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| {{#Wiki_filter:~\UNXTEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONXntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant,UnitNo.l)))'I)DocketNo.50-244))APPLICATIONFORAMENDMENTTOOPERATINGLICENSEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RG&E"),holderofProvisionalOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecifica-tion3.7setforthinAppendixAtothatlicensebeamendedtomodifytherequirementsforoperabilityofthed.c.electricalsystems.ITheproposedtechnicalspecificationchangeissetforthinAttachmentAtothisApplication.AsafetyevaluationissetforthinAttachmentB.Thisevaluationalsodemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Justi--ficationforclassificationoftheamendmentpursuantto10CFRSection170.22isincludedasAttachmentC.AcheckfortheappropriatefeeaccompaniesthisApplication. | | {{#Wiki_filter:~\UNXTEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION XntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.l)))'I)DocketNo.50-244))APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission" |
| WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoProvisionalOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.Nhie,Jr.VicePresident,.ElectricandSteamProductionSubscribedandsworntobeforemeonthis/O-dayofOctober,1978.SHARONG.CAVALERINOTARYPUBLIC,StateofN.Y.,h'lonroeCountyMyCommfssionExpiresMarch30,29/.g AttachmentAReplaceTechnicalSpecificationpages3.7-1through3.7-4withtherevisedpages3.7-1through3.7-4. | | ),Rochester GasandElectricCorporation |
| 3.7AUXILIARYELECTRICALSYSTEMSAplicabilitAppliestotheavailabilityofelectricalpowerfortheoperationofplantauxiliaries.Todefinethoseconditionsofelectricalpoweravailabilitynecessary(1)toprovideforsafereactoroperation,and(2)toprovideforthecontinuingavailabilityofengineeredsafeguards.Secification3.7.1Thereactorshallnotbemaintainedcriticalwithout:a.The34.5KV-4160Voltstationservicetransformerinservice.b.480-voltbuses14,16,17and18energized.c.4160-voltbuses12Aand12Benergized.d.Twodieselgeneratorsoperablewithonsitesupplyof10,000gallonsoffuelavailable.e.Bothbatteriesandbothd.c.systemsoperable,andratleastone150ampbatterycharger-ortwo75ampbatterychargersinserviceforeachbattery.3.7.2Duringreactoroperationtherequirementof3.7.1maybemodifiedasfollows:3~71 a.Poweroperationmaycontinuewith'thestationservicetransformeroutofserviceprovided(a)thefailureshallbereportedtoNRCwithin24hourswithanoutlineoftheplansforpromptrestorationofoffsitepowerandthe.additionalprecautionstobetakenwhilethetransformerWisoutofserviceand(b)bothdiesel.generatorsareoperable.Underconditionsoffulfillmentof(b)andnon-fulfillmentof(a),continuedpoweroperationshallnotextendbeyond24hours.Non-fulfillmentof(b)shallbeide'emedsufficientcauseforimmediatereactorshutdown.b.Poweroperationmaycontinueifonedieselgeneratorisoutofserviceprovided(a)theremainingdieselgeneratorisruncontinuously,and(b)thestationservicetrans-formerisinserviceand(c)suchoperationisnotinexcessof7day(totalforbothdiesels)duringanymonth.c.Poweroperationmaycontinueifthebatterycharger(s)forloned.c.systemareinoperable,aslongastheinoperablebatterychargersarerestoredtooperablestatuswithintwohours.Ifnotrestored,thereactorshallbeplaced;:inthehotshutdownconditionwithinthenextsixhoursandinthecoldshutdownconditionwithinthefollowing30hours..Basis:'i(Theelectricalsyst'mequipmentisarrangedsothatnosinglecontingencycaninactivateenoughsafeguardsequipmenttojeopardizetheplantsafety.The480-voltequipmentisarranged3~72 