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| {{#Wiki_filter:SAFETYLIMITLIMITINGSAFETYSYSTEMSETTINGc.Theneutronfluxshallnotexceeditsscramsettingforlongerthan1.5secondsasindicatedbytheprocesscomputer.Whentheprocesscomputerisoutofservice,asafetylimitviolationshallbeassumediftheneutronfluxexceedsthescramsettingandcontrolrodscramdoesnotoccur.ToensurethattheSafetyLimitestablishedinSpecifications2.1.laand2.l.lbisnotexceeded,eachrequiredscramshallbeinitiatedbyitsexpectedscramsignal.TheSafetyLimitshallbeassumedtobeexceededwhenscramisaccomplishedbyameansotherthantheexpectedscramsignal.d.e.Thereactorwaterlowlevelscramtripsettingshallbenolowerthan-12inches(53inchesindicatorscale)>elativetotheminimumnormalwaterlevel(302'9").Thereactorwaterlow-lowlevelsettingforcoresprayinitiationshallbenolessthan-5feet(5inchesindicatorscale)relativetotheminimumnormalwaterlevel(Elevation302'9").f.~TheflowbiasedAPRMrodblocktripsettingsshallbelessthanorequaltothatshowninFigure2.l.l.d.Wheneverthereactorisintheshutdownconditionwithirradiatedfuelinthereactorvessel,thewaterlevelshallnotbemorethan6feet,3inches(-10inchesindicatorscale)belowminimumnormalwaterlevel(Elevation302'9")exceptasspecifedin"e"below.e.Forthepurposeofperformingmajormaintenance(nottoexceed12weeksinduration)onthereactorvessel;thereactorwaterlevelmaybelowered9'elowtheminimumnormalwaterleve)(Elevation302'9").Wheneverthereactor.waterlevelistobeloweredbelowthelow-low-lowlevelsetpointredundantinstrumentationwillbeprovidedtomonitorthereactorwaterlevel.840406032i840402PDRADOCK05000220PPDR | | {{#Wiki_filter:SAFETYLIMITLIMITINGSAFETYSYSTEMSETTINGc.Theneutronfluxshallnotexceeditsscramsettingforlongerthan1.5secondsasindicated bytheprocesscomputer. |
| | Whentheprocesscomputerisoutofservice,asafetylimitviolation shallbeassumediftheneutronfluxexceedsthescramsettingandcontrolrodscramdoesnotoccur.ToensurethattheSafetyLimitestablished inSpecifications 2.1.laand2.l.lbisnotexceeded, eachrequiredscramshallbeinitiated byitsexpectedscramsignal.TheSafetyLimitshallbeassumedtobeexceededwhenscramisaccomplished byameansotherthantheexpectedscramsignal.d.e.Thereactorwaterlowlevelscramtripsettingshallbenolowerthan-12inches(53inchesindicator scale)>elativetotheminimumnormalwaterlevel(302'9"). |
| | Thereactorwaterlow-lowlevelsettingforcoresprayinitiation shallbenolessthan-5feet(5inchesindicator scale)relativetotheminimumnormalwaterlevel(Elevation 302'9").f.~TheflowbiasedAPRMrodblocktripsettingsshallbelessthanorequaltothatshowninFigure2.l.l.d.Wheneverthereactorisintheshutdowncondition withirradiated fuelinthereactorvessel,thewaterlevelshallnotbemorethan6feet,3inches(-10inchesindicator scale)belowminimumnormalwaterlevel(Elevation 302'9")exceptasspecifedin"e"below.e.Forthepurposeofperforming majormaintenance (nottoexceed12weeksinduration) onthereactorvessel;thereactorwaterlevelmaybelowered9'elowtheminimumnormalwaterleve)(Elevation 302'9").Wheneverthereactor.waterlevelistobeloweredbelowthelow-low-low levelsetpointredundant instrumentation willbeprovidedtomonitorthereactorwaterlevel.840406032i 840402PDRADOCK05000220PPDR |
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| BASESFOR2.1.1FUELCLADDING-SAFETYLIMITDuringperiodswhenthereactorisshutdown,considerationmustalsobegiventowaterlevelrequirements,duetotheeffectofdecayheat.Ifreactorwaterlevelshoulddropbelowthetopoftheactivefuelduringthistime,theabilitytocoolthecoreisreduced.Thisreductionincorecoolingcapabilitycouldleadtoelevatedcladdingtemperaturesandcladperforation.Thecorewillbecooledsufficientlytopreventcladmeltingshouldthewaterlevelbereducedtotwo-thirdsofthecoreheight.Thelowestpointatwhichthereactorwaterlevelcannormallybemonitoredisapproximately7feet11inchesbelowminimumnormalwaterlevelor4feet8inchesabovethetopoftheactivefuel.Thisisthelocationofthereactorvesseltapforthelow-low-lowwaterlevelinstrumentation.Theactuallow-low-lowwaterleveltrippointis6feet3inches(-10inchesindicatorscale)belowminimumnorma)waterlevel(Elevation302'-9").The20inchdifferenceresultedfromanevaluationoftherecomnendationscontainedinGeneralElectricServiceInformationLetter299"HighDrywellTemperatureEffectonReactorVesselWaterLevelInstrumentation."Thelow-low-lowwaterleveltrippointwasraised20inchestoconservativelyaccountforpossibledifferencesinactualtoindicatedwaterlevelduetopotentiallyhighdrywelltemperatures.Thesafetylimithasbeenestablishedheretoprovideapointwhichcanbemonitoredandalsocanprovideadequatemargin.However,forperformingmajormaintenanceasspecifiedinSpecification2.1.l.e,redundantinstrumentationwillbeprovidedformonitoringreactorwaterlevelbelowthelow-low-lowwaterlevelsetpoint.(Forexample,byinstallingtemporaryinstrumentlinesandreferencepointstoredundantleveltransmitterssothatthereactorwaterlevelmayhemonitoredovertherequiredrange.)Inadditionwrittenprocedures,whichidentifyallthevalveswhichhavethepotentialofloweringthewaterlevelinadvertently,areestablishedtopreventtheiroperationduringthemajormaintenancewhichrequiresthewaterleveltohebelowthelow-lowlevelsetpoint.Thethermalpowertransientresultingwhenascramisaccomplishedotherthanbytheexpectedscramsignal(e.g.,scramfromneutronfluxfollowingclosureofthemainturbinestopvalves)doesnotnecessarilycausefueldamage.However,forthisspecificationasafetylimitviolationwi]lbeassumedwhenascramisonlyaccomplishedbymeansofabackupfeatureoftheplantdesign.Theconceptofnqtapproachingasafetylimitprovidedscramsignalsareoperableissupportedbytheextensiveplantsafetyanalysis.t13 | | BASESFOR2.1.1FUELCLADDING-SAFETYLIMITDuringperiodswhenthereactorisshutdown,consideration mustalsobegiventowaterlevelrequirements, duetotheeffectofdecayheat.Ifreactorwaterlevelshoulddropbelowthetopoftheactivefuelduringthistime,theabilitytocoolthecoreisreduced.Thisreduction incorecoolingcapability couldleadtoelevatedcladdingtemperatures andcladperforation. |
