ML17250A779
| ML17250A779 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/12/1980 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250A777 | List: |
| References | |
| NUDOCS 8011200277 | |
| Download: ML17250A779 (27) | |
Text
Attachment ARemoveTechnical Specification pagesii,1-1,3.1-1through3143824314324ll1~4112InsertrevisedTechnical Specification pagesii,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.)4.0SURVEILLANCE REQUIREMENTS Pacae4.14.24.34.54.64.74.84.94.104.114.124.134.144.154.16Operational SafetyReviewInservice Inspection ReactorCoolantSystemContainment TestsSafetyInjection, Containment, SprayandIodineRemovalSystemsTestsEmergency PowerSystemPeriodicTestsMainSteamStopValvesAuxiliary Feedwater SystemReactivity Anomalies Environmental Radiation SurveyRefueling EffluentSurveillance Radioactive MaterialSourceLeakageTestShockSuppressors (Snubbers)
FireSuppression SystemTestOverpressure Protection System4.1-14.2-14.3-14.4-14.5-14.6-14.7-14.8-14.9-14.10-14.11-14.12-14.13-14.14-14.15-14.16-15.0DESIGNFEATURES5.1Site5.2Containment DesignFeatures5.3ReactorDesignFeatures5.4FuelStorage5.1-15.2-15.3-15.4-1*~Qll<Proposed TECHNICAL SPECIFICATIONS DEFINITIONS Thefollowing termsaredefinedforuniforminterpreta-tionofthespecifcations.
ThermalPowerTheratethat,thethermalenergygenerated bythefuelisaccumulated bythecoolantasitpassesthroughthereactorvessel.Reactor0eratinModesCoolant.ModeRefueling ColdShutdownReactivity akk'10Temperature oFT<140Tavg<200HotShutdownTavg-Operating
~f0Tavg~580Anyoperation withinthecontainment involving
- movement, offueland/orcontrolrodswhenthevesselheadisun-bolted.~OerableCapableofperforming allintendedfunctions intheintendedmanner.1-1PROPOSED
3.0 LIMITINGCONDITIONS
FOROPERATION 3.1ReactorCoolantSstemb'1'pplies totheoperating statusoftheReactorCoolantSystemwhenfuelisinthereactor.~b'ospecifythoseconditions oftheReactorCoolantSystemwhichmustbemet,toassuresafereactoroperation.
3.1.10erational Comonents3.1.1.1ReactorCoolantLoosa~b.Whenthereactorpowerisabove130MWT(8.5%),bothreactorcoolantloopsandtheirassociated steamgenerators andreactorcoolantpumpsshallbeinoperation.
Iftheconditions of3.1.1.l.a arenotmet,thenimmediate powerreduction shallbeinitiated underadministrative control.Iftheshutdownmargin/meetstheonelooprequirements ofFigure3.10-2,thenthepowershallbereducedtolessthan130MWT.IftheoneloopshutdownmarginofFigure3.10-2isnotmet,theplantshallbetakentothehotshutdowncondition andtheoneloopshutdownmarginshallbemet.~'b<tJ3.1-1PROPOSED c.Exceptforspecialtests,whentheaveragecoolanttemperature isabove350'F,orwhenthereactorisathotshutdownoriscriticalwiththereactorpowerlessthanorequalto130NWT(8.5%),atleastonereactorcoolantloopanditsassociated steamgenerator andreactorcoolantpumpshallbeinopera-tion.Theotherloopanditsassociated steam'enerator mustbeoperablesothat.heatcould-beremovedvianaturalcirculation.
However,bothreactorcoolantpumpsmaybede-energized forupto1hourprovided(1)nooperations arepermitted thatwouldcausedilutionofthereactorcoolantsystemboronconcentration, and(2)coreoutlettemperature ismaintained atleast10'Fbelow.saturation temperature.
d.Iftheconditions of3.1.1.l.c arenotmet,suspendalloperations involving areduction inboronconcentration oftheReactorCoolant:Systemandimmediately initiate'orrective actiontoreturntherequiredcoolantlooptooperation.
e.Whenthereactorisatcoldshutdownorwhentheaveragecoolanttemperature isbetween200'Fand350'F,atleasttwoofthefollowing coolantloopsshallbeoperable:
(i)reactorcoolantloopAanditsassociated steamgenerator
~IN&IILL,II(ii)reactorcoolantandreactorcoolantpump.loopBanditsassociated steamgenerator andreactorcoolantpump.3.1-2PROPOSEDhe.-~,.iaw.~'a.-e.~~*.-JtAM~bawwwaa04a,aoaewoa~
g.(iii)residualheatremovalloop.A.*(iv)residualheat,removalloopB.*Whileatcoldshutdownorwhentheaveragecoolanttemperature isbetween200'Fand350'F,at.leastoneofthecoolantloopslistedinparagraph 3.1.1.1.e shallbeinoperation.
