ML17264A979

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Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A979
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/05/1997
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A976 List:
References
AP-RCS.3, NUDOCS 9708130145
Download: ML17264A979 (83)


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EOP:AP-RCS.3TITLE:HIGHREACTORCOOLANTACTIVITYREV:7PAGE1of6ROCHESTER GASANDELECTRICCORPORATION GINNASTATIONCONTROLLED COPYNUMBERRESPONSIB MANAGEREFFECTIVE DATECATEGORY1.0REVIEWEDBY:9708iSOCR05000244pi459'70805PDRADOCF EOP:AP-RCS.3HIGHREACTORCOOLANTACTIVITYREV7PAGE2of6A.PURPOSE-Thisprocedure providesguidancenecessary tooperatetheplantwithindication ofhighreactorcoolantactivity.

B.ENTRYCONDITIONS/SYMPTOMS 1.SYMPTOMS-ThesymptomsofHIGHREACTORCOOLANTACTIVITYare;a.Unexplained increaseinletdownlinemonitor,R-9,orb.Samplingindicates I-131equivalent GREATERTHAN1.0uCi/gm,orc.Samplingindicates grossdegassedactivityGREATERTHAN20uCi/gm,ord.Sampling, indicates thattotalspecificactivityexceeds100/E.

I'I EOP:AP-RCS.3TITLE:HIGHREACTORCOOLANTACTIVITYREV:7PAGE3of6STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINEDCAUTIONoIFLETDOWNFLOWEXCEEDS60GPM,THENLOCALLYMONITORD/PACROSSTHECVCSDI(S)TOVERIFYTHATFLOWISCONTINUING ANDTHATRELIEFVALVE,V-209,HASNOTLIFTED.oLETDOWNFLOWTHROUGHTHEDI'SSHOULDBELIMITEDTO90GPM.**********'k******************************NOTE:Conditions shouldbeevaluated forsitecontingency reporting (RefertoEPIP-1.0, GINNASTATIONEVENTEVALUATION ANDCLASSIFICATION.

1VerifyRCSActivity:

a.DirectRPTechtosampleRCSforactivityb.RCS,activity-GREATERTHANNORMAL(CheckwithRPDepartment fornormalactivity) b.IFnormalactivityverified, THENdirect1&Ctocheckoperability ofR-9,letdownlinemonitor,ANDreturntonormaloperations.

yEOP:AP-RCS~3TITLE:HIGHREACTORCOOLANTACTIVITYREV:7PAGE4of6STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED2IncreaseLetdownFlowTo60GPMa.Verifydeborating DIisolated-DIVERTVLVCATIONDEBORDIAOV-244INBYPASSPOSITIONa.PlaceAOV-244inbypassposition.

b.Placeletdowncontrollers inMANUALat60%open~TCV-130~PCV-135c.Increaseletdownflowasfollows:1)Closeletdownorificevalve(AOV-200A orAOV-200B) 2)Immediately open60gpmletdownorificevalve,AOV-202Wd.Adjustlowpressureletdownpressuretoapproximately 250psige.PlaceTCV-130inAUTOat105'Ff.PlacePCV-135inAUTOat250psigg.AdjustchargingpumpspeedandHCV-142asnecessary eC)

EOP:AP-RCS.3TITLE:HIGHREACTORCOOLANTACTIVITYREV:7PAGE5of6STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED3CheckLetdownLineMonitor,R-9-LESSTHAN200MR/HRABOVEBACKGROUND Evaluateconditions todetermine whetherlocalradiation emergency exists(RefertoEPIP1-13,LOCALRADIATION EMERGENCY).

CAUTIONPLACINGANEWDIINSERVICEMAYRESULTINAPOSITIVEORNEGATIVEREACTIVITY ADDITIONDUETOABORONCHANGE.4DirectRPTechToSampleLetdownDIEfficiency-DECONTAMINATION FACTORGREATERTHAN10IFDIefficiency isNOTacceptable, THENplaceanewmixedbedinservice(RefertoS-3.2B,PLACINGAMIXEDBEDDEMINERALIZER INSERVICEBORONCONCENTRATION DIFFERENT THANRCS).5EvaluateAUXBLDGRadiation Levels:a.DirectRPTechtosurveyAUXBLDG'.CheckAUXBLDGradiation monitors-NORMAL~R-4~R-9~R-10B~R-13~R-14b.Performthefollowing:

1)DirectRPTechtosurveyAUXBLDGareasasnecessary.

2)Evaluateconditions todetermine whetherlocalradiation emergency exists(RefertoEPIP1-13,LOCALRADIATION EMERGENCY).

00 EOP:AP-RCS.371ILE:HIGHREACTORCOOLANTACTIVITYREV:7PAGE6of6STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED6Determine IfPlantOperation CanContinue(ConsultPlantstaffifnecessary)

OPERATION CANCONTINUEIFplantshutdownisrequired,=

THENreferto0-2.1,NORMALSHUTDOWNTOHOTSHUTDOWN.

NOTE:Referto0-9.3,NRCIMMEDIATE NOTIFICATION, forreporting requirements.

7NotifyHigherSupervision

-END-ii, Distribution SheetDistri-1.txt Priority:

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Copies:00000OKOKOKOKOKOKOKOKOKPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID011700281:1

Subject:

'mprovedTechnical Specifications (ITS),Amendment No.-79;ITSBasesRevision20;andTechnical Requirements ManualRevision17.DocumentDate:06/07/2001 Body:ADAMSDISTRIBUTION NOTIFICATION.

A001-ORSubmittal:

GeneralDistribution forPowerReactor(10CFR50)Submittals Title:ImprovedTechnical Specifications (ITS),Amendment No.79;ITSBasesRevision20;andTechnical Requirements ManualRevision17.DocketNumber:05000244DocumentDate:06/07/2001 AuthorName:HardingTLAuthorAffiliation:

Rochester Gas8ElectricCorpPage1 t7 Addressee Name:Addressee Affiliation:

DocumentType:ManualAvailability:

PubliclyAvailable DocumentSensitivity:

Non-Sensitive Comment:Distri-1.txt Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML011700281.

Page2

8ROCHESTER GASEc,ELECTRICCORPORATION DOCUMENTCONTROLDocumentTransmittal To:DOCUMENTCONTROLDESKUSNRCATT:GUYVISSINGPROJECTDOCTORATE l-lWASHINGTON DC20555Transmittal:

200106005 053Date:06/07/2001 Holder:1217LISTEDBELOWARENEWORREVISEDCONTROLLED DOCUMENTS.

REVIEWTHEATTACHEDINSTRUCTION LETTER(IFAPPLICABLE),

ANDUPDATEYOURCONTROLLED DOCUMENTINACCORDANCE WITHEP-3-S-0901 DocIdTRMDocTitleTECHNICAL REQUIREMENTS MANUALFORGINNASTATIONRevRevDateQty01706/08/2001 1ReceiptAcknowledgement andActionTaken:Signature DateReturnENTIREFORMto:Rochester Gas&ElectricCorporation GinnaStation-RecordsManagement 1503LakeRoadOntario,NewYork14519 Rochester GasandElectricCorporation Inter-Office Correspondence June7,2001

Subject:

ImprovedTechnical Specifications (ITS),Amendment No.79;ITSBasesRevision20;andTechnical Requirements Manual(TRM)Revision17TotDistribution AttachedisAmendment No.79totheGinnaStationImprovedTechnical Specifications (ITS).ThisAmendment revisestheITSrequirements forthestorageofnewandspentfuelwithintheSpentFuelPool.ThisAmendment wasapprovedbytheNRCinasafetyevaluation datedDecember7,2000.InadditiontotheAmendment, theassociated changestotheITSBasesandtheTechnical Requirements Manualareincluded.

