Application for Amend to License DPR-18,changing Tech Specs to Reflect Overpressure Protection Sys Requirements.Safety Evaluation & Justification for Continued Operation Encl| ML17244A180 |
| Person / Time |
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| Site: |
Ginna  |
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| Issue date: |
10/11/1978 |
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| From: |
WHITE L D
ROCHESTER GAS & ELECTRIC CORP. |
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| To: |
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| Shared Package |
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| ML17244A179 |
List: |
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| References |
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| TASK-05-03, TASK-5-3, TASK-RR NUDOCS 7810190069 |
| Download: ML17244A180 (17) |
|
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[Table view] |
Text
UNITEDSTATESOFAMERICANUCIEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant.,UnitNo.l))))DocketNo.50-244))APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"
),Rochester GasandElectricCorporation
("RG&E"),
holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifica-tionssetforthinAppendixAtothatlicensebeamendedtoincludereactoroverpressure protection systemrequirements.
Theproposedtechnical specification changeisset.forthinAttachment AtothisApplication.
Asafetyevaluation issetforthinAttachment, B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
Justifi-cationforclassification oftheamendment pursuantto10C.F.R.Section170.22isincludedasAttachment, C.Acheckfortheappropriate feeaccompanies thisApplication.
lS(o]qoo6q WHEREFORE, Applicant respectfully requeststhat.AppendixAtoProvisional Operating LicenseNo.DPR-l8beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.Whxe,Jr.VicePresident, ElectricandSteamProduction Subscribed andsworntobeforemeonthis///FLBayofOctober,1978.GARYL.REISSNOTARYPUBLIC,StatoofN.Y.MonroeCo.MyCommtssioo ExpiresMarchpp,19,./yg Attachment AFigure3.10-2isnotmet,theplantshallbetakentothehotshutdowncondition andtheoneloopshutdownmarginshallbemet.d.Atleastonereactorcoolantpumpshallbeinoperation foraplannedtransition fromoneReactorOperating Modetoanotherinvolving anincreaseintheboronconcentration ofthereactorcoolant.e.AreactorcoolantpumpshallnotbestartedwithoneormoreoftheRCScoldlegtemperatures
<330'Funless1)thepressurizer watervolume7slessthan324cubicfeet(38%level)or2)thesecondary watertemperature ofeachsteamgenerator islessthan50'FaboveeachoftheRCScoldlegtemperatures.
3.1.1.2SteamGenerator a.Onesteamgenerator shallbecapableofperforming itsheattransferfunctionwhenevertheaveragecoolanttemperature isabove350'F.b.Thetemperature difference acrossthetubesheetshallnotexceed100'F.3.1.1.3SafetValvesa~Atleastonepressurizer codesafetyvalveshallbeoperablewheneverthereactorheadisonthevessel.b.Bothpressurizer codesafetyvalvesshallbeoperablewheneverthereactoriscritical.
Basis:Whentheboronconcentration ofthereactorcoolantsystemistobereducedtheprocessmustbeuniformtopreventsuddenreactivity changesinthereactor.Mixingofthereactorcoolantwillbesufficient 3+12Proposed
Eachofthepressurizer codesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturated steamatthevalvesetpoint.Below350'Fand350psiginthereactorcoolantsystem,theresidualheatremovalsystemcanremovedecayheatandtherebycontrolsystemtemperature andpressure.
Ifnoresidualheat.wereremovedbyanyofthemeansavailable theamountofsteamwhichcouldbegenerated atsafetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.
Onevalvetherefore providesadequatedefenseagainstoverpressurization.
Prohibiting reactorcoolantpumpstartswithoutalargevoidinthepressurizer orwithoutalimitedRCStemperature differential willpreventRCSoverpressurization duetoexpansion ofcoolerRCSwaterasitentersawarmersteamgenerator.
A38%levelinthepressurizer willaccommodate theswellresulting fromareactorcoolantpumpstartwithaRCStemperature of140'Fandsteamgenerator secondary sidetemperature of340'F,orthemaximumtemperature whichusuallyexistspriortocoolingthereactorwiththeRHRsystem.Thespecification permitsanorderlyreduction inpowerifareactorcoolant(gamp islostduringoperation between130MWTand50%ofratedpower.Above50%power,anautomatic reactortripwilloccurifeitherpumpislost.Thepower-to-flow ratiowillbemaintained equaltoorlessthanonewhichensuresthattheminimumDNBratioincreases atlowerflowsincethemaximumenthalpyrisedoesnotincrease.