However,bothreactorcoolantpumpsandresidualheatremovalpumpsmaybede-energized forupto1hourpro-vided1)nooperations arepermitted thatwouldcausedilutionoftherreactorcoolantsystemboronconcentration, and2)coreoutlettemperature ismaintained atleast10'Fbelowsaturation tempera-ture.Iftheconditions of3.1.1.1.e arenotmet,immediately initiatecorrective actiontoreturntherequiredloopstooperablestatus,andifnotincoldshutdownalready,beincoldshutdownwithin24hours.Iftheconditions of3.1.1.1.f arenotmet,thensuspendalloperations involving areduction inboronconcentration oftheReactorCoolantSystemandimmediately initiatecorrective actiontoreturntherequiredcoolantlooptooperation.
- Thenormalor-;,emergency powersourcemaybeinoperable whileincoldshutdown~
)4~3.1-3PROPOSED i.Atleastonereactorcoolantpumportheresidualheatremovalsystemshallbeinoperation whenareduction ismadeintheboronconcentration ofthereactorcoolant.j.Atleastonereactorcoolantpumpshallbeinoperation foraplannedtransition fromoneReactorOperating Modetoanotherinvolving anincreaseintheboronconcentration ofthereactorcoolant,except.foremergency boration.
k.Areactorcoolantpumpshallnot.bestartedwithoneormoreoftheRCScoldlegtemperatures
<330'Funless1)thepressurizer watervolumeislessthan324cubicfeet(38%level)or2)thesecondary watertemperature ofeachsteamgenerator islessthan50'FaboveeachoftheRCScoldlegtemperatures.
3.1.1.2SteamGenerator a.Thetemperature difference acrossthetubesheet,shallnotexceed100'F.~fla.Atleastonepressurizer codesafetyvalveshallbeoperablewheneverthereactorheadisboltedonthevessel.b.Bothpressurizer codesafetyvalvesshallbeoperablewheneverthereactoriscritical.
Theplantisdesignedtooperatewithallreactorcoolantloopsinoperation andmaintaintheDNBRabove1.30duringallnormal3.1-4PROPOSED operations andanticipated transients.
Heattransferanalyses(1)showthatreactorheatequivalent to130NWT(8.5%)canberemovedbynaturalcirculation alone.Therefore operation withoneoperating reactorcoolantloopwhilebelow130NWTprovidesadequatemargin.Thespecification permitsanorderlyreduction inpowerifareactorcoolantpumpislostduringoperation between130MWTand50%ofratedpower.Above50%power,anautomatic reactortripwilloccurifeitherpumpislost.Thepower-to-flow ratiowillbemaintained equaltoorlessthanonewhichensuresthattheminimumDNBratioincreases atlowerflowsincethemaximumenthalpyrisedoesnotincrease.
Whenthereactorcoolantsystemaveragetemperature isabove350'F,asinglereactorcoolantloopprovidessufficient heatremovalcapability forremovingdecayheat;however,singlefailureconsiderations requireoneloopbeinoperation andtheotherloopbecapableofremovingheatvianaturalcirculation.
Whenthereactorcoolantsystemaveragetemperature isbetween200'Fand350'Forwhileincoldshutdown, asinglereactorcoolantlooporRHRloopprovidessufficient heatremovalcapability forremovingdecayheat;butsinglefailureconsiderations requirethatatleasttwoloopsbeoperable.
Thus,ifthereactorcoolantloopsarenotoperable, thisspecification requirestwoRHRloopstobeoperable.
