheFSARDBA-LOCAanalysisgiveninPP&Lcalculation FX-C-DAM-014.

Theboundinganalysisforthedosecontribution fromparticulate isbasedonpost-LOCA suppression poolliquidactivitysourcetermsgiveninSusquehanna ProjectBechtelCalculation 200-201.Forallcladdamageandfuelmeltcases,theisotopicchemicalformoftheactivityreleasedfromthecoreisassumedtobeasfollows:Iodines=91%elemental

=4%organic=5%particulate Cesiums=100%particulate NobleGases=100%elemental Thisassumption isconsistent withUSNRCRegulatory Guide1.3forcorefueldamage.Forthecladdamagecases,NUREG-1465 indicates thatthechemicalformforiodineenteringcontainment is95%particulate and5%elemental, butwithoutPhcontrolofthesuppression poolwater,arelatively largefractionoftheparticulate iodinedissolved insuppression poolwaterwillbeconverted toelemental iodine.Therefore, theabovechemicalformsassumedforthisanalysisareconservative forthecladdamagecases.Theprimarycontainment designbasisleakagerateis1%/day.FortheFSARlicensing basisDBA-LOCAanalysisthisleakagerateisassumedforthedurationoftheaccident.

Forthisevaluation, atimedependent realistic containment leakageratebasedoncontainment Integrated LeakageRateTesting(ILRT)resultsandthecalculated containment post-LOCA pressureresponseisusedforboththecladdamageand100%fuelmeltcases.TheILRTtestpressurecorresponds tothemaximumcalculated containment post-LOCA pressurewithadesignmarginapplied.Therealistic containment leakageratewascalculated byreducingtheILRTmeasuredleakagerateproportionately totheILRTtestpressureandthecalculated containment pressureresponseforaLOCA.Forthisanalysis, themostup-to-date leakageratedataisusedsothatthedoseestimates reflectthemostup-to-date containment leakageconditions.

Therefore, themeasuredleakagerateof0.606%/day fromtheUnit1ILRTperformed 5/5/92isassumedforthisanalysis.

Aleakagerateof0.606%/day isalsorepresentative oftypicalmeasuredleakageratesatSSESUnits1&2.NUREG-0737 providesguidanceforevaluating operatoraccesstovitalplantareasforpost-accidentoperations.

ItstatesunderItem(2)SystemsContaining TheSourcethatforpost-LOCA accidentoperations, "Radiation fromleakageofsystemslocatedoutsideofcontainment neednotbeconsidered forthisanalysis".

Therefore, itisassumedforthisevaluation thattheleakageofpost-LOCA containment airborneactivitythroughcontainment penetrations thatarewatersealedPage4 ATTACHMENT 1toPLA<069neednotbeconsidered.

Therealistic containment leakagerateusedforboththecladandfueldamagecasesarebasedonthemeasuredleakageratesthroughcontainment penetrations thatarenotwatersealed.Basedontheaboveactivityflowpathways, theTACT5codeprovidestotalactivityinthereactorbuildingandsuppression poolasafunctionoftimepostaccident.

Attherequiredevaluation time(24hourspostaccident),

isotopicactivities weretakenfromtheTACT5outputeditanddividedbytheappropriate dispersal volumetogiveactivityconcentrations.

Radiation dosesinsidethereactorbuildingareevaluated forboth"airborneactivityandforsuppression poolwatercontained sources.Operatoraccessdosesorarearadiation doseratesareevaluated ineachoftheareasthatrequireaccesstoprovideESWmakeup.Radiation dosesareevaluated usingtheMICROSHIELD computercodewiththeTACT5generated activityconcentration sourceterms.Thedoseratefromairborneactivityinsidethereactorbuildingisactuallyanimmersion dose.However,sincetheMICROSHIELD computercodecannotcalculate doseratesinternaltothesource,slabgeometryisused.Onehalfofthesourcevolumeismodeledasarectangular volumesourceandadoserateonthesurfaceofthisvolumeiscalculated.

Theimmersion doseisthencalculated bymultiplying thecontactdoseratefromhalfofthesourcevolumebyafactorof2.Allimmersion doseratesareconservatively calculated atthecenterline oftheroom.Doseratesfromthecontained suppression poolliquidpipingsourcesarecalculated usingcylindrical sourcegeometrywithreceiveratside.Inordertoevaluateoperatoraccessdoses,operatorwalkingratesandstairclimbingratesarerequired.

Atimemotionstudywasperformed toverifyoperatoraccesstraveltimesinsidethereactorbuildingunderLOCAconditions.

Anoperatorwasdressedinprotective clothingandworeaSelfContained Breathing Apparatus andactualtransittimestovalveslocatedonelevations 670'nd749'fthereactorbuildingweremeasured.

AccesstothesevalvesisrequiredtoprovideESWmakeuptothespentfuelpool.Basedupontheresultsofthistimemotionstudy,anoperatorwalkingrateof200ft/minandastairclimbingrateof50.ft/minareconservatively assumedforoperatoringress/egress dosecalculations foraccesstothereactorbuildingunderLOCAconditions.

Alsoaspartofthisstudy,usingsparevalves,thevalveopeningtimeforthe2inchvalvesusedforESWsystemtie-inandflowcontrolwasmeasuredtobe10to15seconds,butforcalculational conservatism, avalveopeningtimeof1minutewasused.Theincorporation ofthetime-motion studyintothefinalcalculation resultedinthepreliminary dosetotheoperatorincreasing from4.22Rem.to4.57Rem.,foraccesstothevalvesonelevations 670.The4.22RemvaluewasreportedinPPkL'sAugust16,1993submittal.

Operatoraccessdosesareonlyevaluated forUnit1~Theoperatoraccessarealocations forUnits1and2areidentical exceptfortheareacontaining thevalvesrequiredfortie-inoftheESWsystemformakeup(ValveNos.153500,153501and253500,253501).Basedonthepost-accident radiation levelsgiveninFigures18.1-3and18.1-4oftheSSESFSAR,theareacontaining theUnit1valvesforESWsystemtie-inhashigherdoseratesthantheUnit2area.Page5 ATTACHMENT 1toPLA-4069Therefore doseratescalculated fortheUnit1areawillbeconservative fortheUnit2area.Therefore, allofthecalculated operatoraccessdosesforUnit1areapplicable toUnit2.Operatoraccessdosesareevaluated at24hourspost-LOCA.

Forlossofspentfuelpoolcooling,thefuelpoolbeginstoboilinapproximately 48hours.Forthecondition whereaLossofOffsitePower(LOOP)isalsopostulated, powerisexpectedtoberestoredwithin24hours.Therefore, 24hourswaschosenasthelatesttimeoperatoractioncouldbetakentorestorecoolingand/ormake-uptothepullandassurethoseactionswouldbecompleted priortoSFPboilingSomedoseratesarealsocalculated atothertimespost-LOCA andtoshowthatpost-LOCA doseratesaredecreasing fortimeperiodsgreaterthan24hours.Forthe100%fuelmeltcase,adosefactorisusedtotakeintoaccountthedosecontribution fromparticulate inthesuppression poolliquid(seeSection5.1,Assumption 5).Theparticulate dosefactorisdefinedastheratioofthedosefromsuppression poolliquidsourcescontaining coreiodineandparticulate activitytothedosefromsuppression poolliquidsourcescontaining iodineactivityonly.Alldosesfromcontained sourcesforthe100%fuelmeltcasearecalculated usingtheMICROSHIELD computercodewithasuppression poolsourcetermthatcontainsiodinesonly.TheMICROSHIELD resultsforcontained sourcesforthe100%fuelmeltcasearethenmultiplied bytheparticulate dosefactortotakeintoaccountthedosecontribution fromparticulate.

Thisdosefactoriscalculated at24hourspost-LOCA andcanonlybeappliedtooperatoraccessdosesfromsuppression poolliquidsourcesevaluated atthissametimeperiodpost-accident.