Temperature requirements forthesteamgenerator'correspond withmeasuredNDTfortheshellandallowable thermalstressesinthetubesheet.References (1)FSARSection14.1.6(2)FSARSection7.2.3Proposed c~Oneboricacidtankmaybeoutofserviceprovidedaminimumof2,000gallonsofa12%to13%byweightboricacidsolutionatatemperature ofatleast145'Fiscontained intheoperabletankandprovidedthatthetankisrestoredtooperablestatuswithin24hours.d.Onechannelofheattracingmaybeoutofserviceprovideditisrestoredtooperablestatuswithin24hours.3.2.4Basis:Wheneverthereactorcoolantsystemis>200'FandisbeingcooledbytheRHRsystemandtheoverpressure protection systemisnotoperable, atleastonechargingpumpshallbedemonstrated inoperable at,leastonceper12hoursbyverifying thatthecontrolswitchisinthepull-stop position.
Thechemicalandvolumecontrolsystemprovidescontrolofthereactorcoolantsystemboroninventory.
Thisisnormallyaccomplished byusingeitheroneofthethreechargingpumpsinserieswithoneofthetwoboricacidpumps.Analternate methodofborationwillbetousethechargingpumpsdirectlyfromtherefueling waterstoragetank.Athirdmethodwillbetodepressurize andusethesafetyinjection pumps.Therearetwosourcesofboratedwateravailable forinjection throughthreedifferent paths.(1)Theboricacidtransferpumpscandelivertheboricacidtankcontents(12%concentration ofboricacid)tothechargingpumps.(2)Thechargingpumpscantakesuctionfromtherefueling waterstoragetank.(2,000ppmboronsolution)
(3)Thesafetyinjection pumpscantaketheirsuctionsfromeithertheboricacidtanksortherefueling waterstoragetank.Thequantityofboricacidinstoragefromeithertheboricacidtanksortherefueling waterstoragetankissufficient toborate.thereactorcoolant.inordertoreachcoldshutdownatanytimeduringcorelife.Approximately 1800gallonsofthe12%to13%solutiqy)of boricacidare.requiredtomeetcoldshutdowncondi-tions.'hus, aminimumof2000gallonsintheboricacidtanksisspecified.
Anupperconcentration limitof13%boricacidinthetankisspecified tomaintainsolutionsolubility atthespeci-fiedlowtemperature limitof145'F.Twochannelsofheattracingareinstalled onlinesnormallycontaining concentrated boricacidsolutiontomaintainthespecified lowtemperature limit,.3~23Proposed Placingachargingpumpinpull-stop wheneverthereactorcoolantsystemtemperature is>200'FandisbeingcooledbyRHRwithout,theoverpressure protection systemoperablewillpreventinadvertayP) overpressurization oftheRHRsystemshouldletdownbeterminated.
References:
(1)FSAR,Section9.2(2)FSAR,Page9.2-37(3)L.D.White,Jr.lettertoA.Schwencer, NRC,datedFebruary24,19773.2-4Proposed (ii)Thetworeactorcoolantdraintankpumpsshallbetestedandtheiroperability demon-stratedpriortoinitiating repairsoftheinoperable residualheatremovalpump.d.Oneresidualheatexchanger maybeoutofserviceforaperiodofnomorethan24hours.e.Anyvalverequiredforthefunctioning ofthesafetyinjection orresidualheatremovalsystemsmaybeinoperable providedrepairsarecompleted within12hours.Priortoinitiating repairs,allvalvesinthesystemsthatprovidetheduplicate functionshallbetestedtodemonstrate operability.