Whentheborozf-'"co'ncenCration ofthereactorcoolantsystemistobereducedtheprocessmustbeuniformtopreventsuddenreactivity 3.1-4aPROPOSED changesinthereactor.Mixingofthereactorcoolantwillbesufficient topreventasuddenincreaseinreactivity ifatleastonereactorcoolantpumporoneresidualheatremovalpumpisrunningwhilethechangeistakingplace.Theresidualheatremovalpumpwillcirculate theprimarysystemvolumeinapproximately onehalfhour.Thepressurizer isofnoconcernbecauseofthelowpressurizer volumeandbecausethepressurizer boronconcentration willbehigherthanthatoftherestofthereactorcoolant.Whentheboronconcentration ofthereactorcoolantsystemistobeincreased, theprocessmustbeuniformtopreventsuddenreactivity increases inthereactorduringsubsequent startupofthereactorcoolantpumps.Mixingofthereactorcoolantwillbesufficient tomaintainauniformboronconcentration ifatleastonereactorcoolantpumpisrunningwhilethechangeistakingplace.Emergency borationwithoutareactorcoolantpumpinoperation isnotprohibited bythisspecification.
Prohibiting reactorcoolantpumpstartswithoutalargevoidinthepressurizer orwithoutalimitedRCStemperature differential willpreventRCSoverpressurization duetoexpansion ofcoolerRCSwaterasitentersawarmersteamgenerator.
A38%levelinthepressurizer willaccommodate theswellresulting fromareactorcoolantpumpstartwithaRCStemperature of140'Fandsteamgenerator secondary sidetemperature of340'F,orthemaximumtemperature whichusuallyexistspriortocoolingthereactorwith-"-CKe"-RHR"'system.
3.1-4b Temperature requirements forthesteamgenerator correspond withmeasuredNDTfortheshellandallowable thermalstressesinthetubesheet.Eachofthepressurizer codesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturated steamatthevalvesetpoint.Below3SO'Fand350psiginthereactorcoolantsystem,theresidualheatremovalsystemcanremovedecayheatandtherebycontrolsystemtemperature andpressure.
Ifnoresidualheatwereremovedbyanyofthemeansavailable theamountofsteamwhichcouldbegenerated at,safetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.
Onevalvetherefore providesadequatedefenseagainstoverpressurization.
References (1)FSARSection14.1.6(2)FSARSection7.2.33.1-4c d.e.g.h.least,onesourcerangenetronfluxmonitorshallbeinservice.Atleastoneresidualheatremovalloopshallbeinoperation.*
Immediately beforereactorvesselheadremovalandwhileloadingandunloading fuelfromthereactor,theminimumboronconcentration of2000ppmshallbemaintained intheprimarycoolantsystemandcheckedbysamplingtwiceeachshift.Directcommunication betweenthecontrolroomandtherefueling cavitymanipulator craneshallbeavailable wheneverchangesincoregeometryaretakingplace.Inadditiontothereguirements ofparagraph 3.8.l.d,whileintherefueling modewithlessthan23feetofwaterabovethetopofthereactorvesselflange,tworesidualheatremovalloopsshallbeoperable.*
Duringmovementoffuelorcontrolrodswithinthereactorvesselcavity,atleast23feet.ofwatershallbemaintained overthetopofthereactorvessel*Eitherthenormalortheemergency powersourcemaybeinoperable foreachresidual.
heat;.removal loop.C'~OS'~qeewweee3.8-2PROPOSED 3.8.2flange.Ifthiscondition isnotmet,alloperations involving movementoffuelorcontrolrodsinthereactorvesselshallbesuspended.
Ifanyofthespecified limitingconditions forrefueling isnotmet.,refueling ofthereactorshallcease;workshallbeinitiated tocorrecttheviolatedconditions sothatthespecified limitsaremet;nooperations whichmayincreasethereactivity ofthecoreshallbemade.Basis:Theequipment.
andgeneralprocedures tobeutilizedduringrefueling arediscussed intheFSAR.Detailedinstructions, theabovespecified precautions, andthedesignofthefuelhandlingequipment incorporating built-ininterlocks andsafetyfeatures, provideassurance that.noincidentcouldoccurduringtherefueling operations thatwouldresultinahazard-~.~MmMCSW@~rS=
V.Xm..sk3.8-2aPROPOSED
'I~I
'(~providedontheliftinghoisttopreventmovementofmorethanonefuelassemblyatatime.Thespentfueltransfermechanism canaccommodate onlyonefuelassemblyatatime.Inadditioninterlocks ontheauxiliary buildingcranewillpreventthetrolleyfrombeingmovedoverstoragerackscontaining spentfuel.
