ML17263A210: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:Attachment ARevisetheTechnical Specification pagesasfollows:Remove3.6-43.6-63.6-7A3.6-10Insert.3.6-43.6-63.6-7A3.6-109'304090209 930405PDRADOCK,05000244 P'DR TABLE3.6-1CONTAINMENT ISOLATION VALVESPENT.NO.29IDENTIFICATION/DESCRIPTION FuelTransfertube100Charginglineto"B"loop101SZPump1Bdischarge 113SZPump1Adischarge 120NitrogentoAccumulators 120Pressurizer ReliefTank(PRT)toGasAnalyzer(GA)102Alternate chargingto"A"coldleg103Construction FireServiceWater105Containment SprayPump1A106"A"ReactorCoolantPump(RCP)sealwaterinlet107SumpAdischarge toWasteHoldupTank108RCPsealwateroutandexcessletdowntoVCT109Containment SprayPump1B110"B"RCPsealwaterinlet110SZtestline111RHRto"B"coldleg112LetdowntoNon-regen. | ||
HeatExchanger ZSOLATZON BOUNDARYflangeCV370BCV889BCV870BCV383BweldedflangeCV862ACV304AAOV1728MOV313CV862BCV304BMV879MOV720(20)AOV371CV889ACV870ACV8623AOV539MAXIMUMISOLATION TIME*(SEC)NANANANANANANANA6060NANANANA60NANANA60ISOLATION BOUNDARY(1)(2)(5)(5)(2)MV5129(3)(2)AOV1723(4)(3)(2)(5)(6)AOV200AAOV200BAOV202RV203(5)(5)AOV846MV546(7)MAXIMUM/ISOLATION TIME*(SEC)NANANANANANANA60NANANANANA606060NANANA60NA PgPENT.NO141142g0143IDENTIFICATION/DESCRIPTION RHR-tlpumpsuctionfromSumpBRHR-g2pumpsuctionfromSumpBRCDTpumpsuctionZSOLATION BOUNDARYMOV850A(13)MOV850B(13)AOV1721MAXIMUMISOLATION TIME*(SEC)NANA60ISOLATION BOUNDARYMOV851A(13)MOV851B(13)AOV1003AAOV1003BMAXIMUM/ISOLATION TIME*(SEC)NANA60604PI201ReactorCompart.CoolingUnitA&B202"B"Hydrogenrecombiner (pilot&main)203Contain.Press.Transmitter PT-947&948203Postaccidentairsampleto"B"fan204ShutdownPurgeSupplyDuct[PurgeSupplyDuct]205Hotlegloopsample206Przr.liquidspacesample206"A"S/Gsample207Przr.Steamspacesample207"B"S/Gsample209ReactorCompartment. | |||
CoolingUnitsA&B210OxygenmakeuptoA&Brecombiners MV4757(16)MV4636(16)MV1076BMV1084BPT947PT948MV1563MV1566flange(22)[AOV5870]AOV966CAOV966BAOV5735AOV966AAOV5736MV4758(16)MV4635(16)MV1080ANANANANANANANANANA[5]6060606060NANANASOV-IV-3B SOV<<ZV-5B MV1819CMV1819DMV1565MV1568AOV5869(22)MV956D(14)MV956E(14)(17)MV956F(17)SOVZV-2ASOVIV-2BNANormallyClosedNANormallyClosedNANANANANANANANANANANANANormallyClosedNANormallyClosed00 PENT.o'O.O315316g0317318319320IDENTIFICATION/DESCRIPTION ServiceWaterfrom"C"fancoolerServiceWaterto"B"fancoolerLeakagetestsupplyDeadweighttester(decomissioned) | |||
ServiceWaterfrom"A"fancoolerServicewaterto"C"fancooler4PI321AS/GBlowdown322BS/GBlowdown323ServiceWaterfrom"D"fancooler324Demineralized watertoContainment 332Cont.Press.Trans.PT-944,949&950ISOLATION BOUNDARYMV4643(16)MV4628(16)flangeweldedshutMV4629(16)MV4647(16)AOV5738AOV5737MV4644(16)CV8419PT944PT949PT950MAXIMUMISOLATION TZME*(SEC)NANANANANANA6060NANANANANAISOLATION BOUNDARY(11)(ll)MOV7443weldedshut(ll)(11)(17)(17)(11)AOV8418MV1819GMV1819FMV1819EMAXIMUM/ZSOLATZON TIME*(SEC)NANANormallyClosedNANANANANANANANANANA332Leakagetestandhydrogenmonitorinstrumentation linesMV7448MV7452MV7456SOV921SOV922SOV923SOV924NANANANANANANAcapcapcap(21)(21)(21)(21)NANANANANANAm~00 (10)(11)(12)(13)(14)(15)(16)(17)Thepressuretransmitter providesaboundary. | |||
Normallyoperating incomingandoutgoinglineswhichareconnected toclosedsystemsinsidecontainment andprotected againstmissilesthroughout theirlength,areprovidedwithatleastonemanualisolation valveoutsidecontainment (FSAR5.2.2pg.5.2.2-2). | |||
Thesingleremotelycontrolled containment isolation valveisnormallyopenandmotoroperated. | |||
Thecoolingwaterreturnlineisnotdirectlyconnected tothereactorcoolantsystemand,shouldremainopenwhilethecoolantpumpisrunning.Asecondautomatic isolation barrierisprovidedbythecomponent coolingwaterloop,aclosedsystem.(FSAR5.2.2pg.5.2.2-1a) | |||
SeeFSARTable5.2.2-1andFigure5.2.2-2.Sumplinesareinoperation andfilledwithfluidfollowing anaccident. | |||
Containment leakagetestingisnotrequired. | |||
Thevalvesaresubjected toRHRsystemhydrostatic test.Normallyoperating outgoinglinesconnected totheReactorCoolantSystemareprovidedwithatleastoneautomatically operatedtripvalveandonemanualisolation valveinserieslocatedoutsidethecontainment. | |||
Inadditiontotheisolation valves,eachlineconnected totheReactorCoolantSystemisprovidedwitharemoteoperatedrootvalvelocatednearitsconnection totheReactorCoolantSystem.(FSAR5.2.2pg.5.2.2-1)SeeFSARTable5.2.2-1andFigure5.2.2-17. | |||