| | Thecorewillbecooledsufficiently topreventcladmeltingshouldthewaterlevelbereducedtotwo-thirds ofthecoreheight.Thelowestpointatwhichthereactorwaterlevelcannormallybemonitored isapproximately 7feet11inchesbelowminimumnormalwaterlevelor4feet8inchesabovethetopoftheactivefuel.Thisisthelocationofthereactorvesseltapforthelow-low-low waterlevelinstrumentation. |
| | Theactuallow-low-low waterleveltrippointis6feet3inches(-10inchesindicator scale)belowminimumnorma)waterlevel(Elevation 302'-9"). |
| | The20inchdifference resultedfromanevaluation oftherecomnendations contained inGeneralElectricServiceInformation Letter299"HighDrywellTemperature EffectonReactorVesselWaterLevelInstrumentation." |
| | Thelow-low-low waterleveltrippointwasraised20inchestoconservatively accountforpossibledifferences inactualtoindicated waterlevelduetopotentially highdrywelltemperatures. |
| | Thesafetylimithasbeenestablished heretoprovideapointwhichcanbemonitored andalsocanprovideadequatemargin.However,forperforming majormaintenance asspecified inSpecification 2.1.l.e,redundant instrumentation willbeprovidedformonitoring reactorwaterlevelbelowthelow-low-low waterlevelsetpoint.(Forexample,byinstalling temporary instrument linesandreference pointstoredundant leveltransmitters sothatthereactorwaterlevelmayhemonitored overtherequiredrange.)Inadditionwrittenprocedures, whichidentifyallthevalveswhichhavethepotential ofloweringthewaterlevelinadvertently, areestablished topreventtheiroperation duringthemajormaintenance whichrequiresthewaterleveltohebelowthelow-lowlevelsetpoint.Thethermalpowertransient resulting whenascramisaccomplished otherthanbytheexpectedscramsignal(e.g.,scramfromneutronfluxfollowing closureofthemainturbinestopvalves)doesnotnecessarily causefueldamage.However,forthisspecification asafetylimitviolation wi]lbeassumedwhenascramisonlyaccomplished bymeansofabackupfeatureoftheplantdesign.Theconceptofnqtapproaching asafetylimitprovidedscramsignalsareoperableissupported bytheextensive plantsafetyanalysis. |
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| REFERENCESFORBASES2.1.1AND2.1.2FUELCLADDING(1)GeneralElectricBHRThermalAnalysisBasis(GETAB)Data,CorrelationandDesignApplication,NEDO-10958andNEDE-10958.(2)Linford,R.B.,"AnalyticalMethodsofPlantTransientEvaluationsfortheGeneralElectricBoilingplaterReactor,"NED0-10801,February1973.(3)FSAR,VolumeII,AppendixE.(4)FSAR,SecondSupplement.(5)FSAR,VolumeII,AppendixE.(6)FSAR,SecondSupplement.(7)Letters,PeterA.Horris,DirectorofReactorLicensing,USAEC,toJohnE.Logan,Vice-President,JerseyCentralPowerandLightCompany,datedNovember22,1967andJanuary9,1968.(8)TechnicalSupplementtoPetitiontoIncreasePowerLevel,datedApril1970.(9)Letter,T.J.Brosnan,NiagaraMohawkPowerCorporation,toPeterA.Morris,DivisionofReactorLicensing,USAEC,datedFebruary28,1972.(10)Letter,PhilipD.Raymond,NiagaraMohawkPowerCorporation,toA.Giambusso,USAEC,datedOctober15,1973.-(ll)NineMilePointNuclearPowerStationUnit1LoadLineLimitAnalysis,NEDO24012,May,1977.(12)LicensingTopicalReportGeneralElectricBoilingMaterReactorGenericReloadFuelApplication,NEOE-24011-P-A,August,1978.(13)NineMilePointNuclearPowerStationUJ)it1,ExtendedLoadLineLimitAnalysis,LicenseA)))end)ventSubmittal(Cycle6),NED0-24185,April1979.(14)GeneralElectricSIL299"HighOryuel1TemperatureEffectonReactorVesselWaterLevelInstrusientation."20
| | REFERENCES FORBASES2.1.1AND2.1.2FUELCLADDING(1)GeneralElectricBHRThermalAnalysisBasis(GETAB)Data,Correlation andDesignApplication, NEDO-10958 andNEDE-10958. |
| | (2)Linford,R.B.,"Analytical MethodsofPlantTransient Evaluations fortheGeneralElectricBoilingplaterReactor," |
| | NED0-10801, February1973.(3)FSAR,VolumeII,AppendixE.(4)FSAR,SecondSupplement. |
| | (5)FSAR,VolumeII,AppendixE.(6)FSAR,SecondSupplement. |
| | (7)Letters,PeterA.Horris,DirectorofReactorLicensing, USAEC,toJohnE.Logan,Vice-President, JerseyCentralPowerandLightCompany,datedNovember22,1967andJanuary9,1968.(8)Technical Supplement toPetitiontoIncreasePowerLevel,datedApril1970.(9)Letter,T.J.Brosnan,NiagaraMohawkPowerCorporation, toPeterA.Morris,DivisionofReactorLicensing, USAEC,datedFebruary28,1972.(10)Letter,PhilipD.Raymond,NiagaraMohawkPowerCorporation, toA.Giambusso, USAEC,datedOctober15,1973.-(ll)NineMilePointNuclearPowerStationUnit1LoadLineLimitAnalysis, NEDO24012,May,1977.(12)Licensing TopicalReportGeneralElectricBoilingMaterReactorGenericReloadFuelApplication, NEOE-24011-P-A, August,1978.(13)NineMilePointNuclearPowerStationUJ)it1,ExtendedLoadLineLimitAnalysis, LicenseA)))end)vent Submittal (Cycle6),NED0-24185, April1979.(14)GeneralElectricSIL299"HighOryuel1Temperature EffectonReactorVesselWaterLevelInstrusientation." |
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| LIMITINGCONDITIONFOROPERATIONSURVEILLANCEREQUIREMENTc~Ifaredundantcomponentineachofthecorespraysystemsbecomesinoperable,bothsystemsshallbeconsideredoperableprovidedthatthe.componentisreturnedtoanoperableconditionwithin7daysandtheadditionalsurveillancerequiredisperformed.d.Ifacorespraysystembecomesinoperableandallthecomponentsareoperableintheothersystem,thereactormayremaininoperationforaperiodnottoexceed7days.checkcalibratetestOnce/dayOnce/3monthsOnce/3monthsd.Coresprayheader<Pinstrumentatione.IfSpecificationsa,b,canddarenotmet,anormalorderlyshutdownshallbeinitiatedwithinonehourandthereactorshallbeinthecoldshutdownconditionwithintenhours.Ifbothcorespraysystemsbecomeinoperablethereactorshallbeinthecoldshutdownconditionwithintenhoursandnowork(exceptasspecifiedin"f"and"h"below)shallbeperformedonthereactororitsconnectedsystemswhichcouldresultinloweringthereactorwaterleveltomorethansixfeet,threeinchesbelowminimumnormalwaterlevel(-10inchesindicatorscale).e.SurveillancewithInoperableComponentsllhenacomponentorsystembecomesinoperableitsredundantcomponentorsystemshallbedemonstratedtobeoperableimmediatelyanddailythereafter.f.Surveillanceduringcontrolrod'drivemaintenancewhichissimultaneouswiththesuppressionchamberunwateredshallincludeatleasthourlychecksthattheconditionslistedin3.1.4faremet.
