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| {{#Wiki_filter:ATTACHMENT5INDIANA8NIICHIGANEIECMIGCDNP4NYDONALDC.COOKNUCLEARPLANTFORM5411PROCEDURECOVERSHEETpggg~iireNo.2-OHP4021.002.00DRAININGREACTORCOOLANTSYSTEMHevhionNo.2SCOPEOFREVIS1ONRevision1-Revisedandrewrittentostandardizeformat.AddressedChangeSheets1through6.Revision2-Minorrevisionsduetoshiftreview.DeletdDataSignoffSheet5.2AddressedProcedureChangeSheets1and2.SIGNATURESREVISIONNUMBERORIGINALRev.1Rev.2PREPAREDBYDEPARTMENTHEADAPPROVALJ.OsborneR.BlthB.SverssonK.Bakerp///A/INTERFACINGDEPARTMENTHEADCONCURRENCEQUALITYASSURANCESUPERVISORAPPROVALPLANTNUCLEARSAFETYCOMMITTEEPLANTMANAGERAPPROVALAPPROVALDATER.KeithJ.StietzelD.ShallerD.Palme.06-07-7702-18-82R.JurgensenW.Smith,Jr..i'~',.-,-EFFECTIVEDATE84052202028405i7PDRADQCK050003i6P.PDR6.-0-7702-18-82'I'-Z4 sa2-OHP4021.002.005LZSTOFEFFECTZVEPAGESPAGENUMBERPage1of6Page2of6Page3of6Page4of6Page5of6Page6of6REVZSZONNUMBERANDDATERevision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84DATA/SZGNOFFSHEET5.1Page1of2Page2o2Revision2,03-09-84Revision2,03-09-84?age1of1Rev.2 2-OHP4021.002'05INDIANA6MICHIGANELECTRICCOMPANYDONALDC.COOKNUCLEARPLANTDRAININGREACTORCOOLANTSYSTEM1.0OBJECTIVE1.1TolowerthereactorcoolantlevelintheReactorCoolantSystempriortoremovingthereactorvesselheadorperformingmaintenanceworkrequiringareducedwaterlevel. | | {{#Wiki_filter:ATTACHMENT 5INDIANA8NIICHIGAN EIECMIGCDNP4NYDONALDC.COOKNUCLEARPLANTFORM5411PROCEDURE COVERSHEETpggg~iire No.2-OHP4021.002.00DRAININGREACTORCOOLANTSYSTEMHevhionNo.2SCOPEOFREVIS1ONRevision1-Revisedandrewritten tostandardize format.Addressed ChangeSheets1through6.Revision2-Minorrevisions duetoshiftreview.DeletdDataSignoffSheet5.2Addressed Procedure ChangeSheets1and2.SIGNATURES REVISIONNUMBERORIGINALRev.1Rev.2PREPAREDBYDEPARTMENT HEADAPPROVALJ.OsborneR.BlthB.SverssonK.Bakerp///A/INTERFACING DEPARTMENT HEADCONCURRENCE QUALITYASSURANCE SUPERVISOR APPROVALPLANTNUCLEARSAFETYCOMMITTEE PLANTMANAGERAPPROVALAPPROVALDATER.KeithJ.StietzelD.ShallerD.Palme.06-07-7702-18-82R.Jurgensen W.Smith,Jr..i'~',.-,- |
| | EFFECTIVE DATE8405220202 8405i7PDRADQCK050003i6P.PDR6.-0-7702-18-82'I'-Z4 sa2-OHP4021.002.005 LZSTOFEFFECTZVE PAGESPAGENUMBERPage1of6Page2of6Page3of6Page4of6Page5of6Page6of6REVZSZONNUMBERANDDATERevision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84DATA/SZGNOFF SHEET5.1Page1of2Page2o2Revision2,03-09-84Revision2,03-09-84?age1of1Rev.2 2-OHP4021.002'05INDIANA6MICHIGANELECTRICCOMPANYDONALDC.COOKNUCLEARPLANTDRAININGREACTORCOOLANTSYSTEM1.0OBJECTIVE 1.1TolowerthereactorcoolantlevelintheReactorCoolantSystempriortoremovingthereactorvesselheadorperforming maintenance workrequiring areducedwaterlevel. |
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| ==2.0REFERENCES== | | ==2.0REFERENCES== |
| 2.1TechnicalSpecifications,AppendixA,Section3.9.1.2.2AEPFlowDiagrams:2.2.12-OP-5128-4,ReactorCoolantSystem.2.2.22-OP-5128A-10,ReactorCoolantSystem.2.2.32-OP-5'29-3,CVCSReactorLetdownandCharging.2.2.412-OP-5137A-5,WDSVentsandDrains.2.2.52-OP-5143-3,EmergencyCoreCooling.2.3PlantOperatingProcedure,2-OHP4021.017.002,PlacinginServiceandOperationofResidualHeatRemovalLoop.3.0INITIALCONDITIONS?ERFORi~iEDBY3.13~23.3Ifreactorvesselheadistobeunbolted,verifyKefflessthanorequalto0.95andTavglessthanorequalto140'F.Zfincoldsnutdown,verifyKefflessthan0.99andTavglessthanorequalto200'F.TheResidualHeatRemovalSystemisinoperation,maintainingreactorcoolantsystemtemperature.Thereactorcoolantdraintankandaminimumofoneothedraintankpumpsisoperable.Thedischargeofthereactorcoolantdraintankpumpis1'neduptoselectedCVCSHUTtanksthroughCS-460.Page1of6Rev.2 PERFORMEDBY3'ThereissufficientcapacityintheCVCSholduptankstoreceivecoolantreleasedfromtheReactorCoolantSystemwhenthepressurizerandthereactorvesselheadaredrained.3.53.6Thepressurizerbackupandvariableheaterbreakersmustbetaggedopen.Thepressurizerisopentothepressurizerrelieftankthroughapoweroperatedreliefvalve.3.7Anitrogenblanketof5psigisbeingmaintainedinthepressurizerfromthepressurizerrelieftankthroughthereliefvalvedischargeline.3.8Atemporarytygonhoseisconnectedtovalve2-RC-116-L3forlevelindication.Thetygonhoseisloopedsothetopoftheloopisatleastten(10)feetabovetheintendedlevelindicationdesiredandattachedtomanualvent2-WD-238onthepressur'zerrel'eftanksTheblanklangeonthePRTvent(2-WD-238)requiresbeingreplacedbyaflangewithapipingteeon'twithtemporaryvalvesonthetwo(2)freeends.Oneendistoconnecttotheleveltygonhose.Theotheristobeconnectedtoatygonhosethatisroutedtotheinstrumentroompurgeexhaustsuctionvalve.Ensuretherearenoloopsealsorkinksinthetygonhosetobeusedorlevelindication.3.9Pressurizerlevelisintheindicatingrangeorfilledsolid.3.10Thereactorheadventisconnectedtothepressurizerrelieftankviainstalledventspoolpiece.3.11Shutandtagshutprimarywatertoboricacidblender12-PW-263.