Page6 ATTACHMENT 1toPLA-40692.0Summof0eratorDosesforESWMake-uValvesTABLE2.1SUMMARYOFCALCULATED OPERATORACCESSDOSESTOPROVIDEESWMAKEUPTOSPENTFUELPOOL--REACTORBUILDINGUNIT1-ACCESSTOVALVES153500AND153501-ELEV.670'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToValves153500&153501OperatorStayTimeAtValves153500Ec153501TotalsDoseFromAirborneActivity7.22-37.45-30.0147DoseFromContained Sources0.4764.21-30.480DoseFromAirborneActivity7.22-57.45-51.47-4DoseFromContained Sources4.76-34.21-54.80-3DoseFromAirborneActivity0.1980.2040.402DoseFromContained Sources4.120.04764.168TotalIngress/Egress TotalOperatorStayTime0.48330.01174.83-31.17-44.3180.252TOTALACCESSDOSE0.494.90-34.57NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page7 ATTACHMENT 1toPLA-4069-TABLE2.2SUMMARYOFCALCULATED OPERATORACCESSDOSESTOCONTROLESWMAKEUPFLOW-REACTORBUILDINGUNIT2-ACCESSTOHEATEXCHANGER PUMPROOM(1-514)-ELEV.749'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToHeatExchanger PumpRoom(11-514)OperatorStayTimeInHeatExchanger PumpRoom(11-514)TotalsDoseFromAirborneActivity0.0280.02250.0505DoseFromContained Sources0.02882.77-40.0291DoseFromAirborneActivity2.80-42.25-45.05-4DoseFromContained Sources2.88-42.77-62.91-4DoseFromAirborneActivity0.7040.6151.319DoseFromContained Sources0.2922.65-30.295TotalIngress/Egress TotalOperatorStayTime0.05700.02285.70-42.28-40.9960.618TOTALACCESSDOSE0.07987.98-41.61NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.PageS ATTACHMENT 2toPLA-4069ATTACHMENT 2RESPONSETOQUESTION2OFNRC11/23/93RAIPage9 ATTACHMENT 2toPLA-4069OVVONProvideoperatordoseestimates forthoseoperatoractionsneededtomaintainthenormalspentfuelpoolcoolingfunctionunderDBAaccidentconditions, assumingthenormalspentfuelpoolcoolingsystemisoperational following anaccident.

Considerthoseactionsneededtorestorenormalspentfuelfollowing automatic ormanualloadshedofthespentfuelpoolcoolingsystem.Includethesamelevelofdetailasinyourresponsetoquestion1.RE<SPONSK 2Thefollowing providesacompleteresponsetoquestion2oftheNovember23,1993NRCRAIconcerning radiological evaluations fortheLossofSFPCoolingissue.Forthisevaluation, ESWwasevaluated asthesourceofmake-upwatersinceitissafety-related.

Othersourcesofnon-safetyrelatedwatercouldbeusedbutwerenotevaluated inordertominimizetheamountofcalculations performed.

Asnotedintheresponsetoquestion1,restoration ofnormalSFPcoolingistheexpectedcourseofactionforresponding toaLossofSFPcoolingevent.Thisresponseisbrokenintothreeparts.Section1.0providesadescription ofthemodelingtechniques andassumptions usedforevaluating operatoraccesstorestorenormalSpentFuelPool(SFP)Cooling.Section2.0adescription oftheactionsrequiredtorestoreandmaintainnormalSFPCooling.Itisimportant tonotethatnotime-motion studywasperformed fortheseactions.Thetimingisbasedonoperatorexperience sincetheseactionsareperformed onaregularbasis.Section3.0providessummarytablesofthedoses(bothairborneandcontained) foreachofthesegments/actions assumedinthecalculation.

Itshouldbenotedthatseveralseparateactions,atdifferent locations arerequiredtorestoreandmaintainnormalSFPcooling.ThesetablesshowdosesforaDBALOCAwith1%claddamage,100%claddamage,and100%fuelmelt(i.e.,Reg.Guide1.3sourceterm).1.0DetailedDescritionofModelinTechniuesThecalculation performed todetermine theoperatordosesforrestoration ofnormalSFPcoolingisbasedonthecalculation performed fortheresponsetoquestion1.Theonlydifferences areassociated withthestaytimesandlocationoftheoperators withregardtodistancefromcontained sources.Theresultsofthetime-motion studyperformed forquestion1wereusedtodetermine operatortransittimes,whileoperatorexperience.was.used todetermine thetimetoperformtheactions.Page10 ATTACHMENT 2toPLA-40692.0ActionsforRestoration ofNormalSFPCoolinTheactionsarebasedonthefollowing sequences ofeventsandplantconfiguration':

TIMEDESCRIPTION 0hrs.FuelPoolsareisolated; Botharefilled;U2poolheatload=8.2MBTU/HR(justcompleted a40dayoutage);U1poolheatload=6.27MBTU/HR(lastoutagebegan135daysago);PoolTemp=110'F.U2LOCA/LOOP occurs;Lossoffuelpoolcoolingoccurstobothpools;ReactorbuildingHVACrecirculation systemstarts;SGTSstarts.24Hrs.ON-135(235)-001 LOSSOFFUELPOOLCOOLING/COOLANT INVENTORY entered.U1controlled shutdownbeginsduetotheLOOPcondition.

Accessavailable toESWinbothUnits.Offsitepowerisrestored.

Implement OffNormalProcedures (LOSSOFFUELPOOLCOOLING)tocheckthatthesystemcanbeoperatedandthenimplement OP-135(235)-001 toplacefuelpoolcoolingintooperation.

TheON-135(235)-001 (LOSSOFFUELPOOLCOOLING)wouldhavebeenenteredattime0oftheeventandwouldhavebeenimplemented tocheckthatthesystemcanbeoperated.

Itwouldhavebeendetermined thatitcouldnotduetoaLOOP.Oncepowerisrestored(assumedtooccuratnolaterthan24hoursaftereventinitiation) theONprovisions wouldguidetheoperatortodetermine thatthesystemandthenecessary supportsystemsareavailable.

Implementation oftheON'swillassurethesupportsystemsareoperableandfunctionasrequiredtosupportfuelpoolcoolingsystemoperation.

Theseprocedures requireachecktoassurenosystembreachhasoccurred.

Whenentranceismadetorestorethesystem,itwillbeassumedthatatthistimeanybreachwouldbeobviousandthatnospecial.entrancetolookforasystembreachisnecessary.

Thedemineralizer portionofthesystemwillnothavetobeinspected asitwillbeisolatedfromthecoolingportionofthesystembyvalves15406/25406/05406 and15444/25444/05444.

Thesevalvesgoclosedonthelossofpowerattime0oftheevent.NoneoftheotherONactionsrequireentrancetothereactorbuilding(exceptforthanfuelpoolcoolingsystemstart-upandfuelpoollevelmakeupwhichwillbediscussed below)~AUNIT2LOCAISASSUMEDFORTHISCONDITION SINCEITRESULTSINTHEWORSTCASERADIOLOGICAL CONDITIONS

~Page11

~~ATTACHMENT 2toPLA%069Oncethesupportsystemsareassuredfunctioning andavailable, thefuelpoolcoolingsystemoperation willberestored.

Thedemineralizer functionwillnotberestoreduntilsometimelaterwhenconditions haveimprovedsuchthatitcanbeinspected forpossiblesystembreach.Itwillbeassumedhoweverthatanoperatorwillgotothedemineralizer panelOC207onelevation 779'odetermine thatthefuelpoolfilterdemineralizer subsystem isappropriately isolated.

Itisconservatively estimated thattheoperatorwillspend10minutesatthepanel.Theskimmersurgetankandfuelpoollevelwillbemorethanadequatetosupportsystemoperation asthepoolswellduetoheatup(including evaporative losses)willcauseaslightincreaseinSFPlevel.Ithasbeencalculated thatitwillatmosttake20minutestomakeupthevolumeofwaterlostduetoevaporation duringthe24hoursinwhichitisassumedcoolingislost.ThisassumesoneloopofESWat35gpmmake-uprate.Thusthepumpsmaybestartedoncethebypassvalve153013isclosed,whichtakesatmost2minutes(assuming thevalvewasfullopenattime0oftheevent).Thisvalveisamanuallyoperatedvalveandwouldnotchangepositionattime0oftheevent.Also,ittakesapproximately 5minutestoturnonthethreepumpsandadjustthebypassvalve153013opentopassthe1800GPMfiow.Oncethebypassvalveisproperlyadjustedandthethreepumpsareoperating, nootheractionsarerequired.

