ML17250A779

Tech Specs Table of Contents,Page ii;1.0,definitions & 3.0 for Limiting Conditions of Operation

ML17250A779
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Site:	Ginna
Issue date:	11/12/1980
From:	ROCHESTER GAS & ELECTRIC CORP.
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AttachmentARemoveTechnicalSpecificationpagesii,1-1,3.1-1through3143824314324ll1~4112InsertrevisedTechnicalSpecificationpagesii,l-l3.1-1through3.1-4,3.1-4a,3.1-4b,3.1-4c,3.8-2,3.8-2a,3.8-4,3.11-2through3.11-4,4.3-1through4.3-3,4.11-1through4.11-3.

~1C4v TABLEOFCONTENTS(cont.)4.0SURVEILLANCEREQUIREMENTSPacae4.14.24.34.54.64.74.84.94.104.114.124.134.144.154.16OperationalSafetyReviewInserviceInspectionReactorCoolantSystemContainmentTestsSafetyInjection,Containment,SprayandIodineRemovalSystemsTestsEmergencyPowerSystemPeriodicTestsMainSteamStopValvesAuxiliaryFeedwaterSystemReactivityAnomaliesEnvironmentalRadiationSurveyRefuelingEffluentSurveillanceRadioactiveMaterialSourceLeakageTestShockSuppressors(Snubbers)FireSuppressionSystemTestOverpressureProtectionSystem4.1-14.2-14.3-14.4-14.5-14.6-14.7-14.8-14.9-14.10-14.11-14.12-14.13-14.14-14.15-14.16-15.0DESIGNFEATURES5.1Site5.2ContainmentDesignFeatures5.3ReactorDesignFeatures5.4FuelStorage5.1-15.2-15.3-15.4-1*~Qll<Proposed TECHNICALSPECIFICATIONSDEFINITIONSThefollowingtermsaredefinedforuniforminterpreta-tionofthespecifcations.ThermalPowerTheratethat,thethermalenergygeneratedbythefuelisaccumulatedbythecoolantasitpassesthroughthereactorvessel.Reactor0eratinModesCoolant.ModeRefuelingColdShutdownReactivityakk'10TemperatureoFT<140Tavg<200HotShutdownTavg-Operating~f0Tavg~580Anyoperationwithinthecontainmentinvolvingmovement,offueland/orcontrolrodswhenthevesselheadisun-bolted.~OerableCapableofperformingallintendedfunctionsintheintendedmanner.1-1PROPOSED 3.0LIMITINGCONDITIONSFOROPERATION3.1ReactorCoolantSstemb'1'ppliestotheoperatingstatusoftheReactorCoolantSystemwhenfuelisinthereactor.~b'ospecifythoseconditionsoftheReactorCoolantSystemwhichmustbemet,toassuresafereactoroperation.3.1.10erationalComonents3.1.1.1ReactorCoolantLoosa~b.Whenthereactorpowerisabove130MWT(8.5%),bothreactorcoolantloopsandtheirassociatedsteamgeneratorsandreactorcoolantpumpsshallbeinoperation.Iftheconditionsof3.1.1.l.aarenotmet,thenimmediatepowerreductionshallbeinitiatedunderadministrativecontrol.Iftheshutdownmargin/meetstheonelooprequirementsofFigure3.10-2,thenthepowershallbereducedtolessthan130MWT.IftheoneloopshutdownmarginofFigure3.10-2isnotmet,theplantshallbetakentothehotshutdownconditionandtheoneloopshutdownmarginshallbemet.~'b<tJ3.1-1PROPOSED c.Exceptforspecialtests,whentheaveragecoolanttemperatureisabove350'F,orwhenthereactorisathotshutdownoriscriticalwiththereactorpowerlessthanorequalto130NWT(8.5%),atleastonereactorcoolantloopanditsassociatedsteamgeneratorandreactorcoolantpumpshallbeinopera-tion.Theotherloopanditsassociatedsteam'eneratormustbeoperablesothat.heatcould-beremovedvianaturalcirculation.However,bothreactorcoolantpumpsmaybede-energizedforupto1hourprovided(1)nooperationsarepermittedthatwouldcausedilutionofthereactorcoolantsystemboronconcentration,and(2)coreoutlettemperatureismaintainedatleast10'Fbelow.saturationtemperature.d.Iftheconditionsof3.1.1.l.carenotmet,suspendalloperationsinvolvingareductioninboronconcentrationoftheReactorCoolant:Systemandimmediatelyinitiate'orrectiveactiontoreturntherequiredcoolantlooptooperation.e.Whenthereactorisatcoldshutdownorwhentheaveragecoolanttemperatureisbetween200'Fand350'F,atleasttwoofthefollowingcoolantloopsshallbeoperable:(i)reactorcoolantloopAanditsassociatedsteamgenerator~IN&IILL,II(ii)reactorcoolantandreactorcoolantpump.loopBanditsassociatedsteamgeneratorandreactorcoolantpump.3.1-2PROPOSEDhe.-~,.iaw.~'a.-e.~~*.-JtAM~bawwwaa04a,aoaewoa~