| | LIMITINGCONDITION FOROPERATION SURVEILLANCE REQUIREMENT c~Ifaredundant component ineachofthecorespraysystemsbecomesinoperable, bothsystemsshallbeconsidered operableprovidedthatthe.component isreturnedtoanoperablecondition within7daysandtheadditional surveillance requiredisperformed. |
| | d.Ifacorespraysystembecomesinoperable andallthecomponents areoperableintheothersystem,thereactormayremaininoperation foraperiodnottoexceed7days.checkcalibrate testOnce/dayOnce/3monthsOnce/3monthsd.Coresprayheader<Pinstrumentation e.IfSpecifications a,b,canddarenotmet,anormalorderlyshutdownshallbeinitiated withinonehourandthereactorshallbeinthecoldshutdowncondition withintenhours.Ifbothcorespraysystemsbecomeinoperable thereactorshallbeinthecoldshutdowncondition withintenhoursandnowork(exceptasspecified in"f"and"h"below)shallbeperformed onthereactororitsconnected systemswhichcouldresultinloweringthereactorwaterleveltomorethansixfeet,threeinchesbelowminimumnormalwaterlevel(-10inchesindicator scale).e.Surveillance withInoperable Components llhenacomponent orsystembecomesinoperable itsredundant component orsystemshallbedemonstrated tobeoperableimmediately anddailythereafter. |
| | f.Surveillance duringcontrolrod'drivemaintenance whichissimultaneous withthesuppression chamberunwatered shallincludeatleasthourlychecksthattheconditions listedin3.1.4faremet. |
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| LIMITINGCONDITIONFOROPERATIONSURVEILLANCEREQUIREf1ENTh.Forthepurposeofperformingmajormaintenance(nottoexceed12weeksinduration)onthereactorvessel,thereactorwaterlevelmaybeloweredto9'elowtheminimumnormalwaterlevel(elevation302'9").Wheneverthereactorwaterlevelistobeloweredbelowthelow-.low-lowlevelsetpointredundantisntrumentationwillbeprovidedtomonitorthereactorwaterlevelandwrittenprocedureswillbedevelopedandfollowedwheneverthereactorwaterlevelisloweredbelowthelow-lowlevelsetpoint.Theprocedureswilldefinethevalvesthatwillbeusedtolowerthevesselwaterlevel.Allothervavesthathavethepotentialofloweringthevesselwaterlevelwillbeidentifiedbyvalvenumberintheproceduresandthesevalveswillberedtaggedtoprecludetheiroperationduringthemajormaintenancewiththewaterlevelbelowthelow-lowlevelsetpoint.Duringtheperiodofmajormaintenancerequiringloweringthewaterleveltomorethan6feet,3inchesbelowminimumnormalwaterlevel(-10inchesindicatorscale),eitherbothCoreSpraySystemsmustbeoperableor,ifoneCoreSpraySystemisinoperablebecauseofthemaintenance,alloftheredundantcomponentsoftheotherCoreSpraySystemmustbeoperable.53a
| | LIMITINGCONDITION FOROPERATION SURVEILLANCE REQUIREf1ENT h.Forthepurposeofperforming majormaintenance (nottoexceed12weeksinduration) onthereactorvessel,thereactorwaterlevelmaybeloweredto9'elowtheminimumnormalwaterlevel(elevation 302'9").Wheneverthereactorwaterlevelistobeloweredbelowthelow-.low-low levelsetpointredundant isntrumentation willbeprovidedtomonitorthereactorwaterlevelandwrittenprocedures willbedeveloped andfollowedwheneverthereactorwaterlevelisloweredbelowthelow-lowlevelsetpoint.Theprocedures willdefinethevalvesthatwillbeusedtolowerthevesselwaterlevel.Allothervavesthathavethepotential ofloweringthevesselwaterlevelwillbeidentified byvalvenumberintheprocedures andthesevalveswillberedtaggedtoprecludetheiroperation duringthemajormaintenance withthewaterlevelbelowthelow-lowlevelsetpoint.Duringtheperiodofmajormaintenance requiring loweringthewaterleveltomorethan6feet,3inchesbelowminimumnormalwaterlevel(-10inchesindicator scale),eitherbothCoreSpraySystemsmustbeoperableor,ifoneCoreSpraySystemisinoperable becauseofthemaintenance, alloftheredundant components oftheotherCoreSpraySystemmustbeoperable. |
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| BASESFOR3.1.5AND4.1.5SOLENOID-ACTUATEDPRESSURERELIEFVALVESPressureBlowdownIntheeventofasmalllinebreak,substantialcoolantlosscouldoccurfromthereactorvesselwhileitwasstilIatrelativelyhighpressures.Apressureblowdownsystemisprovidedwhichinconjunctionwiththecorespraysystemwillpreventsignificantfueldamageforallsizedlinebreaks(AppendixE-11.2.0*).Operationofthreesolenoid-actuatedpressurereliefvalvesissufficienttodepressurizetheprimarysystemto110psigwhichwi11permitfullflowofthecorespraysystemwithinrequiredtimelimits(AppendixE-11.2~).Requiring-'allsixofthereliefvalvestobeoperable,therefore,providestwicetheminimumnumberrequired.Priortoorfollowingrefuelingatlowreactorpressure,eachv'alvewillbe<aanuallyopenedtoverifyvalveoperability.Themalfunctionanalysis(SectionII.XV,"Technica'ISupplementtoPetitiontoIncreasePowerLevel,"<late<iApril1970).demonstratesthatnoseriousconsequencesresultifonevalvefailstoclosesincetheresultingblowdowniswell.withindesignlimits.Intheeventofsmalllinebreak,considerabletimeisavailablefortheoperatortopermitcoresprayoperationbymanuallydepressurizingthevesselusingthesolenoid-actuatedvalves.However,toensurethatthedepressurizationwillbeaccomplished,automaticfeaturesareprovided.Thereliefvalvesshallbecapableofautomaticinitiationfromsimultaneouslow-low-lowwaterlevel(6feet,3inchesbelowminimumnormalwaterlevelatElevation302'",-10inchesindicatorscale)andhighcontainmentpressure(3.5psig).ThesystemresponsetosmallbreaksrequiringdepressurizationisdiscussedinSectionVII-.A.3.3*andthetimeavailabletotakeoperatoractionissummarizedinTableVII-1*.AdditionalinformationisincludedintheanswerstoguestionsIII-1andIII-5oftheFirstSupplement.~Steamfromthereactorvesselisdischargedtothesuppressionchamberduringvalvetesting.Conductingthetestswiththereactoratlowpressuresuchasjustpriortoorjustafterrefuelingminimizesthestressonthereactorcoo1antsystern.aThetestintervalofonceperoperatingcycleresultsinasystemfailureprobabilityof7.0x10-7(FifthSupplement,p.115)andisconsistentwithpracticalconsideration.*FSAR59E | | BASESFOR3.1.5AND4.1.5SOLENOID-ACTUATED PRESSURERELIEFVALVESPressureBlowdownIntheeventofasmalllinebreak,substantial coolantlosscouldoccurfromthereactorvesselwhileitwasstilIatrelatively highpressures. |