TheServ'iceWatersystemoperates-atapressurehigherthanthecontainment accidentpressureandismissileprotected insidecontainment. | |||
Therefore, thesevalvesareusedforflowcontrolonlyandneednotbeleaktested.TheS/Gtubesandsecondary sideprovideaclosedsysteminsidecontainment. | |||
(18)FireServiceWaterwillbeusedonlytofightfiresinsidecontainment. | |||
AOV9227isclosedduringpoweroperation. | |||
Acontainment isolation signaltoautomatically closethisvalveisnotrequiredbecauseaspurioussignalduringafiremaybehazardous topersonnel andmayimpedefiresuppression activities. | |||
(19)(20)SeeFSARTable5.2.2-1andFigure5.2.2-16. | |||
Containment leakagetestingisnot,requiredperL.D.White,Jr.lettertoDennisL.Ziemann,USNRCdatedSeptember 21,1978.3.6-10Proposed Attachment BPage1of2Attachment BThepurposeofthisamendment istoreviseseveralpenetration listingsinTechnical Specification Table3.6-1tosupportanIntegrated LeakRateTest(ILRT)oftheGinnaStationcontainment duringthe1993Refueling Outage.Asaresultofpreparing forthistest,RG&Edetermined thatadiscrepancy existedbetweentheTechnical Specifications andtheNRCapprovedIn-Service Test(IST)Program.Currently, Technical Specification Table3.6-1identifies twomanualvalves(820and204A)ascontainment isolation valves(CIVs)forPenetration 112.Aspartofthethird10yearISTprogramsubmittal forGinnaStation,RG&Eidentified thatvalves820and204AwouldberemovedfromtheISTprogramsincetheirpressureandcontainment isolation functions werebeingperformed byvalves200A,200B,and202(Reference a).TheNRCacceptedthischangebyReference (b).Therefore, RG&ErequeststhatTable3.6-1bechangedtoreplacevalves820and204AwithAOVs200A,200B,and202.Inaddition, reliefvalve203,whichislocatedbetweencontainment isolation valves200A,200B,202and371forthispenetration, willbeaddedtothetable.Allfivevalvesarecurrently intheGinnaStationAppendixJtestingprogram.ThischangewillenablePenetration 112tomeettheexplicitrequirements ofGDC56.ThecurrentTable3.6-1Note17willalsobedeletedsinceitisnolongerused.Technical Specification Table3.6-1alsoidentifies amanualvalveinserieswithanair-operated valveastheCIVsforPenetrations 206,207,321,and322.Thesepenetrations containthesteamgenerator (S/G)blowdownandblowdownsamplepiping.RG&ErequeststhatthemanualvalvesberemovedfromTable3.6-1sincetheS/Gtubesandsecondary sideprovideonecontainment barrier.Thesepenetrations willthenbetreatedanalogous tothemainsteamandfeedwater lineswhichareofsimilarconfiguration. | |||
Table3.6-1Note17willthenberevisedandaddedtothesefourpenetrations toreflecttheuseoftheS/Gtubesandsecondary sideasacontainment boundary. | |||
Table3.6-1Note7willalsobedeletedfromthesefourpenetrations. | |||
Thisnotewasoriginally appliedtotheS/Gblowdownlinessincetheypenetrate themissileshieldinsidecontainment inordertoreachtheS/Gs.However,theNRChasapprovedtheuseof"leak-before-break" (LBB)withrespecttolargediameterReactorCoolantSystempipingatGinnaStation(Reference c).TheuseofLBBexcludestheconsideration ofthedynamiceffectsassociated withpostulated piperupturesper10CFR50,AppendixA,GDC4.Inaddition, plantwalkdowns andareviewofSystematic Evaluation Program(SEP)TopicIII-S.A,EffectsofPipeBreakonStructures, Systems,andComponents InsideContainment, (Reference d)confirmsthateventhoughthesefourlinespenetrate themissileshield,theyarenotsusceptible toanyhighenergylinesources.Thisincludestheaffectsofpipewhipandjetimpingement. | |||
Therefore, thedynamiceffectsassociated withanyhighenergylinebreakinsidecontainment doesnotrequireconsideration withrespecttotheS/Gclosedsystem.Theblowdownlinesinsidecontainment arealsoSeismicCategoryIandSafetyClass2.Consequently, thelinesareconsidered missileprotected basedontheirpresentlocationandhavethenecessary closedsystemdesignrequirements. | |||
Attachment BPage2of2RG&Ewillalsoeliminate 10CFR50AppendixJtestingrelatedtothefourAOVsforPenetrations 206,207,321,and322sincetherearenotanyrequirements toperformthistesting.Instead,RG&Ewillhydrostatically testthesevalvesinaccordance with'theoriginalrequirements asoutlinedintheapprovedthird10yearISTprogramforGinnaStation(IWV-3421 through3425)asaminimum.Thiswillprovidethenecessary assurance thatthevalveswillperformtheirrequiredisolation function. | |||