Instructions forthenecessary changestoyourcontrolled copyoftheITSareattached.

Thesechangesareconsidered effective June8,2001.PleasecontactTomHarding(extension 3384)ifyouhaveanyquestions.

rx-~~ThomasL.Harding Attachment APleasereplacethefollowing pagesofyourcontrolled copyoftheITSasfollows:VolumeSectionRemoveInsertIIIIIIIIIIIIIIIIIIIIIIIIAttachment AtoLicenseAttachment AtoLicenseChapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)Chapter3.7(LCO)FirstPageLEP-ithroughLEP-vii3.7-293.7-303.7-313.7-31a3.7-31bFirstPageLEP-ithroughLEP-vii3.7-293.7-303.7-313.7-31a3.7-31b3.7-31c3.7-31d3.7-31e3.7-31f3.7-31g3.7-3lh3.7-31iChapter3.7(Bases)Chapter3.7(Bases)B3.7.12-1throughB3.7.12-3B3.7.12-1throughB3.7.12-4B3.7.13-1through83.7.13-6B3.7.13-1throughB3.7.13-7IIIIIIIIIIIIIIIIIIIIIIIIIIIChapter4.0Chapter4.0TRMTRMTRMTRMChapter3.7(TR)TRMChapter3.7(TR)TRMChapter3.7(Bases)TRMChapter3.7(Bases)TRMChapter3.7(Bases)TRMChapter3.7(Bases)TRMChapter3.7(Bases)TRMChapter3.7(Bases)4.0-24.0-3FirstPageLEP-iLEP-iiTR3.7.7-1TR3.7.7-2TR3.7.7-1TR3.7.7-2TR3.7.7-3TR3.7.7-4TR3.7.7-54.0-24.0-3FirstPageLEP-iLEP-iiTR3.7.7-1TR3.7.7-2TRB3.7.7-1TRB3.7.7-2TRB3.7.7-3TRB3.7.7-4TRB3.7.7-5TRB3.7.7-6 a+iR.E.GinnaNuclearPowerPlantTechnical Requirements MaalTRMRevision16Responsibl Manager:GeorgerobelEffctiveDate:6/(/goo6/1/2001Controlle CopyNo.R.E.GinnaNuclearPowerPlantTRM-1Revision6 ListofEffective Pages(TRM)PageTOCRev.PageRev.PageRev.PageRev.Section4.0Section1.0TR1.0-1Section2.0TR2.1-1Section3.0TR3.0-1TR3.0-2Section3.1TR3.1.1-1TR3.1.1-2TR3.1.1-3TR3.1.2-1TR3.1.2-2Section3.2TR3.2-1151514141414141414141414TR3.3.4-1TR3.3.4-2TR3.3.4-3TR3.3.4QTR3.3.4-5TR3.3.4-6TR3.3.4-7TR3.3.5-1TR3.3.5-2TR3.3.5-3Section3.4TR3.4.1-1TR3.4.1-2TR3.4.2-1TR3.4.2-2TR3.4.2-3TR3.4.3-1TR3.4.3-2TR3.4.3-3TR3.4.34TR3.4.3-5TR3.4.3-6Section3.5TR3.5-1Section3.614141414141414141414141414141414141414141414TR3.7.2-1TR3.7.2-2TR3.7.2-3TR3.7.2CTR3.7.2-5TR3.7.3-1TR3.7.3-2TR3.7.3-3TR3.7A-1TR3.7.4-2TR3.7.4-3TR3.7.4-4TR3.7.5-1TR3.7.5-2TR3.7.5-3TR3.7.5-4TR3.7.5-5TR3.7.6-1TR3.7.6-2TR3.7.7-1TR3.7.7-2TR3.7.8-1TR3.7.8-2Section3.8TR3.8.1-1TR3.8.2-1TR3.8.2-2Section3.91414141414141414141414141414141414141414141515141414TR4.0-114Section5.0TR5.1-116TR5.1-2'6Section3.3TR3.3.1-1TR3.3.1-2TR3.3.2-1TR3.3.2-2TR3.3.3-11414141414TR3.6-1Section3.7TR3.7.1-1TR3.7.1-2TR3.7.1-314141414TR3.9.1-1TR3.9.2-1TR3.9.2-2TR3.9.3-1TR3.9.4-1TR3.9.4-2141414'141414R.E.GinnaNuclearPowerPlantLEP-iRevision16 iistofEffective Pages(TRMBases)PageTOCRev.PageRev.PageSection3.7Rev.PageRev.Section2.0Section3.0Section3.1Section3.215TRB3.7.1-1TRB3.7.2-1TRB3.7.3-1TRB3.7.4-1TRB3.7.5-1TRB3.7.6-1TRB3.7.7-1TRB3.7.7-2TRB3.7.7-3TRB3.7.7-4TRB3.7.7-5TRB3.7.8-1TRB3.7.8-2TRB3.7.8-31414141414141414141414151515Section3.3Section3.8Section3.4Section3.9Section3.5Section3.6TRB3.9.1-1TRB3.9.1-2TRB3.9.1-3TRB3.9.2-1TRB3.9.3-1TRB3.9.4-1TRB3.9.4-2TRB3.9.4-3TRB3.9.4Q141414141414141414Section4.0Section5.0R.E.GinnaNuclearPowerPlantLEP-iiRevision16 SFPCoolingSystemTR3.7.73.7PLANTSYSTEMSTR3.7.7SpentFuelPool(SFP)CoolingSystemTR3.7.7TheSFPcoolingsystemshallbemaintained asfollows:a.TheSFPwatertemperature shallbe<150'F;andb.TwoSFPcoolingsystemsshallbeOPERABLE, eachcommensurate withtheSFPheatload.-NOTE-TheSFPheatloadandSFPcoolingcapabilities aredetermined byNuclearEngineering Services.

APPLICABILITY:

Wheneveranyirradiated fuelassemblyisstoredintheSFP.ACTIONSCONDITION REQUIREDACTIONCOMPLETION TIMEA.SFPtemperature notwithinlimit.A.1Suspendmovementofirradiated fuelassemblies fromthereactortotheSFP.Immediately ANDB.OnerequiredSFPcoolingsysteminoperable.

A.2InitiateactiontorestoreSFPImmediately temperature towithinlimit.B.1SuspendmovementofImmediately irradiated fuelassemblies fromthereactortotheSFP.AND8.2RestoreasecondSFPcoolingsystemtoOPERABLEstatus.14daysR.E.GinnaNuclearPowerPlantTR3.7.7-1Revision14 SFPCoolingSystemTR3.7.7CONDITION C.BothrequiredSFPcoolingsystemsinoperable.

REQUIREDACTIONC.1PerformTSR3.7.7.1.COMPLETION TIMEOncewithin1hourandevery4hoursthereafter ANDC.2RestoreoneSFPcoolingsystemtoOPERABLEstatus.PriortotheSFPwatertemperature exceeding 120'FSURVEILLANCE REQUIREMENTS.

SURVEILLANCE FREQUENCY TSR3.7.7.1VerifySFPtemperature iswithinlimit.24HoursTSR3.7.7.2Verifypoweravailable tothetwoOPERABLESFPcoolingsystems.7daysR.E.GinnaNuclearPowerPlantTR3.7.7-2Revision14 SpentFuelf(SFP)CoolingSystemTRB3.7.7B3.7PLANTSYSTEMSTRB3.7.7SpentFuelPool(SFP)CoolingSystemBASESBACKGROUND TheSpentFuelPool(SFP)CoolingSystemisdesignedtoremov'efromtheSFPtheheatgenerated bystoredspentfuelassemblies.