~TerifyCLOSEDandhangaclearanceonprimarywatertochemicalmix'gtank2-PW-256andprimarywaterflushtoemergencvborationline2-PW-265.Thishelpstoavoidaninadvertentdilutionwhileathalfloop.3.12Ifatygonhoseistobeusedforlevelindication,theclosedcircuittelevisionmonitormusbeconnectedandfuntioningproperly.Page2of6Rev.2 | | |
| ~g's~~2-OHP4021.002.0054.0PRECAUTIONS4.14.2TheapplicableRadiationProtectionproceduresforhandlingradioactiveliquidsandforventingvaporsandgassesmustbeobserved.Thewaterlevelinthereactorvesselmustbebelowthevesselflangebeforetheheadisunboltedforremoval.Thereactorflangeelevationis621feet,14inches.Theelevationof4loopis614feet,0inches.ForRCPsealworkand/orsteamgeneratormanwayremoval,thelevelmustbebroughttothecenterlineofthehotandcoldlegs.Thisiscommonlyreferredtoashalfloop.Thelevelshouldbeathalfloopforaperi-odofeighthoursafterthePRTandtygonlevelinstru-mentationisventedtoatmospherebeforeallowingman-waystoberemoved.4.34.44.5Thepressurizerrelieftanklevelmustbereducedtolessthan5%toallownitrogenflowtothepressurizerthroughtheopenpoweroperatedreliefvalve.Maintainreactorcoolantsystemtemperaturegreaterthan60'Ftoensurethereactorheadtemperatureremainsgreaterthan60'FuntiltensionisrelievedfromthereactorheadstudsperWestinghouserefuelingprocedure.DonotdrainReactorCoolantSystembelowcenterlineoftheloops(614'")whennuclearfuelisinthevesselorwhileonRHR.4.6AnytimedrainingoftheRCSisinprogress,carefulobservationoftheRHRSystemisrecuired.Thepumpamperageisthefirs"indicationocavitationorlossofsuction.5.0DATA/SIGNOFFSHEETS5.1Data/SignofSheet5.1,DrainingReactorCoolanValveLineup.6.0INSTRUCTIONSPERFORMEDBY6.16.2CompletetheattachedData/SignoffSheet5.1,DrainingPeactorCoolantValveLineup.StartlowpessureletdownfromtheReactorCoolantSystemviatheResidualHeatRemovalSystemfollowing2-OHP4021.017.002,PlacingInServiceandOperationofResidualHeatRemovalLoop.Page3of6Rev.2 | | 2.1Technical Specifications, AppendixA,Section3.9.1.2.2AEPFlowDiagrams: |
| ~I~~2-OHP4021.002.005PERZORMEDBY6.3Monitorpressurizerrelieftankpressurewhiledrainingthesystem.Maintainapositivenitrogenpressurenottoexceed5psig.6.46.5Closereactorcoolantdraintankventstoventheader2-DCR-201and2-DCR-203.ThisistopreventgettingwaterintoventheaderwhendrainingReactorCoolantSystem.Openloopdrainisolationvalves2-RC-113-L1,2-RC-113-L2,2-RC-113-L3,and2-RC-113-L4.6.6Loopdrainsflushing-Thesestepsaretobedoneinsequencesotheloopdrainsareflushedcleanofcrud.Openthedrainvalveswidetoallowfullflowtothereactorcoolantdraintank.Valveoffifnecessarytocontrolreactorcoolantdraintanklevelandthenreopentoobtaintherequiredflushingtime.6..6.1,Open2-RC-114-L'ndallowfullflowforaminimumoftwo(2)minutes.6.6.2Open2-RC-114-L4andallowfullflowforaminimumofthree(3)minutes.6.6.3Open2-RC-1'4-L2andallowfullflowfor'minimumoftwo(2)minutes.6.6.4Open2-RC-114-L3andallowfullflowforaminimumofthree(3)minutes.6.7Aftercompletionofste'p6.6,theour(4)loopdrainsshouldbeusedassystemdrains.Thesedrainsandthelowpressureletdownofstep6.2othisprocedurecanbeusedinanycombinationtocontrolthedrainagefromthesystem.NCTEWhenusingloopdrains,stationanoperatorattheWasteDisposalSystempaneltoobservereactorcoolantdra'ntanklevelsothatdrainagecanbecontrolledtopreventfloodingthereactorcoolantdraintank.Page4of6Rev.2 