on6buses.The4160-voltequipment,alsoissuppliedfrom4buses.Twoseparateoutsidesourcessupplystationservicepowertotheplant.Theplantauxiliaryisarrangedelectricallysothatmul-tipleitemsreceivetheirpowerfromthetwodifferentsources.Thechargingpumpsaresuppliedfromthe480-voltbusesNo.14and16.Thefourcontainmentfansaredividedbetween480-voltbusesNo.14and16.Thetworesidualheatpumpsareonseparate480-voltbuses.motorcontrolcenters.ValvesaresuppliedfromIOneoutsidesourceofpowerisrequiredtogivesufficientpowertorunnormaloperatingequipment.Onetransmissionlinecansupplyalltheplantauxiliarypower.The115-34.5kvstationservicetransformercansupplyalltheauxiliaryloads.Thebusarrangementsspecifiedforoperationensurethatpowerisavailabletoanadequatenumberofsafeguardsauxiliaries.Withadditionalswitching,moreequipmentcouldbeoutofservicewithoutinfringingonsafety.Twodieselgeneratorshavesufficientcapacitytostartandrunatdesignloadalltheengineeredsafeguardsequipment.TheS/safeguardsoperatedfromonedieselgeneratorcanadequatelylCcoolthecoreforanyloss-of-coolantincident,andtheyalso3~73 maintainthecontainmentpressurewithinthedesignvalue.Theminimumdieselfueloilinventoryatalltimesismaintainedtoassuretheoperationofbothdieselscarryingdesignloadofalltheengineeredsafeguardsequipmentforatleast40hours.-Commercialoilsuppliesandtruckingfacilitiesexisttoassuredeliverieswithin8hours.Atleastone150ampbatterychargerortwo75ampbatterychargersshallbein.serviceforeachbatterysothatthebatterieswilltalwaysbeatfullcharge.Thisensuresthatadequatedcpowerwillbeavailable.Theplantcanbesafelyshutdownwithouttheuseofoffsitepowersinceallvitalloads(sa'fetysystems,instrumentsetc.)canbesuppliedfromtheemergencydieselgenerators.Thetwodieselgenerators,eachcapableofsupplyingsafeguardsloads,andthestationauxiliarytransformerprovidethreeseparatesourcesofpowersupplysystemmeetsthesinglefailurecriteriarequiredofsafetysystems.(2)\Refernces:(1)FSAR-(2)FSAR-Section-8.2.1Appendix8Asjpl3.7-4 Attachment.BTechnicalSpecification3.7.1epresentlyrequiresthatonlyonebatterycharger(whichhasa150ampcapacity)needstobeoperablewhilethereactoriscritical.Thetotalnormald.c.loadispresentlyabout170amps.Twoadditionalbatterychargers,eachwitha75ampchargingcapacity,havebeeninstalled.Withallbatterychargersoperationalandintheirnormalconfiguration,thereisatotalbatterychargercapacityof225ampsperbattery.Intheeventeitherofthe150ampbatterychargersbecomesinoperable,manualtransferofone75ampbatterychargerwillresultinabatterychargercapacitytoeachbatteryof150amps.Thisconfigurationandcapacityisconsistent.withtheguidanceprovidedinRegulatoryGuides1.6and1.32.RegulatoryGuide1.6,Rev.0,positionD.3,statesthat"eachd.c.loadgroupshouldbeenergizedbyabatteryandbatterycharger.Thebattery-chargercombinationshouldhavenoautomaticconnectiontoanyotherredundantd.c.loadgroup."Thisguidanceissatisfiedbyhavingonlymanualconnectionbetweend.c.loadgroups.Regulatory~P'Guide1.32,Rev.2,SectionC.l.b,statesthat"...thecapacityofthebatterychargersupplyshouldbebasedonthelargestcombined+emandsofthevarioussteadystatesloadsandthechargingcapacitytorestorethebatteryfromthedesignminimumchargestatetothefullychargedstate,irrespectiveofthestatusoftheplantduringwhichthesedemandsoccur." | | ("RG&E"), |
| 'Thenormalcontinuousloadoneachd.c.systemisapproxi-mately85amps.TheshutdownloadsthatarerequiredintheeventofalossofoffsitepowerarelistedinFSARTable8.2-.2.Theonlysteadystate(8hour)loadlisted,otherthanthein-verter,whichoperatebothduringnormaloperationandforsafeplantshutdown,istheTurbine-DrivenAuxiliaryFeedwaterPumpDCOilPump.Thispumprepresentsanadditionalpotential22amploadonBattery1B.Thelargestpossiblecombinedload-couldthusoccurduringaplantshutdownfollowinglossofoffsitepower,whenallnormalloadcontinuedoperating,andtheturbine-drivenauxiliaryfeedwaterpumpwasalsoengaged.Thiscombinedloadof85ampsplus22amps,foratotalof107amps,ismuch'-lowerthanthecapacityofthe150ampbatterychargers.ItisthereforeapparentthatthebatterychargersizingcriteriaofRegulatoryGuide1.3.2,andIEEE308-1974,Section5.3.4areeasilymet.Ifthebatterychargerforoned.c.systemwerefoundtobeinoperable,itwouldbepossibleinmostcasestoeffectrepairsandrestorethesystemtooperabilitywithinarelativelyshortrtime.Thisconfigurationwouldnotnegatetheabilityofthed.c.Isystemtoperformitsfunction,butitwouldreducetheredundancyprovidedinthereactordesi.'gn,andtherebylimittheabilitytotolerateadditionalequipmentfailures.