TheSFPCoolingSystemconsistsofthreecoolingloops(seeFigureTRB3.7.7-1).

Theprimaryloop(loopB)ismadeupoftheSFPPumpB,SFPHeatExchanger B,andpiping.Thebackuploopsincludeinstalled loopAwiththeSFPPumpA,SFPHeatExchanger A,andpiping,andastandbyloopwiththeSkid-Mounted SFPPump,SFPStandbyHeatExchanger, andhoses.Servicewater(SW)circulates throughtheshellwhileSFPwatercirculates throughthetubesofallthreeheatexchangers.

TheSFPCoolingSystemloopBissizedfor100%ofthedesignSFPheatload.TheSFPCoolingSystemloopAandthestandbyloopareeachcapableofremovingthenormalbasisheatloadandwhenoperatedinparallelcanremovemorethan100%ofthedesignheatload(Ref.1).Motor-operatedvalvesprovideautomatic andremotemanualisolation oftheSWsupplytotheheatexchangers associated withtheSFPCoolingSystemloopsAand8andtheComponent CoolingWaterHeatExchangers.

Thesevalvescloseautomatically uponcoincidence ofsafetyinjection andlossofoffsitepower.Handwheels areprovidedformanualoperation.

TheSFPCoolingSystemisdesignedtomaintainthepool(120'Fduringnormalrefueling conditions ands150'Fduringfullcoredischarge operations (Ref:1).ThecoolingsystemscantakeasuctionfromeithernearthesurfaceoftheSFPand/oratapointabovetheirradiated fuelassemblies, suchthatafailureofanypipeinthesystemwillnotdrainthepooltoapointwherethefuelwouldbeexposed.Thecoolingsystemreturnlinetothepoolalsocontainsa0.25inchventholelocatedneartheSFPsurfaceleveltopreventsiphoning.

ControlboardalarmsexistwithrespecttotheSFPlevelandtemperature.

Thesefeaturesallhelptopreventinadvertent drainingoftheSFP.APPLICABLE SAFETYANALYSESForstructural integrity reasons,thepoolwatertemperature isnottoexceed180'F.Inordertoprovidesufficient timetotakecorrective actionintheeventofaSFPCoolingSystemfailure,thepooltemperature limitisnottoexceed150'Fforallmodesofoperation including afullcoredischarge.

Therequirement fortwo100%SFPCoolingSystemsisbasedonbeingabletoprovidecoolingfollowing eitheralossofoffsitepoweroranactivesinglefailurewithintheSFPCoolingSystem.R.E.GinnaNuclearPowerPlantTRB3.7.7-1Revision14 SpentFuelP(SFP)CoolingSystemTRB3.7.7'TRTheSFPwatertemperature isrequiredtobe<150'F.Thespecified watertemperature providessufficient margintotheassumptions oftheSFPstructural integrity.

Assuch,itisthemaximumallowedwhilestoringirradiated fuelassemblies withintheSFP.ToensurethattheSFPtemperature canbemaintained withintherequiredlimit,twoSFPCoolingSystemsmustbeOPERABLE.

Thisrequirement providesfor100%backupcapability assumingeitheralossofoffsitepoweroranactivesinglefailurewithintheSFPCoolingSystem.SFPCoolingSystemloopAandloopBareconsidered OPERABLEwhentherespective pumphaspoweravailable andtherespective heatexchanger iscapableofproviding coolingwaterwiththeabilitytoremovethedecayheatloadoftheirradiated fuelassemblies storedwithintheSFP.Thestandbyloopisconsidered OPERABLEwhentheSkid-MountedSFPPumphaspowerconnected toatemporary powersource,theSFPStandbyHeatExchanger hasbeenstaged,andthetemporary hoseshavebeenconnected andleakchecked.DuringafullcoreoffloadtheSFPCoolingSystemloopAandstandbyloopmaybeoperatedinparalleltocompriseoneoftherequiredOPERABLEsystems.LoopAandthestandbyloophavetheabilitytoutilizefirewaterforcoolinginlieuofSWtoprovideforincreased redundancy.

Thetemporary electrical powersourceforthestandbylooppumpmayalsobevariedtoprovideforincreased redundancy.

Alsoincludedinthedetermination ofOPERABILITY areallnecessary supportsystemsnotaddressed bythisTR(e.g.,servicewater,firewater,electrical).

Singleactivefailuresarenotrequiredtobeconsidered withinthesupportsystemsforthepurposeofthisTR;however,thesupportsystemsmustbecapableofperforming theirsupportfunctionperthedefinition ofOPERABLE-OPERABILITY inITSSection1~1.TheTRismodifiedbyanote.TheSFPheatloadfromtheirradiated fuelassemblies storedwithintheSFPisavariablebasedonthetotalnumberofassemblies stored,thepowerhistoryoftheindividual assemblies, andthetimesincetheassemblies werelastirradiated.

Theheatremovalcapabilities oftheindividual SFPcoolingloopsisalsoavariablebasedonthetemperature andflowrateofthecoolingsource,SWorfirewater.TheSFPheatloadandtheSFPCoolingSystemheatremovalcapabilities aredetermined byNuclearEngineering Servicesandprovided, asnecessary, basedonplantconditions.

R.E.GinnaNuclearPowerPlantTRB3.7.7-2Revision14 SpentFuelbt(SFP)CoolingSystemTRB3.7.7APPLICABILITY ThisTRapplieswheneveranyirradiated fuelassemblyisstoredintheSFP,toprovidesufficient margintotheassumptions oftheSFPstructural integrity.

Specificrequirements applicable duringafullcoredischarge arecoveredbyTR3.9.4.ACTIONSA.1andA.2IftheSFPtemperature isnotwithinlimit,stepsshouldbetakentoprecludetheassumptions oftheSFPstructural integrity frombeingexceeded.

Suspending anyoperation thatwouldincreaseSFPdecayheatload,suchasdischarging afuelassemblyfromthereactortotheSFP,isaprudentactionunderthiscondition.

Therefore, actionsshallbetakenimmediately tosuspendmovementofirradiated fuelassemblies fromthecoretotheSFP.Withthepotential forexceeding theassumptions oftheSFPstructural integrity, corrective actionstorestoretheSFPtemperature towithinlimitshallbeinitiated immediately.

B.tandB2WithoneoftherequiredSFPCoolingSystemsinoperable, suspending anyoperation thatwouldincreaseSFPdecayheatload,suchasdischarging anirradiated fuelassemblyfromthereactortotheSFP,isaprudentactionunderthiscondition.

Therefore, actionsshallbetakenimmediately tosuspendmovementofirradiated fuelassemblies fromthecoretotheSFP.Withthesuspension offueldischarge intotheSFPthenasecondSFPCoolingSystemmustberestoredtoOPERABLEstatuswithin14days.Inthiscondition theremaining OPERABLESFPCoolingSystemisadequatetoremovethedecayheatload.The14dayCompletion Timeisadequatetoperformtypicalmaintenance activities associated withaSFPCoolingSystemandtakesintoaccountthelargeheatsinkcapabilities oftheSFP.R.E.GinnaNuclearPowerPlantTRB3.7.7-3Revision14 SpentFuetOtt(SFP)CoolingSystemTRB3.7.7C.1andC.2IfnoSFPCoolingSystemisOPERABLE, therewillbenoforcedcoolingoftheSFPandassuchtheSFPtemperature mustbemonitored morefrequently untilthecoolingisrestored.