2-OHP4021.002.005PERFORMEDBY6.8Whenpressurizerlevelisreducedto5%indicated,openthereactorheadventvalves2-RC-132and2-RC-133.Reactorcoolantwillnowflowthroughtheconnectedsightglasstothepressurizerrelieftank.Monitorthistanklevelwhiledrainingthiswayandmaintainthelevellessthan5%.6.9Whenreactorcoolantstops'flowingthroughtheflowindicatorconnectedtotheheadventvalve,closealldrains.6.10Placetemporaryrefuelingwater.levelindicatorinservice(tygonhose)byopeningvalves2-RC-113-L3,2-RC-116-L3,1-WD-238,andtemporaryvalveontygonhose.RefertoPrecaution4.3.6.11ContinuedrainingtheReactorCoolantSystembyeitherorbothmethodsofstep6.7ofthisprocedure.Donotusetheloo3drainforthisbecauseitwillcauseafalselevelindication.6.12Astheindicatedlevelapproacheshalfloop,slowdownthedrainageandstopitwhenthelevelisreached.6.13Whilemaintaininglevelathalfloopperformthefollowingsteps:6.13.1Closetnetemporaryvalveontheleve'ygonatthePRTvent.6.13.2RemoveNsupplyfromPRTbyclosing1-GCR-30$.6.13.3SlowlyventPRTtoinstrumentroompurgeexhaustbycrackingorthrottlingtemporaryvalve.6.13.4WhenPRTisfullyvented,slowlythrottleopentemporaryvalveonthetygonlevelhose.6.14CloseRC-116-L3.6.15ClosetemporaryvalveontygonlevelhoseatPRT.Thendisconnectthetygon.hosefromthevalveandhaveitrunupalongsideI3RCPtoaheightgreaterthanthereactorflange(greaterthan622'levation).Page5of6Rev.2 | | 2.2.12-OP-5128-4, ReactorCoolantSystem.2.2.22-OP-5128A-10, ReactorCoolantSystem.2.2.32-OP-5'29-3, CVCSReactorLetdownandCharging. |
| ~$'1~e~2MHP4021.002.005PERFORMEDBY6.16Whilemonitoringthelevel,slowlyopenRC-116-L3.(Ensureitisnotallowedtooverflow.)6.17Reestablishlevelathalflooporwheredesiredforworktobeperformed.6.18Maintainlevelathalfloopforeighthourspre-ferred(aminimumof4hours).6.19DeclareRCSathalfloop.PROCEDUREVERIFIEDCOMPLETEBYDATEREVIEWEDBYSRODATE7.0FINALCONDITIONS.7.1Reactorcoolantlevelisatthedesiredlevelre-quiredforsystemmaintenance.Thislevelcanbeanywheredowntothecenterlineoftheloops.Page6of6Rev.2 2-OHP4021.002.005DATA/SIGNOFFSHEET5.1LATESTEEV.CHECKEDDPPZNINQPEACTORCOOLANTVALVELINEUPVALVENUMBER2-NRV-1632-NRV-1642-GCR-3012-RRV-1032-RC-1182-RCllo2-DRV-100DESCRIPTIONPressurizerSprayLoop3PressurizerSprayLoop4N2toPressurizerPeliefTankPressurierFe'iefTankVentReactorVesselFlangeLeakoff(Outer)ReactorVesselFlangeLeakoff(Inner)Reacto"VesselFlangeLeakoffIsolationVALVEPOSITIONCLCLOPCLCLCLPERFORMEDBY2-RC-113LlReactorCoolantLoop1Dra'nValve2-RC-113L2Reacto"Coo'antLoop2DrainValveCLCL2-RC-313L32-RC-113L42-RC-114LlReactorCoo'antLoop3DrainValveReactorCoclantLoop4DrainValveReactcrCoolartLccpIsolatior.ValveDrainCLC2-RC-''4L2ReactorCoolantLcopIsolationValve2DrainCL2-RC-114L3ReactorCco'antLoop3DrainIsolaticnVa'eCL2-RC-114L4ReactorCcolantLoop4DrainZsolat'onValveCLOP-OpenCL-ClosedPage1of2Rev~2 2-OHP4021.002.005DATA/SIGNOFFSHEET5.1DPAININGREACTORCOOLANTVALVELINEUPVALVENUMBER2-RC-116L32-NRV-153DESCRIPTIONRefuelingWaterLevel'ndicatorsolationP.O.RelieftoPressurizerReliefTankVALVEPOSITIONCLOPPERFORMEDBY2-NRV-152P.O.PelieftoReliefTankPressurizerOP2-NRV-1512-RC-1212-RC-137P.O.PelieftoPressurizerReliefTankR.V.HeadVenttoPressurizerReliefTankR.V.HeadVenttoPressurizerReliefTankOPOPOP2-RC-1382-RC-1322-RC-133R.V.VenttoR.V.LevelInstrumentationSightglassInletIsolationSightglassOut'etIsolat'onCPCLTemporaryvalve"orPRTVenttoInstrumentRoomPurgeEvhaustCLDATA/SIGNOFFSHEETVERIFIEDCOMPLETEBYDATEREVIEWEDBYSRODATEOP-OpenCL-ClosedPage2ofRev.2 | | 2.2.412-OP-5137A-5, WDSVentsandDrains.2.2.52-OP-5143-3, Emergency CoreCooling.2.3PlantOperating Procedure, 2-OHP4021.017.002, PlacinginServiceandOperation ofResidualHeatRemovalLoop.3.0INITIALCONDITIONS |
| | ?ERFORi~iED BY3.13~23.3Ifreactorvesselheadistobeunbolted, verifyKefflessthanorequalto0.95andTavglessthanorequalto140'F.Zfincoldsnutdown, verifyKefflessthan0.99andTavglessthanorequalto200'F.TheResidualHeatRemovalSystemisinoperation, maintaining reactorcoolantsystemtemperature. |
| | Thereactorcoolantdraintankandaminimumofoneothedraintankpumpsisoperable. |
| | Thedischarge ofthereactorcoolantdraintankpumpis1'neduptoselectedCVCSHUTtanksthroughCS-460.Page1of6Rev.2 PERFORMEDBY3'Thereissufficient capacityintheCVCSholduptankstoreceivecoolantreleasedfromtheReactorCoolantSystemwhenthepressurizer andthereactorvesselheadaredrained.3.53.6Thepressurizer backupandvariableheaterbreakersmustbetaggedopen.Thepressurizer isopentothepressurizer relieftankthroughapoweroperatedreliefvalve.3.7Anitrogenblanketof5psigisbeingmaintained inthepressurizer fromthepressurizer relieftankthroughthereliefvalvedischarge line.3.8Atemporary tygonhoseisconnected tovalve2-RC-116-L3 forlevelindication. |