(Althoughit'shouldbenotedthatthebatteriesbythemselvescouldcarryallshutdownlloadsfor-8hours).Theredundantd.c.systemwouldbethoroughlycheckedtoensureitsoperability.Ifitdevelopedthatthe | | holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifica-tion3.7setforthinAppendixAtothatlicensebeamendedtomodifytherequirements foroperability ofthed.c.electrical systems.ITheproposedtechnical specification changeissetforthinAttachment AtothisApplication. |
| ~~~inoperabled.c.systemcouldnotbemadeoperablewithintwohours,thereactorwouldbeplacedinthehotshutdowncondition,toprovideforreductionofdecayheatfromthefuel.Ifafteranothersixhoursthemalfunctionwerenotcorrected,thereactorwouldbeplacedinacoldshutdownconditionwithin30hours,usingnormalshutdownandcooldownprocedures.ThesetimeperiodsareconsistentwiththeguidanceprovidedinRegulatoryGuide1.93,Rev.0,"AvailabilityofElectricPowerSources",RegulatoryPosition5.rP' | | Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility. |
| ~~IAtt'achme'ntC.TheproposedAmendmenttotheProvisionalOperatingLicensehasbeenevaluatedanddeterminedtofallwithinthedefinitionofClassIIIof10CFRSection170.22therebyrequiringafeeof$4,000.Theproposedamendmentsimplyclarifiesasinglesafetyissue,batterychargercapacity.TheissuehasbeenclearlyidentifiedbyNRCregulatoryguides.C P~t}} | | Justi--fication forclassification oftheamendment pursuantto10CFRSection170.22isincludedasAttachment C.Acheckfortheappropriate feeaccompanies thisApplication. |
| | WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.Nhie,Jr.VicePresident, |
| | .Electric andSteamProduction Subscribed andsworntobeforemeonthis/O-dayofOctober,1978.SHARONG.CAVALERINOTARYPUBLIC,StateofN.Y.,h'lonroeCountyMyCommfssion ExpiresMarch30,29/.g Attachment AReplaceTechnical Specification pages3.7-1through3.7-4withtherevisedpages3.7-1through3.7-4. |
| | 3.7AUXILIARY ELECTRICAL SYSTEMSAplicabilit Appliestotheavailability ofelectrical powerfortheoperation ofplantauxiliaries. |
| | Todefinethoseconditions ofelectrical poweravailability necessary (1)toprovideforsafereactoroperation, and(2)toprovideforthecontinuing availability ofengineered safeguards. |
| | Secification 3.7.1Thereactorshallnotbemaintained criticalwithout:a.The34.5KV-4160Voltstationservicetransformer inservice.b.480-voltbuses14,16,17and18energized. |
| | c.4160-volt buses12Aand12Benergized. |
| | d.Twodieselgenerators operablewithonsitesupplyof10,000gallonsoffuelavailable. |
| | e.Bothbatteries andbothd.c.systemsoperable, andratleastone150ampbatterycharger-or two75ampbatterychargersinserviceforeachbattery.3.7.2Duringreactoroperation therequirement of3.7.1maybemodifiedasfollows:3~71 a.Poweroperation maycontinuewith'thestationservicetransformer outofserviceprovided(a)thefailureshallbereportedtoNRCwithin24hourswithanoutlineoftheplansforpromptrestoration ofoffsitepowerandthe.additional precautions tobetakenwhilethetransformer Wisoutofserviceand(b)bothdiesel.generators areoperable. |
| | Underconditions offulfillment of(b)andnon-fulfillment of(a),continued poweroperation shallnotextendbeyond24hours.Non-fulfillment of(b)shallbeide'emedsufficient causeforimmediate reactorshutdown. |