Thesechangeswillbedocumented intheGinnaStationISTProgramwhichwillbesubmitted totheNRCfollowing theconclusion ofthe1993Refueling OutagesinceRG&Eexpectstomakeseveralotherunrelated ISTProgramchangesatthattime.ThesechangeswillnotrequireNRCapprovalpriortoimplementation. | |||
Inaccordance with.10CFR50.91,thesechangestotheTechnical Specifications havebeenevaluated todetermine iftheoperation ofthefacilityinaccordance withtheproposedamendment would:1.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentpreviously evaluated; or3.involveasignificant reduction inamarginofsafety.Theseproposedchangesdonotincreasetheprobability orconsequences ofapreviously evaluated accidentorcreateanewordifferent typeofaccident. | |||
Furthermore, thereisnoreduction inthemarginofsafetyforanyparticular Technical Specification. | |||
Thedetailedchangesaredescribed inAttachment C.Therefore, Rochester GasandElectricsubmitsthattheissuesassociated withthisAmendment requestareoutsidethecriteriaof10CFR50.91;andanosignificant hazardsfindingiswarranted. | |||
==References:== | ==References:== | ||
(a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | (a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | ||
==Subject:== | ==Subject:== | ||
Inservice PumpandValveTestingProgram,datedMay23,1989.(b)LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&E, | |||
==Subject:== | ==Subject:== | ||
R.E.GinnaNuclearPowerP1antISTProgramforPumpsandValves,1990- | R.E.GinnaNuclearPowerP1antISTProgramforPumpsandValves,1990-1999 Third10-YearInterval, datedApril15,1991.(c)LetterfromD.DiIanni,NRC,toR.Kober,RG&E, | ||
==Subject:== | ==Subject:== | ||
ResolutionofUSI'-2," | ResolutionofUSI'-2,"Asymmetric LOCALoads",datedSeptember 9,1986.(d)NUREG-0821, Integrated PlantSafetyAssessment Systematic Evaluation Program,R.E.GinnaNuclearPowerPlant,December1982. | ||
IChangesAttachment CTechnical Specification ChangesEffect2.3.ReviseTable3.6-1Penetration 112todeletevalves204Aand820andaddvalves200A,200B,202,and203.ReviseTable3.6-1Penetration 206,207,321Iand322toreplacemanualisolation valveswithS/Gclosedsystem.AlsodeleteNote7fromthesepenetrations. | |||
TABLE3.6- | DeletecurrentTable3.6-1Note17andreplacewithnewNote17.Penetration nowsatisfies explicitrequirements ofGDC56.Penetration isnowconsistent withthemainsteamandfeedwater penetrations. | ||
~P(10)(11)(12)(13)(14)(15)(16) | S/Gclosedsystemprovidesanacceptable containment barrier.CurrentNote17isnolongerused.Newnoteprovidesinformation withrespecttoS/Gclosedsystem.Notechnical change. | ||
TABLE3.6-1CONTAINMENT ISOLATION VALVESPENT.NO.29IDENTIFICATION/DESCRIPTION FuelTransfertube100Charginglineto"B"loop101SIPump1Bdischarge 113SZPump1Adischarge 120NitrogentoAccumulators 120Pressurizer ReliefTank(PRT)toGasAnalyzer(GA)102Alternate chargingto"A"coldleg103Construction FireServiceWater105Containment SprayPump1A106"A"ReactorCoolantPump(RCP)sealwaterinlet107SumpAdischarge toWasteHoldupTank108RCPsealwateroutandexcessletdowntoVCT109Containment SprayPump1B110"B"RCPsealwaterinlet110SItestline111RHRto"B"coldleg112LetdowntoNon-regen. | |||
HeatExchanger ISOLATION BOUNDARYflangeCV370BCV889BCV870BCV383BweldedflangeCV862ACV304AAOV1728MOV313CV862BCV304BMV879MOV720(20)AOV371CV889ACV870ACV8623AOV539MAXIMUMISOLATION TIME*(SEC)NANANANANANANANA6060NANANANA60NANANA60ISOLATION BOUNDARY(1)(2)(5)(5)(2)MV5129(3)(2)AOV1723(4)(3)(2)(5)(6)~%4AXOV:'::200AmSueAOi~~20,0E, | |||
+14~+AOV,".".:":202:. | |||
RV,'.::.:2,03 (5)(5)AOV846MV546(7)MAXIMUM/ISOLATION TIME*(SEC)NANANANANANANA60NANANANANARA60.~i@NANA60NA 4lChIChPENT.NO.IDENTIFICATION/DESCRIPTION 141RHR-¹1pumpsuctionfromSumpB142RHR-¹2pumpsuctionfromSumpB143RCDTpumpsuction201ReactorCompart.CoolingUnitA&B202"B"Hydrogenrecombiner (pilot&main)203Contain.Press.Transmitter PT-947&948203Postaccidentairsampleto"B"fan210OxygenmakeuptoA&Brecombiners 204ShutdownPurgeSupplyDuct[PurgeSupplyDuct]205Hotlegloopsample206Przr.liquidspacesample206"A"S/Gsample207Przr.Steamspacesample207"B"S/Gsample209ReactorCompartment. | |||
CoolingUnitsA&BISOLATION BOUNDARYMOV850A(13)MOV850B(13)AOV1721MV4757(16)MV4636(16)MV1076BMV1084BPT947PT948MV1563MV1566flange(22)[AOV5870]AOV966CAOV966BAOV5735AOV966AAOV5736MV4758(16)MV4635(16)MV1080AMAXIMUMISOLATION TIME*(SEC)NANA60NANANANANANANANANA[5]6060606060NANANAZSOLATZON BOUNDARYMOV851A(13)MOV851B(13)AOV1003AAOV1003BSOV-ZV-3B SOV-IV-5B MV1819CMV1819DMV1565MV1568AOV5869(22)MV956D(14)MV956E(14)MV956FSOVIV-2ASOVZV-2BMAXIMUM/ISOLATION'TIME | |||