ThusforUnit1inwhichthe153013valveisnexttothe1C206panel,itwilltakeoneoperatoramaximumof7minutestoplacethesysteminoperation withthreepumpsexcluding ingressandegresstimes.Thedoseassociated withaningressandegresstimeof=6minutesiscalculated andreflected inthetablesinsection3.0.OnUnit2,oneoperatorwillhavetooperatethe253013valve(approximate 4minuteoperation) andonewillhavetooperatethepumpcontrolbuttons(2minuteoperation) asthevalveisnotinthevicinityofthepanel.Page12 ATIACHMENT 2toPLA-40693.0Summaof0eratorDosesforRestoration ofNormalSFPCoolinTABLE3.1SUMMARYOFCALCULATED OPERATORACCESSDOSESTORESTORETHESPENTFUELPOOLCOOLINGSYSTEM-REACTORBUILDINGUNIT1-ACCESSTOCONTROLPANEL1C206/VALVE 153013-ELEV.749'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToControlPanel1C206/Valve 153013OperatorStayTimeAtControlPanel1C206/Valve 153013TotalsDoseFromAirborneActivity0.02720.0400.0672DoseFromContained Sources0.04710.4450.492DoseFromAirborneActivity2.72-44.0-46.72-4DoseFromContained Sources4.71-44.45-34.92-3DoseFromAirborneActivity0.6891.0791.768DoseFromContained Sources0.504.9145.414TotalIngress/Egress TotalOperatorStayTime0.07430.4857.43-44.85-31.1895.993TOTALACCESSDOSE0.5595.59-37.182NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page13

~~N ATTACHMENT 2toPLA-4069.

i<TABLE3.2SUMMARYOFCALCULATED OPERATORACCESSDOSESTORESTORETHESPENTFUELPOOLCOOLING'.SYSTEM-REACTORBUILDINGUNIT2-MISSION1,ACCESSTOCONTROLPANEL2C206-ELEV.749'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToControlPanel2C206OperatorStayTimeAtControlPanel2C206TotalsDoseFromAirborneActivity0.02720.0400.0672DoseFromContained Sources0.04710.4450.492DoseFromAirborneActivity2.72-44.0-46.72-4DoseFromContained Sources4.71-44.45-34.92-3DoseFromAirborneActivity0.6891.0791.768DoseFromContained Sources0.504.9145.414TotalIngress/Egress TotalOperatorStayTime0.07430.4857.43-44.85-31.1895.993TOTALACCESSDOSE0.5595.59-37.182NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page14 ATIACHMENT 2toPLA-4069.

TABLE3.3SUMMARYOFCALCULATED OPERATORACCESSDOSESTORESTORETHESPENTFUELPOOLCOOLING'YSTEM-REACTORBUILDINGUNIT2-MISSION2,ACCESSTOVALVE253013-PLATFORMELEV.762'-10"OPERATORACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToValve253013OperatorStayTimeAtValve253013TotalsDoseFromAirborneActivity0.02720.03960.0668DoseFromContained Sources0.1420.5380.68DoseFromAirborneActivity2.72-43.96-46.68-4DoseFromContained Sources1.42-35.38-36.80-3DoseFromAirborneActivity0.7461.0791.825DoseFromContained Sources1.5696.087.649TotalIngress/Egress TotalOperatorStayTime0.1690.5781.69-35.78-32.3157.159TOTALACCESSDOSE0.757.50-39.47NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page15 ATTACHMENT 2toPLA-4069.

TABLE3.4SUMMARYOFCALCULATED OPERATORACCESSDOSESTOCHECK.DEMNERALIZER PANELOC207REACTORBUILDINGUNIT1-ACCESSTOPANELOC207-ELEV.779'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToControlPanelOC207OperatorStayTimeAtControlPanelOC207TotalsDoseFromAirborneActivity0.02430.05640.0807DoseFromContained Sources0.02880.0288DoseFromAirborneActivity2.43-45.64-48.07-4DoseFromContained Sources2.88-42.88-4DoseFromAirborneActivity0.6681.542.208DoseFromContained Sources0.2920.292TotalIngress/Egress TotalOperatorStayTime0.05310.05645.31-45.64-40.9601.54TOTALACCESSDOSE0.111.10-32.5NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page16 ATTACHMENT 2toPLA-4069.

TABLE3.5SUMMARYOFCALCULATED OPERATORACCESSTOPROVIDEMAKE-UPWATERTOTHESPENTFUELPOOL-'REACTORBUILDINGUNIT1-ACCESSTOROOMI-514ANDPANEL1C206-ELEV.749'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE(1)100%FUELMELTDOSELOCATION/

SOURCEIngress/Egress ToRoomI-514DoseToCheckWaterLevelAtPanel1C206DoseInsideRoomI-514TotalsDoseFromAirborneActivity0.02410.006810.1010.132DoseFromContained Sources0.03260.05671.24-30.0905DoseFromAirborneActivity2.41-46.81-51.01-31.32-3DoseFromContained Sources3.26-45.67-41.24-59.05-4DoseFromAirborneActivity0.6620.1862.7493.597DoseFromContained Sources0.3340.6320.01180.978TotalIngress/Egress TotalOperatorStayTime0.05670.1665.67-41.66-30.9963.579TOTALACCESSDOSE0.2232.23-34.58NOTES:(1)Post-LOCA radiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page17

~~44.~'