| | Apressureblowdownsystemisprovidedwhichinconjunction withthecorespraysystemwillpreventsignificant fueldamageforallsizedlinebreaks(Appendix E-11.2.0*). |
| | Operation ofthreesolenoid-actuated pressurereliefvalvesissufficient todepressurize theprimarysystemto110psigwhichwi11permitfullflowofthecorespraysystemwithinrequiredtimelimits(Appendix E-11.2~). |
| | Requiring |
| | -'allsixofthereliefvalvestobeoperable, therefore, providestwicetheminimumnumberrequired. |
| | Priortoorfollowing refueling atlowreactorpressure, eachv'alvewillbe<aanually openedtoverifyvalveoperability. |
| | Themalfunction analysis(SectionII.XV,"Technica'I Supplement toPetitiontoIncreasePowerLevel,"<late<iApril1970).demonstrates thatnoseriousconsequences resultifonevalvefailstoclosesincetheresulting blowdowniswell.withindesignlimits.Intheeventofsmalllinebreak,considerable timeisavailable fortheoperatortopermitcoresprayoperation bymanuallydepressurizing thevesselusingthesolenoid-actuated valves.However,toensurethatthedepressurization willbeaccomplished, automatic featuresareprovided. |
| | Thereliefvalvesshallbecapableofautomatic initiation fromsimultaneous low-low-low waterlevel(6feet,3inchesbelowminimumnormalwaterlevelatElevation 302'",-10inchesindicator scale)andhighcontainment pressure(3.5psig).Thesystemresponsetosmallbreaksrequiring depressurization isdiscussed inSectionVII-.A.3.3* |
| | andthetimeavailable totakeoperatoractionissummarized inTableVII-1*.Additional information isincludedintheanswerstoguestions III-1andIII-5oftheFirstSupplement. |
| | ~Steamfromthereactorvesselisdischarged tothesuppression chamberduringvalvetesting.Conducting thetestswiththereactoratlowpressuresuchasjustpriortoorjustafterrefueling minimizes thestressonthereactorcoo1antsystern.aThetestintervalofonceperoperating cycleresultsinasystemfailureprobability of7.0x10-7(FifthSupplement, p.115)andisconsistent withpractical consideration. |
| | *FSAR59E |
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| LIMITINGCONDITIONFOROPERATIONSURVEILLANCERE(UIREtiENTc.Ifaredundantcomponentineachofthecontainmentspraysystemsortheirassociatedrawwatersystemsbecomeinoperable,bothsystemsshallbeconsideredoperableprovidedthatthecomponentisreturnedtoanoperableconditionwithin7daysandthattheadditionalsurveillancerequiredisperformed.C.RawWaterCoolingPumpsAtleastonceperquartermanualstartupandoperabilityoftherawwatercoolingpumpsshallbedemonstrated.d.Ifacontainmentspraysystemoritsassociatedrawwatersystembecomesinoperableandallthecomponentsareoperableintheothersystems,thereactormayremaininoperationforaperiodnottoexceed7days.d.SurveillancewithInoperableComponents,/henacomponentorsystembecomesinoperableitsredundantcomponentorsystemshallbedemonstratedtobeoperableimmediatelyanddailythereafter.e.IfSpecifirations"a"or"b"arenotmet,shutdownshallbeginwithinonehourandthereactorcoolantshallbebelow215Fwithintenhours.Ifbothcontainmentspraysystemsbecomeinoperablethereactorshallbeinthecoldshutdownconditionwithintenhoursandnowork(exceptasspecifiedin"f"below)shallbeperformedonthereactorwhichcouldresultinloweringthereactorwaterleveltomorethansixfeet,threeinches(-10inchesindicatorscale)belowminimumnormalwaterlevel:(Elevation302'").e.Surveillanceduringcontrolroddrivemaintenancewhichissimultaneouswiththesuppressionchamberunwateredshallincludeatleasthourlychecksthattheconditionslistedin3.3.7.faremet.159QJEC(DE
| | LIMITINGCONDITION FOROPERATION SURVEILLANCE RE(UIREtiENT c.Ifaredundant component ineachofthecontainment spraysystemsortheirassociated rawwatersystemsbecomeinoperable, bothsystemsshallbeconsidered operableprovidedthatthecomponent isreturnedtoanoperablecondition within7daysandthattheadditional surveillance requiredisperformed. |
| | C.RawWaterCoolingPumpsAtleastonceperquartermanualstartupandoperability oftherawwatercoolingpumpsshallbedemonstrated. |
| | d.Ifacontainment spraysystemoritsassociated rawwatersystembecomesinoperable andallthecomponents areoperableintheothersystems,thereactormayremaininoperation foraperiodnottoexceed7days.d.Surveillance withInoperable Components |
| | ,/henacomponent orsystembecomesinoperable itsredundant component orsystemshallbedemonstrated tobeoperableimmediately anddailythereafter. |
| | e.IfSpecifirations "a"or"b"arenotmet,shutdownshallbeginwithinonehourandthereactorcoolantshallbebelow215Fwithintenhours.Ifbothcontainment spraysystemsbecomeinoperable thereactorshallbeinthecoldshutdowncondition withintenhoursandnowork(exceptasspecified in"f"below)shallbeperformed onthereactorwhichcouldresultinloweringthereactorwaterleveltomorethansixfeet,threeinches(-10inchesindicator scale)belowminimumnormalwaterlevel:(Elevation 302'").e.Surveillance duringcontrolroddrivemaintenance whichissimultaneous withthesuppression chamberunwatered shallincludeatleasthourlychecksthattheconditions listedin3.3.7.faremet.159QJEC(DE |
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| Tab1e3.6.2fINSTRUMENTATIONTHATINITIATESAUTODEPRESSURIZATIONLiiigiiO>>iParameterMinimumNo.ofTrippedorOperable~TriSystems4MinimumNo.ofOperableInstrumentChannelsperOperableT~riSystemSet-PointReactorModeSwitchPositioninWhichFunctionMustBeOperableINITIATION(1)a.b.Low-Low-LowReactorWaterLevelHighOrywellPressure2(a)2(a)2(a)~-10inches*(Indicatorscale)<3.5psig(b)(b)(b)x(b)x*greaterthan(>)meanslessnegative213}} | | Tab1e3.6.2fINSTRUMENTATION THATINITIATES AUTODEPRESSUR IZATIONLiiigiiO>>iParameter MinimumNo.ofTrippedorOperable~TriSystems4MinimumNo.ofOperableInstrument ChannelsperOperableT~riSystemSet-Point ReactorModeSwitchPositioninWhichFunctionMustBeOperableINITIATION (1)a.b.Low-Low-Low ReactorWaterLevelHighOrywellPressure2(a)2(a)2(a)~-10inches*(Indicator scale)<3.5psig(b)(b)(b)x(b)x*greaterthan(>)meanslessnegative213}} |