*(SEC)NANA6060NANANANormallyClosedNANormally~ | |||
ClosedNANANANANANANANANAm~NANormallyClosedNANormallyClosed80 a.PENT.NO.IDENTIFICATION/DESCRIPTION ISOLATION BOUNDARYMAXIMUMISOLATION TIME*(SEC)ZSOLATION BOUNDARYMAXIMUM/ISOLATION'TZ~ | |||
*(SEC)316ServiceWaterto"B"fancooler317Leakagetestsupply318Deadweighttester(decomissioned)- | |||
319320ServiceWaterfrom"A"fancoolerServicewaterto"C"fancooler321AS/GBlowdown322BS/GBlowdown323ServiceWaterfrom"D"fancooler332Leakagetestandhydrogenmonitorinstrumentation lines324Demineralized watertoContainment 332Cont.Press.Trans.PT-944,949&950MV4628(16)flangeweldedshutMV4629(16)MV4647(16)AOV5738AOV5737MV4644(16)CV8419PT944PT949PT950MV7448MV7452MV7456SOV921SOV922SOV923SOV924NANANANANA6060NANANANANANANANANANANANA(11)MOV7443weldedshut(ll)(11)(ll)AOV8418MV1819GMV1819FMV1819Ecapcapcap(21)(21)(21)(21)NANANormallyClosedNANANANANANANANANANANANANANANANA | |||
~P(10)(11)(12)(13)(14)(15)(16)Thepressuretransmitter providesaboundary. | |||
Normallyoperating incomingandoutgoinglineswhichareconnected toclosedsystemsinsidecontainment andprotected againstmissilesthroughout theirlength,areprovidedwithatleastonemanualisolation valveoutsidecontainment (FSAR5.2.2pg.5.2.2-2). | |||
Thesingleremotelycontrolled containment isolation valveisnormallyopenandmotoroperated. | |||
Thecoolingwaterreturnlineisnotdirectlyconnected tothereactorcoolantsystemand,shouldremainopenwhilethecoolantpumpisrunning.Asecondautomatic isolation barrierisprovidedbythecomponent coolingwaterloop,aclosedsystem.(FSAR5.2.2pg.5.2.2-la) | |||
SeeFSARTable5.2.2-1andFigure5.2.2-2.Sumplinesareinoperation andfilledwithfluidfollowing anaccident. | |||
Containment leakagetestingisnotrequired. | |||
Thevalvesaresubjected toRHRsystemhydrostatic test.Normallyoperating outgoinglinesconnected totheReactorCoolantSystemareprovidedwithatleastoneautomatically operatedtripvalveandonemanualisolation valveinserieslocatedoutsidethecontainment. | |||
Inadditiontotheisolation valves,eachlineconnected totheReactorCoolantSystemisprovidedwitharemoteoperatedrootvalvelocatednearitsconnection totheReactorCoolantSystem.(FSAR5.2.2pg.5.2.2-1)SeeFSARTable5.2.2-1andFigure5.2.2-17. | |||
TheServiceWatersystemoperatesatapressurehigherthanthecontainment accidentpressureandismissileprotected insidecontainment. | |||
Therefore, thesevalvesareusedforflowcontrolonlyandneednotbeleaktested.(17)(18)MNg+P">UP'P~..'S%%..g?N~"y+8%CP | |||
.~MgWCYW:,Ã>Y>g'eQP4CAVPehSWPV YV~'P~4QTne::,:Sy'G:;;::tubes',:".:::,::and:::;::s'e'conairj:.:."s'iai | |||
.':jr'ov'icte ji.:.:,:::,:glosi d~iyjjtem!rxniiide::,'.:':b'oi"i,0'a!i'n'i''eri'i ijFireServiceWaterwillbeusedonlytofightfiresinsidecontainment. | |||
AOV9227isclosedduringpoweroperation. | |||
Acontainment isolation signaltoautomatically closethisvalveisnotrequiredbecauseaspurioussignalduringafiremaybehazardous topersonnel andmayimpedefiresuppression activities. | |||
(19)SeeFSARTable5.2.2-1andFigure5.2.2-16. | |||
(20)Containment leakagetestingisnotrequiredperL.D.White,Jr.lettertoDennisL.Ziemann,USNRCdatedSeptember 21,1978.3.6-10 r,0,It}} | |||
Revision as of 12:02, 29 June 2018
| ML17263A210 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 04/05/1993 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A207 | List: |
| References | |
| NUDOCS 9304090209 | |
| Download: ML17263A210 (13) | |
Text
Attachment ARevisetheTechnical Specification pagesasfollows:Remove3.6-43.6-63.6-7A3.6-10Insert.3.6-43.6-63.6-7A3.6-109'304090209 930405PDRADOCK,05000244 P'DR TABLE3.6-1CONTAINMENT ISOLATION VALVESPENT.NO.29IDENTIFICATION/DESCRIPTION FuelTransfertube100Charginglineto"B"loop101SZPump1Bdischarge 113SZPump1Adischarge 120NitrogentoAccumulators 120Pressurizer ReliefTank(PRT)toGasAnalyzer(GA)102Alternate chargingto"A"coldleg103Construction FireServiceWater105Containment SprayPump1A106"A"ReactorCoolantPump(RCP)sealwaterinlet107SumpAdischarge toWasteHoldupTank108RCPsealwateroutandexcessletdowntoVCT109Containment SprayPump1B110"B"RCPsealwaterinlet110SZtestline111RHRto"B"coldleg112LetdowntoNon-regen.