Thismonitoring isaccomplished byperforming surveillance TSR3.7.7.1toverifySFPtemperature iswithinlimit.TheCompletion Timeof1hourandevery4hoursthereafter issufficient duetothelargeheatsinkoftheSFPandslowheatuprate.Actionsmustalsobeinitiated torestoreoneSFPCoolingSystemto,OPERABLE statuspriortotheSFPtemperature exceeding 120'F.The120'Fisnotasafetyrequirement butisalimitsetfornormaloperation andprovidesadequatemargintothe150'Flimit.SURVEILLANCE TSR3.7.7.1REQUIREMENTS ThisTSRverifiesthattheSFPtemperature iswithintherequiredlimit.Thetemperature intheSFPmustbecheckedperiodically toensuretheSFPstructural integrity ismet.The24hourFrequency isappropriate duetothelargevolumeofwaterinthepoolandtherelatively slowheatuprate.Verification ofSFPwatertemperature isnormallyaccomplished bytheuseofTIA-635,whichalsoprovidesaSFPhightemperature alarmtoalerttheoperators ofanincreasing SFPtemperature.

T~SR3.7.7.Verification thattherequiredpumpsareOPERABLEensuresthatanadditional SFPpumpcanbeplacedinoperation, ifneeded,tomaintaindecayheatremoval.Verification isperformed byverifying properbreakeralignment andpoweravailable totherequiredpumps.TheFrequency of7daysisconsidered reasonable inviewofotheradministrative controlsavailable andhasbeenshowntobeacceptable byoperating experience.

REFERENCES 1.UFSAR,Section9.1.3.R.E.GinnaNuclearPowerPlantTRB3.7.7-4Revision14 SpentFuetept(SFP)CoolingSystemTRB3.7.7I8664ISpentFuelPoolSkid-mounted SFPPumpglSWStandbyHXlSW/Fire781782Il8662aesgfsra+eari8614SFPHXASFPPumpA8654t-SW/Fire8663SFPHXBSFPPumpB8657Legend:-LoopeFlowpalhLoopAFlowpathStandbyLoopFlowpathForillustration onlyFigureTRB3.7.7-1SFPCoolingSystemR.E.GinnaNuclearPowerPlantTRB3.7.7-5Revision14 Priority:

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'idsManager IRODHagan~~FILECENTER01~DennisHagan0001'0OKOKOKPaperCopyPaperCopyOKExternalRecipients:

TotalCopies:Item:ADAMSPackageLibrary:MLADAMS"HQNTAD01ID:011590048

Subject:

RevisiontoEmergency PlanImplementing Procedures R.G.GinnaNuclearPowerPlant.DocumentDate:06/04/2001 Body:ADAMSDISTRIBUTION NOTIFICATION.

A045-ORSubmittal:

Emergency Preparedness Plans,Implementing Procedures, Corre-'pondence Title:RevisionfoEmergency PlanImplementing Procedures R.G.GinnaNuclearPowerPlant.DocketNumber:05000244DocumentDate:06/04/2001 Page1 Distri-l.txt AuthorName:PoifleitPSAuthorAffiliation:

Rochester Gas8:ElectricCorpAddressee Name:VissingGSAddressee Affiliation:

NRC/Document ControlDeskAddressee Affiliation:

NRC/NRR/DLPM/LPDI DocumentType:Emergency Preparedness-Emergency PlanImplementing Procedures Availability:

PubliclyAvailable DocumentSensitivity:

Non-Sensitive Comment:Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML011590048.

Page2

tiiruuzzzzzvuzz~tZii!"'IZsuu'!g',

ROCHESTER GASANDELECTRICCORPORATION o89EASTAVENUE,ROCHESTER, N.Y.14649-0001 June4,2001TELEPHONE ARE*cooE716546.2700U.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555Attn:Mr.GuyS.Vissing(MailStop14D11)ProjectDirectorate I-1

Subject:

RevisiontoEmergency PlanImplementing Procedures R.E.GinnaNuclearPowerPlantDocketNo.50-244~CGentlemen:

Inaccordance with10CFR50.4(b)(5),

enclosedarerevisions toGinnaStationEmergency PlanImplementing Procedures (EPIPs).Wehavedetermined, pertherequirements of10CFR50.54(q),

thattheseprocedure changesdonotdecreasetheeffectiveness ofourNuclearEmergency ResponsePlan.Verytrours,I~IjlI5~PeterS.PolfleitCorporate NuclrEergencyPlannerEnclosures 5Qxc:5USNRCRegion1(2copiesofletterand2copiesofeachprocedure)

ResidentInspector, GinnaStation(1copyofletterand1copyofeachprocedure)

RGSENuclearSafetyandLicensing (1copy'ofletter)Dr.RobertC.Mecredy(2copiesofletteronly)PSP/jtw PROCEDURE REVISIONNUMBEREPIP1-5EPIP2-1EPIP2-5EPIP2-17EPIP3-1EPIP4-7EPIP5-1EPIP5-7431915172132 (tI Priority:

NormalFrom:E-RIDS3,Distribution SheetDistri-l.txtActionRecipients:

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TotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:011630044:1

Subject:

R.E.GinnaNuclearPowerPlantTechnical Requirements ManualTRM,Revision'l6.DocumentDate:05/31/2001 Body:ADAMSDISTRIBUTION NOTIFICATION.

A001-ORSubmittal:

GeneralDistribution forPowerReactor(10CFR50)Submittals Title:R.E.GinnaNuclearPowerPlantTechnical Requirements ManualTRM,Revision16.DocketNumber:05000244DocumentDate:05/31/2001 Page1

Distri-l.txtAuthorName:AuthorAffiliation:

Rochester Gas&ElectricCorpAddressee Name:VissingGAddressee Affiliation:

NRC/Document ControlDeskAddressee Affiliation:

NRC/NRR/DLPM/LPD1 DocumentType:ManualDocumentType:Technical Specification Availability:

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Page2 ROCHESTER GAS6ELECTRICCORPORATION DOCUMENTCONTROLDocumentTransmittal To:DOCUMENTCONTROLDESKUSNRCATT:GUYVISSINGPROJECTDOCTORATE 1-1WASHINGTON DC20555Transmittal:

200105037 053Date:05/31/2001 Holder:1217LISTEDBELOWARENEWORREVISEDCONTROLLED DOCUMENTS.

REVIEWTHEATTACHEDINSTRUCTION LETTER(IFAPPLICABLE),

ANDUPDATEYOURCONTROLLED DOCUMENTINACCORDANCE WITHEP-3-S-0901 DocIdTRMDocTitleTECHNICAL REQUIREMENTS MANUALFORGINNASTATIONRevRevDateQty01606/01/2001 1ReceiptAcknowledgement andActionTaken:Signature DateReturnENTIREFORMto:Rochester Gas&ElectricCorporation GinnaStation-RecordsManagement 1503LakeRoadOntario,NewYork14519 Rochester GasandElectricCorporation Inter-Office Correspondence May31,2001

Subject:

Technical Requirements Manual(TRM)Revision16To:Distribution AttachedaretherevisedpagesfortheGinnaStationTechnical Requirements Manual(TRM).Thechange,includedwithinRevision16issummarized asfollows:TableTR5.1-1wasrevisedtoaddanewmoreconservative, letdownflowratebased,requirement forreactorcoolantDOSEEQUIVALENT I-131specificactivityastheresultofACTIONReport2000-0450.