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\Amendment 113.8-4PROPOSED 3.11.23.11.33.11.43.11.53.11.6e.Charcoaladsorbers shallbeinstalled intheventi-lationsystemexhaustfromthespentfuelstoragepitareaandshallbeoperable.
Radiation levelsinthespentfuelstorageareashallbemoniioredcontinuously.
Thetrolleyoftheauxiliary buildingcraneshallneverbestationed orpermitted topassoverstoragerackscontaining spentfuel.Fuelassemblies withlessthan60dayssinceirradiation shallnotbeplacedinstoragepositions withlessspacingbetweenthemthanthatindicated inFigure3.11-1bythedesignation RDF.Thespentfuelpooltemperature shallbelimitedto150'F.Thespent.fuelshippingcaskshallnotbecarriedbythe'auxiliary buildingcrane,pendingtheevaluation ofthespent,fuelcaskdropaccidentandthecranedesignbyRGGEandNRCreviewandapproval.
Basis:Charcoaladsorbers willreducesignificantly theconsequences ofarefueling accidentwhichconsiders thecladfailureofasingleirrad-iatedfuelassembly.
Therefore, charcoaladsorbers shouldbeemployedwheneverirradiated fuelisbeinghandled.Thisrequiresthattheventilation systemshouldbeoperating anddrawingairthroughtheadsorbers.
Thedesired.='air.-..<low=-.path,
~whenhandlingirradiated fuel,isfromtheouterdeoPt'heuiidrngintotheoperating floorareatowa,r dthespe'nt'uel'"storage pit,intotheareaexhaustducts,throughtheChange4Amendment 11,343.11-2PROPOSED
adsorbers, andoutthroughtheventilation systemexhausttothefacilityvent.Operation ofamainauxiliary buildingexhaustfanassuresthatairdischarged intothemainventilation systemexhaustductwillgothroughaHEPAandbedischarged tothefacilityvent.Operation oftheexhaustfanforthespentfuelstoragepitareacausesairmovementontheoperating floortobetowardsthepit.Properoperation ofthefansandsettingofdamperswouldresultinanegativepressureontheoperating floorwhichwillcauseairleakagetobeintothebuilding.
Thus,theoverallairflowisfromthelocationoflowactivity(outsidethebuilding) totheareaofhighestactivity(spentfuelstoragepit).Theexhaustairflowwouldbethrougharoughingfilterandcharcoalbeforebeingdischarged fromthefacility.
TheroughingfilterprotectstheIfadsorberfrombecomingfouledwithdirt;theadsorberremovesiodine,theisotopeofhighestradiological significance, resulting fromafuelhandlingaccident.
Theeffectiveness ofcharcoalforremovingiodineisassuredbyhavingahighthroughput andahighremovalefficiency.
Thethroughput isattainedbyoperation oftheexhaustfans.Thehighremovalefficiency isattainedbyminimizing theamountofiodinethatbypassesthecharcoalandhavingcharcoalwithahighpotential forremovingtheiodinethat,doespassthroughthecharcoal.
Theminimumspacingspecified forfuelassemblies withlessthan60daysdecayisbasedonmaintaining thepotential releaseoffissionproddcCs=
that"could occurshouldanobjectfallonanddam~aestox'edfueltolessthanthatwhichcouldhaveoccurredwithfuel'storedintheoriginalfuel'torage racks.3%113 Thespent,fuelpooltemperature islimitedto150'Fbecauseifthespentfuelpoolcoolingsystemislostatthattemperature, suf-ficienttime(approximately 7hours)isavailable toprovideback-upcooling,assumingthemaximumanticipated heatload(fullcoredischarge 6previously storedfuel),untilatemperature of180'Fisreached,thetemperature atwhichthestructural integrity ofthepoolwasanalyzedandfoundacceptable.
References (1)FSAR-Section9.3-1(2)ANS-5.1(N18.6),October1973~<8hfQit~aJSNCV'Kl!t AK"s.;iS~Proposed
~)~~4.3REACTORCOOLANTSYSTEM~11'pplies tosurveillance ofthereactorcoolantsystemanditscomponents.
Toensureoperability ofthereactorcoolantsystemanditscomponents.