| | b.Poweroperation maycontinueifonedieselgenerator isoutofserviceprovided(a)theremaining dieselgenerator isruncontinuously, and(b)thestationservicetrans-formerisinserviceand(c)suchoperation isnotinexcessof7day(totalforbothdiesels)duringanymonth.c.Poweroperation maycontinueifthebatterycharger(s) forloned.c.systemareinoperable, aslongastheinoperable batterychargersarerestoredtooperablestatuswithintwohours.Ifnotrestored, thereactorshallbeplaced;:inthehotshutdowncondition withinthenextsixhoursandinthecoldshutdowncondition withinthefollowing 30hours..Basis:'i(Theelectrical syst'mequipment isarrangedsothatnosinglecontingency caninactivate enoughsafeguards equipment tojeopardize theplantsafety.The480-voltequipment isarranged3~72 on6buses.The4160-volt equipment, alsoissuppliedfrom4buses.Twoseparateoutsidesourcessupplystationservicepowertotheplant.Theplantauxiliary isarrangedelectrically sothatmul-tipleitemsreceivetheirpowerfromthetwodifferent sources.Thechargingpumpsaresuppliedfromthe480-voltbusesNo.14and16.Thefourcontainment fansaredividedbetween480-voltbusesNo.14and16.Thetworesidualheatpumpsareonseparate480-voltbuses.motorcontrolcenters.ValvesaresuppliedfromIOneoutsidesourceofpowerisrequiredtogivesufficient powertorunnormaloperating equipment. |
| | Onetransmission linecansupplyalltheplantauxiliary power.The115-34.5kvstationservicetransformer cansupplyalltheauxiliary loads.Thebusarrangements specified foroperation ensurethatpowerisavailable toanadequatenumberofsafeguards auxiliaries. |
| | Withadditional switching, moreequipment couldbeoutofservicewithoutinfringing onsafety.Twodieselgenerators havesufficient capacitytostartandrunatdesignloadalltheengineered safeguards equipment. |
| | TheS/safeguards operatedfromonedieselgenerator canadequately lCcoolthecoreforanyloss-of-coolant |
| | : incident, andtheyalso3~73 maintainthecontainment pressurewithinthedesignvalue.Theminimumdieselfueloilinventory atalltimesismaintained toassuretheoperation ofbothdieselscarryingdesignloadofalltheengineered safeguards equipment foratleast40hours.-Commercial oilsuppliesandtruckingfacilities existtoassuredeliveries within8hours.Atleastone150ampbatterychargerortwo75ampbatterychargersshallbein.serviceforeachbatterysothatthebatteries willtalwaysbeatfullcharge.Thisensuresthatadequatedcpowerwillbeavailable. |
| | Theplantcanbesafelyshutdownwithouttheuseofoffsitepowersinceallvitalloads(sa'fetysystems,instruments etc.)canbesuppliedfromtheemergency dieselgenerators. |
| | Thetwodieselgenerators, eachcapableofsupplying safeguards loads,andthestationauxiliary transformer providethreeseparatesourcesofpowersupplysystemmeetsthesinglefailurecriteriarequiredofsafetysystems.(2)\Refernces: |
| | (1)FSAR-(2)FSAR-Section-8.2.1 Appendix8Asjpl3.7-4 Attachment. |
| | BTechnical Specification 3.7.1epresently requiresthatonlyonebatterycharger(whichhasa150ampcapacity) needstobeoperablewhilethereactoriscritical. |
| | Thetotalnormald.c.loadispresently about170amps.Twoadditional batterychargers, eachwitha75ampchargingcapacity, havebeeninstalled. |
| | Withallbatterychargersoperational andintheirnormalconfiguration, thereisatotalbatterychargercapacityof225ampsperbattery.Intheeventeitherofthe150ampbatterychargersbecomesinoperable, manualtransferofone75ampbatterychargerwillresultinabatterychargercapacitytoeachbatteryof150amps.Thisconfiguration andcapacityisconsistent. |
| | withtheguidanceprovidedinRegulatory Guides1.6and1.32.Regulatory Guide1.6,Rev.0,positionD.3,statesthat"eachd.c.loadgroupshouldbeenergized byabatteryandbatterycharger.Thebattery-chargercombination shouldhavenoautomatic connection toanyotherredundant d.c.loadgroup."Thisguidanceissatisfied byhavingonlymanualconnection betweend.c.loadgroups.Regulatory |