Revision16oftheTRMisconsidered effective June1,2001.Instructions forthenecessary changestoyourcontrolled copyoftheITSareasfollows:VolumeSectionRemoveInsertIII111IIIIIIIIITRMTRMTRMTRMChapter5.0TRMChapter5.0CoverPageLEP-iLEP-iiTRM5.1-1TRM5.1-2CoverPageLEP-ILEP-iiTRM5.1-1TRM5.1-2PleasecontactTomHarding(extension 3384)ifyouhaveanyquetions.ThomasL.arding II R.E.GinnaNuclearPowerPlantTechnical Requirement anualTRMRevisio15ResposibleManager:.~GeorgerelEffective Date:I<)/c>/810/11/2000 Controlled CopyR.E.GinnaNuclearPowerPlantTRM-1Revision15 0sf0 ListofEffective Pages(TRM)PageTOCRev.PageRev.PageRev.PageRev.Section4.0Section1.0TR1.0-1Section2.0TR2.1-1Section3.0TR3.0-1TR3.0-2Section3.1TR3.1.1-1TR3.1.1-2TR3.1.1-3TR3.1.2-1TR3.1.2-2Section3.2TR3.2-1Section3.3TR3.3.1-1TR3.3.1-2TR3.3.2-1TR3.3.2-2TR3.3.3-11515141414141414141414141414141414TR3.3.4-1TR3.3.4-2TR3.3.4-3TR3.3.4-4TR3.3.4-5TR3.3.4-6TR3.3.4-7TR3.3.5-1TR3.3.5-2TR3.3.5-3Section3.4TR3.4.1-1TR3.4.1-2TR3.4.2-1TR3.4.2-2TR3.4.2-3TR3.4.3-1TR3.4.3-2TR3.4.3-3TR3.4.3-4TR3.4.3-5TR3.4.3-6Section3.5TR3.5-1Section3.6TR3.6-1Section3.7TR3.7.1-1TR3.7.1-2TR3.7.1-31414141414141414141414141414141414141414141414141414TR3.7.2-1TR3.7.2-2TR3.7.2-3TR3.7.2-4TR3.7.2-5TR3.7.3-1TR3.7.3-2TR3.7.3-3TR3.7.4-1TR3.7.4-2TR3.7.4-3TR3.7.4-4TR3.7.5-1TR3.7.5-2TR3.7.5-3TR3.7.5-4TR3.7.5-5TR3.7.6-1TR3.7.6-2TR3.7.7-1TR3.7.7-2TR3.7.8-1TR3.7.8-2Section3.8TR3.8.1-1TR3.8.2-1TR3.8.2-2Section3.9TR3.9.1-1TR3.9.2-1TR3.9.2-2TR3.9.3-1TR3.9.4-1TR3.9.4-21414141414141414141414141414141414141414141515141414141414141414TR4.0-1Section5.0TR5.1-1TR5.1-2141414R.E.GinnaNuclearPowerPlantLEP-iRevision15 PageTOCRev.PageListofEffective Pages(TRMBases)Rev.PageSection3.7Rev.PageRev.Section2.0Section3.0Section3.1Section3.2Section3.3Section3.415TRB3.7.1-1TRB3.7.2-1TRB3.7.3-1TRB3.7.4-1TRB3.7.5-1TRB3.7.6-1TRB3.7.7-1TRB3.7.7-2TRB3.7.7-3TRB3.7.7-4TRB3.7.7-5TRB3.?.8-1TRB3.7.8-2TRB3.7.8-3Section3.8Section3.91414141414141414141414151515Section3.5Section3.6TRB3.9.1-1TRB3.9.1-2TRB3.9.1-3TRB3.9.2-1TRB3.9.3-1TRB3.9.4-1TRB3.9.4-2TRB3.9.4-3TRB3.9.4-4141414141414141414Section4.0Section5.0R.E.GinnaNuclearPowerPlantLEP-iRevision15 TeraryLCORequirements TR5.15.0ADMINISTRATIVE CONTROLSTR5.1Temporary LCORequirements Thissectiondefinesadditional administrative restrictions placedonsystems,structures, andcomponents (SSCs)whichareaddressed withintheITSinordertoensurethattheyremainOPERABLEwithrespecttotheirITSrequirements.

Thesearetemporary requirements onlyuntiltheITScanbemodifiedviaalicenseamendment request,plantmodification withasubsequent baseschange,etc.TableTR5.1-1containsthelistingoftemporary LCOrequirements andallassociated background information.

R.E.GinnaNuclearPowerPlantTR5.1-1Revision14 TraryLCORequirements

,TR5.1TableTR5.1-1Temporary LCORequirements ItemActionReportffTemporary LCORequirement RequiredActionsIfNotMetEffective Dates5.1.197-0783a.VerifykeyswitchesforMOVs852Aand852Barein'offposition" every31days.a.Declareassociated ECCStraininoperable perLCO3.5.2.6/19/97untilLCO3.5.2ischanged5.1.297-0894a.VerifyNaOHSystemtankNaOHsolutionconcentration is635%byweightevery184days.a.DeclareNaOHsysteminoperable perLCO3.6.6.6/19/97untilLCO3.6.6ischanged.R.E.GinnaNuclearPowerPlantTR5.1-2Revision14 k

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Revision20toNuclearEmergency ResponsePlanR.E.GinnaNuclearPowerPlant.Body:ADAMSDISTRIBUTION NOTIFICATION.

Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML011440392.

A045-ORSubmittal:

Emergency Preparedness Plans,Implementing Procedures,Correspondence Docket:05000244Page1 V

e.~zapzan'l!IVIIIIIIIIII 1066tIgj)gIiIIIIIROCHESTER GASANDELECTRICCORPORATION o89EASTAVENUE,ROCHESTER, N.Y.14649-0001 TELEPHONE AREAcoDE7I6546-2700May18,2001U.S.NuclearRegulatory Commission:'

DocumentControlDeskWashington, DC20555Attn:Mr.GuyS.Vissing(MailStop14D11)ProjectDirectorate I-1

Subject:

RevisiontoNuclearEmergency ResponsePlanR.E.GinnaNuclearPowerPlantDocketNo.50-244Gentlemen:

Inaccordance with10CFR50.4(b)(5),

en'closed arecorrections toRevision20oftheGinnaStationNuclearEmergency ResponsePlan(NERP).Wehavedetermined, pertherequirements of10CFR50.54(q),

thatthechangesdonotdecreasetheeffectiveness oftheNuclearEmergency ResponsePlan.Verytrulyyours,PeterS.PoliCorporate NucarEmergency PlannerEnclosures xc:USNRCRegion1(2copiesofletter'and 2copiesoftheplan)ResidentInspector, GinnaStation(1copyofletterand1copyoftheplan)RGSENuclearSafetyandLicensing (1copyofletter)Dr.RobertC.Mecredy(2copiesofletteronly)PSP/jtwyr~wt'IclI>

~~~gfe~~s'~

~%~OROCHESTER GASSELECT4kCORPORATION INTEROFFICE CORRESPONDENCE Date:May17,2001

Subject:

ChangestoRev.20oftheNuclearEmergency ResponsePlan(NERP)From:PeterPolfleIt(Ext.6772)To:.Controlled Copyholders Attachedpleasefindthecorrected pagesforRevision20oftheNuclearEmergency ResponsePlan.Pleaseremove/add thepagesasdirectedbelow:RemoveRelaceWith25252727292990909191929298989999100100

~~I+>~

TableofContentscontinued

~PaeNo.6.0Emergency Facilities 6.1Emergency ResponseFacilities (RG8E)6.2Communications System6.3Assessment Facilities 6.4Protective Facilities 6.5FirstAidandMedicalFacilities 6161697288917.0Maintaining NuclearEmergency Preparedness 7.1TrainingandDrills7.2ReviewandRevisionofthePlanandProcedures 7.3Emergency Equipment andSupplies7.4Auditing92929898998.0Recovery8.1RecoveryActions100100 C0

~~~Thecompany's Emergency SupportOrganization ischargedwiththeresponsibility ofbringingtogetheracohesivecompanymanagerrient andtechnical team.Thisorganization willbecallinguponthemaximumresources available withinthecompanyandtheentirenuclearindustiyforthepurposeof(1)assuringthesafeshutdownandrecoveryofGinnaStationfollowing anaccidentcondition and,(2)minimizing theimpactofthesituation onthehealthandsafetyofthepublic.TheGinnaStationshort-term responding organization ismadeupofsitepersonnel, thoseon-shiftandthoseimmediately available fromtheplantstaffcomplement.