Revised Pages to Tech Specs Re Triple Low Reactor Water Level Setpoint.Changes Involve Replacing 147.1 Inch Indicator Scale w/-10 Inch Indicator Scale| ML18038A666 |
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Nine Mile Point  |
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04/02/1984 |
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NIAGARA MOHAWK POWER CORP. |
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| ML17054A598 |
List: |
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| References |
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| NUDOCS 8404060321 |
| Download: ML18038A666 (16) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17059C7911999-09-30030 September 1999
Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS
ML20211P5931999-09-10010 September 1999
Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc
ML20211H2231999-08-26026 August 1999
Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML20206P2661998-12-30030 December 1998
Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys
ML20197K1041998-12-0404 December 1998
Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles
ML20196H0671998-11-30030 November 1998
Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101
ML20196D2081998-11-24024 November 1998
Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate
ML20154R1101998-10-16016 October 1998
Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open
ML20217N7911998-04-24024 April 1998
Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49
ML20202G3751998-02-0505 February 1998
Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405
ML20197H3371997-12-15015 December 1997
Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation
ML20211M5231997-10-0707 October 1997
Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts
ML20217G9011997-07-31031 July 1997
Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation
ML20148A7751997-04-30030 April 1997
Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii
ML20116D8121996-07-26026 July 1996
Proposed Tech Specs Re Option B of App J to 10CFR50
ML20115H1521996-07-12012 July 1996
Proposed Tech Specs Section 6.2.2.i Re App a
ML20117F9501996-05-15015 May 1996
Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation
ML20101F4281996-03-20020 March 1996
Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5
ML20101D7551996-03-15015 March 1996
Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool
ML20097D2391996-02-0707 February 1996
Proposed Tech Specs Re Administrative Controls
ML20100C1021996-01-25025 January 1996
Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation
ML20096G8401996-01-17017 January 1996
Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR
ML20094B5421995-10-25025 October 1995
Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level
ML20091Q9571995-08-28028 August 1995
Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity
ML20081E2491995-03-0909 March 1995
Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test
ML20077N1591995-01-0606 January 1995
Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks
ML20077N2071995-01-0606 January 1995
Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1
ML20078Q9241994-12-13013 December 1994
Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs
ML20077E1561994-12-0202 December 1994
Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid
ML20078J3781994-11-14014 November 1994
Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig
ML20078E0331994-10-28028 October 1994
Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position
ML20078B9841994-10-21021 October 1994
Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs
ML20073L8781994-10-0505 October 1994
Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation
ML20072U3491994-09-0202 September 1994
Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys
ML17059A4471994-09-0101 September 1994
Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases
ML20072P6211994-08-26026 August 1994
Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut
ML20071G2771994-07-0101 July 1994
Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2
ML20029D4001994-04-27027 April 1994
Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity
ML20058N3491993-12-14014 December 1993
Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves
ML20056G9391993-09-0202 September 1993
Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators
ML20056G1951993-08-27027 August 1993
Proposed Tech Specs,Revising TS 4.8.1.1.2.e, AC Sources - Operating & Adding TS 4.8.1.1.2.f
ML20044G6261993-05-26026 May 1993
TS Section 6.8 Re Review & Approval Process for Procedure Changes
ML20044F7421993-05-21021 May 1993
Proposed Tech Specs Pages 2-3,3/4 2-2,3/4 3-60,3/4 3-62, 3/4 3-63,3/4 3-64,3/4 3-65 & 6-22 & Bases Page B3/4 2-1
ML20044F3041993-05-19019 May 1993
Proposed Tech Specs Sections 3.4.3.1 & 3.4.3.2 Re Generic Ltr 88-01,drywell Leak Detection Requirements
ML17058B7751993-05-14014 May 1993
Proposed Tech Specs,Reflecting Editorial Changes, Administrative Corrections & Retyping of TS
ML17056C3281993-03-29029 March 1993
Proposed TS Pages 139 & 140 Re LCO SR for Type a & Local Leak Rate Type B & C Tests
ML20012G5441993-02-27027 February 1993
Proposed TS Sections 1.0, Definitions & 3/4.3.6, Control Rod Block Instrumentation.
