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{{#Wiki_filter: | {{#Wiki_filter: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:== | ==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:== | ==DearMr.Miller:== | ||
AttachedisPP8rL'sresponsetoyourNovember23, | 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. | ||
~~N | 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.~' | ~~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' | ATI'ACHMENT 3RESPONSE70QUESTION3OFNRC11/23/93RAI | ||
81~1394P~12JATl' | 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 useoftheaeidearun''sRHRsystemfor<<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. | ATTACHMENT' to~~ThSLE2.1SUMhQiRYOFChLCULATED OPERATORhCXHSSDOSESFokRHRFUELPOOLGOOfINGhS8)STPR~MON-hQQIHKI'NIT | ||
TYPICALMARKIICONTAINMENT' | -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$TotalI0.03l25.43-36.91-30.7)90.641')OTALhCCEaSDOSE0.06090.0]23NOTES:())Post-LOCA adxrmradikioadoses6xthe)%daddamage~ageobtaig)ed byyzgg~ggygg tbeI~c)~d~~~bof0.01.Page21 FuelPoolCoolingIssueBackround~Issueraisedbytwocontractors | |||
~Contractors contendthatalossofFPC,concurrent withLOCAresultsin:-boilingSFPandfuelmeltoutsidecontainment | |||
-lossofallECCSandfailureofcontainment integrity | |||
~PP&Lmaintains thatadequatecapability existstorespondtoalossofFPCevent FuelPoolCoolingIssueBackground | |||
~LossofnormalFPCsystemdueto:-Seismic-LOOP.-'LOCA~NormalFPCsystemisfirstlineofdefense~Othersystemsavailable toprovide:-makeuptoSFP-coolingtoSFP FuelPoolCoolingIssueLA~Hydrodynamic Loads~FPCnot.designed forhydrodynamic loads~PP&Lassessment concluded normalEPCsystemmayremainfunctional afterLOCA FuelPoolCoolingIssuePPLPosition~SSESLicensing BasisdoesnotconsiderlossofFPCforotherthanSeismicevents~Operators havetimetoreact(50to130hrs)~Safety-grade makeupsourcealwaysavailable | |||
~Safety-grade coolingviaRHRFPCmode~Boilingenvironment canbemitigated e | |||
TYPICALMARKIICONTAINMENT | |||
'CONTAINMENT WALL.QbVENT-~:.e.'Oai<'.i~'V.PRDBSliALWETWELL~C0WELLRhR..JETVENTo'p.'A.iioP0.."~~jt6>>i:rAgo~%p,+~+~~~n~~~Jt~.%':)~o)~t~~4I~SUPPORTCOLUMNSA!0$"'<.i4"4si""4' SUSQIJKHANNA CONTAINMKNT DESIGN+GEMARKIICONTAINMENT DESIGN-DRYWELLOVERSUPPRESSION CHAMBER+REACTORCOOLANTPRESSUREBOUNDARYCOMPONENTS LOCATEDINDRYWELL+87DOWNCOMERS TOROUTENON-CONDENSABLES ANDSTEAMFROMTHEDRYWELLTOSUPPRESSION POOLDURINGALOCA+INTERNALDESIGNPRESSURE-53PSIG+SUPPRESSION CHAMBERDESIGNTEMPERATURE | |||
-220'F+DRYWELLDESIGNTEMPERATURE | |||
-340'F LOCAHYDRODYNAMIC LOADS+DESIGNBASISLOCA:POSTULATED DOUBLEENDEDBREAKOFTHERECIRCULATION SUCTIONPIPEINTHEDRYWELL+PRODUCESHYDRODYNAMIC LOADSDUETOFLOWOFNON-CONDENSABLES ANDSTEAMFROMTHEDRYWELLTOSUPPRESSION POOLVIATHEDOWNCOMERS | |||