3.3.1.3f.Powermayberestoredtoanyvalvereferenced in3.3.1.1gforthepurposesofvalvetestingproviding nomorethanonesuchvalvehaspowerrestoredandprovidedtestingiscompleted andpowerremovedwithin12hours.Exceptduringdieselgenerator loadandsafeguard sequencetestingorwhenthevesselheadisremovedorthesteamgenerator manwayisopenamaximumofonesafetyinjection pumpshallbeoperablewheneverthetemperature ofoneormoreoftheRCScoldlegsis<330'F.3.3.1.3.1 3.3.23.3.2.1Wheneveramaximumofonesafetyinjection pumpmaybeoperableby3.3.1.3atleasttwoofthesafetyinjection pumpsshallbedemonstrated inoperable atleastoncepertwelvehoursbyverifying thatthecontrolswitchesareinthepull-stop position.
Containment CoolinandIodineRemovalThereactorshallnotbemadecriticalexceptforlowtemperature physicstests,unlessthefollowing condi-tionsaremet:a~b.c~Thesprayadditivetankcontainsnotlessthan4500gallonsofsolutionwithasodiumhydroxide concentration ofnotlessthan30%byweight.Atleasttwocontainment spraypumpsare'perable.
Atleastthreefancoolerunitsareoperable.
3.3-4Proposed
'untilrepairswereeffected.
Thefacilityhasfourservicewaterpumps.Onlyoneisneededduringtheinjection phase,andtwoarerequiredduringtherecirculation phaseofapostulated loss-of-coolant accident.
(8)Thelimitsfortheaccumulator pressureandvolumeassurethere-quiredamountofwaterinjection duringanaccident, andarebasedonvaluesusedfortheaccidentanalyses.
Theindicated levelof50%corresponds to1108cubicfeetofwaterintheaccumulator andtheindicated levelof82%corresponds to1134cubicfeet.Thelimitation foramaximumofonesafetyinjection pumptobeoperableandthesurveillance requirement toverifythattwosafetyinjection pumpsareinoperable below330'Fprovidesassurance thatamassadditionpressuretransient canberelievedbytheoperation ofasinglePORV.3~312Proposed 3.15OveressureProtection Sstem~lb1Applieswheneverthetemperature ofoneormoreoftheRCScoldlegsis<330'F.Ob'ctiveTopreventoverpressurization ofthereactorcoolantsystem.Secification 3.15.1Atleastoneofthefollowing overpressure protection systemsshallbeoperable:
a.Twopressurizer poweroperatedreliefvalves(PORVs)withaliftsettingof<435psig,orb.Areactorcoolantsystemventof>1.1squareinches.3.15.1.1WithonePORVinoperable, eitherrestoretheinoperable PORVtooperablestatuswithin7daysordepressurize andventtheRCSthrougha1.1squareinchvent(s)withinthenext8hours;maintaintheRCSinaventedcondition untilbothPORVshavebeenrestoredtooperablestatus.3.15.1.23.15.1.3WithbothPORVsinoperable, depressurize andventtheRCSthrougha1.1squareinchvent(s)within8hours;maintaintheRCSinaventedcondition untilbothPORVshavebeenrestoredtooperablestatus.Useoftheoverpressure protection systemtomitigateaRCSpressuretransient shallbereportedinaccordance with6.9.3.BasisTheoperability oftwopressurizer PORVsoranRCSventopeningofgreaterthan1.1squareinchesensuresthattheRCSwillbeprotected frompressuretransients whichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsare<330'F.EitherPORVhasadequaterelieving capability toprotecttheRCSfromoverpressurization whenthetransient, islimitedtoeither(1)thestartofanidleRCPwiththesecondary watertemperature ofthesteamgenerator
<50'FabovetheRCScoldlegtemperature or(2)thestartof~1~afetyinjection pumpanditsinjection intoawatersolidRCS.
References:
(1)L.D.White,Jr.lettertoA.Schwencer, NRC,datedJuly29,19773.15-1Proposed OveressureProtection SstemAlicabilit
- Appliestothereactorcoolantsystemoverpressure protection system.Ob'ective:
Toverifythattheoverpressure protection systemwillfunctionproperlyifneeded.Secification EachPORVshallbedemonstrated operableby:a~Performance ofachannelfunctional testonthePORVactuation channel,butexcluding valveopera-tion,within31dayspriortoenteringacondition inwhichthePORVisrequiredoperableandatleastonceper31daysthereafter whenthePORVisrequiredoperable.
b.Performance ofachannelcalibration onthePORVactuation channelat,leastonceper18months.c.Verifying thePORVisolation valveisopenatleastonceper72hourswhentheoverpressure protection systemisrequiredtobeoperable.