g.(iii)residualheatremovalloop.A.*(iv)residualheat,removalloopB.*Whileatcoldshutdownorwhentheaveragecoolanttemperatureisbetween200'Fand350'F,at.leastoneofthecoolantloopslistedinparagraph3.1.1.1.eshallbeinoperation.However,bothreactorcoolantpumpsandresidualheatremovalpumpsmaybede-energizedforupto1hourpro-vided1)nooperationsarepermittedthatwouldcausedilutionoftherreactorcoolantsystemboronconcentration,and2)coreoutlettemperatureismaintainedatleast10'Fbelowsaturationtempera-ture.Iftheconditionsof3.1.1.1.earenotmet,immediatelyinitiatecorrectiveactiontoreturntherequiredloopstooperablestatus,andifnotincoldshutdownalready,beincoldshutdownwithin24hours.Iftheconditionsof3.1.1.1.farenotmet,thensuspendalloperationsinvolvingareductioninboronconcentrationoftheReactorCoolantSystemandimmediatelyinitiatecorrectiveactiontoreturntherequiredcoolantlooptooperation.*Thenormalor-;,emergencypowersourcemaybeinoperablewhileincoldshutdown~)4~3.1-3PROPOSED i.Atleastonereactorcoolantpumportheresidualheatremovalsystemshallbeinoperationwhenareductionismadeintheboronconcentrationofthereactorcoolant.j.AtleastonereactorcoolantpumpshallbeinoperationforaplannedtransitionfromoneReactorOperatingModetoanotherinvolvinganincreaseintheboronconcentrationofthereactorcoolant,except.foremergencyboration.k.Areactorcoolantpumpshallnot.bestartedwithoneormoreoftheRCScoldlegtemperatures<330'Funless1)thepressurizerwatervolumeislessthan324cubicfeet(38%level)or2)thesecondarywatertemperatureofeachsteamgeneratorislessthan50'FaboveeachoftheRCScoldlegtemperatures.3.1.1.2SteamGeneratora.Thetemperaturedifferenceacrossthetubesheet,shallnotexceed100'F.~fla.Atleastonepressurizercodesafetyvalveshallbeoperablewheneverthereactorheadisboltedonthevessel.b.Bothpressurizercodesafetyvalvesshallbeoperablewheneverthereactoriscritical.TheplantisdesignedtooperatewithallreactorcoolantloopsinoperationandmaintaintheDNBRabove1.30duringallnormal3.1-4PROPOSED operationsandanticipatedtransients.Heattransferanalyses(1)showthatreactorheatequivalentto130NWT(8.5%)canberemovedbynaturalcirculationalone.Thereforeoperationwithoneoperatingreactorcoolantloopwhilebelow130NWTprovidesadequatemargin.Thespecificationpermitsanorderlyreductioninpowerifareactorcoolantpumpislostduringoperationbetween130MWTand50%ofratedpower.Above50%power,anautomaticreactortripwilloccurifeitherpumpislost.Thepower-to-flowratiowillbemaintainedequaltoorlessthanonewhichensuresthattheminimumDNBratioincreasesatlowerflowsincethemaximumenthalpyrisedoesnotincrease.Whenthereactorcoolantsystemaveragetemperatureisabove350'F,asinglereactorcoolantloopprovidessufficientheatremovalcapabilityforremovingdecayheat;however,singlefailureconsiderationsrequireoneloopbeinoperationandtheotherloopbecapableofremovingheatvianaturalcirculation.Whenthereactorcoolantsystemaveragetemperatureisbetween200'Fand350'Forwhileincoldshutdown,asinglereactorcoolantlooporRHRloopprovidessufficientheatremovalcapabilityforremovingdecayheat;butsinglefailureconsiderationsrequirethatatleasttwoloopsbeoperable.Thus,ifthereactorcoolantloopsarenotoperable,thisspecificationrequirestwoRHRloopstobeoperable.Whentheborozf-'"co'ncenCrationofthereactorcoolantsystemistobereducedtheprocessmustbeuniformtopreventsuddenreactivity3.1-4aPROPOSED