+POOLSWELL+STEAMCONDENSATION LOADS-CONDENSATION OSCILLATION (CO)ANDCHUGGING+DISCUSSION THATFOLLOWSARETHEDESIGNBASISLOCAHYDRODYNAMIC LOADSPREVIOUSLY APPROVEDBYTHENRC-NONEWINFORMATION POOLSWELLLOADS+NON-CONDENSABLE ATTHEDOWNCOMER EXITSGROWANDCOALESCEINTOPANCAKEBUBBLEANDCAUSERAPIDRISEINPOOL+MAXIMUMPOOLSWELLHEIGHTIS18.2'BOVE INITIALPOOLSURFACE+POOLSWELLZONEEXTENDSFROMDOWNCOMER EXITELEVATION TOMAXIMUMPOOLSWELLHEIGHT+POOLSWELLCAUSES--IMPACT,DRAGANDFALLBACKLOADSONCOMPONENTS (I.E.,PIPING,DG,DOWNCOMER BRACING,ETC.)LOCATEDINPOOLSWELLZONE-AIRBUBBLELOADSONSUPPRESSION POOLSTRUCTURE OLSWELLDOESNOTPRODUCELOADSONCOMPONENTS LOCATEDOUTSIDETHESTRUCTURES ORCPOOLSWELLXONE 0 | |||
POOLSWELLLOADNIETHODOLOGY WATlh1LL!0ltBASEDONGENERICMARKIILOADMETHODOLOGY | |||
~METHODOLOGY APPROVEDBYNUREG-0487 ANDSUPPLEMENTS) | |||
ANDNUREG-0808 | |||
~POOISWELLANALYTICAL MODELPSAIVITOCALCULATE | |||
: PRESSURE, POOLVEIOCITY,ACCELERATION ANDHEIGTHI POOLSWELLAlRBUBBLELOADELdHIIKtIFR0%SKINTr~LOADSTATICALLY APPLIEDTOCONTAINMENT BOUNDARYINACCORDANCE WITHNUREG-0487 AIRBUBBLELOADDOESNOTAFFECTCOMPONENTS LOCATEDINREACTORBUILDING POOLSWELLLOADSONCOMPONENTS | |||
+AFFECTSCOMPONENTS LOCATEDINWETWELLBETWEENDOWNCOMER EXITELEVATION ANDMAXIMUMSWELLHEIGHT(PIPING, | |||
: SUPPORTS, BRACING,ETC.)+LOADSONVERTICALLY ORIENTEDCOMPONENTS ARENEGLIGIBLE ANDARENOTCONSIDERED FORDESIGN+VELOCITYANDACCELERATION VS.TIMEANDELEVATION CALCULATED WITHPSAM+IMPACT,DRAGANDFALLBACKLOADSBASEDONACCELERATION, | |||
: VELOCITY, COMPONENT ELEVATION ANDSIZE+LOADSONCOMPONENTS ARENOTTRANSMITTED TOREACTORBUILDING-LOCALAFFECTSONLY LOCASTEAMCONDENSATION LOADS+BASEDONGENERICMAIMIIACOUSTICMETHODOLOGY APPROVEDINNUREG-0808 | |||
+ACOUSTICMODELOFSSESKITHCHUGANDCO'SOURCES'LACED ATTHEDOWNCOMER EXITS+CHUGANDCOSOURCESDERIVEDFROMPLANT-UNIQUE GKM-IIMLOCATESTPROGRAJVl CONDUCTED BYKRAFTWERK UNION(KWU)+GKM-IIMTESTSCOVEREDSPECTRUMOFLOCABREAKSIZES LOCASTEAMCONDENSATION LOAD+KWUSELECTED4CHUGSANDICOPRESSURETRACEFROMTHEGKM-IIMDATAFORSOURCING+DESIGNCHUGANDCO'SOURCES'PPLIED TOACOUSTICMODELOFSSESSUPPRESSION POOL+PRESSURELOADSCALCULATED ATPOOLBOUNDARYFOREACHSOURCE+PRESSURETIMEHISTORIES INPUTTEDTOSTRUCTURAL MODELOFCONTAINMENT | |||
+DBALOCADOCADOESNOTPRODUCETHELARGESTCI-IUGGING ANDCOLOAD+LOCALOADISTHEENVELOPOFALLCHUGANDCOPRESSURETIMEHISTORIES FORALLBREAKSIZES l' | |||
JAERlCOIlPARlSON EBSSfdddl.4ANU344ATl,dA44JAKATCUUASATldll04ru4I',ZI416l.FAEGUENCY | |||
<hz)8I~SSESLOCASTEAMCONDENSATION METHODOLOGY COMPAREDW)THJAERITESTDATA~JAERITESTFACILITYWASA20'LICEOFAMARK)ICONTAINMENT | |||
-7DOWNCOMERS SIGNIFICANT CONSERVATISM INLOCALOAD | |||
PRESENTATION OUTLINE~DEVELOPMENT OFLOCARESPONSESPECTRAINTHEREACTORBlJILDING | |||
-LOCAANALYSISOFTHECONTAINMENT | |||