| | Thetygonhoseisloopedsothetopoftheloopisatleastten(10)feetabovetheintendedlevelindication desiredandattachedtomanualvent2-WD-238onthepressur'zer rel'eftanksTheblanklangeonthePRTvent(2-WD-238) requiresbeingreplacedbyaflangewithapipingteeon'twithtemporary valvesonthetwo(2)freeends.Oneendistoconnecttotheleveltygonhose.Theotheristobeconnected toatygonhosethatisroutedtotheinstrument roompurgeexhaustsuctionvalve.Ensuretherearenoloopsealsorkinksinthetygonhosetobeusedorlevelindication. |
| | 3.9Pressurizer levelisintheindicating rangeorfilledsolid.3.10Thereactorheadventisconnected tothepressurizer relieftankviainstalled ventspoolpiece.3.11Shutandtagshutprimarywatertoboricacidblender12-PW-263. |
| | ~TerifyCLOSEDandhangaclearance onprimarywatertochemicalmix'gtank2-PW-256andprimarywaterflushtoemergencv borationline2-PW-265. |
| | Thishelpstoavoidaninadvertent dilutionwhileathalfloop.3.12Ifatygonhoseistobeusedforlevelindication, theclosedcircuittelevision monitormusbeconnected andfuntioning properly. |
| | Page2of6Rev.2 |
| | ~g's~~2-OHP4021.002.005 |
| | |
| | ==4.0 PRECAUTIONS== |
| | 4.14.2Theapplicable Radiation Protection procedures forhandlingradioactive liquidsandforventingvaporsandgassesmustbeobserved. |
| | Thewaterlevelinthereactorvesselmustbebelowthevesselflangebeforetheheadisunboltedforremoval.Thereactorflangeelevation is621feet,14inches.Theelevation of4loopis614feet,0inches.ForRCPsealworkand/orsteamgenerator manwayremoval,thelevelmustbebroughttothecenterlineofthehotandcoldlegs.Thisiscommonlyreferredtoashalfloop.Thelevelshouldbeathalfloopforaperi-odofeighthoursafterthePRTandtygonlevelinstru-mentation isventedtoatmosphere beforeallowingman-waystoberemoved.4.34.44.5Thepressurizer relieftanklevelmustbereducedtolessthan5%toallownitrogenflowtothepressurizer throughtheopenpoweroperatedreliefvalve.Maintainreactorcoolantsystemtemperature greaterthan60'Ftoensurethereactorheadtemperature remainsgreaterthan60'FuntiltensionisrelievedfromthereactorheadstudsperWestinghouse refueling procedure. |
| | DonotdrainReactorCoolantSystembelowcenterlineoftheloops(614'")whennuclearfuelisinthevesselorwhileonRHR.4.6AnytimedrainingoftheRCSisinprogress, carefulobservation oftheRHRSystemisrecuired. |
| | Thepumpamperageisthefirs"indication ocavitation orlossofsuction.5.0DATA/SIGNOFF SHEETS5.1Data/Signof Sheet5.1,DrainingReactorCoolanValveLineup.6.0INSTRUCTIONS PERFORMED BY6.16.2CompletetheattachedData/Signoff Sheet5.1,DrainingPeactorCoolantValveLineup.StartlowpessureletdownfromtheReactorCoolantSystemviatheResidualHeatRemovalSystemfollowing 2-OHP4021.017.002, PlacingInServiceandOperation ofResidualHeatRemovalLoop.Page3of6Rev.2 |
| | ~I~~2-OHP4021.002.005 PERZORMEDBY6.3Monitorpressurizer relieftankpressurewhiledrainingthesystem.Maintainapositivenitrogenpressurenottoexceed5psig.6.46.5Closereactorcoolantdraintankventstoventheader2-DCR-201 and2-DCR-203. |
| | ThisistopreventgettingwaterintoventheaderwhendrainingReactorCoolantSystem.Openloopdrainisolation valves2-RC-113-L1, 2-RC-113-L2, 2-RC-113-L3, and2-RC-113-L4. |
| | 6.6Loopdrainsflushing-Thesestepsaretobedoneinsequencesotheloopdrainsareflushedcleanofcrud.Openthedrainvalveswidetoallowfullflowtothereactorcoolantdraintank.Valveoffifnecessary tocontrolreactorcoolantdraintanklevelandthenreopentoobtaintherequiredflushingtime.6..6.1,Open2-RC-114-L'nd allowfullflowforaminimumoftwo(2)minutes.6.6.2Open2-RC-114-L4 andallowfullflowforaminimumofthree(3)minutes.6.6.3Open2-RC-1'4-L2 andallowfullflowfor'minimumoftwo(2)minutes.6.6.4Open2-RC-114-L3 andallowfullflowforaminimumofthree(3)minutes.6.7Aftercompletion ofste'p6.6,theour(4)loopdrainsshouldbeusedassystemdrains.Thesedrainsandthelowpressureletdownofstep6.2othisprocedure canbeusedinanycombination tocontrolthedrainagefromthesystem.NCTEWhenusingloopdrains,stationanoperatorattheWasteDisposalSystempaneltoobservereactorcoolantdra'ntanklevelsothatdrainagecanbecontrolled topreventfloodingthereactorcoolantdraintank.Page4of6Rev.2 2-OHP4021.002.005 PERFORMED BY6.8Whenpressurizer levelisreducedto5%indicated, openthereactorheadventvalves2-RC-132and2-RC-133. |