ATTACKMfNT 3toPLA-4069ATTACHMENT 3RESPONSETOQUESTION3OFNRC11/23/93RAIPage18

~~~

ATTACHMENT 3toPLA-4069SQUESIQNPiovideoperatordoseestimates forthoseoperatoractionsneededtomaintainalternative spentfuelpoolcoolingfunctions underDBAaccidentconditions (i.e.useofaccidentandnon-accident unitspentfuelpoolcoolingsystemtocooltheaccidentunitfuelpool,etc.)assumingtheaccidentunitnormalspentfuelpoolcoolingsystemhasfailedasaresultofaLOCA.Includethesamelevelofdetailasinyourresponsetoquestion1~RESPONSE1Thefollowing providesacompleteresponsetoquestion3oftheNovember23,1993NRCRAIconcerning radiological evaluations fortheLossofSFPCoolingissue.Thisresponseisbrokenintotwoparts.Section1.0providesa'discusses theavailability ofalternative SFPcoolingunderDBA(Reg.Guide1.3)LOCAconditions.

Section2.0providesasummarytableofthedoses(bothairborneandcontained) forRHRSFPcoolinginthenon-accident unit.ThistableshowsdosesforaDBALOCAwith1%claddamage,100%claddamage,and100%fuelmelt(i.e.,Reg.Guide1.3sourceterm).1.0Availabili ofAlternative SentFuelPoolCoolinAsdiscussed inPP&L'sMay24andAugust16,1993submittals, RHRSFPCoolingintheaccidentunitandtheRefueling floorareinaccessible foraDBALOCAwithanassumedReg.Guide1.3sourceterm.PP&Lhasnotperformed acalculation foraReg.Guide1.3sourcetermforRHRSFPcoolingmode,however,thedoseratesfor100%claddamageareontheorderof50to440Rem/hour.

Basedontheseresults,thedoseratesforafuelmelt(Reg.Guide1.3)wouldprohibitoperatoraccess.UnderDBALOCAconditions (i.e.1%claddamage)operatoraccesswouldbepossiblesincethedoserateswouldbeontheorderof0.5to4.4Rem/hour.

Therefore, useoftheaccidentunit'sRHRsystemforalternative SFPcoolingisnotanoptionifaReg.Guide1.3sourcetermisassumed,butispossiblefortheconditions expectedinaDBALOCA.AsreportedinPP&L'sMay24,1993submittal, thedoserateontheRefueling floorat24hoursafteraReg.Guide1.3DBALOCAis79.8Rem/hour.

Thedosesforthe100%and1%claddamageconditions werereportedtobe3.8and0.038Rem/hour, respectively.

Sincethetimetopullthecaskpitgatesisontheorderofashift,itisnotpossibletoaccomplish thisactivityandincuranacceptable dosetotheoperatorforunderRegGuide1.3conditions withairborneradiation.

Therefore, useofthenon-accident unit'ssystems(normalSFPcoolingandRHR)tocooltheaccidentunit'sSFPisnotanoptionifthecaskstoragepitgatesareinstalled andaReg.Guide1.3sourcetermispresent.Theseactionscouldbeperformed fortheDBALOCAforthe100%and1%claddamageconditions.

Thecalculation usedtodetermine theabovedoseratesisthesamecalculation described intheresponsetoquestion1.Page19 ATTACHMENT 3toPLA<0692.0Summaof0eratorDosesfortheNon-Accident Unit'sRHRSFPCoolinThefollowing tablesummarizes thedosethatanoperatorwouldexperience establishing RHRSFPcoolingtothenon-accident unit.Whilethisisnotspecifically requested intheRAI,PP&Lisproviding thisinformation toestablish theaccessibility ofthenon-accident uniteveniftheventilation isnotisolatedfromtheaccidentunit.Non-isolation ofnon-accident unitisassumedforthiscaseinordertomaximizethedoseinthenon-accident unit.AsnotedinPP&L'sAugust16,1993submittal, thenon-accident unitcanbeisolatedfromthereactorbuildingHVACrecirculation plenum,therebypreventing thespreadofradiation tothenon-accident unit.Thedosesarebasedonthesamecalculation usedtoobtainthedosesfortheanswertoquestion2.ThetimetostroketheRHRvalvesfromfullclosedtofullopenis2minutespervalveandaseparateoperatorwouldbesenttomanipulate eachvalve.Page20 ATTACHMENT 3toPLA-4069TABLE2.1SUMMARYOFCALCULATED OPERATORACCESSDOSESFORRHRFUELPOOLCOOLINGASSISTFROMNON-ACCIDENT UNIT-,REACTORBUILDINGUNIT1-ACCESSTOVALVES151060AND151070PLATFORMELEV.705'PERATOR ACCESSDOSESAT24HOURSPOST-LOCA (R)100%CLADDAMAGE1%CLADDAMAGE100%FUELMELTDOSELOCATION/

SOURCEDoseFromAirborneActivityDoseFromContained SourcesDoseFromAirborneActivityDoseFromContained SourcesDoseFromAirborneActivityDoseFromContained SourcesIngress/Egress ToValves151060&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/Egress TotalOperatorStayTime0.03120.02975.43-36.91-30.7190.641TOTALACCESSDOSE0.06090.01231.36NOTES:(1)Post-LOCA airborneradiation dosesforthe1%claddamagecaseareobtainedbymultiplying the100%claddamagedosesbyafactorof0.01.Page21 il 01~4-1984 14(G~rP.O2ENCLOSURE 1Pennsylvania PowerRLightCompanyVeONOrthNinthStreeihllentOWn, PAtbtct.ttre oStb/7744151 Robert0.Syrem2$IM74-7502 DirectorofNuclearReactorRegulation Attention:

Mr.C,L.Miller,ProjectDirectorProjectDirectorate 1-2DivisionofReactorProjectsU.S.NuclearRegulatory Commission Washington, D.C.20555CrSUSQUEHhNNh STEAMBLBCTRICSThTIONREQUESTFORADDITIONAL INPORMATION ONLO55OtStENTWELtOOLCOOLINQEVENTSQodcatNo@504tlandSMSIDearMr.Miller.AttachedisPP&?.'areayonaatayourNovember23.1993RequestforAdditional Infortnation conccttting personnel accesstiwsthnstisulting floepostulated lossofspentfuelpoolcoolingevents.PlasscontactMr.JamesM.Kennyat(215)774-7914shouMyourrequiteadditional infomtation.

Vctytrulyyours,I9<pllsppp6 Attachment cc:NRCDocumentControlDesk(oriiinal)

NRCRegionlMr.G,S,Barber,NRCSr.ResidentInspector

-SSSSMr,R.J.Clek,NRCSr,ProjectManager-.Rockvtlle AlThCHMENT 1topLA~ATTACHMENT 1RESPONSETOQUESTION1OFNRC11/23/93RAIPage1 AlTACHMENT 1toPLA~Provideadetaileddescription ofthemodelingtechniques usedtogeneratethe4,22RemcitedintheAugus!16,1993submittal ssthedosereceiveddWngtbaaerationofthespentSuelpoolemergency servicewatersupplyvalves.Describeindetailthetime-motion analysisperformed todetermine exposuretimeeeoclatedwithrequiredoperatoractions.1ncludctheparameters andassumptions usedtoSeneratcthecontained andairbornesourcetermsandcalculate therespective dosecomponents associated witheachsegmentofthethne-motion analysis.

Thefollowing providesacompleteresponsetoquestionIoftheNovember23,1993NRCRAIconcsrains radiological evaluations fortheLossofSFPCoolingissue.Asdiscussed inPP&L'sMay24andAugust16,1993submittals, restoration ofthenormalSFPcoolingsystempriortoboQingisexpccld.Consequently, PALwouldnotexpectittobcaccessary tousaE8Wformake-upsincethenoanalsystetnscouldbeusedormake-upfhmthenon-accident unitcouldbeprovided, Thisresponseisseparated intotwoparts.Section1.0providesadescription ofthemodelingtechniques andassumptiona uasdforevaluating operatoraccesstothcESWmake-upvalves,Alsoincludedinthissection,isadiscussion ofhowtheresultstimemotionstudywerefactoredintotheanalysis.