-LOADTRANSFER-LOCAANALYSISOFTHEREACTORBUILDING~COMPARISON OFLOCAANDSSERESPONSESPECTRAINTHEREACTORBUILDING | |||
LOCAANALYSISOFCONTAINMENT~ | LOCAANALYSISOFCONTAINMENT | ||
~PRESSURETIMEHISTORIES FROMTHEACOUSTICMODELARECONVERTED TONODALFORCETIMEHISTORIES | |||
~FORCETIMEHISTORIES AREAPPLIEDTOA3DFINITEELEMENTMODEL-MODELDEVELOPED FORHYDRODYNAMIC LOADANALYSIS-MODELCONSIDERS SOILSTRUCTURE INTERACTION | |||
~DYNAMICANALYSISPERFORMED USINGANSYSPROGRAM~ANALYSISRESULTS(ACCELERATION TIMEHISTORIES) | |||
USEDTODEVELOPINPUTSFORTHEREACTORBUILDINGANALYSIS I' | |||
~y)~I~CIS~ | ~y)~I~CIS~ | ||
RPVNOTE:X~AXISISINPLANTEWANDY-AX! | RPVNOTE:X~AXISISINPLANTEWANDY-AX!SINPLANTNSDIRECTION RPVSHIElDCONTAINMENT RPVPEDESTALRev.9,07/85SINQUEHANNA STEAMELECTRICNTJUNITS1AND2DESIGNASSESSMENT REPORT3-DCONTAZNMENT FZNZTEELEMENTMODEL(ANSYSMODEL) | ||
LOADTRANSFER~ | LOADTRANSFER~NODIRECTCOUPLINGOFTHECONTAINMENT ANDREACTORBUILDINGEXCEPTATBASEMAT~HORIZONTAL MOTIONSAREFULLYTRANSFERRED; ACCELERATION TIMEHISTORIES AROUNDTHEPERIMETER AREAVERAGED-oVERTICALMOTIONSARETRANSFERRED TOTHEREACTORBUILDINGTHROUGHTHEROCK.LOADATTENUATION (BASEDONDISTANCEAMAYFROMTHESOURCE)ISCONSIDERED LOCAANALYSISOFREACTORBUILDING~"AVERAGED" TIMEHISTORIES AREAPPLIEDTOTHEBASEOFSTICKMODELS~3STICKMODELSAREUSED-ONEFOREACHDIRECTION | ||
)IJ C-1058REVISION0~O'ILSOHCh~SIRIWFN0NOSESggaoLL0ogO1ONSuSSa~woMAIS0LAHOf00Z~141Q~w. | -SAMEMODELSASTHOSEUSEDINTHESEISMICANALYSIS~TIMEHISTORYANALYSESPERFORMED USINGSECHTELIN-HOUSEPROGRAMS~RESULTING NODEPOINTTIMEHISTORIES ARECONVERTED TONODEPOINTRESPONSESPECTRA~LOCAFLOORENVELOPING RESPONSESPECTRAAREDEVELOPED | ||
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~ | ~HYDRODYNAMIC LOADINPUT-MAXIMUMHORIZONTAL ACCELERATION | ||
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+20Hz.PIPESTRESSAFFECTS-NON-SEISMIC PIPINGFREQUENCY TYPICALLY | |||
+11Hz.-DISPLACEMENTS OFPIPEANTICIPATED TOBESMALLDUETOHIGHFREQUENCY INPUT-PREDICTACCEPTABLE PIPESTRESSESDUETOLOMDISPLACEMENTS | |||
-REVIEMOFSAFETYRELATEDANALYSISDEMONSTRATES LOMMAGNITUDE PIPEDISPLACEMENTS/STRESSES DUETOHYDRODYNAMIC LOADS | |||
~PIPESUPPORTADEQUACY- | ~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}} |
Revision as of 04:49, 29 June 2018
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$TotalI0.03l25.43-36.91-30.7)90.641')OTALhCCEaSDOSE0.06090.0]23NOTES:())Post-LOCA adxrmradikioadoses6xthe)%daddamage~ageobtaig)ed byyzgg~ggygg tbeI~c)~d~~~bof0.01.Page21 FuelPoolCoolingIssueBackround~Issueraisedbytwocontractors
~Contractors contendthatalossofFPC,concurrent withLOCAresultsin:-boilingSFPandfuelmeltoutsidecontainment
-lossofallECCSandfailureofcontainment integrity
~PP&Lmaintains thatadequatecapability existstorespondtoalossofFPCevent FuelPoolCoolingIssueBackground