TheEmergency SupportOrganization willbeavailable totheGinnaStationPlantManagerforimplementation oflong-term recoveryoperations.

Thecompany's Emergency SupportOrganization isestablished undertheleadership ofasingleindividual calledtheEOF/Recovery Manager.TheEOF/Recovery Managerissupported byvarioustechnical andadvisorydisciplines including Engineering, Facilities andPersonnel, NuclearOperations, PublicCommunications andEnergyDelivery.

4.2.4Imlementation oftheOffsiteEmerencOranization:

GinnaStationprocedures providethattheEOF/Recovery Manager(orqualified alternate) isnotifiedandprovidedwithdetailsconcerning theemergency, theemergency classification, stationstatus,andimmediate corporate assistance, ifany,whichmayberequired.

TheEOF/Recovery Managerhastheauthority toactivatetheEmergency Operations Facility.

TheEmergency SupportOrganization (Figure4.2C)willbeactivated undertheAlert,SiteAreaEmergency andGeneralEmergency categories althoughitmaybeactivated underothercategories.

Uponactivation oftheEmergency SupportOrganization, theEOFisestablished inthebasementoftheleasedofficebuildingat49EastAvenue,adjacentofthemaincorporate officebuilding.

AJointEmergency NewsCenter(JENC)willalsobeactivated inthemaincorporate officebuilding, TheJENCwillbeusedtocoordinate allnewsreleasesandpressconferences withtheappropriate Federal,Stateandlocalauthorities.

Personnel whohaveresponsibilities intheEOFwillbenotifiedofanincidentandtheneedforthemtoreporttotheEOFaccording toanapprovedprocedure.

Eachindividual assignedtotheEOFwillhaveadesignated alternate whowillbenotifiedasnecessary.

25

~1~~O.0 Desigriahdconstruction supportwiththeresponsibility ofcoordinating theactivities ofthecompany,AIE,NSSSsupplierandconstruction forcesonproposedstationmodifications orotherdesignandconstruction supportrequiredforresponseandrecovery.

4.Advisorysupportfunctions withadvisorysupportconsisting of,seniorrepresentatives oftheNSSSsupplierandspecialconsultants asnecessary.

5.PublicCommunications'taff withtheresponsibility ofproviding administration, logistics, communications, andpersonnel supportfortheresponseandrecoveryoperations.

6.Administration andlogistics withtheresponsibility ofproviding administration, logistics, communications, andpersonnel supportfortheresponseandrecoveryoperations.

TheEOFwillbeorganized asshownontheattachedEmergency SupportOrganization Chart,Figure4.2C.Thepositions willbefilledbytrainedindividuals aslistedinSection4.2.6.27

~~4.2.6Thefollowing positions aretheprincipal managersandcoordinators whichmakeuptheteamintheEOFandJointEmergency NewsCenterinresponsetoanuclearemergency atGinnaStation.Theresponsibilities foreachpositionaregiveninEPIP4-7andEPIP5-7.4.2.6.1EOF/Recovery Managerassumesoverallcommandandcontroloftherecoveryoperation oftheGinnafacility.

4.2.6.2EnergyDistribution Liaisonprovidesadvisortechnical support,supplementary andcomplementary toonsitepersonnel usingconsultants andin-housetechnical experts,asnecessary.

Directselectricsystemoperations tomeettheemergency.

4.2.6.3NuclearOperations ManagerassistsEOF/Recovery Managerincoordinating activities oftheoffsiteorganization tosupportsiteactivities.

4.2.6.4Engineering Managercoordinates thedesignandconstruction activities oftheutility,A/E,NSSSSupplier, construction forces,andoutsidevendors.4.2.6.5Facilities andPersonnel Managerprovidesadministrative,

logistic, communications, andpersonnel supportfortherecoveryoperation.

4.2.6.6NewsCenterManagerdirectsimplementation ofprocedures governing JENCfacilityactivation, operations andpublicinformation functions.

4.2.6.7Corporate Spokesperson advisesthemediaandthecommunity throughthePublicCommunications functionofcurrentandpotential plantconditions.

4.2.6.8OffsiteAgencyLiaisonadvisesCounty,State,andFederalAgencyRepresentatives intheEOForoutsideofconditions relatedtotheincident.