Section2,0providessununarytablesofthedoses(bothairbotnaandcontained) foreachofthcsegmentsassumedlnthecalculatioL ThesetablesshowdosesforaDBALOCAwith19ocladdamage,1N%claddaautgc,and10%tMtnelt{i,e.,Reg.Guide1.3sourcetarn).1.011QzmimTheTACT5computercodeisusedtoevaluatepost.LOCAradiation sourcesinsidethereactorbuildingusingtheCESARChsytcr15.6.5DBA-LOCAactivityQowpathmodelwithrealistic estimates ofcontainment l<<akagerateaAirborneactivityconcentrations inthereactorbuilding!bNtf~!U!!Ip!Ihd!!!Nlhd%Id!failure(NURE&14N) andhealmolt(Regulatory Guide1.3)sourceterms,Usingthesepost-LOCA sourceterms,radiation doseratesinsidethereactorbuildinghornairborneaotivityand&unsuppression poolwatercontained sourcesaeevaluated usingtheMICROSHIELD computercodaOperatoraccessrequirements insidethemactbrbuildingwaredetermined forestablishing ESVmahruptothespentfbe1poolunderpost-LOCA conditions.

OperatoraccusroutesandmisaomwercidentKedanddlvidafintos<<quential segmentsforth<<purpose ofevaluating operatoraccessPage2 ATTACHMENT 1toPEA~9doses.Operatoraccessdosesarccomputedbymultiplying ihcradiation doseratesfromboihairborneandcontained sourcesinagivenmissionsegmentbythetimespentbytheoperatorinthatmissionscgmcnt,Thesumoftheradiation dosesforallsegmentsofthemissionprovidesthetotalmissiondose.1,2Thisanalysisevaluates personnel accessdosesinsidethereactorbuildingfnrthefollowing postulated LOCAinitiated coredamagecases:1%claddamage,100%claddamage,and100%fueliuclt.Thecladdamagecasesareevaluated usingassumptions consistent withtheaccidentsourcetermsdescribed inVUREG-1465,Thefuelmeltcaseiscnnservatively evaluated usingaccidentsourcetermsconsistent withUSNRCRegulatory Guide1.3andthePSARChapter15.6.5DBA-LOCAlicensing basisevaluation.

Forallcases,realistic cstimatos ofthccontainmcnt Icekegorateareused.FortheactivityRnwpathmadelusedinthisanalysis, theactivityconcentrations insidethenodalvolumesarecalculated bydividing'the activityinthenodeatthetimeofinterestbythenodal~volumeandtherefore aredirectlyproportional totheactivitysourcetermrclcascd&omthefuelintothccontainment andsuppression pool,Forthepostulated LOCA'sthatassumecladdamage,theamountofactivityreleasedisdirectlyproportional totheamountofcladdamage,Therefore, acompletesourcetermanddoseanalysisisperfozmcd forthclOONcladdamagecaseandsourcetcrznsanddoseresultsforthcI/ocladdamagecaseazcobtainedbymultiplying the100%claddamageresultsby0,01,hKGKG-1465 wasusedtosupplyreleasedataforthecladdamagecases.SincenospeciQcnumerical guidanceisprovidedinNURE6-1465, theamountofcladactivityreleased&omthecorewhichbecomesairbornemsidccontainment orrenudnsinthcsupprcoion poolwaterisbasedontakingcreditfor55atonproductscrubMngandretention inaccordance withStandardReviewPlhn6,5,5.Inaddition, forthecladdamagecases,anaerosolremovalrateof0.73hz"'orparticulate iodineandcesiumisassumedbasedoninfozznatioa providedinNUREG-1465, TableS,6fortheLaSalleNuclearPowerPlantwhichisalsoaBWRMarkIIcontainment design,Nocreditforaerosolremovalwastakeninthe18%fhclmeltcase.Cozeactivityrelease&actionsforaLOCAwith15%fuelmeltarebasedonthcrequirements ofRegulatory Guide1.3stndNURBO-0737 andazcth¹25%oftheiodincsand100%ofthenoblegasesareinstantaneously airborneinpriniarycontainznent andavailable forleakageand50%ofthecoreinventory ofiodizlsand1%oftheparticulate arereleasedtothesupprcssioe poolwater,Ductothenumberofparticulate isotopesintbccoreandthenumberofdosecalculations

required, theparticul¹e ectivityreleasekhanthecorewasnotexplicitly includedinthcsuppression poolactivitysourcetennforthe100%fbelmeltcase.Instead,boundingdosecalculations usingpost-LOCA Nipyxession poolcontained sourceswithandwithoutparticulate Page3 ATTACHJHENT 0top~~wereusedtodetermine adosemultiplia whichwasusedtoaccountforthedosecontribution from198particulate inthesuppression poolwater,Theiodineandnoblegasactivities releasedfortbe100%Smlmeltcaseareobtained&amtheFSARDBA.LOCAanalysisgiveninPP8Q.calculation FXMDAM<14.

TheSoundinganalys'Iforthedosecoatributloa bornperticulere isbasedonpost-LOCA suppression poolliquidactivitysourcetermsgiveninSusquehanna ProjootBechtclGdcuiation 21M-201.Forailcladdamageandfbclmeltcases,theisotopicchemicalformoftheactivityreleasedfromthecoreisassumedtobeasallows:Iodincs~91%elemental

~4%iorganic~5%particulate Cesiums10N4particulate NobleGases~100%elenental Thisassumption isconsistent withUSNRCRegulatory

&dde1,3forcorefueldamage.Forthecladdaaagecases,NUREQ-1465 indicates thatthechemicalformforiodineenteringcontainmcmt is95%particulat and5%elemental, butwitboutPhcontrolofthesuppression poolwater,arelatively large&actionoftheparticul¹e iodinedissolved insupIxelion yoolwaterwillbeconverted toeleInental iodine.'Qierekre, theabovechemicalformsassumedforthisanaiyisalecohshrvative fortheclatdamagecases.Thoprimaryccntainmcnt designbasisleakagerateis1&day.ForthePSARliccninsbasisDBA-LOCAanalysisthisleakagerateiaassumedforthedurationoftheaccident.

Pocthisevaluation, aonedepmkntrealistsoontainaMstt leakageratabasedoacontainlnettt Integr¹ed LeakageRataTostinggLRT)jesuitsandthecalculasal costtaheeat poet-LOCA IeeaamreapolmiaueedScbeththecladdamageaatIQ%MddtornaTheILRTtestpressurecorresponds tothcmaxhnumcalcul¹cd containment poNLOCApressurewithadesignmarginapplied.Therealistic coatainment leakageratewaacalculated byreducingtheILRTmeasuredleakager¹eproportion¹ely totheILRTtestpressureandthecalculated containment pressureresponseforaLOCA.Foethhanalyda,themostuy-to~1eaksgeratedataiausedsothatthodoseestimate>>

reQectthemostup-~latecontainment leakagecoaditiona Tbetefore, themeasuredIcakagorateat0.606&day 5omtheUnit1ILRTperformed 5/5/92iaaounedforthisanalyiaAleakager¹eofO.N6&dayisalsorepresentative oftypicalmeasuredleakageratesatSSESUnita142.NUItE64737 providesguidanceforevaluating operatoracceNtovitalplantmmforpost-accidentoperations, It!tiesunderItetn(2)SystemaContaininl TbeSourcetha!forpost-LOCA accidentoperationa, "IbdMon&omleakageofsystetns locatedoutsideofcontainment baaednotbeconsidered forthisanalysis".

Tbaehx>>,itisammedScthiaevaluation th¹thelealageofpner-I,OCA o~aha~airborneactivitythoughoorltallanltt yeaetratiooa thatmeveroeelodPage4 nssdzMstbeoeasidecod.

Thercaliltic coeaiarnent leakagerateusedfbrboththecladandfueldamagecases<<rebasedonthemeasuredleakageratesQnaughcontainment penetrations thatarenotwatersealsBasedontheaboveactivityflowpathways,.

theTACTScodeprovidestotalactivityinthereactorbuildingandsuppresaian poolasafunctionoftimepostaccident.

Attherequiredevaluation time(24hourspostaccident),