Secifications:
4.3.1ReactorVesselMaterialSurveillance Testing4.3.1.1Thereactorvesselmaterialsurveillance testingprogramisdesignedtomeettherequirements ofAppendixHto10CFRPart50.Thisprogramconsistsofthe,metal-lurgicalspecimens receiving thefollowing test:tensile,charpyimpactandtheWOLtest.ThesetestsoftheRadiation CapsuleSpecimens shallbeperformed asfollows:~CasuleTimeTestedEndof1stcorecycleEndof3rdcorecycle10years,at,nearestrefueling 20years,atnearestrefueling 30years,at,nearestrefueling N44elXQMAQW~
ici'.3.1.2NStandbyThereportoftheReactorVesselMaterialSurveillance shallbewrittenasaSummaryTechnical ReportasrequiredQ~~LCIAOl"
>>'I0by~ppendi~~~
CERPart50.eac4o~Coolant Loops4.3-1Proposed 4.3.2.1Whenreactorpowerisabove130NWt(8.5%),thereactorcoolantpumpsshallbeverifiedtobeinoperation andcirculating reactorcoolantatleastonceper12hours.4.3.2.2Whentheaveragecoolanttemperature isabove350'Fbutthereactorisnotcritical, whenthereactorisathotshutdown, orwhenthereactoriscriticalbut'reactor powerislessthanorequalto130NWt,(8.5%):
a)theoperating reactorcoolantpump(s)shallbeverifiedtobeinoperation andcirculating reactorcoolantat,leastonceper12hoursb)reactorcoolantpumpwhichisnotoperating,,
butmustbeoperable, shallbedemonstrated operableonceper7daysbyverifying correctbreakeralignments andindicated poweravailability.
4.3.2.3Whenthereactorisatcoldshutdownorwhentheaveragecoolanttemperature isbetween200'Fand350'F,andfuelisinthereactor,thefollowing shallbeperformed todemonstrate aloopisoperable.
Testsneednotbeper-,formedifaloopisnotreliedupontosatisfythere-quirements ofSpecification 3.1.1.1.e.
a)todemonstrate areactorcoolantloopoperable, thereactorcoolantpump(s),ifnotinoperation, shallbedemonstrated operableatleastonceper7daysbyverifying correctbreakeralignments
.,..~~~andindicated.
poweravailability.
iNL~Jill4y$,$$4.3-2Proposed
~~)b)todemonstrate aresidualheatremovalpumpisoperable, thesurveillance specified intheInservice PumpandValveTestProgrampreparedpursuantto10CFR50.55ashallbeperformed.
4.3.2.4Whenthereactorisatcoldshutdownorwhentheaveragecoolanttemperature isbetween200'Fand350'Fandfuelisinthereactoratleastonecoolantloopshallbeverifiedtobeinoperation andcirculating reactorcoolantatleastonceper12hours.Basis:Thismaterialsurveillance programmonitorschangesinthefracturetoughness properties offerriticmaterials inthereactorvesselbeltlineregionofthereactorresulting fromexposuretoneutronirradiation andthethermalenvironment.
Thetest.dataobtainedfromthisprogramwillbeusedtodetermine theconditions underwhichthereactorvesselcanbeoperatedwithadequatemarginsofsafetyagainstfracturethroughout itsservicelife.4.3-3Proposed 4.11Refuelin~11'pplies torefueling andtofuelhandlinginthespent.fuelpit.'f'.11.1SpentFuel:PitCharcoalAdsorberSystem4.11.1.1Within60dayspriortoeachmajorfuelhandling, thespentfuelpitcharcoaladsorbersystemshallhavethefollowing conditions demonstrated.
Aftertheconditions havebeendemonstrated, theoccurrence ofpainting, fireorchemicalreleaseinanyventilation zonecommunicat-ingwiththespentfuelpitcharcoaladsorbersystemshallrequirethatthefollowing conditions beredemonstrated beforemajorfuelhandling*
maycontinue.
a.Thetotalairflowratefromthecharcoaladsorbers shallbeatleast75%ofthatmeasuredwithacom-pietesetofnewadsorbers.