ML17056C2741993-02-18018 February 1993
Proposed TS Table 3.2.7 Re RCS Isolation Valves,Table 3.2.7.1 Re Primary Coolant Sys Pressure Isolation Valves & Table 3.3.4 Re Primary Containment Isolation Valves,Lines Entering Free Space of Containment
ML17056C2571993-02-12012 February 1993
Proposed,Revised TS Pages 204,204a,207,225a & 230 to Clarify Operator Actions in Event of Loss of Two Instrument Channels
ML20126H9941992-12-30030 December 1992
Proposed Tech Specs 3.4.3.1 & 3.4.3.2 Re RCS Leakage Detection Sys & Operational Leakage to Conform W/ Recommendations of Generic Ltr 88-01
1999-09-30
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17059C7911999-09-30030 September 1999
Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS
ML20211P5931999-09-10010 September 1999
Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc
ML20211H2231999-08-26026 August 1999
Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML18041A0731999-07-27027 July 1999
Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2.
ML20206P2661998-12-30030 December 1998
Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys
ML20197K1041998-12-0404 December 1998
Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles
ML20196H0671998-11-30030 November 1998
Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101
ML20196D2081998-11-24024 November 1998
Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate
ML20154R1101998-10-16016 October 1998
Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open
ML20217N7911998-04-24024 April 1998
Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49
ML20202G3751998-02-0505 February 1998
Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405
ML20197H3371997-12-15015 December 1997
Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation
ML20211M5231997-10-0707 October 1997
Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts
ML20217G9011997-07-31031 July 1997
Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation
ML20148A7751997-04-30030 April 1997
Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii
ML17059B2911996-09-0404 September 1996
NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan.
ML20116D8121996-07-26026 July 1996
Proposed Tech Specs Re Option B of App J to 10CFR50
ML20115H1521996-07-12012 July 1996
Proposed Tech Specs Section 6.2.2.i Re App a
ML20117F9501996-05-15015 May 1996
Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation
ML20101F4281996-03-20020 March 1996
Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5
ML20101D7551996-03-15015 March 1996
Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool
ML20097D2391996-02-0707 February 1996
Proposed Tech Specs Re Administrative Controls
ML20100C1021996-01-25025 January 1996
Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation
ML20096G8401996-01-17017 January 1996
Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR
ML20094B5421995-10-25025 October 1995
Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level
ML20091Q9571995-08-28028 August 1995
Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity
ML20081E2491995-03-0909 March 1995
Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test
ML17059B0221995-02-15015 February 1995
Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore.
ML17059B0211995-02-10010 February 1995
Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions.
ML17059B0201995-02-10010 February 1995
Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions.
ML17059A8881995-01-18018 January 1995
Rev 0 to Field Disposition Instruction 0245-90800, Shroud.
ML20077N1591995-01-0606 January 1995
Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks
ML20077N2071995-01-0606 January 1995
Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1
ML20078Q9241994-12-13013 December 1994
Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs
ML20077E1561994-12-0202 December 1994
Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid
ML20078J3781994-11-14014 November 1994
Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig
ML17059A5661994-11-0909 November 1994
Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys.
ML20078E0331994-10-28028 October 1994
Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position
ML20078B9841994-10-21021 October 1994
Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs
ML20073L8781994-10-0505 October 1994
Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation
ML20072U3491994-09-0202 September 1994
Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys
ML17059A4471994-09-0101 September 1994
Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases
ML20072P6211994-08-26026 August 1994
Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut
ML17059A4241994-07-0606 July 1994
Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML20071G2771994-07-0101 July 1994
Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2
ML20029D4001994-04-27027 April 1994
Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity
ML18040A2941993-12-17017 December 1993
Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML20058N3491993-12-14014 December 1993
Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves
ML17059A0971993-10-25025 October 1993
Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan.
ML20056G9391993-09-0202 September 1993
Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators
1999-09-30
[Table view] |
Text
SAFETYLIMITLIMITINGSAFETYSYSTEMSETTINGc.Theneutronfluxshallnotexceeditsscramsettingforlongerthan1.5secondsasindicated bytheprocesscomputer.
Whentheprocesscomputerisoutofservice,asafetylimitviolation shallbeassumediftheneutronfluxexceedsthescramsettingandcontrolrodscramdoesnotoccur.ToensurethattheSafetyLimitestablished inSpecifications 2.1.laand2.l.lbisnotexceeded, eachrequiredscramshallbeinitiated byitsexpectedscramsignal.TheSafetyLimitshallbeassumedtobeexceededwhenscramisaccomplished byameansotherthantheexpectedscramsignal.d.e.Thereactorwaterlowlevelscramtripsettingshallbenolowerthan-12inches(53inchesindicator scale)>elativetotheminimumnormalwaterlevel(302'9").