isotopicactivities weretaken&omtheTACTSoutputeditanddividedbytheappropriate dispersal volumetogiveactivityconcentrations, Radiation dosesinsMethereactorbuildingareevaluated forbothairborneactivityandforsuppression poolwatercontained sources.Operatoraccessdosesorarearadiation doseratciareevaluated ineachoftheareasthatrequireaccesstoprovideBSWmakeup,Rahstiondosesareevaluated usingtheMIGROSKELD coaqtuter codewiththeTACTSgenerated activityconcentration sourceterms,Thedoserate&omairborneactivityinsidethereactorbuildingisactuallysnimmsrsion dose.However,sincetheMICROSHIELD computercodecatuxrtcalcuhrte doserateshternaltothesource,slabgeometryisused.Onehalfofthesourcevolumeismodeledasarectangular volumesourceandadoserateonthesurheeofthisvolumeiscalculated.

Theinuncnion doseisthcalculated bymultiplying thecontactdoserate6amhalfofthesourcevolumebyafactorof2.Allimmersion doseratesarcconservatively calculated atthecenterline oCLho@xnan,Dose~&omthemntainedsuppression poollhiuidpipingsourcessrecalctdated usingcylindrical sourcegeometryvdthreceiveratside.InordertoevaluateoperatoracceNdoses,operatorwalkhgratesandstirclimbingratesarerequired.

Atabacmotionstudywaspcrfoanod tovmifyoperatoraccesetraveltimesinsidethereactorbuildingunderLOCAconditions.

AnopetahewaadressedinpeNctivaclothingandworlaSelfCelledSrlathmgAIyardusandactualtransitthaeatovalveslocatedonelevationa 670'nd749'fthetea~bi48ngweremeaseel.AnisetothesevalvesisrequiredtoprovideBSVmaIkauptoOwspentheipool.Baadupontberesultsofthistimemotionstudy,anoperatorwalkingrateof200ft/minandastairclhnbingrateot50.fthninareconservatively ammedforoperatorlngresa/egresa dosscatcuistiona foraccesstothereactorbuiMingunderLOCAconditionL Alsoaspattofthisstudy,usingsparevalves,thevalveopeungthneforthe2inchvalvesusedforBS%systemtie-insadQowcoldrolwasmealuredtobe10ISdl,bafMldll~~%&~IIflTheincoqecadoa ofthotime.motion studyhtothefhalcalculation resultedinthepreliminary dosetotheoglerimeasing&om422Rem.to4,57Rem.,foracoesatothevalvesonelevations 670.TheM2RccnvaluewasreportedinPPN'aAugust16,1993submittal.

OIeratoraccasdosesareonlyevaluated forUnit1.Theoperatoraccessarealocations forUnits1and2areidccdcaleaceptlbrtheareacontaining thevalvesrcxpirN1ibrtie-inofdeESWsyltemfotmakeup(ValveNoL153500,153501anal253S00,2S3501).Buononthepost-accident radiation levelsgiveninFigures1$.1-3and11.14oftheSSESPSAR,theareacontaining theUnit1valvesforRS%systemtieinhashigherdoseratesthandeUrtit2axea.Page5 ATTACHMENT 1toPUAOHTherefore dosoratescalculated fortheUnit1areaw111beconservative fortheUnit2area.Therefore, allofthecalculated operatoraccessdosesforUnit1areapylicable toUnit2,Operatoraces'oses areevaluated at24hourspost-LOCA.

FarloisofspentSwlpooloooHng,thefbelpoolbeiinstoboBinappoximately 4Ihours,Forthecondition whereaLouofCHMtePower(LOOP)isalsopost~i,povnclsoxpaMtoberestoredwithin24bours,Therefote, 24hourswaschosenssthelatesttimeoperatoractioncouldbetakentorestorecoolingand/ormakeuptothepullandassurethoseactionswouldbecompleted priortoSFPboiHngSomedoseratesareaiiocalculated atothertimespost.LOCAandtoshowthatpoet-LOCA doseratesaredecreasing fortimeperiodsyeaterthan24boaForthe1$%fidelmeltca+,adosefactorisusedtotakeintoaccountthedosecontribution

&ompsrticulate inthesuppression poolliquid(secSection5.1,Assumption 5).Theparticulate dosefactorisdefinedastheratioofthednsaRemsuppceaaion poolliquidsourcescontaining coream~~~~pool liqtnd~~conta Sactivityonly.Alldoses&emcontained sourcesforthe18%fbolmeltcasearecalculated ushgthehQCROSHIELD computercodewithasuppression poolsourcetermthcontainsiodinesonly.TheMICROSHIELD resultsforcontained sourcesSrthe18%healmeltceoarethenmultiyHed bytheparticulate dosefctnrtotakeinto~untthedosecontribution Cromparticulate, Thisdosefactoriscalculated at24hourspost-LOCA andcanonlybeappliedtooperatoraccessdoseskomsuppression poolliquidsourcesevaluated atNssatnethneperiodpost~acctdent

ThBLE2.1SUMMARYOFChLCULATKD OPERATORAUChSSDOSESTOPROVIDEESWMAKEUPToSPECI'UEL POOL-REACTORBUILDINGUNITI-AOCIXS1QVALVES153500AND153501-ELEV.670'PERATOR ACCESSDOSESAT24HOURSPOST-I.OCA (R)IM%CXADDAMAGEHCCLADDAMAGE(1)~'TVd1535004153501DoseFambib'ctivity 722-3DoseFmaDoseFmraCaaimxlAirborneSourceshctivityOA7672?5DnaFamDoseFamCoaamalhiramScxxecsActivity4.76-3O.1911DoseFaxaCoataijsad Sources4.12OleraltaStayTmehtValves153500A153501T0447.45-30.0147heal-3OASO7.45-S1.47-4heal-54.80-3O.402O.N764.16$TealTotalQpaatorQayTmc0.01174.83-31.17-443]802520.494.9D-3QQ~:(I)poat4A)CA tahatioadosesfortbcI<chddamageca+meobtaiaxlbyaadtiplyiag the1095ciadogedosesbyo~yofOOI8 ThBLE22SUMMhRYOFChJAULLEDOPERATORhCCESSBOSFATOOONTROLESWMAKEOPFLAY-REA~RBUILIXNGUNIT2-AOCKSS'IQHEATEXCHANGER PUMPROOM(I-514)-ELEV.749'PERATOR.

hOCESSDOSEShT24HOURSMST-LCICA (R)iN%CLhDDhhhLGE1%CLaDOhMAGE(1)1W%FUELMELT~TogaeleheapIaogtgI-SI4)QietatnrstayTimelnHeatEacbmgerPmyIpaaa(H-Sl4)DoseFaanhirbcxmActivity0.0225DoaeFrcmDateFnrnCocancdAirboraeSoiacxaActivity0.02882.854DoseFxocnCo&aiaedSourcesDoseFromhirbaea:herky0.7040.615DoseFernCoatauxxl Sources02922.65-30.9291S.Q5-42.91-419190.295TotalTotalOy~rQayT~S.7040.9960.61$0.079$7.9@41.61NOH%.(I)post-L0CA radistioa doecgfmtbe1%daddamagecareaxeobtainedbYmultiplVinS the100Yechddaaaagedosesbyafactorof0.01.

01-04-1994 11'0ATTACHMENT 2toPLA~ATTACHMENT 2RESPONSETOQUESTION2OFNRCi1/23/93RAIPage9 GX-04-1984 11I<0Provideoperatordoseestnnates forthoseoperatoractionsneededtomaintainthenormalspentgaelpoolcoolingfbncdonunderDBAaccidentconditions, assumingthenortnalspentfuelpoolcoolingsystetnisoperational foHowinganaccident.

Considerthoseactionsneededtorestorenormalspentfbelfollowing automatic ormanuallpadshedofthespentfuelpoolcoolingsystczn,Includethesamelevelofdetailasinyourresponsetoquestionl.Thefollowing providesacompleteresponsetoquestion2oftheNovember23,1993NRCRAIconcerning radiological evaluations fortheLossofSFPCoolingissue.Forthisevaluation, BSWwasevaluated asthesourceofnuke.upwatersinceitissafetyrelated.Othersourcesofnon-safetyrelatedwatercouldbeusedbutwerenotevaluated inordertomInimizetheamountofcalculations performed.

Asnotedintheresponsetoquestion1,restoration ofnormalSPPcoolingIstbeexpectedcourseofactinforresponding'to aLossofSFPcoolingevent.Thisresponseisbrokenintothreeparts.Section1.0providesadescription ofthemodelingtechniques andassumptions usedforevaluating operateaccesstorestorenormalSpentFuelPool(SPP)CooHng.Section2.0adescription oftheactionsrequiredtorestoreandmaintainnortnalSFPCooling,ItIsImponaatonotethatggtime.motionstudywaspccformod fotthoseao6ans,Thetiaungisbasedonoperatoreqertence sincetheseactionsareperformed onaregulabasis.Section3,0providessudsytablesofthedoses{bothairborneandcontahml) foreachofthesegnNnlactions assumedinthecalculation.