TheRCSvent(s)shallbeverifiedtobeopenatleastonceper12hourswhenthevent(s)isbeingusedforoverpressure protection exceptwhenthevent,pathwayisprovidedwithavalvewhichislocked,sealed,orotherwise securedintheopenposition.
Thenverifythesevalvesopenatleastonceper31days.Proposed (2)Annually:
Atabulation onanannualbasisofthenumberofstation,utilityandotherper-sonnel(including contractors) receiving ex-posuresgreaterthan200mrem/yrandtheirassociated manremexposureaccording toworkandjobfunctions, e.g.,reactoroperations andsurveillance, inservice inspection, routinemaintenance, specialmaintenance (describe maintenance),
wasteprocessing, andrefueling.
Thedoseassignment tovariousdutyfunctions maybeestimates basedonpocketdosimeter, TU),orfilmbadgemeasure-ments.Smallexposures totalling lessthan20%oftheindividual totaldoseneednotbeaccounted for.Intheaggregate, atleast80%ofthetotalwholebodydosereceivedfromexternalsourcesshallbeassignedtospecificmajorworkfunctions.
(NOTE:Thistabulation supplements there-quirements ofSection20.407of10CFRPart20.)ReactorOverpressure Protection SystemOperation IntheeventeitherthePORVsortheRCSvent(s)areusedtomitigateaRCSpressuretransient, aSpecialReportshallbepreparedandsubmitted totheCommission within30days.Thereportshalldescribethecircumstances initiating thetransient, theeffectofthePORVsorvent(s)onthetransient andanyothercorrective actionnecessary topreventrecurrence.
6.9-10Proposed Attachment BAreactorcoolantsystemoverpressure protection systemhasbeeninstalled atR.E.Ginnatomitigatepressuretransients thatmightotherwise exceedthoselimitswhicharebaseduponAppendixGto10CFRPart50.Thesystemisdesignedtomitigatetransients whichmayresultfrompersonnel error,equipment malfunction orprocedural deficiencies.
Adescription ofthissystemwasprovidedinlettersfromMr.L.D.White,Jr.,Rochester GasandElectricCorporation, toMr.A.Schwencer, U.S.NuclearRegulatory Commission, datedFebruary24,1977,March31,1977,andJuly29,1977.Theoverpressure protection systemwillpreventawatersolidreactorcoolantsystemfromexceeding apressureof535psigforasafetyinjection pumpdischarging tothereactorcoolantsystem,areactorcoolantpumpstartwitha50'Ftemperature differential betweentheprimaryandsecondary systemorlessseveremassinputorheatinputtransients.
Thespecification prohibiting reactorcoolantpumpstartsunlessthefilledpressurizer volumeislessthan324ft(38%level)orunlessthetemperature differential betweentheprimaryandsecondary systemsislessthan50'Fwillproperlylimitheatinput,transients.
Apressurizer levelof38%willaccommodate theswellresulting fromareactorcoolantpumpstartwithareactortemperature of140'Fandsteamgenerator temperature of340'Fwithouttheneedforoperation oftheoverpressure protec-tionsystem.Relieffromthepressurizer poweroperatedreliefvalves(PORVs)would,however,increasethemarginbetweenthepeaktransient pressureandthelimitofTechnical Specification 3.1.2.Withnogasorsteambubbleinthepressurizer theover-pressureprotection systemwillbyitselfpregytthepressurefromexceeding Technical Specification 3.1.2.Thespecification tolimitthenumberofchargingpumpswhichmaybeoperablewhenthereactorcoolantsystemtemperature isgreaterthan200'Fandtheoverpressure protection systemisinoperable willpreventapotential overpressurization oftheresidualheatremovalsystem(RHR)shouldletdownbeisolated.
AnalysishasshownthattheRHRsystemcanrelievetheinputfromthreechargingpumpswhenthereactorcoolantsystemtemperature islessthan200'Fandcanrelievetheinputoftwocyygingpumpsattemperatures greaterthanorequalto200'F.Thecombinedcapacityof3chargingpumpsislessthanthat,ofonesafetyinjection pumpandwillnotproducetransient pressures greaterthanthosewhichcanbemitigated bytheoverpressure protection systemwhenthatsystemisoperable.