b.In-placeFreontesting,underambient.conditions, shallshowatleast99%removal.c.Theresultsoflaboratory analysisonacarbonsampleshallshow90%orgreaterradioactive methyliodideremovalwhentestedatatleast150'Fand95%RHandat1.5to2.0mg/mloadingwithtaaaedCHI.~RSQCW~~~~~>>mi g.,aI&4~flII%WC'~0'-k'~l0II4ej'athefuelassemblies fromthereactorvessel.4".;.Amendment No.344.11-1.:,.;.~",.....,,
PROPOSEDQWe4~r@s44'c~~~~.W A.u%Nmss."~44~OWL, d.Flowshallbemaintained throughthesystemusingeitherthefilterorbypassflowpathforatleast15minuteseachmonth.4.11.1.2Aftereachreplacement ofacharcoalfilterdrawerorafteranystructural maintenance onthecharcoalhousingforthespentfuelpitcharcoaladsorbersystem,thecondition ofSpecification 4.11.1.1.bshallbedemonstrated fortheaffectedportionofthesystem.4.11.2ResidualHeat.RemovalandCoolantCirculation 4.11.2.1Whenthereactorisintherefueling modeandfuelisinthereactor,atleastoneresidualheat,removalloopshallbeverifiedtobeinoperation andcirculating reactorcoolantatleastonceper4hours.4.11.2.2Whenthewaterlevelabovethetopofreactorvesselflangeislessthan23feet,bothRHRpumpsshallbeverifiedtobeoperablebyperforming thesurveillance specified intheInservice PumpandValveTestProgram4.11.3preparedpursuantto10CFR50.55a.Waterfevel-ReactorVessel4.11.3.1Thewaterlevelinthereactorcavityshallbedetermined tobeatleastitsminimumreguireddepthwithin2hourspriortothestartofandatleastonceper24hoursthereafter duringmovementoffuelassemblies orcontrolrodsincontainment.
Basisemeasuremen assuresthatairisbeingwithdrawn
.'.-Xrom.'the:;sjent-.
Xiiej..-.pig area,.and passedthroughtheadsorbers.
Theflowismeasuredpriortoemploying theadsorbers toestablish that4.11-2 therehasbeennogrosschangeinperformance sincethesystemwaslastused.TheFreontestprovidesameasureoftheamountofleakagefromaroundthecharcoaladsorbent.
Theabilityofcharcoaltoadsorbiodinecandeteriorate asthecharcoalagesandweathers.
Testingthecapacityofthecharcoaltoadsorbiodineassuresthatanacceptable removalefficiency underoperating conditions wouldbeobtained.
Thedifference betweenthetest,requirement ofaremovalefficiency of90%formethyliodineandthepercentage assumedintheevaluation ofthefuelhandlingaccidentprovidesadequatesafetymarginfordegrada-tionofthefilterafterthetests.Retesting ofthespentfuelpitcharcoaladsorbersystemintheevent,ofpainting, fire,orchemicalreleaseisrequiredonlyifthesystemisoperating andisproviding filtration fortheareainwhichthepainting, fire,orchemicalreleaseoccurs.Testingoftheairfiltration systemswillbetested,totheextent:itcanbegiventheconfiguration ofthesystems,inaccordance withANSIN510-1975, "TestingofNuclearAir-Cleaning Systems".
Reference:
(1)LetterfromE.J.Nelson,Rochester GasandElectricCorporation toDr.PeterA.Morris,U.S.AtomicEnergyCommission, datedFebruary3,1971CCQskji~i4.11-3 Attachment BTechnical Specifications havebeenpreparedfordecayheatremovalsystemwhichgenerally followstheguidanceoftheletterfromDarrelG.EisenhutdatedJune11,1980.SinceanewTechnical Specification addressing waterlevelduringrefueling operation isbeingproposed, NRCguidanceasprovidedbyThomasM.Novak'sletterdatedAugust15,1980isalsobeingincorporated.
Theconditions foroneloopoperation havenotbeenrevised.Oneloopoperation hasrecentlybeenreviewedbytheNRCundertheSystematic Evaluation Programandfoundtobeacceptable (seetheletterdatedMay29,1979fromDennisL.Ziemann).
Analyseshaveshownthatnaturalcirculation canremoveheat,uptotheequivalent of130MWt(8.5%).Thus,thesinglefailureoftheoperating reactorcoolantpumpwhilebelow130MWt(8.5%)doesnot.resultinanunacceptable condition.
Atlowtemperature conditions, twoloopsarerequiredtobeoperable.
Thisensuresthat,intheeventofasinglefailurecausinglossofoneloop,residualheatcanstillberemoved.Duringrefueling whenthereactorcavityisfilled,onlyoneloopneedbeoperable.
Thisisduetothesubstantial heatsink.offeredbythewaterinthecavity.'41Ar~,w.~>alEI~'oV~ala'<<'ggslyA!.*\~II~49L~~e~iClPIHk 0Say,l