| | Reactorcoolantwillnowflowthroughtheconnected sightglass tothepressurizer relieftank.Monitorthistanklevelwhiledrainingthiswayandmaintainthelevellessthan5%.6.9Whenreactorcoolantstops'flowingthroughtheflowindicator connected totheheadventvalve,closealldrains.6.10Placetemporary refueling water.levelindicator inservice(tygonhose)byopeningvalves2-RC-113-L3, 2-RC-116-L3, 1-WD-238, andtemporary valveontygonhose.RefertoPrecaution 4.3.6.11ContinuedrainingtheReactorCoolantSystembyeitherorbothmethodsofstep6.7ofthisprocedure. |
| | Donotusetheloo3drainforthisbecauseitwillcauseafalselevelindication. |
| | 6.12Astheindicated levelapproaches halfloop,slowdownthedrainageandstopitwhenthelevelisreached.6.13Whilemaintaining levelathalfloopperformthefollowing steps:6.13.1Closetnetemporary valveontheleve'ygon atthePRTvent.6.13.2RemoveNsupplyfromPRTbyclosing1-GCR-30$ |
| | .6.13.3SlowlyventPRTtoinstrument roompurgeexhaustbycrackingorthrottling temporary valve.6.13.4WhenPRTisfullyvented,slowlythrottleopentemporary valveonthetygonlevelhose.6.14CloseRC-116-L3. |
| | 6.15Closetemporary valveontygonlevelhoseatPRT.Thendisconnect thetygon.hosefromthevalveandhaveitrunupalongside I3RCPtoaheightgreaterthanthereactorflange(greaterthan622'levation). |
| | Page5of6Rev.2 |
| | ~$'1~e~2MHP4021.002.005 PERFORMED BY6.16Whilemonitoring thelevel,slowlyopenRC-116-L3. |
| | (Ensureitisnotallowedtooverflow.) |
| | 6.17Reestablish levelathalflooporwheredesiredforworktobeperformed. |
| | 6.18Maintainlevelathalfloopforeighthourspre-ferred(aminimumof4hours).6.19DeclareRCSathalfloop.PROCEDURE VERIFIEDCOMPLETEBYDATEREVIEWEDBYSRODATE7.0FINALCONDITIONS. |
| | 7.1Reactorcoolantlevelisatthedesiredlevelre-quiredforsystemmaintenance. |
| | Thislevelcanbeanywheredowntothecenterlineoftheloops.Page6of6Rev.2 2-OHP4021.002.005 DATA/SIGNOFF SHEET5.1LATESTEEV.CHECKEDDPPZNINQPEACTORCOOLANTVALVELINEUPVALVENUMBER2-NRV-163 2-NRV-164 2-GCR-301 2-RRV-103 2-RC-1182-RCllo2-DRV-100 DESCRIPTION Pressurizer SprayLoop3Pressurizer SprayLoop4N2toPressurizer PeliefTankPressurierFe'iefTankVentReactorVesselFlangeLeakoff(Outer)ReactorVesselFlangeLeakoff(Inner)Reacto"VesselFlangeLeakoffIsolation VALVEPOSITIONCLCLOPCLCLCLPERFORMEDBY2-RC-113LlReactorCoolantLoop1Dra'nValve2-RC-113L2Reacto"Coo'antLoop2DrainValveCLCL2-RC-313L32-RC-113L42-RC-114LlReactorCoo'antLoop3DrainValveReactorCoclantLoop4DrainValveReactcrCoolartLccpIsolatior. |
| | ValveDrainCLC2-RC-''4L2ReactorCoolantLcopIsolation Valve2DrainCL2-RC-114L3ReactorCco'antLoop3DrainIsolaticn Va'eCL2-RC-114L4ReactorCcolantLoop4DrainZsolat'on ValveCLOP-OpenCL-ClosedPage1of2Rev~2 2-OHP4021.002.005 DATA/SIGNOFF SHEET5.1DPAININGREACTORCOOLANTVALVELINEUPVALVENUMBER2-RC-116L32-NRV-153DESCRIPTION Refueling WaterLevel'ndicator solationP.O.RelieftoPressurizer ReliefTankVALVEPOSITIONCLOPPERFORMED BY2-NRV-152 P.O.PelieftoReliefTankPressurizer OP2-NRV-1512-RC-1212-RC-137P.O.PelieftoPressurizer ReliefTankR.V.HeadVenttoPressurizer ReliefTankR.V.HeadVenttoPressurizer ReliefTankOPOPOP2-RC-1382-RC-1322-RC-133R.V.VenttoR.V.LevelInstrumentation Sightglass InletIsolation Sightglass Out'etIsolat'on CPCLTemporary valve"orPRTVenttoInstrument RoomPurgeEvhaustCLDATA/SIGNOFF SHEETVERIFIEDCOMPLETEBYDATEREVIEWEDBYSRODATEOP-OpenCL-ClosedPage2ofRev.2 |
| ~aI~e~}} | | ~aI~e~}} |
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Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5551999-04-19019 April 1999
Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A3581998-12-0303 December 1998
Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A3681998-12-0303 December 1998
Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys
ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
ML17335A3621998-12-0303 December 1998
Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4701996-02-0808 February 1996
In-Service Pump Test Plan, Units 1 & 2
ML17334B5661995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class,1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 1, Final Plan
ML17334B5671995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class 1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 2, Final Plan
ML17332A2521994-08-0303 August 1994
Rev 3 to Plant Manager Procedure (PMP) 12 PMP 3150 PCP.100, Radwaste Pcp.
ML17332A2491994-08-0303 August 1994
Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm.