HeatExchanger ZSOLATZON BOUNDARYflangeCV370BCV889BCV870BCV383BweldedflangeCV862ACV304AAOV1728MOV313CV862BCV304BMV879MOV720(20)AOV371CV889ACV870ACV8623AOV539MAXIMUMISOLATION TIME*(SEC)NANANANANANANANA6060NANANANA60NANANA60ISOLATION BOUNDARY(1)(2)(5)(5)(2)MV5129(3)(2)AOV1723(4)(3)(2)(5)(6)AOV200AAOV200BAOV202RV203(5)(5)AOV846MV546(7)MAXIMUM/ISOLATION TIME*(SEC)NANANANANANANA60NANANANANA606060NANANA60NA PgPENT.NO141142g0143IDENTIFICATION/DESCRIPTION RHR-tlpumpsuctionfromSumpBRHR-g2pumpsuctionfromSumpBRCDTpumpsuctionZSOLATION BOUNDARYMOV850A(13)MOV850B(13)AOV1721MAXIMUMISOLATION TIME*(SEC)NANA60ISOLATION BOUNDARYMOV851A(13)MOV851B(13)AOV1003AAOV1003BMAXIMUM/ISOLATION TIME*(SEC)NANA60604PI201ReactorCompart.CoolingUnitA&B202"B"Hydrogenrecombiner (pilot&main)203Contain.Press.Transmitter PT-947&948203Postaccidentairsampleto"B"fan204ShutdownPurgeSupplyDuct[PurgeSupplyDuct]205Hotlegloopsample206Przr.liquidspacesample206"A"S/Gsample207Przr.Steamspacesample207"B"S/Gsample209ReactorCompartment.
CoolingUnitsA&B210OxygenmakeuptoA&Brecombiners MV4757(16)MV4636(16)MV1076BMV1084BPT947PT948MV1563MV1566flange(22)[AOV5870]AOV966CAOV966BAOV5735AOV966AAOV5736MV4758(16)MV4635(16)MV1080ANANANANANANANANANA[5]6060606060NANANASOV-IV-3B SOV<<ZV-5B MV1819CMV1819DMV1565MV1568AOV5869(22)MV956D(14)MV956E(14)(17)MV956F(17)SOVZV-2ASOVIV-2BNANormallyClosedNANormallyClosedNANANANANANANANANANANANANormallyClosedNANormallyClosed00 PENT.o'O.O315316g0317318319320IDENTIFICATION/DESCRIPTION ServiceWaterfrom"C"fancoolerServiceWaterto"B"fancoolerLeakagetestsupplyDeadweighttester(decomissioned)
ServiceWaterfrom"A"fancoolerServicewaterto"C"fancooler4PI321AS/GBlowdown322BS/GBlowdown323ServiceWaterfrom"D"fancooler324Demineralized watertoContainment 332Cont.Press.Trans.PT-944,949&950ISOLATION BOUNDARYMV4643(16)MV4628(16)flangeweldedshutMV4629(16)MV4647(16)AOV5738AOV5737MV4644(16)CV8419PT944PT949PT950MAXIMUMISOLATION TZME*(SEC)NANANANANANA6060NANANANANAISOLATION BOUNDARY(11)(ll)MOV7443weldedshut(ll)(11)(17)(17)(11)AOV8418MV1819GMV1819FMV1819EMAXIMUM/ZSOLATZON TIME*(SEC)NANANormallyClosedNANANANANANANANANANA332Leakagetestandhydrogenmonitorinstrumentation linesMV7448MV7452MV7456SOV921SOV922SOV923SOV924NANANANANANANAcapcapcap(21)(21)(21)(21)NANANANANANAm~00 (10)(11)(12)(13)(14)(15)(16)(17)Thepressuretransmitter providesaboundary.