changesinthereactor.Mixingofthereactorcoolantwillbesufficienttopreventasuddenincreaseinreactivityifatleastonereactorcoolantpumporoneresidualheatremovalpumpisrunningwhilethechangeistakingplace.Theresidualheatremovalpumpwillcirculatetheprimarysystemvolumeinapproximatelyonehalfhour.Thepressurizerisofnoconcernbecauseofthelowpressurizervolumeandbecausethepressurizerboronconcentrationwillbehigherthanthatoftherestofthereactorcoolant.Whentheboronconcentrationofthereactorcoolantsystemistobeincreased,theprocessmustbeuniformtopreventsuddenreactivityincreasesinthereactorduringsubsequentstartupofthereactorcoolantpumps.Mixingofthereactorcoolantwillbesufficienttomaintainauniformboronconcentrationifatleastonereactorcoolantpumpisrunningwhilethechangeistakingplace.Emergencyborationwithoutareactorcoolantpumpinoperationisnotprohibitedbythisspecification.ProhibitingreactorcoolantpumpstartswithoutalargevoidinthepressurizerorwithoutalimitedRCStemperaturedifferentialwillpreventRCSoverpressurizationduetoexpansionofcoolerRCSwaterasitentersawarmersteamgenerator.A38%levelinthepressurizerwillaccommodatetheswellresultingfromareactorcoolantpumpstartwithaRCStemperatureof140'Fandsteamgeneratorsecondarysidetemperatureof340'F,orthemaximumtemperaturewhichusuallyexistspriortocoolingthereactorwith-"-CKe"-RHR"'system.3.1-4b TemperaturerequirementsforthesteamgeneratorcorrespondwithmeasuredNDTfortheshellandallowablethermalstressesinthetubesheet.Eachofthepressurizercodesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturatedsteamatthevalvesetpoint.Below3SO'Fand350psiginthereactorcoolantsystem,theresidualheatremovalsystemcanremovedecayheatandtherebycontrolsystemtemperatureandpressure.Ifnoresidualheatwereremovedbyanyofthemeansavailabletheamountofsteamwhichcouldbegeneratedat,safetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.Onevalvethereforeprovidesadequatedefenseagainstoverpressurization.References(1)FSARSection14.1.6(2)FSARSection7.2.33.1-4c d.e.g.h.least,onesourcerangenetronfluxmonitorshallbeinservice.Atleastoneresidualheatremovalloopshallbeinoperation.*Immediatelybeforereactorvesselheadremovalandwhileloadingandunloadingfuelfromthereactor,theminimumboronconcentrationof2000ppmshallbemaintainedintheprimarycoolantsystemandcheckedbysamplingtwiceeachshift.Directcommunicationbetweenthecontrolroomandtherefuelingcavitymanipulatorcraneshallbeavailablewheneverchangesincoregeometryaretakingplace.Inadditiontothereguirementsofparagraph3.8.l.d,whileintherefuelingmodewithlessthan23feetofwaterabovethetopofthereactorvesselflange,tworesidualheatremovalloopsshallbeoperable.*Duringmovementoffuelorcontrolrodswithinthereactorvesselcavity,atleast23feet.ofwatershallbemaintainedoverthetopofthereactorvessel*Eitherthenormalortheemergencypowersourcemaybeinoperableforeachresidual.heat;.removalloop.C'~OS'~qeewweee3.8-2PROPOSED 3.8.2flange.Ifthisconditionisnotmet,alloperationsinvolvingmovementoffuelorcontrolrodsinthereactorvesselshallbesuspended.Ifanyofthespecifiedlimitingconditionsforrefuelingisnotmet.,refuelingofthereactorshallcease;workshallbeinitiatedtocorrecttheviolatedconditionssothatthespecifiedlimitsaremet;nooperationswhichmayincreasethereactivityofthecoreshallbemade.Basis:Theequipment.andgeneralprocedurestobeutilizedduringrefuelingarediscussedintheFSAR.Detailedinstructions,theabovespecifiedprecautions,andthedesignofthefuelhandlingequipmentincorporatingbuilt-ininterlocksandsafetyfeatures,provideassurancethat.noincidentcouldoccurduringtherefuelingoperationsthatwouldresultinahazard-~.~MmMCSW@~rS=V.Xm..sk3.8-2aPROPOSED