ML20063K0631994-02-11011 February 1994
Change Sheet 1 to Rev 5 to Plant Manager Procedure (PMP) 12 PMP 6010 RPP.304, Use of HEPA Vacuum Cleaners. W/ Updated Index,Page 14
ML17331B0441993-11-0909 November 1993
Rev 15 to Emergency Response Manual. W/931109 Ltr
ML17334B4851993-08-0909 August 1993
Rev 14 to Emergency Response Manual. W/930809 Ltr
ML17334B4821993-04-0202 April 1993
Rev 3 of Pump Inservice Test Program.
ML17329A5431992-06-11011 June 1992
Change Sheet 7 to Rev 6 to Procedure PMP 2080 EPP.107, Notification of Plant Personnel.
ML20077S7281991-03-14014 March 1991
Rev 3 to PMP 6010.OSD.001, Odcm
ML17325B3791990-03-0101 March 1990
Change Sheet 1 to Rev 3 to Procedure PMP 2080 EPP.106, Initial Offsite Notification.
ML17334B3551990-02-0505 February 1990
Rev 2 to DC Cook Nuclear Plant Units 1 & 2 Inservice Testing Pump Program.
ML17334B3561990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML17334B3571990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML20246M2191989-03-21021 March 1989
Procedure MS-3.2.1.9-1B, Maint & Surveillance Ite Medium Voltage Switchgear Equipment
ML17325B0511988-12-0909 December 1988
Interim Acceptance Criteria for Safety-Related Piping Sys.
ML17334B1491987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML17334B1501987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML20212A3191986-10-0202 October 1986
Rev 1 to Procedure 12 PMP 4021 TRP.001, Reactor Trip Review
ML17324A9301986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.001, Maint Procedure for Repowering RHR Pump.
ML17324A9321986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.003, Maint Procedure for Repowering Pressurizer Backup Heaters.
ML17324A9331986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.005, Maint Procedure for Repowering Containment Valves.
ML17324A9341986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.304, Pressurizer PORV Cable Repair.
ML17324A9351986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.305, App R Post-Fire Repowering of In-Containment Valves.
ML17334A9711986-05-22022 May 1986
Rev 0 to Procedure 12-OHP 4023.100.001, Unit 1 Emergency Remote Shutdown.
ML20213F6011986-05-15015 May 1986
Rev 1 to Procedure PMP 6010.OSD.001, Offsite Dose Calculation Manual
ML17324A9001986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Iv,Training for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8991986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Ii,Writers Guide for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8971986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part I,Specific Technical Guidelines for Donald C Cook Nuclear Plant.
ML18005A0161986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part III, Verification/Validation for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML20195C5361986-03-15015 March 1986
Public Version of Emergency Response Manual for DC Cook Nuclear Plant
ML20141D7121986-02-28028 February 1986
Rev 0 to Master Insp Plan
ML20137J6061985-12-17017 December 1985
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 2 to Erp 2.07, Outside Agency Liaison, Rev 1 to Erp 2.08, Initial Assessment Group Runner & Rev 2 to Erp 5.01.W/860117 Release Memo
ML17334A9441985-11-0505 November 1985
Change Sheet 1 of Rev 9 to Spec DCCFP101QCN, Matl & Application Spec - Initial & Repair Installations, Revising App D Silicon Foam Scope of Work to Identify New Fire Barriers & for Cross Referencing Fire Zones
ML17334A9191985-10-15015 October 1985
Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept
1999-05-07
[Table view] |
Text
ATTACHMENT 5INDIANA8NIICHIGAN EIECMIGCDNP4NYDONALDC.COOKNUCLEARPLANTFORM5411PROCEDURE COVERSHEETpggg~iire No.2-OHP4021.002.00DRAININGREACTORCOOLANTSYSTEMHevhionNo.2SCOPEOFREVIS1ONRevision1-Revisedandrewritten tostandardize format.Addressed ChangeSheets1through6.Revision2-Minorrevisions duetoshiftreview.DeletdDataSignoffSheet5.2Addressed Procedure ChangeSheets1and2.SIGNATURES REVISIONNUMBERORIGINALRev.1Rev.2PREPAREDBYDEPARTMENT HEADAPPROVALJ.OsborneR.BlthB.SverssonK.Bakerp///A/INTERFACING DEPARTMENT HEADCONCURRENCE QUALITYASSURANCE SUPERVISOR APPROVALPLANTNUCLEARSAFETYCOMMITTEE PLANTMANAGERAPPROVALAPPROVALDATER.KeithJ.StietzelD.ShallerD.Palme.06-07-7702-18-82R.Jurgensen W.Smith,Jr..i'~',.-,-
EFFECTIVE DATE8405220202 8405i7PDRADQCK050003i6P.PDR6.-0-7702-18-82'I'-Z4 sa2-OHP4021.002.005 LZSTOFEFFECTZVE PAGESPAGENUMBERPage1of6Page2of6Page3of6Page4of6Page5of6Page6of6REVZSZONNUMBERANDDATERevision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84Revision2,03-09-84DATA/SZGNOFF SHEET5.1Page1of2Page2o2Revision2,03-09-84Revision2,03-09-84?age1of1Rev.2 2-OHP4021.002'05INDIANA6MICHIGANELECTRICCOMPANYDONALDC.COOKNUCLEARPLANTDRAININGREACTORCOOLANTSYSTEM1.0OBJECTIVE 1.1TolowerthereactorcoolantlevelintheReactorCoolantSystempriortoremovingthereactorvesselheadorperforming maintenance workrequiring areducedwaterlevel.
2.0REFERENCES
2.1Technical Specifications, AppendixA,Section3.9.1.2.2AEPFlowDiagrams:
2.2.12-OP-5128-4, ReactorCoolantSystem.2.2.22-OP-5128A-10, ReactorCoolantSystem.2.2.32-OP-5'29-3, CVCSReactorLetdownandCharging.