Normallyoperating incomingandoutgoinglineswhichareconnected toclosedsystemsinsidecontainment andprotected againstmissilesthroughout theirlength,areprovidedwithatleastonemanualisolation valveoutsidecontainment (FSAR5.2.2pg.5.2.2-2).
Thesingleremotelycontrolled containment isolation valveisnormallyopenandmotoroperated.
Thecoolingwaterreturnlineisnotdirectlyconnected tothereactorcoolantsystemand,shouldremainopenwhilethecoolantpumpisrunning.Asecondautomatic isolation barrierisprovidedbythecomponent coolingwaterloop,aclosedsystem.(FSAR5.2.2pg.5.2.2-1a)
SeeFSARTable5.2.2-1andFigure5.2.2-2.Sumplinesareinoperation andfilledwithfluidfollowing anaccident.
Containment leakagetestingisnotrequired.
Thevalvesaresubjected toRHRsystemhydrostatic test.Normallyoperating outgoinglinesconnected totheReactorCoolantSystemareprovidedwithatleastoneautomatically operatedtripvalveandonemanualisolation valveinserieslocatedoutsidethecontainment.
Inadditiontotheisolation valves,eachlineconnected totheReactorCoolantSystemisprovidedwitharemoteoperatedrootvalvelocatednearitsconnection totheReactorCoolantSystem.(FSAR5.2.2pg.5.2.2-1)SeeFSARTable5.2.2-1andFigure5.2.2-17.
TheServ'iceWatersystemoperates-atapressurehigherthanthecontainment accidentpressureandismissileprotected insidecontainment.
Therefore, thesevalvesareusedforflowcontrolonlyandneednotbeleaktested.TheS/Gtubesandsecondary sideprovideaclosedsysteminsidecontainment.
(18)FireServiceWaterwillbeusedonlytofightfiresinsidecontainment.
AOV9227isclosedduringpoweroperation.
Acontainment isolation signaltoautomatically closethisvalveisnotrequiredbecauseaspurioussignalduringafiremaybehazardous topersonnel andmayimpedefiresuppression activities.
(19)(20)SeeFSARTable5.2.2-1andFigure5.2.2-16.
Containment leakagetestingisnot,requiredperL.D.White,Jr.lettertoDennisL.Ziemann,USNRCdatedSeptember 21,1978.3.6-10Proposed Attachment BPage1of2Attachment BThepurposeofthisamendment istoreviseseveralpenetration listingsinTechnical Specification Table3.6-1tosupportanIntegrated LeakRateTest(ILRT)oftheGinnaStationcontainment duringthe1993Refueling Outage.Asaresultofpreparing forthistest,RG&Edetermined thatadiscrepancy existedbetweentheTechnical Specifications andtheNRCapprovedIn-Service Test(IST)Program.Currently, Technical Specification Table3.6-1identifies twomanualvalves(820and204A)ascontainment isolation valves(CIVs)forPenetration 112.Aspartofthethird10yearISTprogramsubmittal forGinnaStation,RG&Eidentified thatvalves820and204AwouldberemovedfromtheISTprogramsincetheirpressureandcontainment isolation functions werebeingperformed byvalves200A,200B,and202(Reference a).TheNRCacceptedthischangebyReference (b).Therefore, RG&ErequeststhatTable3.6-1bechangedtoreplacevalves820and204AwithAOVs200A,200B,and202.Inaddition, reliefvalve203,whichislocatedbetweencontainment isolation valves200A,200B,202and371forthispenetration, willbeaddedtothetable.Allfivevalvesarecurrently intheGinnaStationAppendixJtestingprogram.ThischangewillenablePenetration 112tomeettheexplicitrequirements ofGDC56.ThecurrentTable3.6-1Note17willalsobedeletedsinceitisnolongerused.Technical Specification Table3.6-1alsoidentifies amanualvalveinserieswithanair-operated valveastheCIVsforPenetrations 206,207,321,and322.Thesepenetrations containthesteamgenerator (S/G)blowdownandblowdownsamplepiping.RG&ErequeststhatthemanualvalvesberemovedfromTable3.6-1sincetheS/Gtubesandsecondary sideprovideonecontainment barrier.Thesepenetrations willthenbetreatedanalogous tothemainsteamandfeedwater lineswhichareofsimilarconfiguration.
Table3.6-1Note17willthenberevisedandaddedtothesefourpenetrations toreflecttheuseoftheS/Gtubesandsecondary sideasacontainment boundary.
Table3.6-1Note7willalsobedeletedfromthesefourpenetrations.
Thisnotewasoriginally appliedtotheS/Gblowdownlinessincetheypenetrate themissileshieldinsidecontainment inordertoreachtheS/Gs.However,theNRChasapprovedtheuseof"leak-before-break" (LBB)withrespecttolargediameterReactorCoolantSystempipingatGinnaStation(Reference c).TheuseofLBBexcludestheconsideration ofthedynamiceffectsassociated withpostulated piperupturesper10CFR50,AppendixA,GDC4.Inaddition, plantwalkdowns andareviewofSystematic Evaluation Program(SEP)TopicIII-S.A,EffectsofPipeBreakonStructures, Systems,andComponents InsideContainment, (Reference d)confirmsthateventhoughthesefourlinespenetrate themissileshield,theyarenotsusceptible toanyhighenergylinesources.Thisincludestheaffectsofpipewhipandjetimpingement.