Proposedspecification 3.3.1.3willprohibitmorethanonesafetyinjection pumpfrombeingoperablewhenoneormoreoftheRCScoldlegtemperatures islessthanorequalto330'Fexceptduringdieselgenerator loadandsafeguard sequencetestingorwhenthevesselheadisremovedorthesteamgenerator manwayisopen.Theshutoffheadofthesafetyinjection pumpsislessthan1500psig,apressurewellbelowtheallowable pressurefor RCStemperatures of330'Fandabove.Allsafetyinjection pumpsmaybeoperablefortemperatures above330'F;onepumpmaybeoperablebelow330'F,whenthepotential foroverpressure transients exists,becauseof~)emitigating effectoftheoverpressure protection system.Whenthereactorheadisremovedorwhenasteamgenerator manwayisopenapotential foroverpressurization doesnotexistandthereisnorestriction onsafetyinjection pumpoperation.
Duringdieselgenerator loadandsafeguard sequencetestingextraprecautions aretakentopreventsafetyinjection pumpdischarge tothereactorcoolantsystem.Thepumpdischarge valvesareclosed,thevalvebreakersareopenedandtheDCcontrolfusesareremoved.Theseprecautions reducethepotential foroverpressurization toanacceptable levelduringthetestperiod.Surveillance ofthepumpcontrolsoncepertwelvehourswhenonlyonepumpmaybeoperableisappropriate topreventinadvertent pumpstarts.Proposedspecification 3.15requiresthatanoverpressure protection systembeoperablewhenoneormoreoftheRCScoldlegtemperatures islessthanorequalto330'F.Fortemperatures greaterthan330'Ftheallowable RCSpressureisgreaterthanthenormalreliefpressureofthetwopressurizer poweroperatedreliefvalvessothatnootheroverpressure protection isrequired.
Below330'FeachofthePORVs,usingalowpressuresetpointof435psig,willmitigatepressuretransients inawater-solid RCSresulting fromthedischarge ofasinglesafetyinjection pumporthestartingofareactorcoolantpumpwitha50'Ftemyy~ature differential betweenthereactorandsteamgenerators.
A1.1squareinchventistheorificeareaequivalent tothatofasinglePORV.BecauseeachofthePORVswillprovideoverpressure protec-tion,7daysisanacceptable timeduringwhichoneofthePORVsmaybeinoperable.
Aftersevendays,orintheeventthatbothPORVsareinoperable, 8hoursisanacceptable periodoftimetoestablish aRCSventandisarelatively shortperiodoftimetobewithoutadditional overpressure protection.
Proposedspecification 4.16requiresappropriate actiontoassurethattheoverpressure protection systemfunctions properly.
Achannelfunctional testwillbeperformed priortothetimethatthesystemisrequiredtobeoperableandatleastonceevery31daysthereafter whenit,isoperable.
Achannelcalibra-tionwillbeperformed atleastonceevery18months.Thesetestsandcalibrations aresimilarinnatureandfrequency tothosewhichareperformed onplantprotection systemseventhoughthissystemdoesnotperformwhat,isconsidered tobeasafetyfunction.
Verification thatthePORVisolation valveisopenatleastonceevery72hourswhentheoverpressure protection systemisrequiredtobeoperablewillprovideappropriate assurance thattheoverpressure protection functionhasnotbeeninadvertently defeated.
(1)LetterfromL.D.White,Jr.,Rochester Gas6ElectricCorporation, toA.Schwencer, NuclearRegulatory Commission, July29,1977.(2)LetterfromL.D.White,Jr.,Rochester Gas&ElectricCorporation, toA.Schwencer, NuclearRegulatory Commission, February24,1977 Attachment CTheproposedAmendment.
totheProvisional Operating Licensehasbeenevaluated anddetermined tofallwithinthedefinition ofClassIIIof10C.F.R.Section170.22therebyreguiring afeeof94,000.Theproposedamendment dealswithasinglesafetyissue,over-pressureprotection ofthereactorvessel.Theissuehasbeenclearlyidentified byanNRCposition.
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