| | ~P'Guide1.32,Rev.2,SectionC.l.b,statesthat"...thecapacityofthebatterychargersupplyshouldbebasedonthelargestcombined+emandsofthevarioussteadystatesloadsandthechargingcapacitytorestorethebatteryfromthedesignminimumchargestatetothefullychargedstate,irrespective ofthestatusoftheplantduringwhichthesedemandsoccur." |
| | 'Thenormalcontinuous loadoneachd.c.systemisapproxi-mately85amps.TheshutdownloadsthatarerequiredintheeventofalossofoffsitepowerarelistedinFSARTable8.2-.2.Theonlysteadystate(8hour)loadlisted,otherthanthein-verter,whichoperatebothduringnormaloperation andforsafeplantshutdown, istheTurbine-Driven Auxiliary Feedwater PumpDCOilPump.Thispumprepresents anadditional potential 22amploadonBattery1B.Thelargestpossiblecombinedload-couldthusoccurduringaplantshutdownfollowing lossofoffsitepower,whenallnormalloadcontinued operating, andtheturbine-drivenauxiliary feedwater pumpwasalsoengaged.Thiscombinedloadof85ampsplus22amps,foratotalof107amps,ismuch'-lowerthanthecapacityofthe150ampbatterychargers. |
| | Itistherefore apparentthatthebatterychargersizingcriteriaofRegulatory Guide1.3.2,andIEEE308-1974, Section5.3.4areeasilymet.Ifthebatterychargerforoned.c.systemwerefoundtobeinoperable, itwouldbepossibleinmostcasestoeffectrepairsandrestorethesystemtooperability withinarelatively shortrtime.Thisconfiguration wouldnotnegatetheabilityofthed.c.Isystemtoperformitsfunction, butitwouldreducetheredundancy providedinthereactordesi.'gn, andtherebylimittheabilitytotolerateadditional equipment failures. |
| | (Although it'should benotedthatthebatteries bythemselves couldcarryallshutdownlloadsfor-8hours).Theredundant d.c.systemwouldbethoroughly checkedtoensureitsoperability. |
| | Ifitdeveloped thatthe |
| | ~~~inoperable d.c.systemcouldnotbemadeoperablewithintwohours,thereactorwouldbeplacedinthehotshutdowncondition, toprovideforreduction ofdecayheatfromthefuel.Ifafteranothersixhoursthemalfunction werenotcorrected, thereactorwouldbeplacedinacoldshutdowncondition within30hours,usingnormalshutdownandcooldownprocedures. |
| | Thesetimeperiodsareconsistent withtheguidanceprovidedinRegulatory Guide1.93,Rev.0,"Availability ofElectricPowerSources", |
| | Regulatory Position5.rP' |
| | ~~IAtt'achme'nt C.TheproposedAmendment totheProvisional Operating Licensehasbeenevaluated anddetermined tofallwithinthedefinition ofClassIIIof10CFRSection170.22therebyrequiring afeeof$4,000.Theproposedamendment simplyclarifies asinglesafetyissue,batterychargercapacity. |
| | Theissuehasbeenclearlyidentified byNRCregulatory guides.C P~t}} |
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ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
Text
~\UNXTEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION XntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.l)))'I)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-tion3.7setforthinAppendixAtothatlicensebeamendedtomodifytherequirements foroperability ofthed.c.electrical systems.ITheproposedtechnical specification changeissetforthinAttachment AtothisApplication.
Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
Justi--fication forclassification oftheamendment pursuantto10CFRSection170.22isincludedasAttachment C.Acheckfortheappropriate feeaccompanies thisApplication.
WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.Nhie,Jr.VicePresident,
.Electric andSteamProduction Subscribed andsworntobeforemeonthis/O-dayofOctober,1978.SHARONG.CAVALERINOTARYPUBLIC,StateofN.Y.,h'lonroeCountyMyCommfssion ExpiresMarch30,29/.g Attachment AReplaceTechnical Specification pages3.7-1through3.7-4withtherevisedpages3.7-1through3.7-4.
3.7AUXILIARY ELECTRICAL SYSTEMSAplicabilit Appliestotheavailability ofelectrical powerfortheoperation ofplantauxiliaries.