'I~I

'(~providedontheliftinghoisttopreventmovementofmorethanonefuelassemblyatatime.Thespentfueltransfermechanismcanaccommodateonlyonefuelassemblyatatime.Inadditioninterlocksontheauxiliarybuildingcranewillpreventthetrolleyfrombeingmovedoverstoragerackscontainingspentfuel.

References:

(1)FSAR-Section9.5.2(2)Table3.2.1-1(3)FSAR-Section9.3.1'C4!%f4'-I"9HA4ib%it44~~~SlkWASaakul~.k>,~J%~4~AWfRW4OW4JAl&,'0+~44)t\Amendment113.8-4PROPOSED 3.11.23.11.33.11.43.11.53.11.6e.Charcoaladsorbersshallbeinstalledintheventi-lationsystemexhaustfromthespentfuelstoragepitareaandshallbeoperable.Radiationlevelsinthespentfuelstorageareashallbemoniioredcontinuously.Thetrolleyoftheauxiliarybuildingcraneshallneverbestationedorpermittedtopassoverstoragerackscontainingspentfuel.Fuelassemblieswithlessthan60dayssinceirradiationshallnotbeplacedinstoragepositionswithlessspacingbetweenthemthanthatindicatedinFigure3.11-1bythedesignationRDF.Thespentfuelpooltemperatureshallbelimitedto150'F.Thespent.fuelshippingcaskshallnotbecarriedbythe'auxiliarybuildingcrane,pendingtheevaluationofthespent,fuelcaskdropaccidentandthecranedesignbyRGGEandNRCreviewandapproval.Basis:Charcoaladsorberswillreducesignificantlytheconsequencesofarefuelingaccidentwhichconsidersthecladfailureofasingleirrad-iatedfuelassembly.Therefore,charcoaladsorbersshouldbeemployedwheneverirradiatedfuelisbeinghandled.Thisrequiresthattheventilationsystemshouldbeoperatinganddrawingairthroughtheadsorbers.Thedesired.='air.-..<low=-.path,~whenhandlingirradiatedfuel,isfromtheouterdeoPt'heuiidrngintotheoperatingfloorareatowa,rdthespe'nt'uel'"storagepit,intotheareaexhaustducts,throughtheChange4Amendment11,343.11-2PROPOSED