Itshouldbenotedthatseveralseparateactions,atdifferent locations arerequiredtorestoreandmaintaintNnaalSFFcooling,ThesetablesshowdosesforaDBhLOCAwitb1%cled*mage,1554claddamage,and1$%&elmelt(i.e.,Reg.Guidel.3so+entean).1.0Thecalculation perfornod todetermine theoperatordosesforrestoration ofnormalSFPcoolingisbasedoathecalculation perfortned fortheresponsetoquestionl.Theonlydifferences areassociated withthestaytimesandlocationoftheoIerators withregardtodistancefromcontaitted soureeLTbeIeltltsoftbetimemotionstudy~Nrfosmed forquestion1wereusedtodetertnIM op~&tN5&~%hQ0operatoreaq)aicaao wasusedtodetermine thetimetoparianthe'Ictioea Pagelo OL04189411148AlTAcHMENT 2toplJwoaeTheactionsarebasedonthefollowing sequences ofeventsandplantconfiguration'.

DESCRIPTION 0hrs.FuelPoolsareisolated; Betharefilled,'2 poolheatload$,2MBTU/HR(Iustcompleted a40dayoutage);Ulpoolheatload6.27MBTU/HR(lastoutagebegan135daysago);PoolTemp1104F.24Hr!.UZLOCA/LOOF occurs;Lossoffbelpvvlcvotinloccurstobothpools;ReactorbuildingHVACrecirculation systemstarts;SGTSstartLON<<13S(23$

)M1LOSSOFFUELPOOLCOOLINO/COOLANT INVENTORY entered,Ulcontrolled shutdownbeginsduetotheLOOPcondition.

Accusavailable toES%inbothUnitaat&topowerisrestored, Qttylornent OffNonrtalProcedures (LOSSOFFUELPOOLCOOLINQ)tocheckthatthesystemcanbeoperatedandthenimplement OP-135(235)401 toplacefidelpoolcooHngintooperation.

TheON-l3S(23001 g088OFFUELPOOLCOOLING)wouldhavebeenenteredattime0oftheeventandwouldhavebeenimpletnented tocheckthatthesystetncanbeoperated.

Itwouldhavebeendetacmined thatit.couldnotduetoaLOOP.Oncepowerisrestored(assumedtooccurataolaterthan24boursaftereventinititttion) tbeONprovisions wouMguidetheoperatortodetertrtine thatthosystemandtbottocessary supportsystemsateavailable.

Itnplementation oftheON'swillassurethettupportsystetnsareoperabloandSmctionasrequiredtosupportfho1poolcoolingsystetnoperation.

Thoseprocedures requireachecktoassurenosystetnbreachhasoccurred.

Wbeaetttrance istnadotorestorethesystetrt, it<villbeassuntedthatatthistheargrbreachwouldbeobviousandthataospecialeatrancetolookforasysuanbrcachm.Ih~INffNINISI0'hfIfmltisolatedhemthecoolingportionofthosystambyvalva15406/254ki/05406 andNN044II00444.

IhMII~ltIf~I0fhNoftheotherONactionsteyireantrartce tothoreactorbuHdhg(exceptStthanfidelpoolcooling,systemstartupandSetpoollevelmake@whichvrNbediscusecd bc4ow).aasm2md2!aseam~mzacNsozTLMa~zTaeattscsm~caaIRMzaserlcM, cclrtzmMs

~Pagell 819419&4'icOP.CUATTAt:HMEMT 2toP~HOncethosupportsystemsarcassuredfunctioning andavailablo, thofuelpoolcoolingsystemoperation wiHbcrcstorlxL Thedcmincralizer functionwillnotbcrestoreduntilsometimelaterwhenconditions haveimprovedsuchthatitcanbeinspected forpossiblesystembrcach.ItwillbessaunecLbe+evertharIaoperatorwillIotothedeminaraliiee yanelOC2Monelevarioet WFtodetermine thatthohNlpooL61terdcclrecraliser subsystem isappro1RICCLy isolated.

Itisconservgively estimated thattheopenerwillspend10minutesatthepanel.Thoskimuersurgetankandfuelpoollevelwillbemorethanadequatetosupportsystemoperation asthcpoolswellduetoheatup(including evaporative losses)wiHcauseasHghtmxaasoinSFPleveLIthasbeencalculated thititwilletmoattaloe2Dminutestnmsheq)thevolumeofwaterlostduotoevaporation duringthe24hoursinwhichitisassurMdcoolingislost.ThisassumesoncloopofRSVPat3Sgpmmako.uprute.Thusthopumpsmaybostartedoncetbobypassvalve153013isclosed,whichtalesatmost2minutes(assuming tbevalvewasfullopenattime0ofthcevent),Thisvalveisamanuallyoperatedvalveandwouldnotchangepositionattime0oftheevent.Ahe,ittakesapproximately 5minutestoturnontbethreepumpsandadustthcbypassvalve1S3013opentopassthc1800GPMQow,Oncethebypassvalveisproperlya(ustedandthethroepumpsareoperating, motheractionsarerequired, ThusforUnit1inwhichthe193013valveisnexttotheIC206panel,itwilltaleoneoperatoramaxitnumof7minutestoplacethesysteminoperation withthreepumpscxciudini ingressandcycsstimes.Thedoseassoc}atsd withaningresssadegresstimeofe6minutesiacalculated andrcQcctodinthetablesinscctioa3.0.OnUnit2,oneoperatorwillhavetooperatethe2S3013valve(approximate 4minuteoperation) endonewillhavetooperatethepuapcontrolbuttons(2minutooyoration) asthevalveisnotinthevicinityoftbepaneLPage12 h1ThcHA4ENf g~~anyTABLE3.1SIJMMARYOPCAIZUIATED OPERATORh1X.'KSSDOSESTORESTORETHESPENTFUELPOOLCOOINGSYFHiM-RBhCIORKKlLDKNGUNlI'-hCCESS1Q69NROLPANEL)C206AALVE l53013-KLEV.74KOPERATORhGC)%SDOSESAT24HOURSPOST-LOCA (R)1N%CXhDSAMhGE1%CLADSAMhGE()j1&%HRLMELTDOSELOCA'DON/

SOURCETC)C206/YaIve 1530)3QgecgrQayTiaeAtG~mlPand)C206Nahe I530I3DoseFramhxboroeActivity0.040DoseFaxaDoseFredCoecaimxl Airbrea:SocaccsActivity0.0471Z72WOA45DoseFroriCoatained Sources4.71-44.45-3OaocFranAiR~Activity0.6&9I.079'.761 DoseFromG0QltslBcd Sources4.9145.414TagaIOpa~QIyT~0.07437.43-44.$5-3).)89$9930559$39-37.1N2~~f0rQx:1%claddsmagcceeereoblainedbymaltiptyhg rhcl00$daddaaagcdasesbyaD'oruf0.0l.3Pagel3 AlTAClgmr 2sa~~yapThe%32SUMMARYOFAQXXJLAVED OPERATORACCESSDOSESTORESIORETHESPENTFUELPOOLCOGUNGSVSHQ4-REACMRBO1LD&IQUMT2-MISSIGbll,Al3~8TOCONTROLPANEL2CM6-ELEV.749'PERATOR hCCESSDOSEShT24HOURSPOST-LOCh (R)l%CLADSkhfAGK1%CLADDhMAGE(I)lM%FllKLMELTDOSELOCATEÃ/SOURCEToGyraltiead2C206DoseFmahihxmhctbrkgDoseFramCoataiued Sources.0.0411DmeFamhatbo~ActivityDoeeFramContained Souces4.71-44.4$-3DoseFromAirboca:Activity0.6$9I079DoseFnlrrCarrtamxl Snxcea0.504.9I44.92-35410.4854.85-3l.ls95993TOYALACCIESSDOSE5.59-3V.II2NOIES:(1)FMO-LOChrttrhilborr dosesRcthe1%daddamneecaseareobtaimxibyaulgj8yjgg tbe19'laddarxggpdosesbya~afOAI.Page14 ATtACH~Zw~~ThBLB33SMAMllkYOFCALCULATED OPERATORhCCESSDOSESTORESTORETHESPENfFUELPOOLC0OLPg)SYSTEM-REhCMRBUILDINGUMT2-MISSION2,ACCF~TOVALVE253013-PLATFORhf ELEV.762'-10"OPERATORACCESSDOSESAT24HOURSPOST-LOCA (R)1N%CLADQkb%AGR1%CLADDAMlCE(I)1%E%ELMELTDOSELCXMTION/