Todefinethoseconditions ofelectrical poweravailability necessary (1)toprovideforsafereactoroperation, and(2)toprovideforthecontinuing availability ofengineered safeguards.
Secification 3.7.1Thereactorshallnotbemaintained criticalwithout:a.The34.5KV-4160Voltstationservicetransformer inservice.b.480-voltbuses14,16,17and18energized.
c.4160-volt buses12Aand12Benergized.
d.Twodieselgenerators operablewithonsitesupplyof10,000gallonsoffuelavailable.
e.Bothbatteries andbothd.c.systemsoperable, andratleastone150ampbatterycharger-or two75ampbatterychargersinserviceforeachbattery.3.7.2Duringreactoroperation therequirement of3.7.1maybemodifiedasfollows:3~71 a.Poweroperation maycontinuewith'thestationservicetransformer outofserviceprovided(a)thefailureshallbereportedtoNRCwithin24hourswithanoutlineoftheplansforpromptrestoration ofoffsitepowerandthe.additional precautions tobetakenwhilethetransformer Wisoutofserviceand(b)bothdiesel.generators areoperable.
Underconditions offulfillment of(b)andnon-fulfillment of(a),continued poweroperation shallnotextendbeyond24hours.Non-fulfillment of(b)shallbeide'emedsufficient causeforimmediate reactorshutdown.
b.Poweroperation maycontinueifonedieselgenerator isoutofserviceprovided(a)theremaining dieselgenerator isruncontinuously, and(b)thestationservicetrans-formerisinserviceand(c)suchoperation isnotinexcessof7day(totalforbothdiesels)duringanymonth.c.Poweroperation maycontinueifthebatterycharger(s) forloned.c.systemareinoperable, aslongastheinoperable batterychargersarerestoredtooperablestatuswithintwohours.Ifnotrestored, thereactorshallbeplaced;:inthehotshutdowncondition withinthenextsixhoursandinthecoldshutdowncondition withinthefollowing 30hours..Basis:'i(Theelectrical syst'mequipment isarrangedsothatnosinglecontingency caninactivate enoughsafeguards equipment tojeopardize theplantsafety.The480-voltequipment isarranged3~72 on6buses.The4160-volt equipment, alsoissuppliedfrom4buses.Twoseparateoutsidesourcessupplystationservicepowertotheplant.Theplantauxiliary isarrangedelectrically sothatmul-tipleitemsreceivetheirpowerfromthetwodifferent sources.Thechargingpumpsaresuppliedfromthe480-voltbusesNo.14and16.Thefourcontainment fansaredividedbetween480-voltbusesNo.14and16.Thetworesidualheatpumpsareonseparate480-voltbuses.motorcontrolcenters.ValvesaresuppliedfromIOneoutsidesourceofpowerisrequiredtogivesufficient powertorunnormaloperating equipment.
Onetransmission linecansupplyalltheplantauxiliary power.The115-34.5kvstationservicetransformer cansupplyalltheauxiliary loads.Thebusarrangements specified foroperation ensurethatpowerisavailable toanadequatenumberofsafeguards auxiliaries.
Withadditional switching, moreequipment couldbeoutofservicewithoutinfringing onsafety.Twodieselgenerators havesufficient capacitytostartandrunatdesignloadalltheengineered safeguards equipment.
TheS/safeguards operatedfromonedieselgenerator canadequately lCcoolthecoreforanyloss-of-coolant
- incident, andtheyalso3~73 maintainthecontainment pressurewithinthedesignvalue.Theminimumdieselfueloilinventory atalltimesismaintained toassuretheoperation ofbothdieselscarryingdesignloadofalltheengineered safeguards equipment foratleast40hours.-Commercial oilsuppliesandtruckingfacilities existtoassuredeliveries within8hours.Atleastone150ampbatterychargerortwo75ampbatterychargersshallbein.serviceforeachbatterysothatthebatteries willtalwaysbeatfullcharge.Thisensuresthatadequatedcpowerwillbeavailable.
Theplantcanbesafelyshutdownwithouttheuseofoffsitepowersinceallvitalloads(sa'fetysystems,instruments etc.)canbesuppliedfromtheemergency dieselgenerators.