4.2.6.9'4EOFDoseAssessment ManageradvisesEOF/Recovery Managerofprojected dosesandProtective ActionRecommendations (PARS)tolimitexposuretothepublicintheaffectedEmergency ResponsePlanningareas.29

~~~6.4.5Contamination ControlProvisions:

Theplantsiteisdividedintotwocategories, theCleanAreaandtheRadiologically Controlled Area.EntrytoandexitfromtheRadiologlcally Controlled Areaisnormallythroughthedesignated AccessControlPoint.Anyareainwhichradioactive materials andradiation arepresentshallbesurveyed, classified, ropedandconspicuously postedwiththeappropriate radiation cautionsign.ThesethenbecomeRadiologically Controlled Areasandproperaccessisprovidedandcontrolled.

Plantprocedures providetheradiation orcontamination levelsatwhichanareaisdeclaredaRadiologically Controlled Areaorremovedfromradiation controlstatus.Thegeneralarrangement oftheservicefacilities isdesignedtoprovideadequatepersonnel decontamination andchangeareas.ThecleanlockerroomisusedtostoreitemsofpersonalclothingnotrequiredorallowedintheControlled Area.TheAccessControlPointisemployedasaprotective clothingchangearea.Asupplyofcleanprotective clothingforpersonnel ismaintained inthisarea,andthereisprovision forcollection ofusedprotective clothing.

Allpersonnel willsurveythemselves onleavingtheControlled Areausingequipment providedattheAccessControlPoint.Adecontamination showerandwashroomarelocatedadjacenttotheAccessControlPoint.Personnel decontamination kitswithinstructions postedfortheiruseareavailable inthedispensary described inSection6.5,FirstAidandMedicalFacilities.

Intheeventofasiteevacuation, provisions fordecontamination areavailable attheSurveyCenter.A1000-gallon holdingtankisavailable tocontaindecontamination waterfromasinkandshowerlocatedintheSurveyCenter.Decontamination waterwillbesampledpriortotransfer, treatment ordisposal.

6.4.6Protective EuimentandSulies:Personnel enteringtheControlled Areamayberequiredtowearprotective clothing.

Thenatureoftheworktobedonegovernstheselection ofprotective clothingtobewornbyindividuals.

Theprotective apparelavailable areshoecovers,headcovers,glovesandcoveralls.

Additional itemsofspecialized apparelsuchasplasticsuits, faceshields,andrespirators areavailable foroperations involving highlevelsofcontamination.

Inallcases,Radiation Protection personnel shallevaluatetheradiological conditions andspecifytherequireditemsofprotective clothingtobeworn.90

~~Respiratory protective devicesarerequiredwhereveranairborneradiation areaexistsorisexpected.

Insuchcases,Radiation Protection personnel monitortheairborneconcentrations andspecifythenecessary protective devicesaccording toconcentration andtypeofairbornecontaminants present.Available respiratory devicesincludefullfaceairpurifying respirators (filtertypebothnegativeandpressured poweredairpurifying units).Airlinesuppliedrespirators ofpressuredemandtypeareusedaswellasconstantflowhoods.Self-Contained Breathing Apparatus, usingfullfacemasksandpressuredemandregulators arealsoavailable.

Foruseinanemergency, equipment andsuppliesarelocatedintheControlRoom,Technical SupportCenter,Respiratory Protection FacilityandtheSurveyCenter.Equipment categories aregiveninAppendixD.6.4.7EmerencVehicles:

Intheeventitbecomesnecessary tomakeuseofautomotive equipment, anumberofvehicleswillbeavailable.

Theseincludecompany-owned vehiclesandpersonalvehicles.

AsmalldeliverytruckandasmallworktruckareassignedtotheStation.Thegroundmaintenance garage,nearby,isassigneda4-wheeldrivetruck.Useofpersonalvehiclesisallowedbythecompanypolicyregarding paidmileageforcompanyuse.Lastly,alargeanddiversefleetofvehiclesisavailable fromtheRochester GasandElectricPhysicalServicesDepartment.

6.5FirstAidandMedicalFacilities Firstaidandmedicalprovisions includebothonsiteandoffsitefacilities.

Thelatteraredescribed inSection4.3,Augmentation oftheEmergency Organization.

Adispensary onsitecontainssinks,atoilet,abed,astretcher, andmiscellaneous firstaidequipment andsupplies.

Decontamination kitscanbeobtainedfromthemainRadiation Protection group.Personnel decontamination kitsandbioassaycollection kitsareavailable atRochester GeneralHospitalandNewarkWayneCommunity Hospital.

Auxiliary Operators andSecurityOfficersaretrainedinfirstaidprocedures usingRedCrossMulti-Media oranequivalent program.Anadministrative procedure establishes aFirstAidTeamandtheactionstobefollowedintheeventofillnessorinjuryatGinnaStation.91

\

~~7.0Maintainin NuclearEmer encPrearedness:

0Formalized trainingprogram(s) havebeenestablished toensurethatallpersonnel whoactivelyparticipate intheNuclearEmergency ResponsePlan(NERP)maintaintheirfamiliarity withtheplanandtheirrequiredresponse.

Aradiation emergency exerciseshallbeconducted atleastannually, withemphasisplaceduponorderlyimplementation oftheemergency plan.Personnel trainedforonsiteresponsetoaradiation emergency arepartoftheregularplantstaffandaretrainedtospecificresponsibilities withintheemergency organization.

Trainingisdocumented bytheDepartment Manager,NuclearTraining, andCorporate Nuclear.Emergency Planner.Anyemergency planworkbyconsultants willbeunderthecontrolof,andreviewedby,theCorporate NuclearEmergency Planner.Exercises shallbeevaluated bytheCorporate NuclearEmergency PlannerandreviewedbythePlantOperations ReviewCommittee (PORC),therebyassuringtheeffectiveness oftheplanthroughout thelifetimeoftheR.E.Ginnafacility.

7.1Trainingclassesontheemergency planshallbeconducted annually(+I-3months)forallRG8Epersonnel whomayactivelyparticipate intheradiation emergency plan.Detailsofthetrainingprogramsareestablished inTRC.22(NuclearEmergency ResponsePlanTrainingProgram).

Trainingwillincludeademonstration oftheirabilitytoperformthefunctions towhichtheymaybeassignedbyparticipating inaDrillorExerciseatleastonceeverytwoyears.Duringdrills,on-the-spot corrections oferroneous performance maybemade,followedbyacritiqueorcorrective action.Effortswillalsobemadetovarythetimingoftheexercises suchthatback-shifts willbeinvolvedonceeverysixyears(i.e.between6p.m.and4a.m.).Attemptswillbemadetohavesomedrillsunannounced.

Specialized trainingwillbeprovidedfor:1.Technical SupportCenterassignees 2.Operation SupportCenterassignees 3.FirstAidTeams4.SurveyTeams5.Emergency Operations Facilitypersonnel 92 e~~~~~I~72AnnualReviewandRevisionofthePlanandProcedures; AnnualreviewandrevisionoftheNuclearEmergency ResponsePlan(EPIP5-6)willoccurfollowing theannualQAaudit.Revisions tothePlanaresubjecttoapprovalbyPORCandreviewbytheNuclearSafetyandAuditReviewBoard(NSARB).Revisions tothePlanandEmergency PlanImplementing Procedures (EPIP)maybetheresultofdrills,exercises, trainingorroutinesurveillance.

ThePlanandEmergency PlanImplementing Procedures arereviewedbytheEPIPCommittee.

EPIPProcedure changesarecontrolled usingtheguidanceintheadministrative procedures A-205.2andtheIP-PROseries.Emergency procedure changesarecontrolled sothatonlycurrentcopiesareavailable foruse.Revisedprocedures aredistributed toalistofcontrolled copyholderswithreceiptverification.

ShiftOperators andlicensedstaffaremadeawareofrevisions duringregularly scheduled trainingcoordinated bytheNuclearTrainingDepartment.

Emergency telephone numbersarekeptup-to-date throughquarterly reviewanddistribution ofrevisions.

7.3EmerencEuimentandSu lies:Theoperational readiness ofallitemsofemergency equipment andsupplieswillbeassuredthroughmonthlyinspections ofemergency equipment.

Theimplementing procedure includesinspecting andtestingofequipment storedintheControlRoom,SurveyCenter,Technical SupportCenter,Radiation Protection office,JENCandEOF.Alsoincludedistheprocedure fortestingtheoperability oftheequipment.

Necessary transportation foroffsitesurveyswillbeapersonalcarsuppliedbyonememberoftheteam.Sincemostemployees commutebyprivatecarbecauseoftheremoteness ofthefacility, nolackofvehiclesisanticipated.

Companypolicyprovidesformileagereimbursement.

7.3.1SirenTestsandoerabiliTheGinnaEmergency Sirensshallbeactivated atintervals nottoexceedoneyear(+or-ThreecalendarMonths).Thistestwillbeconsidered successful ifnomorethan10%(10of96)ofthesirensfailtooperateproperly.

Anytimeitisfoundthatmorethan25%(24of96)ofthesirensareinoperable formorethanOneHour,ThenaOne-Hournotification willbemadetotheNRC.Usingprocedure 0-9.3Attachment 3(reference:

10CFR50.72(b)(1)(v)).

98 0)~~1,~

7.4~Auditin:

TheNuclearEmergency ResponsePlan,itsimplementing procedures, equipment, trainingandinterface withStateandcountyauthorities isauditedata12Monthfrequency 3monthsandauditresultsarereviewedbytheNSARB.Follow-up implementation tasksareassignedthroughtheuseoftheACTIONReports.Auditdocuments areretainedfor5years.99 I'~e<~~~tRecoverec Aftertheinitialemergency responseactionsareconcluded (i.e.,theplantisincoldshutdownandundercontrol),

adecisiontobegintherecoveryphasewillbeinitiated.

Anumberofconsiderations willenterintothedecisiontobegintherecoveryphaseanddismantle theEmergency ResponseOrganization.

ThedecisiontoentertherecoveryphasewillbemadebytheEOF/Recovery Managerinconsultation withhissupportmanagers, thePlantOperation ReviewCommittee, andtheNSARBandonsitepersonnel.

EPIP3-4,"Emergency Termination andRecovery" willbeusedbytheorganization totransition fromaresponseorganization toarecoveryorganization.

Thedecisiontoentertherecoveryphaseshouldbebaseduponacomprehensive reviewofstationparameters andconditions.

Theseshouldinclude,butarenotlimitedtothefollowing:

1.Theinitialemergency responseactionsareconcluded (i.e.,thestationisincoldshutdownandundercontrol).

2.Stationparameters ofoperation nolongerindicateapotential oractualemergency exists.3.Thereactorshutdownconditions arestable.4.Thereactorcontainment buildingintegrity isintact.5.Thereleaseofradioactivity fromthestationiscontrollable andnolongerexceedspermissible levels,andnodangertothegeneralpublicfromtheabovesource(s) iscredible.

6.Radioactivity wastesystems anddecontamination facilities areoperabletotheextentneeded.7.Areactorheatsinkisavailable andoperating.

8.Theintegrity ofpowersuppliesandelectrical equipment neededforthestationtobecapableofsustaining itselfinalongteimshutdowncondition isintact.100

~~~~I' Priority:

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Subject:

R.E.GinnaRevisiontoEmergency PlanImplementing Procedures.