adsorbers,andoutthroughtheventilationsystemexhausttothefacilityvent.OperationofamainauxiliarybuildingexhaustfanassuresthatairdischargedintothemainventilationsystemexhaustductwillgothroughaHEPAandbedischargedtothefacilityvent.Operationoftheexhaustfanforthespentfuelstoragepitareacausesairmovementontheoperatingfloortobetowardsthepit.Properoperationofthefansandsettingofdamperswouldresultinanegativepressureontheoperatingfloorwhichwillcauseairleakagetobeintothebuilding.Thus,theoverallairflowisfromthelocationoflowactivity(outsidethebuilding)totheareaofhighestactivity(spentfuelstoragepit).Theexhaustairflowwouldbethrougharoughingfilterandcharcoalbeforebeingdischargedfromthefacility.TheroughingfilterprotectstheIfadsorberfrombecomingfouledwithdirt;theadsorberremovesiodine,theisotopeofhighestradiologicalsignificance,resultingfromafuelhandlingaccident.Theeffectivenessofcharcoalforremovingiodineisassuredbyhavingahighthroughputandahighremovalefficiency.Thethroughputisattainedbyoperationoftheexhaustfans.Thehighremovalefficiencyisattainedbyminimizingtheamountofiodinethatbypassesthecharcoalandhavingcharcoalwithahighpotentialforremovingtheiodinethat,doespassthroughthecharcoal.Theminimumspacingspecifiedforfuelassemblieswithlessthan60daysdecayisbasedonmaintainingthepotentialreleaseoffissionproddcCs=that"couldoccurshouldanobjectfallonanddam~aestox'edfueltolessthanthatwhichcouldhaveoccurredwithfuel'storedintheoriginalfuel'torageracks.3%113 Thespent,fuelpooltemperatureislimitedto150'Fbecauseifthespentfuelpoolcoolingsystemislostatthattemperature,suf-ficienttime(approximately7hours)isavailabletoprovideback-upcooling,assumingthemaximumanticipatedheatload(fullcoredischarge6previouslystoredfuel),untilatemperatureof180'Fisreached,thetemperatureatwhichthestructuralintegrityofthepoolwasanalyzedandfoundacceptable.References(1)FSAR-Section9.3-1(2)ANS-5.1(N18.6),October1973~<8hfQit~aJSNCV'Kl!tAK"s.;iS~Proposed

~)~~4.3REACTORCOOLANTSYSTEM~11'ppliestosurveillanceofthereactorcoolantsystemanditscomponents.Toensureoperabilityofthereactorcoolantsystemanditscomponents.Secifications:4.3.1ReactorVesselMaterialSurveillanceTesting4.3.1.1ThereactorvesselmaterialsurveillancetestingprogramisdesignedtomeettherequirementsofAppendixHto10CFRPart50.Thisprogramconsistsofthe,metal-lurgicalspecimensreceivingthefollowingtest:tensile,charpyimpactandtheWOLtest.ThesetestsoftheRadiationCapsuleSpecimensshallbeperformedasfollows:~CasuleTimeTestedEndof1stcorecycleEndof3rdcorecycle10years,at,nearestrefueling20years,atnearestrefueling30years,at,nearestrefuelingN44elXQMAQW~ici'.3.1.2NStandbyThereportoftheReactorVesselMaterialSurveillanceshallbewrittenasaSummaryTechnicalReportasrequiredQ~~LCIAOl">>'I0by~ppendi~~~CERPart50.eac4o~CoolantLoops4.3-1Proposed 4.3.2.1Whenreactorpowerisabove130NWt(8.5%),thereactorcoolantpumpsshallbeverifiedtobeinoperationandcirculatingreactorcoolantatleastonceper12hours.4.3.2.2Whentheaveragecoolanttemperatureisabove350'Fbutthereactorisnotcritical,whenthereactorisathotshutdown,orwhenthereactoriscriticalbut'reactorpowerislessthanorequalto130NWt,(8.5%):a)theoperatingreactorcoolantpump(s)shallbeverifiedtobeinoperationandcirculatingreactorcoolantat,leastonceper12hoursb)reactorcoolantpumpwhichisnotoperating,,butmustbeoperable,shallbedemonstratedoperableonceper7daysbyverifyingcorrectbreakeralignmentsandindicatedpoweravailability.4.3.2.3Whenthereactorisatcoldshutdownorwhentheaveragecoolanttemperatureisbetween200'Fand350'F,andfuelisinthereactor,thefollowingshallbeperformedtodemonstratealoopisoperable.Testsneednotbeper-,formedifaloopisnotreliedupontosatisfythere-quirementsofSpecification3.1.1.1.e.a)todemonstrateareactorcoolantloopoperable,thereactorcoolantpump(s),ifnotinoperation,shallbedemonstratedoperableatleastonceper7daysbyverifyingcorrectbreakeralignments.,..~~~andindicated.poweravailability.iNL~Jill4y$,$$4.3-2Proposed