Therefore, thedynamiceffectsassociated withanyhighenergylinebreakinsidecontainment doesnotrequireconsideration withrespecttotheS/Gclosedsystem.Theblowdownlinesinsidecontainment arealsoSeismicCategoryIandSafetyClass2.Consequently, thelinesareconsidered missileprotected basedontheirpresentlocationandhavethenecessary closedsystemdesignrequirements.
Attachment BPage2of2RG&Ewillalsoeliminate 10CFR50AppendixJtestingrelatedtothefourAOVsforPenetrations 206,207,321,and322sincetherearenotanyrequirements toperformthistesting.Instead,RG&Ewillhydrostatically testthesevalvesinaccordance with'theoriginalrequirements asoutlinedintheapprovedthird10yearISTprogramforGinnaStation(IWV-3421 through3425)asaminimum.Thiswillprovidethenecessary assurance thatthevalveswillperformtheirrequiredisolation function.
Thesechangeswillbedocumented intheGinnaStationISTProgramwhichwillbesubmitted totheNRCfollowing theconclusion ofthe1993Refueling OutagesinceRG&Eexpectstomakeseveralotherunrelated ISTProgramchangesatthattime.ThesechangeswillnotrequireNRCapprovalpriortoimplementation.
Inaccordance with.10CFR50.91,thesechangestotheTechnical Specifications havebeenevaluated todetermine iftheoperation ofthefacilityinaccordance withtheproposedamendment would:1.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentpreviously evaluated; or3.involveasignificant reduction inamarginofsafety.Theseproposedchangesdonotincreasetheprobability orconsequences ofapreviously evaluated accidentorcreateanewordifferent typeofaccident.
Furthermore, thereisnoreduction inthemarginofsafetyforanyparticular Technical Specification.
Thedetailedchangesaredescribed inAttachment C.Therefore, Rochester GasandElectricsubmitsthattheissuesassociated withthisAmendment requestareoutsidethecriteriaof10CFR50.91;andanosignificant hazardsfindingiswarranted.
References:
(a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,
Subject:
Inservice PumpandValveTestingProgram,datedMay23,1989.(b)LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&E,
Subject:
R.E.GinnaNuclearPowerP1antISTProgramforPumpsandValves,1990-1999 Third10-YearInterval, datedApril15,1991.(c)LetterfromD.DiIanni,NRC,toR.Kober,RG&E,
Subject:
ResolutionofUSI'-2,"Asymmetric LOCALoads",datedSeptember 9,1986.(d)NUREG-0821, Integrated PlantSafetyAssessment Systematic Evaluation Program,R.E.GinnaNuclearPowerPlant,December1982.
IChangesAttachment CTechnical Specification ChangesEffect2.3.ReviseTable3.6-1Penetration 112todeletevalves204Aand820andaddvalves200A,200B,202,and203.ReviseTable3.6-1Penetration 206,207,321Iand322toreplacemanualisolation valveswithS/Gclosedsystem.AlsodeleteNote7fromthesepenetrations.
DeletecurrentTable3.6-1Note17andreplacewithnewNote17.Penetration nowsatisfies explicitrequirements ofGDC56.Penetration isnowconsistent withthemainsteamandfeedwater penetrations.
S/Gclosedsystemprovidesanacceptable containment barrier.CurrentNote17isnolongerused.Newnoteprovidesinformation withrespecttoS/Gclosedsystem.Notechnical change.
TABLE3.6-1CONTAINMENT ISOLATION VALVESPENT.NO.29IDENTIFICATION/DESCRIPTION FuelTransfertube100Charginglineto"B"loop101SIPump1Bdischarge 113SZPump1Adischarge 120NitrogentoAccumulators 120Pressurizer ReliefTank(PRT)toGasAnalyzer(GA)102Alternate chargingto"A"coldleg103Construction FireServiceWater105Containment SprayPump1A106"A"ReactorCoolantPump(RCP)sealwaterinlet107SumpAdischarge toWasteHoldupTank108RCPsealwateroutandexcessletdowntoVCT109Containment SprayPump1B110"B"RCPsealwaterinlet110SItestline111RHRto"B"coldleg112LetdowntoNon-regen.
HeatExchanger ISOLATION BOUNDARYflangeCV370BCV889BCV870BCV383BweldedflangeCV862ACV304AAOV1728MOV313CV862BCV304BMV879MOV720(20)AOV371CV889ACV870ACV8623AOV539MAXIMUMISOLATION TIME*(SEC)NANANANANANANANA6060NANANANA60NANANA60ISOLATION BOUNDARY(1)(2)(5)(5)(2)MV5129(3)(2)AOV1723(4)(3)(2)(5)(6)~%4AXOV:'::200AmSueAOi~~20,0E,
+14~+AOV,".".:":202:.
RV,'.::.:2,03 (5)(5)AOV846MV546(7)MAXIMUM/ISOLATION TIME*(SEC)NANANANANANANA60NANANANANARA60.~i@NANA60NA 4lChIChPENT.NO.IDENTIFICATION/DESCRIPTION 141RHR-¹1pumpsuctionfromSumpB142RHR-¹2pumpsuctionfromSumpB143RCDTpumpsuction201ReactorCompart.CoolingUnitA&B202"B"Hydrogenrecombiner (pilot&main)203Contain.Press.Transmitter PT-947&948203Postaccidentairsampleto"B"fan210OxygenmakeuptoA&Brecombiners 204ShutdownPurgeSupplyDuct[PurgeSupplyDuct]205Hotlegloopsample206Przr.liquidspacesample206"A"S/Gsample207Przr.Steamspacesample207"B"S/Gsample209ReactorCompartment.