~LossofnormalFPCsystemdueto:-Seismic-LOOP.-'LOCA~NormalFPCsystemisfirstlineofdefense~Othersystemsavailable toprovide:-makeuptoSFP-coolingtoSFP FuelPoolCoolingIssueLA~Hydrodynamic Loads~FPCnot.designed forhydrodynamic loads~PP&Lassessment concluded normalEPCsystemmayremainfunctional afterLOCA FuelPoolCoolingIssuePPLPosition~SSESLicensing BasisdoesnotconsiderlossofFPCforotherthanSeismicevents~Operators havetimetoreact(50to130hrs)~Safety-grade makeupsourcealwaysavailable
~Safety-grade coolingviaRHRFPCmode~Boilingenvironment canbemitigated e
TYPICALMARKIICONTAINMENT
'CONTAINMENT WALL.QbVENT-~:.e.'Oai<'.i~'V.PRDBSliALWETWELL~C0WELLRhR..JETVENTo'p.'A.iioP0.."~~jt6>>i:rAgo~%p,+~+~~~n~~~Jt~.%':)~o)~t~~4I~SUPPORTCOLUMNSA!0$"'<.i4"4si""4' SUSQIJKHANNA CONTAINMKNT DESIGN+GEMARKIICONTAINMENT DESIGN-DRYWELLOVERSUPPRESSION CHAMBER+REACTORCOOLANTPRESSUREBOUNDARYCOMPONENTS LOCATEDINDRYWELL+87DOWNCOMERS TOROUTENON-CONDENSABLES ANDSTEAMFROMTHEDRYWELLTOSUPPRESSION POOLDURINGALOCA+INTERNALDESIGNPRESSURE-53PSIG+SUPPRESSION CHAMBERDESIGNTEMPERATURE
-220'F+DRYWELLDESIGNTEMPERATURE
-340'F LOCAHYDRODYNAMIC LOADS+DESIGNBASISLOCA:POSTULATED DOUBLEENDEDBREAKOFTHERECIRCULATION SUCTIONPIPEINTHEDRYWELL+PRODUCESHYDRODYNAMIC LOADSDUETOFLOWOFNON-CONDENSABLES ANDSTEAMFROMTHEDRYWELLTOSUPPRESSION POOLVIATHEDOWNCOMERS
+POOLSWELL+STEAMCONDENSATION LOADS-CONDENSATION OSCILLATION (CO)ANDCHUGGING+DISCUSSION THATFOLLOWSARETHEDESIGNBASISLOCAHYDRODYNAMIC LOADSPREVIOUSLY APPROVEDBYTHENRC-NONEWINFORMATION POOLSWELLLOADS+NON-CONDENSABLE ATTHEDOWNCOMER EXITSGROWANDCOALESCEINTOPANCAKEBUBBLEANDCAUSERAPIDRISEINPOOL+MAXIMUMPOOLSWELLHEIGHTIS18.2'BOVE INITIALPOOLSURFACE+POOLSWELLZONEEXTENDSFROMDOWNCOMER EXITELEVATION TOMAXIMUMPOOLSWELLHEIGHT+POOLSWELLCAUSES--IMPACT,DRAGANDFALLBACKLOADSONCOMPONENTS (I.E.,PIPING,DG,DOWNCOMER BRACING,ETC.)LOCATEDINPOOLSWELLZONE-AIRBUBBLELOADSONSUPPRESSION POOLSTRUCTURE OLSWELLDOESNOTPRODUCELOADSONCOMPONENTS LOCATEDOUTSIDETHESTRUCTURES ORCPOOLSWELLXONE 0
POOLSWELLLOADNIETHODOLOGY WATlh1LL!0ltBASEDONGENERICMARKIILOADMETHODOLOGY
~METHODOLOGY APPROVEDBYNUREG-0487 ANDSUPPLEMENTS)
ANDNUREG-0808
~POOISWELLANALYTICAL MODELPSAIVITOCALCULATE
- PRESSURE, POOLVEIOCITY,ACCELERATION ANDHEIGTHI POOLSWELLAlRBUBBLELOADELdHIIKtIFR0%SKINTr~LOADSTATICALLY APPLIEDTOCONTAINMENT BOUNDARYINACCORDANCE WITHNUREG-0487 AIRBUBBLELOADDOESNOTAFFECTCOMPONENTS LOCATEDINREACTORBUILDING POOLSWELLLOADSONCOMPONENTS
+AFFECTSCOMPONENTS LOCATEDINWETWELLBETWEENDOWNCOMER EXITELEVATION ANDMAXIMUMSWELLHEIGHT(PIPING,
- SUPPORTS, BRACING,ETC.)+LOADSONVERTICALLY ORIENTEDCOMPONENTS ARENEGLIGIBLE ANDARENOTCONSIDERED FORDESIGN+VELOCITYANDACCELERATION VS.TIMEANDELEVATION CALCULATED WITHPSAM+IMPACT,DRAGANDFALLBACKLOADSBASEDONACCELERATION,
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