~~)b)todemonstratearesidualheatremovalpumpisoperable,thesurveillancespecifiedintheInservicePumpandValveTestProgrampreparedpursuantto10CFR50.55ashallbeperformed.4.3.2.4Whenthereactorisatcoldshutdownorwhentheaveragecoolanttemperatureisbetween200'Fand350'Fandfuelisinthereactoratleastonecoolantloopshallbeverifiedtobeinoperationandcirculatingreactorcoolantatleastonceper12hours.Basis:Thismaterialsurveillanceprogrammonitorschangesinthefracturetoughnesspropertiesofferriticmaterialsinthereactorvesselbeltlineregionofthereactorresultingfromexposuretoneutronirradiationandthethermalenvironment.Thetest.dataobtainedfromthisprogramwillbeusedtodeterminetheconditionsunderwhichthereactorvesselcanbeoperatedwithadequatemarginsofsafetyagainstfracturethroughoutitsservicelife.4.3-3Proposed 4.11Refuelin~11'ppliestorefuelingandtofuelhandlinginthespent.fuelpit.'f'.11.1SpentFuel:PitCharcoalAdsorberSystem4.11.1.1Within60dayspriortoeachmajorfuelhandling,thespentfuelpitcharcoaladsorbersystemshallhavethefollowingconditionsdemonstrated.Aftertheconditionshavebeendemonstrated,theoccurrenceofpainting,fireorchemicalreleaseinanyventilationzonecommunicat-ingwiththespentfuelpitcharcoaladsorbersystemshallrequirethatthefollowingconditionsberedemonstratedbeforemajorfuelhandling*maycontinue.a.Thetotalairflowratefromthecharcoaladsorbersshallbeatleast75%ofthatmeasuredwithacom-pietesetofnewadsorbers.b.In-placeFreontesting,underambient.conditions,shallshowatleast99%removal.c.Theresultsoflaboratoryanalysisonacarbonsampleshallshow90%orgreaterradioactivemethyliodideremovalwhentestedatatleast150'Fand95%RHandat1.5to2.0mg/mloadingwithtaaaedCHI.~RSQCW~~~~~>>mig.,aI&4~flII%WC'~0'-k'~l0II4ej'athefuelassembliesfromthereactorvessel.4".;.AmendmentNo.344.11-1.:,.;.~",.....,,PROPOSEDQWe4~r@s44'c~~~~.WA.u%Nmss."~44~OWL, d.Flowshallbemaintainedthroughthesystemusingeitherthefilterorbypassflowpathforatleast15minuteseachmonth.4.11.1.2Aftereachreplacementofacharcoalfilterdrawerorafteranystructuralmaintenanceonthecharcoalhousingforthespentfuelpitcharcoaladsorbersystem,theconditionofSpecification4.11.1.1.bshallbedemonstratedfortheaffectedportionofthesystem.4.11.2ResidualHeat.RemovalandCoolantCirculation4.11.2.1Whenthereactorisintherefuelingmodeandfuelisinthereactor,atleastoneresidualheat,removalloopshallbeverifiedtobeinoperationandcirculatingreactorcoolantatleastonceper4hours.4.11.2.2Whenthewaterlevelabovethetopofreactorvesselflangeislessthan23feet,bothRHRpumpsshallbeverifiedtobeoperablebyperformingthesurveillancespecifiedintheInservicePumpandValveTestProgram4.11.3preparedpursuantto10CFR50.55a.Waterfevel-ReactorVessel4.11.3.1Thewaterlevelinthereactorcavityshallbedeterminedtobeatleastitsminimumreguireddepthwithin2hourspriortothestartofandatleastonceper24hoursthereafterduringmovementoffuelassembliesorcontrolrodsincontainment.Basisemeasuremenassuresthatairisbeingwithdrawn.'.-Xrom.'the:;sjent-.Xiiej..-.pigarea,.andpassedthroughtheadsorbers.Theflowismeasuredpriortoemployingtheadsorberstoestablishthat4.11-2 therehasbeennogrosschangeinperformancesincethesystemwaslastused.TheFreontestprovidesameasureoftheamountofleakagefromaroundthecharcoaladsorbent.Theabilityofcharcoaltoadsorbiodinecandeteriorateasthecharcoalagesandweathers.Testingthecapacityofthecharcoaltoadsorbiodineassuresthatanacceptableremovalefficiencyunderoperatingconditionswouldbeobtained.Thedifferencebetweenthetest,requirementofaremovalefficiencyof90%formethyliodineandthepercentageassumedintheevaluationofthefuelhandlingaccidentprovidesadequatesafetymarginfordegrada-tionofthefilterafterthetests.Retestingofthespentfuelpitcharcoaladsorbersystemintheevent,ofpainting,fire,orchemicalreleaseisrequiredonlyifthesystemisoperatingandisprovidingfiltrationfortheareainwhichthepainting,fire,orchemicalreleaseoccurs.Testingoftheairfiltrationsystemswillbetested,totheextent:itcanbegiventheconfigurationofthesystems,inaccordancewithANSIN510-1975,"TestingofNuclearAir-CleaningSystems".