Thereactorwaterlow-lowlevelsettingforcoresprayinitiation shallbenolessthan-5feet(5inchesindicator scale)relativetotheminimumnormalwaterlevel(Elevation 302'9").f.~TheflowbiasedAPRMrodblocktripsettingsshallbelessthanorequaltothatshowninFigure2.l.l.d.Wheneverthereactorisintheshutdowncondition withirradiated fuelinthereactorvessel,thewaterlevelshallnotbemorethan6feet,3inches(-10inchesindicator scale)belowminimumnormalwaterlevel(Elevation 302'9")exceptasspecifedin"e"below.e.Forthepurposeofperforming majormaintenance (nottoexceed12weeksinduration) onthereactorvessel;thereactorwaterlevelmaybelowered9'elowtheminimumnormalwaterleve)(Elevation 302'9").Wheneverthereactor.waterlevelistobeloweredbelowthelow-low-low levelsetpointredundant instrumentation willbeprovidedtomonitorthereactorwaterlevel.840406032i 840402PDRADOCK05000220PPDR
\1~
BASESFOR2.1.1FUELCLADDING-SAFETYLIMITDuringperiodswhenthereactorisshutdown,consideration mustalsobegiventowaterlevelrequirements, duetotheeffectofdecayheat.Ifreactorwaterlevelshoulddropbelowthetopoftheactivefuelduringthistime,theabilitytocoolthecoreisreduced.Thisreduction incorecoolingcapability couldleadtoelevatedcladdingtemperatures andcladperforation.
Thecorewillbecooledsufficiently topreventcladmeltingshouldthewaterlevelbereducedtotwo-thirds ofthecoreheight.Thelowestpointatwhichthereactorwaterlevelcannormallybemonitored isapproximately 7feet11inchesbelowminimumnormalwaterlevelor4feet8inchesabovethetopoftheactivefuel.Thisisthelocationofthereactorvesseltapforthelow-low-low waterlevelinstrumentation.
Theactuallow-low-low waterleveltrippointis6feet3inches(-10inchesindicator scale)belowminimumnorma)waterlevel(Elevation 302'-9").
The20inchdifference resultedfromanevaluation oftherecomnendations contained inGeneralElectricServiceInformation Letter299"HighDrywellTemperature EffectonReactorVesselWaterLevelInstrumentation."
Thelow-low-low waterleveltrippointwasraised20inchestoconservatively accountforpossibledifferences inactualtoindicated waterlevelduetopotentially highdrywelltemperatures.
Thesafetylimithasbeenestablished heretoprovideapointwhichcanbemonitored andalsocanprovideadequatemargin.However,forperforming majormaintenance asspecified inSpecification 2.1.l.e,redundant instrumentation willbeprovidedformonitoring reactorwaterlevelbelowthelow-low-low waterlevelsetpoint.(Forexample,byinstalling temporary instrument linesandreference pointstoredundant leveltransmitters sothatthereactorwaterlevelmayhemonitored overtherequiredrange.)Inadditionwrittenprocedures, whichidentifyallthevalveswhichhavethepotential ofloweringthewaterlevelinadvertently, areestablished topreventtheiroperation duringthemajormaintenance whichrequiresthewaterleveltohebelowthelow-lowlevelsetpoint.Thethermalpowertransient resulting whenascramisaccomplished otherthanbytheexpectedscramsignal(e.g.,scramfromneutronfluxfollowing closureofthemainturbinestopvalves)doesnotnecessarily causefueldamage.However,forthisspecification asafetylimitviolation wi]lbeassumedwhenascramisonlyaccomplished bymeansofabackupfeatureoftheplantdesign.Theconceptofnqtapproaching asafetylimitprovidedscramsignalsareoperableissupported bytheextensive plantsafetyanalysis.
t13
REFERENCES FORBASES2.1.1AND2.1.2FUELCLADDING(1)GeneralElectricBHRThermalAnalysisBasis(GETAB)Data,Correlation andDesignApplication, NEDO-10958 andNEDE-10958.
(2)Linford,R.B.,"Analytical MethodsofPlantTransient Evaluations fortheGeneralElectricBoilingplaterReactor,"
NED0-10801, February1973.(3)FSAR,VolumeII,AppendixE.(4)FSAR,SecondSupplement.
(5)FSAR,VolumeII,AppendixE.(6)FSAR,SecondSupplement.
(7)Letters,PeterA.Horris,DirectorofReactorLicensing, USAEC,toJohnE.Logan,Vice-President, JerseyCentralPowerandLightCompany,datedNovember22,1967andJanuary9,1968.(8)Technical Supplement toPetitiontoIncreasePowerLevel,datedApril1970.(9)Letter,T.J.Brosnan,NiagaraMohawkPowerCorporation, toPeterA.Morris,DivisionofReactorLicensing, USAEC,datedFebruary28,1972.(10)Letter,PhilipD.Raymond,NiagaraMohawkPowerCorporation, toA.Giambusso, USAEC,datedOctober15,1973.-(ll)NineMilePointNuclearPowerStationUnit1LoadLineLimitAnalysis, NEDO24012,May,1977.(12)Licensing TopicalReportGeneralElectricBoilingMaterReactorGenericReloadFuelApplication, NEOE-24011-P-A, August,1978.(13)NineMilePointNuclearPowerStationUJ)it1,ExtendedLoadLineLimitAnalysis, LicenseA)))end)vent Submittal (Cycle6),NED0-24185, April1979.(14)GeneralElectricSIL299"HighOryuel1Temperature EffectonReactorVesselWaterLevelInstrusientation."
20
LIMITINGCONDITION FOROPERATION SURVEILLANCE REQUIREMENT c~Ifaredundant component ineachofthecorespraysystemsbecomesinoperable, bothsystemsshallbeconsidered operableprovidedthatthe.component isreturnedtoanoperablecondition within7daysandtheadditional surveillance requiredisperformed.
d.Ifacorespraysystembecomesinoperable andallthecomponents areoperableintheothersystem,thereactormayremaininoperation foraperiodnottoexceed7days.checkcalibrate testOnce/dayOnce/3monthsOnce/3monthsd.Coresprayheader<Pinstrumentation e.IfSpecifications a,b,canddarenotmet,anormalorderlyshutdownshallbeinitiated withinonehourandthereactorshallbeinthecoldshutdowncondition withintenhours.Ifbothcorespraysystemsbecomeinoperable thereactorshallbeinthecoldshutdowncondition withintenhoursandnowork(exceptasspecified in"f"and"h"below)shallbeperformed onthereactororitsconnected systemswhichcouldresultinloweringthereactorwaterleveltomorethansixfeet,threeinchesbelowminimumnormalwaterlevel(-10inchesindicator scale).e.Surveillance withInoperable Components llhenacomponent orsystembecomesinoperable itsredundant component orsystemshallbedemonstrated tobeoperableimmediately anddailythereafter.
f.Surveillance duringcontrolrod'drivemaintenance whichissimultaneous withthesuppression chamberunwatered shallincludeatleasthourlychecksthattheconditions listedin3.1.4faremet.