Thetwodieselgenerators, eachcapableofsupplying safeguards loads,andthestationauxiliary transformer providethreeseparatesourcesofpowersupplysystemmeetsthesinglefailurecriteriarequiredofsafetysystems.(2)\Refernces:
(1)FSAR-(2)FSAR-Section-8.2.1 Appendix8Asjpl3.7-4 Attachment.
BTechnical Specification 3.7.1epresently requiresthatonlyonebatterycharger(whichhasa150ampcapacity) needstobeoperablewhilethereactoriscritical.
Thetotalnormald.c.loadispresently about170amps.Twoadditional batterychargers, eachwitha75ampchargingcapacity, havebeeninstalled.
Withallbatterychargersoperational andintheirnormalconfiguration, thereisatotalbatterychargercapacityof225ampsperbattery.Intheeventeitherofthe150ampbatterychargersbecomesinoperable, manualtransferofone75ampbatterychargerwillresultinabatterychargercapacitytoeachbatteryof150amps.Thisconfiguration andcapacityisconsistent.
withtheguidanceprovidedinRegulatory Guides1.6and1.32.Regulatory Guide1.6,Rev.0,positionD.3,statesthat"eachd.c.loadgroupshouldbeenergized byabatteryandbatterycharger.Thebattery-chargercombination shouldhavenoautomatic connection toanyotherredundant d.c.loadgroup."Thisguidanceissatisfied byhavingonlymanualconnection betweend.c.loadgroups.Regulatory
~P'Guide1.32,Rev.2,SectionC.l.b,statesthat"...thecapacityofthebatterychargersupplyshouldbebasedonthelargestcombined+emandsofthevarioussteadystatesloadsandthechargingcapacitytorestorethebatteryfromthedesignminimumchargestatetothefullychargedstate,irrespective ofthestatusoftheplantduringwhichthesedemandsoccur."
'Thenormalcontinuous loadoneachd.c.systemisapproxi-mately85amps.TheshutdownloadsthatarerequiredintheeventofalossofoffsitepowerarelistedinFSARTable8.2-.2.Theonlysteadystate(8hour)loadlisted,otherthanthein-verter,whichoperatebothduringnormaloperation andforsafeplantshutdown, istheTurbine-Driven Auxiliary Feedwater PumpDCOilPump.Thispumprepresents anadditional potential 22amploadonBattery1B.Thelargestpossiblecombinedload-couldthusoccurduringaplantshutdownfollowing lossofoffsitepower,whenallnormalloadcontinued operating, andtheturbine-drivenauxiliary feedwater pumpwasalsoengaged.Thiscombinedloadof85ampsplus22amps,foratotalof107amps,ismuch'-lowerthanthecapacityofthe150ampbatterychargers.
Itistherefore apparentthatthebatterychargersizingcriteriaofRegulatory Guide1.3.2,andIEEE308-1974, Section5.3.4areeasilymet.Ifthebatterychargerforoned.c.systemwerefoundtobeinoperable, itwouldbepossibleinmostcasestoeffectrepairsandrestorethesystemtooperability withinarelatively shortrtime.Thisconfiguration wouldnotnegatetheabilityofthed.c.Isystemtoperformitsfunction, butitwouldreducetheredundancy providedinthereactordesi.'gn, andtherebylimittheabilitytotolerateadditional equipment failures.
(Although it'should benotedthatthebatteries bythemselves couldcarryallshutdownlloadsfor-8hours).Theredundant d.c.systemwouldbethoroughly checkedtoensureitsoperability.
Ifitdeveloped thatthe
~~~inoperable d.c.systemcouldnotbemadeoperablewithintwohours,thereactorwouldbeplacedinthehotshutdowncondition, toprovideforreduction ofdecayheatfromthefuel.Ifafteranothersixhoursthemalfunction werenotcorrected, thereactorwouldbeplacedinacoldshutdowncondition within30hours,usingnormalshutdownandcooldownprocedures.
Thesetimeperiodsareconsistent withtheguidanceprovidedinRegulatory Guide1.93,Rev.0,"Availability ofElectricPowerSources",
Regulatory Position5.rP'
~~IAtt'achme'nt C.TheproposedAmendment totheProvisional Operating Licensehasbeenevaluated anddetermined tofallwithinthedefinition ofClassIIIof10CFRSection170.22therebyrequiring afeeof$4,000.Theproposedamendment simplyclarifies asinglesafetyissue,batterychargercapacity.
Theissuehasbeenclearlyidentified byNRCregulatory guides.C P~t