Body:ADAMSDISTRIBUTION NOTIFICATION.

Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML011280194.

A045-ORSubmittal:

Emergency Preparedness Plans,Implementing Procedures, CorrePage1 spondence Distri-l.txt Docket:05000244Page2

tz!upzzziwQLIQ4Ilk')nrZuZZini7/ZZ,'::ROCHESTER GASANDELECTRICCORPORATION o89EASTAVENUE,ROCHESTER, N.K14649-0001 April30,2001TCLCPHONC ARcAcoDc7le546-2700U.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555Attn:Mr.GuyS.Vissing(MailStop14D11)ProjectDirectorate I-1

Subject:

RevisiontoEmergency PlanImplementing Procedures R.E.GinnaNuclearPowerPlantDocketNo.50-244Gentlemen:

Inaccordance with10CFR50.4(b)(5),

enclosedarerevisions toGinnaStationEmergency PlanImplementing Procedures (EPIPs).Wehavedetermined, pertherequirements of10CFR50.54(q),

thattheseprocedure changesdonotdecreasetheeffectiveness ofourNuclearEmergency ResponsePlan.Verytrulyyours,\PeteS.oeratCorporate NucleEmergency PlannerEnclosures xc:USNRCRegion1(2copiesofletterand2copiesofeachprocedure)

ResidentInspector, GinnaStation(1copyofletterand1copyofeachprocedure)

RGSENuclearSafetyandLicensing (1copyofletter)Dr.RobertC.Mecredy(2copiesofletter'only)

PSP/jtwgLoIIgkO/f'/

PROCEDURE REVISIONNUMBEREPIP2-2EPIP2-11EPIP2-12EPIP4-710151816

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Page1

A002-ORSubmittal:Inadequate CoreCooling(ItemII.F.2)GL82-28Docket:05000244Page2 ANDASubsidiary ofRGSEnergyGroup,Inc.ROCHESTER GASANDELECIRICCORPORATION

~89EASTAVENUE,ROCHESTER, N.Y.Id649CXNI

~716.771-3250 www.rge.corn JOSEPHA.WIDAYVICEPRESIDENT EPlANTMANAGERGINNASTATIONMarch26,2001U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate IWashington, D.C.20555

Subject:

Emergency Operating Procedures R.E.GinnaNuclearPowerPlantDocketNo.50-244

DearMr.Vissing:

Asrequested, enclosedareGinnaStationEmergency Operating Procedures.

Verytrulyyours,6'.JspA.WidaJAW/jdwxc:U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406-1415 GinnaUSNRCSeniorResidentInspector Enclosure(s):

APIndexAP-PRZR.1, Rev12 4

REPORTNO.01REPORT:NPSP0200DOCTYPE:PRAPPARAMETERS:

DOCTYPES-PRAPGINNANUCLEARPOWERPLANTPROCEDURES INDEXABNORMALPROCEDURE STATUS:EFQU5YEARSONLY:03/15/01PAGE:1PROCEDURE NEWERAP-CCW.1AP-CCW.2AP-CCW.3AP-CR.1AP-CVCS.1AP-CVCS.3AP-CW.1AP-ELEC.1AP-ELEC.2AP-ELEC.3 AP-ELEC.14/16AP-ELEC.17/18 AP-FW.1AP-IA.1AP-PRZR.1AP-RCC.1AP-RCC.2AP-RCC.3AP-RCP.1AP.1AP-RCS.2AP-RCS.3AP-RCS.4AP-RHR.1PROCEDURE TITLELGEINTOTHECOMPONENT COOLINGLOOPLOSSOFDURINGPOWEROPERATION LOSSOPCCWPSHUTDOWNCONTROLROOMINACCESSI ITYCVCSLEAKLOSSOFALLCHARGINGFLOWLOSSOFACIRCWATERPIMPLOSSOP12AAND/OR12BBUSSESSAPEGUARD BUSSESLOWVOLTAGEORSYSTEMLOWFREQUENCY LOSSOF12AAND/OR12BTRANSFORMER (BELOW350F)LOSSOFSAFEGUARDS BUS14/16LOSSOFSAPEGUARDS BUS17/18PARTIALORCOMPLETELOSSOFMAINFEEDWATELOSSOFINSTR~iAIRABNORMALPRESSURIZER PRESSCONTINUOUS CONTROLROITHDRAWAL/INSERTION RCC/RPIMALCTIONDROPRODRECOVERYRCPSEALMALFUNCTION REACTORCOOLANTLEAKLOSSOFREACTORCOOLANTFLOWHIGHREACTORCOOLANTACTIVITYSHUTDOWNLOCALOSSOFRHREFFECTREVDATELASTREVIEWNEXTREVIEWST01401/09/0105/01/9805/01/03EF01405/18/0008/17/9908/17/04EF01205/18/0008/17/9908/17/0401601/11/0001/11/0001/115EF01205/01/9805/01/98/01/03EF00202/11/0002/9902/26/04EF01007/16/905/01/9805/01/03EF020/08/0005/01/9805/01/03EF00903/22/9903/22/9903/22/04EF00809/08/0005/01/9805/01/03EF0303/15/0106/09/9706/09/02EP0020/18/9906/09/9706/09/02EP01202/11002/27/9802/27/03EP01712/02/99001/9805/01/03EF01112/02/9912/02/12/02/04EF00602/24/9605/14/9805/03EF00811/16/9802/06/9702/06/02F00411/16/9802/27/9802/27/03EF01306/09/0005/01/9805/01/03EF01509/08/0005/01/9805/01/03EF01012/14/9805/01/9805/01/03EF00708/05/9708/05/9708/05/02EF01112/02/9905/01/9805/01/03EP01502/08/0105/01/9805/01/03EF 1I~tfL REPORTNO.01REPORT:NPSP0200DOCTYPE:PRAPGINNANUCLEARPOWERPLANTPROCEDURES INDEXABNORMALPROCEDURE 03/15/01PAGE:2PARAMETERS:

DOCTYPES-PRAPSTATUS:EFQU5YEARSONLY:PROCEDURE NUMBERAP-RHR.2AP-SG.1AP-SW.1AP-TURB.1AP-TURB.2AP-TURB.3AP>>TURB.4AP-TURB.5PROCEDURE TITLELOSSOFRHRWHILEOPERATING ATRCSREDUCEDINVENTORY CONDITIONS STEAMGENERATOR TUBELEAKSERVICEWATERLEAKTURBINETRIPWITHOUTRXTRIPREQUIREDTURBINELOADREJECTION TURBINEVIBRATION LOSSOFCONDENSER VACUUMRAPIDLOADREDUCTION EFFECTDATELASTREVIEWNEXTREVIEWST00910/13/0003/31/0003/31/05EF00009/08/0009/08/0009/08/05EF01510/18/9906/03/9806/03/03EF01002/12/9910/10/9710/10/02EF01702/11/0005/13/9805/13/03EF01002/11/0002/10/9802/10/03EF01405/01/9805/01/9805/01/03EP00506/09/0006/09/0006/09/05EFTOTALFORPRAP32 l