2.2.412-OP-5137A-5, WDSVentsandDrains.2.2.52-OP-5143-3, Emergency CoreCooling.2.3PlantOperating Procedure, 2-OHP4021.017.002, PlacinginServiceandOperation ofResidualHeatRemovalLoop.3.0INITIALCONDITIONS
?ERFORi~iED BY3.13~23.3Ifreactorvesselheadistobeunbolted, verifyKefflessthanorequalto0.95andTavglessthanorequalto140'F.Zfincoldsnutdown, verifyKefflessthan0.99andTavglessthanorequalto200'F.TheResidualHeatRemovalSystemisinoperation, maintaining reactorcoolantsystemtemperature.
Thereactorcoolantdraintankandaminimumofoneothedraintankpumpsisoperable.
Thedischarge ofthereactorcoolantdraintankpumpis1'neduptoselectedCVCSHUTtanksthroughCS-460.Page1of6Rev.2 PERFORMEDBY3'Thereissufficient capacityintheCVCSholduptankstoreceivecoolantreleasedfromtheReactorCoolantSystemwhenthepressurizer andthereactorvesselheadaredrained.3.53.6Thepressurizer backupandvariableheaterbreakersmustbetaggedopen.Thepressurizer isopentothepressurizer relieftankthroughapoweroperatedreliefvalve.3.7Anitrogenblanketof5psigisbeingmaintained inthepressurizer fromthepressurizer relieftankthroughthereliefvalvedischarge line.3.8Atemporary tygonhoseisconnected tovalve2-RC-116-L3 forlevelindication.
Thetygonhoseisloopedsothetopoftheloopisatleastten(10)feetabovetheintendedlevelindication desiredandattachedtomanualvent2-WD-238onthepressur'zer rel'eftanksTheblanklangeonthePRTvent(2-WD-238) requiresbeingreplacedbyaflangewithapipingteeon'twithtemporary valvesonthetwo(2)freeends.Oneendistoconnecttotheleveltygonhose.Theotheristobeconnected toatygonhosethatisroutedtotheinstrument roompurgeexhaustsuctionvalve.Ensuretherearenoloopsealsorkinksinthetygonhosetobeusedorlevelindication.
3.9Pressurizer levelisintheindicating rangeorfilledsolid.3.10Thereactorheadventisconnected tothepressurizer relieftankviainstalled ventspoolpiece.3.11Shutandtagshutprimarywatertoboricacidblender12-PW-263.
~TerifyCLOSEDandhangaclearance onprimarywatertochemicalmix'gtank2-PW-256andprimarywaterflushtoemergencv borationline2-PW-265.
Thishelpstoavoidaninadvertent dilutionwhileathalfloop.3.12Ifatygonhoseistobeusedforlevelindication, theclosedcircuittelevision monitormusbeconnected andfuntioning properly.
Page2of6Rev.2
~g's~~2-OHP4021.002.005
4.0 PRECAUTIONS
4.14.2Theapplicable Radiation Protection procedures forhandlingradioactive liquidsandforventingvaporsandgassesmustbeobserved.
Thewaterlevelinthereactorvesselmustbebelowthevesselflangebeforetheheadisunboltedforremoval.Thereactorflangeelevation is621feet,14inches.Theelevation of4loopis614feet,0inches.ForRCPsealworkand/orsteamgenerator manwayremoval,thelevelmustbebroughttothecenterlineofthehotandcoldlegs.Thisiscommonlyreferredtoashalfloop.Thelevelshouldbeathalfloopforaperi-odofeighthoursafterthePRTandtygonlevelinstru-mentation isventedtoatmosphere beforeallowingman-waystoberemoved.4.34.44.5Thepressurizer relieftanklevelmustbereducedtolessthan5%toallownitrogenflowtothepressurizer throughtheopenpoweroperatedreliefvalve.Maintainreactorcoolantsystemtemperature greaterthan60'Ftoensurethereactorheadtemperature remainsgreaterthan60'FuntiltensionisrelievedfromthereactorheadstudsperWestinghouse refueling procedure.
DonotdrainReactorCoolantSystembelowcenterlineoftheloops(614'")whennuclearfuelisinthevesselorwhileonRHR.4.6AnytimedrainingoftheRCSisinprogress, carefulobservation oftheRHRSystemisrecuired.
Thepumpamperageisthefirs"indication ocavitation orlossofsuction.5.0DATA/SIGNOFF SHEETS5.1Data/Signof Sheet5.1,DrainingReactorCoolanValveLineup.6.0INSTRUCTIONS PERFORMED BY6.16.2CompletetheattachedData/Signoff Sheet5.1,DrainingPeactorCoolantValveLineup.StartlowpessureletdownfromtheReactorCoolantSystemviatheResidualHeatRemovalSystemfollowing 2-OHP4021.017.002, PlacingInServiceandOperation ofResidualHeatRemovalLoop.Page3of6Rev.2
~I~~2-OHP4021.002.005 PERZORMEDBY6.3Monitorpressurizer relieftankpressurewhiledrainingthesystem.Maintainapositivenitrogenpressurenottoexceed5psig.6.46.5Closereactorcoolantdraintankventstoventheader2-DCR-201 and2-DCR-203.
ThisistopreventgettingwaterintoventheaderwhendrainingReactorCoolantSystem.Openloopdrainisolation valves2-RC-113-L1, 2-RC-113-L2, 2-RC-113-L3, and2-RC-113-L4.