Reference:

(1)LetterfromE.J.Nelson,RochesterGasandElectricCorporationtoDr.PeterA.Morris,U.S.AtomicEnergyCommission,datedFebruary3,1971CCQskji~i4.11-3 AttachmentBTechnicalSpecificationshavebeenpreparedfordecayheatremovalsystemwhichgenerallyfollowstheguidanceoftheletterfromDarrelG.EisenhutdatedJune11,1980.SinceanewTechnicalSpecificationaddressingwaterlevelduringrefuelingoperationisbeingproposed,NRCguidanceasprovidedbyThomasM.Novak'sletterdatedAugust15,1980isalsobeingincorporated.Theconditionsforoneloopoperationhavenotbeenrevised.OneloopoperationhasrecentlybeenreviewedbytheNRCundertheSystematicEvaluationProgramandfoundtobeacceptable(seetheletterdatedMay29,1979fromDennisL.Ziemann).Analyseshaveshownthatnaturalcirculationcanremoveheat,uptotheequivalentof130MWt(8.5%).Thus,thesinglefailureoftheoperatingreactorcoolantpumpwhilebelow130MWt(8.5%)doesnot.resultinanunacceptablecondition.Atlowtemperatureconditions,twoloopsarerequiredtobeoperable.Thisensuresthat,intheeventofasinglefailurecausinglossofoneloop,residualheatcanstillberemoved.Duringrefuelingwhenthereactorcavityisfilled,onlyoneloopneedbeoperable.Thisisduetothesubstantialheatsink.offeredbythewaterinthecavity.'41Ar~,w.~>alEI~'oV~ala'<<'ggslyA!.*\~II~49L~~e~iClPIHk 0Say,l