LIMITINGCONDITION FOROPERATION SURVEILLANCE REQUIREf1ENT h.Forthepurposeofperforming majormaintenance (nottoexceed12weeksinduration) onthereactorvessel,thereactorwaterlevelmaybeloweredto9'elowtheminimumnormalwaterlevel(elevation 302'9").Wheneverthereactorwaterlevelistobeloweredbelowthelow-.low-low levelsetpointredundant isntrumentation willbeprovidedtomonitorthereactorwaterlevelandwrittenprocedures willbedeveloped andfollowedwheneverthereactorwaterlevelisloweredbelowthelow-lowlevelsetpoint.Theprocedures willdefinethevalvesthatwillbeusedtolowerthevesselwaterlevel.Allothervavesthathavethepotential ofloweringthevesselwaterlevelwillbeidentified byvalvenumberintheprocedures andthesevalveswillberedtaggedtoprecludetheiroperation duringthemajormaintenance withthewaterlevelbelowthelow-lowlevelsetpoint.Duringtheperiodofmajormaintenance requiring loweringthewaterleveltomorethan6feet,3inchesbelowminimumnormalwaterlevel(-10inchesindicator scale),eitherbothCoreSpraySystemsmustbeoperableor,ifoneCoreSpraySystemisinoperable becauseofthemaintenance, alloftheredundant components oftheotherCoreSpraySystemmustbeoperable.
53a
BASESFOR3.1.5AND4.1.5SOLENOID-ACTUATED PRESSURERELIEFVALVESPressureBlowdownIntheeventofasmalllinebreak,substantial coolantlosscouldoccurfromthereactorvesselwhileitwasstilIatrelatively highpressures.
Apressureblowdownsystemisprovidedwhichinconjunction withthecorespraysystemwillpreventsignificant fueldamageforallsizedlinebreaks(Appendix E-11.2.0*).
Operation ofthreesolenoid-actuated pressurereliefvalvesissufficient todepressurize theprimarysystemto110psigwhichwi11permitfullflowofthecorespraysystemwithinrequiredtimelimits(Appendix E-11.2~).
Requiring
-'allsixofthereliefvalvestobeoperable, therefore, providestwicetheminimumnumberrequired.
Priortoorfollowing refueling atlowreactorpressure, eachv'alvewillbe<aanually openedtoverifyvalveoperability.
Themalfunction analysis(SectionII.XV,"Technica'I Supplement toPetitiontoIncreasePowerLevel,"<late<iApril1970).demonstrates thatnoseriousconsequences resultifonevalvefailstoclosesincetheresulting blowdowniswell.withindesignlimits.Intheeventofsmalllinebreak,considerable timeisavailable fortheoperatortopermitcoresprayoperation bymanuallydepressurizing thevesselusingthesolenoid-actuated valves.However,toensurethatthedepressurization willbeaccomplished, automatic featuresareprovided.
Thereliefvalvesshallbecapableofautomatic initiation fromsimultaneous low-low-low waterlevel(6feet,3inchesbelowminimumnormalwaterlevelatElevation 302'",-10inchesindicator scale)andhighcontainment pressure(3.5psig).Thesystemresponsetosmallbreaksrequiring depressurization isdiscussed inSectionVII-.A.3.3*
andthetimeavailable totakeoperatoractionissummarized inTableVII-1*.Additional information isincludedintheanswerstoguestions III-1andIII-5oftheFirstSupplement.
~Steamfromthereactorvesselisdischarged tothesuppression chamberduringvalvetesting.Conducting thetestswiththereactoratlowpressuresuchasjustpriortoorjustafterrefueling minimizes thestressonthereactorcoo1antsystern.aThetestintervalofonceperoperating cycleresultsinasystemfailureprobability of7.0x10-7(FifthSupplement, p.115)andisconsistent withpractical consideration.
'
LIMITINGCONDITION FOROPERATION SURVEILLANCE RE(UIREtiENT c.Ifaredundant component ineachofthecontainment spraysystemsortheirassociated rawwatersystemsbecomeinoperable, bothsystemsshallbeconsidered operableprovidedthatthecomponent isreturnedtoanoperablecondition within7daysandthattheadditional surveillance requiredisperformed.
C.RawWaterCoolingPumpsAtleastonceperquartermanualstartupandoperability oftherawwatercoolingpumpsshallbedemonstrated.
d.Ifacontainment spraysystemoritsassociated rawwatersystembecomesinoperable andallthecomponents areoperableintheothersystems,thereactormayremaininoperation foraperiodnottoexceed7days.d.Surveillance withInoperable Components
,/henacomponent orsystembecomesinoperable itsredundant component orsystemshallbedemonstrated tobeoperableimmediately anddailythereafter.
e.IfSpecifirations "a"or"b"arenotmet,shutdownshallbeginwithinonehourandthereactorcoolantshallbebelow215Fwithintenhours.Ifbothcontainment spraysystemsbecomeinoperable thereactorshallbeinthecoldshutdowncondition withintenhoursandnowork(exceptasspecified in"f"below)shallbeperformed onthereactorwhichcouldresultinloweringthereactorwaterleveltomorethansixfeet,threeinches(-10inchesindicator scale)belowminimumnormalwaterlevel:(Elevation 302'").e.Surveillance duringcontrolroddrivemaintenance whichissimultaneous withthesuppression chamberunwatered shallincludeatleasthourlychecksthattheconditions listedin3.3.7.faremet.159QJEC(DE
Tab1e3.6.2fINSTRUMENTATION THATINITIATES AUTODEPRESSUR IZATIONLiiigiiO>>iParameter MinimumNo.ofTrippedorOperable~TriSystems4MinimumNo.ofOperableInstrument ChannelsperOperableT~riSystemSet-Point ReactorModeSwitchPositioninWhichFunctionMustBeOperableINITIATION (1)a.b.Low-Low-Low ReactorWaterLevelHighOrywellPressure2(a)2(a)2(a)~-10inches*(Indicator scale)<3.5psig(b)(b)(b)x(b)x*greaterthan(>)meanslessnegative213