6.6Loopdrainsflushing-Thesestepsaretobedoneinsequencesotheloopdrainsareflushedcleanofcrud.Openthedrainvalveswidetoallowfullflowtothereactorcoolantdraintank.Valveoffifnecessary tocontrolreactorcoolantdraintanklevelandthenreopentoobtaintherequiredflushingtime.6..6.1,Open2-RC-114-L'nd allowfullflowforaminimumoftwo(2)minutes.6.6.2Open2-RC-114-L4 andallowfullflowforaminimumofthree(3)minutes.6.6.3Open2-RC-1'4-L2 andallowfullflowfor'minimumoftwo(2)minutes.6.6.4Open2-RC-114-L3 andallowfullflowforaminimumofthree(3)minutes.6.7Aftercompletion ofste'p6.6,theour(4)loopdrainsshouldbeusedassystemdrains.Thesedrainsandthelowpressureletdownofstep6.2othisprocedure canbeusedinanycombination tocontrolthedrainagefromthesystem.NCTEWhenusingloopdrains,stationanoperatorattheWasteDisposalSystempaneltoobservereactorcoolantdra'ntanklevelsothatdrainagecanbecontrolled topreventfloodingthereactorcoolantdraintank.Page4of6Rev.2 2-OHP4021.002.005 PERFORMED BY6.8Whenpressurizer levelisreducedto5%indicated, openthereactorheadventvalves2-RC-132and2-RC-133.
Reactorcoolantwillnowflowthroughtheconnected sightglass tothepressurizer relieftank.Monitorthistanklevelwhiledrainingthiswayandmaintainthelevellessthan5%.6.9Whenreactorcoolantstops'flowingthroughtheflowindicator connected totheheadventvalve,closealldrains.6.10Placetemporary refueling water.levelindicator inservice(tygonhose)byopeningvalves2-RC-113-L3, 2-RC-116-L3, 1-WD-238, andtemporary valveontygonhose.RefertoPrecaution 4.3.6.11ContinuedrainingtheReactorCoolantSystembyeitherorbothmethodsofstep6.7ofthisprocedure.
Donotusetheloo3drainforthisbecauseitwillcauseafalselevelindication.
6.12Astheindicated levelapproaches halfloop,slowdownthedrainageandstopitwhenthelevelisreached.6.13Whilemaintaining levelathalfloopperformthefollowing steps:6.13.1Closetnetemporary valveontheleve'ygon atthePRTvent.6.13.2RemoveNsupplyfromPRTbyclosing1-GCR-30$
.6.13.3SlowlyventPRTtoinstrument roompurgeexhaustbycrackingorthrottling temporary valve.6.13.4WhenPRTisfullyvented,slowlythrottleopentemporary valveonthetygonlevelhose.6.14CloseRC-116-L3.
6.15Closetemporary valveontygonlevelhoseatPRT.Thendisconnect thetygon.hosefromthevalveandhaveitrunupalongside I3RCPtoaheightgreaterthanthereactorflange(greaterthan622'levation).
Page5of6Rev.2
~$'1~e~2MHP4021.002.005 PERFORMED BY6.16Whilemonitoring thelevel,slowlyopenRC-116-L3.
(Ensureitisnotallowedtooverflow.)
6.17Reestablish levelathalflooporwheredesiredforworktobeperformed.
6.18Maintainlevelathalfloopforeighthourspre-ferred(aminimumof4hours).6.19DeclareRCSathalfloop.PROCEDURE VERIFIEDCOMPLETEBYDATEREVIEWEDBYSRODATE7.0FINALCONDITIONS.
7.1Reactorcoolantlevelisatthedesiredlevelre-quiredforsystemmaintenance.
Thislevelcanbeanywheredowntothecenterlineoftheloops.Page6of6Rev.2 2-OHP4021.002.005 DATA/SIGNOFF SHEET5.1LATESTEEV.CHECKEDDPPZNINQPEACTORCOOLANTVALVELINEUPVALVENUMBER2-NRV-163 2-NRV-164 2-GCR-301 2-RRV-103 2-RC-1182-RCllo2-DRV-100 DESCRIPTION Pressurizer SprayLoop3Pressurizer SprayLoop4N2toPressurizer PeliefTankPressurierFe'iefTankVentReactorVesselFlangeLeakoff(Outer)ReactorVesselFlangeLeakoff(Inner)Reacto"VesselFlangeLeakoffIsolation VALVEPOSITIONCLCLOPCLCLCLPERFORMEDBY2-RC-113LlReactorCoolantLoop1Dra'nValve2-RC-113L2Reacto"Coo'antLoop2DrainValveCLCL2-RC-313L32-RC-113L42-RC-114LlReactorCoo'antLoop3DrainValveReactorCoclantLoop4DrainValveReactcrCoolartLccpIsolatior.
ValveDrainCLC2-RC-4L2ReactorCoolantLcopIsolation Valve2DrainCL2-RC-114L3ReactorCco'antLoop3DrainIsolaticn Va'eCL2-RC-114L4ReactorCcolantLoop4DrainZsolat'on ValveCLOP-OpenCL-ClosedPage1of2Rev~2 2-OHP4021.002.005 DATA/SIGNOFF SHEET5.1DPAININGREACTORCOOLANTVALVELINEUPVALVENUMBER2-RC-116L32-NRV-153DESCRIPTION Refueling WaterLevel'ndicator solationP.O.RelieftoPressurizer ReliefTankVALVEPOSITIONCLOPPERFORMED BY2-NRV-152 P.O.PelieftoReliefTankPressurizer OP2-NRV-1512-RC-1212-RC-137P.O.PelieftoPressurizer ReliefTankR.V.HeadVenttoPressurizer ReliefTankR.V.HeadVenttoPressurizer ReliefTankOPOPOP2-RC-1382-RC-1322-RC-133R.V.VenttoR.V.LevelInstrumentation Sightglass InletIsolation Sightglass Out'etIsolat'on CPCLTemporary valve"orPRTVenttoInstrument RoomPurgeEvhaustCLDATA/SIGNOFF SHEETVERIFIEDCOMPLETEBYDATEREVIEWEDBYSRODATEOP-OpenCL-ClosedPage2ofRev.2
~aI~e~
