Proposed Tech Specs Incorporating Requirements for Reactor Vessel Level Indication Sys| ML17261A624 |
| Person / Time |
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| Site: |
Ginna  |
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| Issue date: |
09/24/1987 |
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| From: |
ROCHESTER GAS & ELECTRIC CORP. |
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| To: |
|
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| Shared Package |
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| ML17261A621 |
List: |
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| References |
|---|
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-2.E.1.2, TASK-2.F.1, TASK-2.F.2, TASK-2.G.1, TASK-TM NUDOCS 8710010029 |
| Download: ML17261A624 (10) |
|
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Text
Attachment ARevisetheTechnical Specification pagesasfollows:RemoveInsertpage3.5-15page4.1-7page3.5-15page4.1-7"9710010029 06000~4487092+PDR~DGC~PDRgj,p
'k TABLE3.5-4AccidentMonitorin Instrumentation TOTAIREQUIREDNO.OFCHANNELS(7)MINIMUMCHANNELSOPERABLE(7)1.Pressurizer WaterLevel(1)2.Auxiliary Feedwater FlowRate(2)(3)3.SteamGenerator WaterLevel-WideRange(3)2/steamgenerator 1/steamgenerator 1/steamgenerator 1/steamgenerator 4.ReactorCoolantSystemSubcooling MarginMonitor(4)5.Pressurizer PORVPositionindicator (5)6.PORVBlockValvePositionIndicator (1)7.Pressurizer SafetyValvePositionIndicator (5)2/Valve1/Valve2/Valve1/Valve0/Valve1/Valve8.Containment Pressure(8)9.Containment WaterLevel(NarrowRange,SumpA)1(6)1(6)10.Containment WaterIevel(WideRange,SumpB)ll.Core-Exit Thermocouples 12.ReactorVesselLevelIndication System4/corequadrant2/corequadrantNotes(1)Emergency powerforpressurizer equipment, NUREG-0737, itemII.G.l.(2)'3)Auxiliary feedwater systemflowindication, NUREG-0737, itemII.E.1.2.
Only2outofthe3indications (twosteamgenerator auxiliary feedwater flowandonewide-range steamgenerator level)arerequiredtobeoperable, NUREG-0737, itemII.E.1.2.
(4)Instrumentation fordetection ofinadequate corecooling,NUREG-0737, itemII.'F.2.1.
(5)Directindication ofreliefandsafetyvalveposition, NUREG-0737, itemII.D.3.TwochannelsincludeaprimarydetectorandRTDasthebackupdetector.
(6)Operation maycontinuewithlessthantheminimumchannelsoperableprovidedthattherequirements ofTechnical Specification 3.1.5.1aremet.(7)SeeSpecification 3.5.2forrequiredaction.(8)Containment pressuremonitor,NUREG-0737, itemII.F.1.4.
3s5)5Proposed II ChannelDescritionTABLE4.1-1'CONTINUED)
CheckCalibrate TestRemarks25.Containment Pressure26.SteamGenerator PressureS27.TurbineFirstStagePressureSMNarrowrangecontainment pressure(-3.0,+3psig)excluded28.Emergency PlanRadiation Instruments 29.j30.IEnvironmental MonitorsLossofVoltage/Degraded Voltage480VoltSafeguards BusNANANA31.TripofMainFeedwater PumpsNA32.SteamFlowAVGNAR34.ChlorineDetector, ControlNARoomAirIntake35.036.AmmoniaDetector, ControlRoomAirIntakeNARadiation Detectors, ControlNARoomAirIntake37.ReactorVesselLevelIndication SystemNA Attachment BTheReactorVesselZ,evelIndication (RVZ,IS)wasinstalled duringtheSpring1986refueling outage.Adescription oftheRVLISandplansforimplementing revisedEmergency Operating Procedures havepreviously beenprovidedtotheNRCinlettersdatedDecember22,1986,March18,1987andSeptember 18,1987.TheRVLISisbeingincorporated intotheGinnaTechnical Specifications tosatisfyaNUREG-0737 requirement transmitted byaD.G.EisenhutletterdatedNovember1,1983.Thisletterprovided"ModelTechnical Specifications" tobeincorporated fortheRVLIS.TheproposedRVZIStechnical specifications areidentical
'tothemodelspecifications excepttheyhavebeenmodifiedtofittheGinnaformat.ThedetailedchangesarelistedonTable1.Inaccordance with10CFR50.91,thischangetotheTechnical Specifications hasbeenevaluated against,threecriteriatodetermine iftheoperation ofthefacilityinaccordance withtheproposedamendement would:l.Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.Createthepossibility ofanewordifferent kindofaccidentpreviously evaluated; or3.Involveasignificant reduction inmarginofsafety.Theproposedchangesdonot,involve asignificant'hange
-intheprobability ofanaccidentpreviously evaluated becauseRVLISisaninstrument systeminvolving smallconnections (3/8inch)tothereactorcoolantsystem.TheRVLISprovidesnoautomatic actuation oncontrolfunctions andtherefore willnot.impacttheprobability ofpreviously analyzedaccidents.
Incorporation oftheRVLISintoTechnical Specifications maydecreasetheconsequences ofcertainaccidents byimplementing instrumentation designedtodetect'an'daidintheresponsetoinadequate corecooling.Theproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated becausethechangesinvolveonlyspecifying operability andsurveillance requirements oftheRVLIS.Theproposedchangesdonotinvolveasignificant reduction inmarginofsafetybecausespecifying operability andsurveill-ancerequirements, infact,increasesafetymarginsbyproviding additional information usefultoplantoperators inresponding totransient eventsandaccidents.
1e~II Therefore, Rochester GasandElectricsubmitsthattheissuesassociated withthisamendment.
requestareoutsidethecriteriaof10CFR50.91 andanosignificant hazardsfindingiswarranted.
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Table1DetailedTechnical Specification ChangesLocationpp3.5-15pp4.1-7DescritionofChaneaddeditem12addeditem37ReasonforChaneNUREG-0737 requirement NUREG-0737 requirement