CoolingUnitsA&BISOLATION BOUNDARYMOV850A(13)MOV850B(13)AOV1721MV4757(16)MV4636(16)MV1076BMV1084BPT947PT948MV1563MV1566flange(22)[AOV5870]AOV966CAOV966BAOV5735AOV966AAOV5736MV4758(16)MV4635(16)MV1080AMAXIMUMISOLATION TIME*(SEC)NANA60NANANANANANANANANA[5]6060606060NANANAZSOLATZON BOUNDARYMOV851A(13)MOV851B(13)AOV1003AAOV1003BSOV-ZV-3B SOV-IV-5B MV1819CMV1819DMV1565MV1568AOV5869(22)MV956D(14)MV956E(14)MV956FSOVIV-2ASOVZV-2BMAXIMUM/ISOLATION'TIME
- (SEC)NANA6060NANANANormallyClosedNANormally~
ClosedNANANANANANANANANAm~NANormallyClosedNANormallyClosed80 a.PENT.NO.IDENTIFICATION/DESCRIPTION ISOLATION BOUNDARYMAXIMUMISOLATION TIME*(SEC)ZSOLATION BOUNDARYMAXIMUM/ISOLATION'TZ~
- (SEC)316ServiceWaterto"B"fancooler317Leakagetestsupply318Deadweighttester(decomissioned)-
319320ServiceWaterfrom"A"fancoolerServicewaterto"C"fancooler321AS/GBlowdown322BS/GBlowdown323ServiceWaterfrom"D"fancooler332Leakagetestandhydrogenmonitorinstrumentation lines324Demineralized watertoContainment 332Cont.Press.Trans.PT-944,949&950MV4628(16)flangeweldedshutMV4629(16)MV4647(16)AOV5738AOV5737MV4644(16)CV8419PT944PT949PT950MV7448MV7452MV7456SOV921SOV922SOV923SOV924NANANANANA6060NANANANANANANANANANANANA(11)MOV7443weldedshut(ll)(11)(ll)AOV8418MV1819GMV1819FMV1819Ecapcapcap(21)(21)(21)(21)NANANormallyClosedNANANANANANANANANANANANANANANANA
~P(10)(11)(12)(13)(14)(15)(16)Thepressuretransmitter providesaboundary.
Normallyoperating incomingandoutgoinglineswhichareconnected toclosedsystemsinsidecontainment andprotected againstmissilesthroughout theirlength,areprovidedwithatleastonemanualisolation valveoutsidecontainment (FSAR5.2.2pg.5.2.2-2).
Thesingleremotelycontrolled containment isolation valveisnormallyopenandmotoroperated.
Thecoolingwaterreturnlineisnotdirectlyconnected tothereactorcoolantsystemand,shouldremainopenwhilethecoolantpumpisrunning.Asecondautomatic isolation barrierisprovidedbythecomponent coolingwaterloop,aclosedsystem.(FSAR5.2.2pg.5.2.2-la)
SeeFSARTable5.2.2-1andFigure5.2.2-2.Sumplinesareinoperation andfilledwithfluidfollowing anaccident.
Containment leakagetestingisnotrequired.
Thevalvesaresubjected toRHRsystemhydrostatic test.Normallyoperating outgoinglinesconnected totheReactorCoolantSystemareprovidedwithatleastoneautomatically operatedtripvalveandonemanualisolation valveinserieslocatedoutsidethecontainment.
Inadditiontotheisolation valves,eachlineconnected totheReactorCoolantSystemisprovidedwitharemoteoperatedrootvalvelocatednearitsconnection totheReactorCoolantSystem.(FSAR5.2.2pg.5.2.2-1)SeeFSARTable5.2.2-1andFigure5.2.2-17.
TheServiceWatersystemoperatesatapressurehigherthanthecontainment accidentpressureandismissileprotected insidecontainment.
Therefore, thesevalvesareusedforflowcontrolonlyandneednotbeleaktested.(17)(18)MNg+P">UP'P~..'S%%..g?N~"y+8%CP
.~MgWCYW:,Ã>Y>g'eQP4CAVPehSWPV YV~'P~4QTne::,:Sy'G:;;::tubes',:".:::,::and:::;::s'e'conairj:.:."s'iai
.':jr'ov'icte ji.:.:,:::,:glosi d~iyjjtem!rxniiide::,'.:':b'oi"i,0'a!i'n'ieri'i ijFireServiceWaterwillbeusedonlytofightfiresinsidecontainment.
AOV9227isclosedduringpoweroperation.
Acontainment isolation signaltoautomatically closethisvalveisnotrequiredbecauseaspurioussignalduringafiremaybehazardous topersonnel andmayimpedefiresuppression activities.
(19)SeeFSARTable5.2.2-1andFigure5.2.2-16.
(20)Containment leakagetestingisnotrequiredperL.D.White,Jr.lettertoDennisL.Ziemann,USNRCdatedSeptember 21,1978.3.6-10 r,0,It