SOURCEToVahe253013Ope~St¹yTmeAtValve2530)3DogeFamAirbriaeActhityBoaeFnmCoettlirred SasacsO.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)Pbo¹tgAKA agleamdosesfoethe1%c)addamagecan:areobtiicecl bymultiplyag theIONt'ladr)ramagedosclbya~oE0.O).Page15O TABLE3.1SUMMARYOFCALCULATED OPEgATQRA@CESSDOSESTO~~@~M;IONIZER PANEL0C207REhClORBUILDS'TI-AOCESSTOPANELOC207-FLED.779'2'ERhTOR ACCESSDOSEShT24HO%KMST-LOCA(R)QIQ1N%CLADShMAGEl%Cl~ShMACE(I)II0%PIIM.MELTDOSELOCA'HONJ'OURCE ToCaaelPandOC?07DoseFramhiahmmhctiviiyQ.92430.0564SoleFamDoseFmnCoaCaiaed AItboaaeSmaoeeActivitytklMS2.43-405.64-4DoseFax'oaCaincd Soaxces2.N-4DoseFamAirboatAcciviy0.66&DoIeFreya.Coasaiaed Soarces0.2921.0740.292T~~ToIsl01~QayT~0.6531531-4ITALNX~SDOSS0.11I.I0-3,NQ'lpga:(I)~LOChzafwda)dosesRtAe1%cMdaalge~mtobasinaibyIrnsICiplymg daIONAoh'srnll@

~ga~oftkOI.Page160

ATFhCiaE~

g~ABLE3.5StjMMhRYOFCMCULATEDQPBRATORAOCESSTOPROVlljEMA1~-UP ly'AppalTOTESP~FUHPOO1-RFM!TQR.$81LIMNOUNIT1-hCCESSTO1INM1-514hNDPANELIC206-EL'.749'%RA&lR AOCBSSDOSESAT24HOURSNKI'-IANNA gt)IIMCCLADDhhklCR1%CLADQA59LGE(1)IM%FllELMIXTDOSELOCATION/

SOURCE~Tm1-5NDaceFmcahirhxmhcIIivity 06241DaceFromDaceFaxnGoahIined hirbarrs:

SonreelAcuity0.03262A1%DoseFmmDoseFromCoIeaitljd hirborneSoaxccsActbity32640.662DoseFranCtmainedSouaxmDoseToEback.%~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'ACHMENT 3RESPONSE70QUESTION3OFNRC11/23/93RAI

81~1394P~12JATl'ACHMENT 3toNAAOHProvideoperatordoseestimates forthoseoperatoractionsneededtomaintainaltera<<&re spentfidelpoolcooliaghmctionsunderDBhaccidentccnciitiens (i.e.useof<<ccideatautnon-accident unitspentfuelpoolcoolingsystemtocooltheaccidentuaitfoolpool,etc.)assunungthe<<ccideatuaitaorjxllspoatfidelpoolcoolialsystemhefilledas<<resultofaLOCA.IncludeWsamelevelofdetailasinyourresponsetoquestion1.'Oefollowiag providesacompleteresporsetoquestion3oftheNovember23,1993NRCRAIcoacerniag radiological evaluations fortheLossofSFPCoolingissue.Thisresponseisbrokenintotwoparts,Section1.0providesadiscusses theavailsMity ofaltern<<tive SFPcoolingundeDBA(Reg.Guide1.3)LOCAcotgiitioaL Section2.0providesaNaaamytableofthedoses0drb~~)faHRSFPthighd~Tl'lkdosesforaDBALOCAwith1%claddamage,105icladdamage,snd15%fbelmelt(i.e.,Reg.Quide1.3sourceterm).1,0Asdiscussed inPPM.'sMay24andAugust15,1993sabmittals, RHRSFPCoolingiatbeaccidcrrt unitandtheRefbeliag fhorareiaaeessible foraDBALOCAwithanassumedReg,Guide13sourcetenn.PALh<<snotperformed acalculatioa foraRag.QuMe1.3pureetermforRHRSPPcoolingmode,however,thedoseratesfor100%claddamageNeoatheorderof$0to440Rcaulllur.

S<<sadoatbcseresults,tbsjdoseratesforafbo1molt@Log.Guide1,$)wouldprohibitope~raccesLUaderDBALOCAconditions (i.e.1%claddamge)operatoracce<<awouldbepossiblesincethedoserateswouMbeoatheorderof0,5to4.4RNnthour.

Therefoee useoftheaeidearunsRHRsystemfor<<ltern<<tive SFPcaallnglsnotsnoptionifaReg.(halte1.3sousetermisassumed,butispossibleforthecosditioas exyectedinaDBALOCA.AsreportediaPPN,'sMay24,1993subraittal, thedoserateoetheReheUag5oarat24hours<<her~Res,(Idaho1.3MALOCAh%SReathea,VisedeeseAetheIONIC<<aL1%cl<<ddamageexxRCom~appedtoba34aalLNIRemlbaa,rasyeetiveiy.

QaoethethnetepullSe~plCANietlr.the ocdeofashat,ftis~poedbietoawomryiish thh<<ctivity<<ndiacutat'Nt8theoperltocforunderRegOuMe13ootMItiom with<<irwin<<radhNadfuaofthememcMunit'ssystems(tlcmalSFPcooling<<ndRHR)tocoolthe<<ocidartunit'sSPPisnetmopt@aitthecaskstoragepitI<<te<<aremetall<<d<<adakeg.Gute1,3sourceternisimleaL'Hsaa:tioasoomph}bepe5xamdhrtheDSALOCAhctheIDOLasd1%cddaaNIeooa5thaarTbecalcuia8aa usedtodetcemiae theabovedoseratesisthesamecalculstioa described inthere<<yea<<etoyee&ml.Page19

AtThCRMENY 3toI'~H2.0~efo]]owiag tableaummarina thedosethatanopcmtorwouldexperlEnce establishing RHRSFPcoolingtothenoa~cident unit.WhilethisisnotspcciQcaQy requested intheRAI,PPALispcevidinl thisinforamtion toestablish tboeecelsibility ofthenon~dentuaitIteniftheventi&onisggisolatedBomtheaccidentunit.Non-isolation ofaon-accident unitisassumedforthiscaseiaordertotnsxindxe thedoseiathenon~ident unit,AsnotedinPPN.'sAugust1t41993subrnitta4 thenoncident unitumbe)solated&enthereactorbuildingHVACrecircubLtion plenum,therebypreveatial thespreadofradhtiontotheaoa-accident uait,ThedosesarobasedoathesamecalcuMoausedtoobtainthedosesibr,theanswertoquestion'.

Thetitaeto¹roketheRHRvalves6amMlcloaxltofbi'penis2minutespervalveandaseparateopentorwouldbeseattomanipuilte eachvalve.

ATTACHMENT' to~~ThSLE2.1SUMhQiRYOFChLCULATED OPERATORhCXHSSDOSESFokRHRFUELPOOLGOOfINGhS8)STPR~MON-hQQIHKI'NIT

-IEhCfORBUILKMsUNIT1-hGCKSSTOVALVES151060hND)5)070NA%0RMKLBV.705'PMh1QR ACCESSDOSESAT24BOURSMST-DKA(R)HLCXADDhMAGRHMCFllBLMELTDOSELOCA'GON/

SOURCEDoleFranhislxxaeActivhyDoseFaxnCoalmalSoars@DoseFryhirbanahctiviyfl)DoseFexnDoseFamOatma}Air@~84HIKcsActivityBoaeFernCaauaiaed SeesToVahesI51060A151070O.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-LOCA adxrmradikioadoses6xthe)%daddamage~ageobtaig)ed byyzgg~ggygg tbeI~c)~d~~~bof0.01.Page21 FuelPoolCoolingIssueBackround~Issueraisedbytwocontractors

~Contractors contendthatalossofFPC,concurrent withLOCAresultsin:-boilingSFPandfuelmeltoutsidecontainment

-lossofallECCSandfailureofcontainment integrity

~PP&Lmaintains thatadequatecapability existstorespondtoalossofFPCevent FuelPoolCoolingIssueBackground

~LossofnormalFPCsystemdueto:-Seismic-LOOP.-'LOCA~NormalFPCsystemisfirstlineofdefense~Othersystemsavailable toprovide:-makeuptoSFP-coolingtoSFP FuelPoolCoolingIssueLA~Hydrodynamic Loads~FPCnot.designed forhydrodynamic loads~PP&Lassessment concluded normalEPCsystemmayremainfunctional afterLOCA FuelPoolCoolingIssuePPLPosition~SSESLicensing BasisdoesnotconsiderlossofFPCforotherthanSeismicevents~Operators havetimetoreact(50to130hrs)~Safety-grade makeupsourcealwaysavailable

~Safety-grade coolingviaRHRFPCmode~Boilingenvironment canbemitigated e

TYPICALMARKIICONTAINMENT

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VELOCITY, COMPONENT ELEVATION ANDSIZE+LOADSONCOMPONENTS ARENOTTRANSMITTED TOREACTORBUILDING-LOCALAFFECTSONLY LOCASTEAMCONDENSATION LOADS+BASEDONGENERICMAIMIIACOUSTICMETHODOLOGY APPROVEDINNUREG-0808

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~PIPESUPPORTADEQUACY-HANGERSAREMAINLYCOMPONENT TYPESUPPORTS(SPRINGCANS,STRUTS,RIGIDRODS,KTC.)-OTHERSUPPORTSCOMPRISED OFSTRUCTURAL STEELMEMBERS-PIPESUPPORTCATALOGCOMPONENTS TYPICALLY HAVELARGESAFETYFACTORS-PREDICTSMALLPIPKSUPPORTLOADINCREASES DUETOINPUTMAGNITUDE

-REVIEWOFSAFETYRELATEDANALYSESINTHER/BDEMONSTRATES THATHYDRODYNAMIC LOADSARKLESSTHAN25%OFDEADWEIGHT LOADS~SPATIALINTERACTION/ANCHOR MOVEMENTS

-SMALLPIPEDISPLACEMENTS WILLMINIMIZEADVERSEAFFECTSDUETO:DIFFERENTIAL ANCHORMOVEMENTS IMPACTOFADJACENTCOMPONENTS/SYSTEMS SLIPPAGEOFPIPEOFFSUPPORTS