ML17261A781

Application for Amend to License DPR-18,requesting License Be Amended to Expire at Midnight of 090918 Instead of 060425

ML17261A781
Person / Time
Site:	Ginna
Issue date:	01/19/1988
From:	SNOW B A ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17261A780	List: ML17261A779 ML17261A781
References
NUDOCS 8801260531
Download: ML17261A781 (20)

Text

UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElect:ric Corporation (R.E.GinnaNuclearPowerPlant:))))DocketNo.50-244))APPLICATION FOR28996)MENT TOOPERATING'ICENSE PursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"

),Rochester GasandElectricCorporation

("RG&E),

holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhatthislicensebeamendedtoexpireatmidnightSeptember 18,2009viceApril25,2006.TheproposedchangeissetforthinAttachment AtothisApplication.

Asafetyevaluation issetforthinAttachment B.Thisevaluation also,demonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

Asdemonstrated inAttachment B,theproposedchangedoesnotinvolveasignificant hazardsconsideration.

880126053i 880ii9PDRADQCK05000244F' 4r/

WHEREFORE, Applicant respectfully requeststhatFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasExhibitA.Rochester GasandElectricCorporation ByBruceA.SnowSuperintendent, NuclearProduction Subscribed andsworntobeforemeonthis19thdayofJanuary,1988.LYNNI.HAUCKNotaryPob5cirrtheStateoiNewYorkMONROECOVEYCorarnission ExpiresNov.30,19' ATTACHMENT AR.E.GXNNANUCLEARPOWERPLANTLicenseAmendment RequestDescritionofProosed'Chan etoeratinLicenseDPR-18Pursuantto10CFRPart50,Section50.90,theholdersofOperating LicenseDPR-18her'ebyproposethefollowing changes:LicenseirationDateChangeparagraph FoftheFacilityOperating LicensefortheR.E.GinnaNuclearPowerPlantLicenseNo.DPR-18toread:F.Thisamendedlicenseiseffective asofthedateofissuanceand.shallexpireatmidnightSeptember 18,2009.RefertoExhibitAfortheactualpagechanges.

EXHIBITAROCHESTER GASANDELECTRICCORPORATION DOCKETNO.50-244R.E.GINNANUCLEARPOWERPLANTFACILITYOPERATING LICENSELicenseNo.DPR-181.TheNuclearRegulatory Commission (theCommission) hasfoundthat:A.Theapplication complieswiththerequirements oftheAtomicEnergyActof1954,asamended(theAct),andtheregulations oftheCommission setforthin10CFRChapter'andallre-quirednotifications tootheragenciesorbodieshave beendulymade;B.Construction oftheR.E.GinnaNuclearPowerPlant(thefacility) hasbeensubstantially completed inconformity withConstruction PermitNo.CPPR-19,asamended,andtheapplication, theprovisions oftheAct,andtherulesandregulations oftheCommission; C.Thefacilitywilloperateinconformity withtheapplication, theprovisions oftheAct,andtherulesandregulations oftheCommission; D.Thereisreasonable assurance (i)thatthefacilitycanbeoperatedatpowerlevelsupto1520megawatts (thermal)

'withoutendangering thehealthand.safetyofthepublic;and(ii)thatsuchactivities willbeconducted incompliance withtheregulations oftheCommission; E.Theapplicant istechnically andfinancially qualified toengageintheactivities authorized.

bythisoperating licenseinaccordance withtherulesandregulations oftheCommission; F.Theapplicant hasfurnished.

proofoffinancial protection thatsatisfies therequirements of10CFRPart140;andG.Theissuanceofthislicensewillnotbeinimicaltothecommondefenseandsecurityortothehealthandsafety.ofthepublic.2.TheProvisional Operating LicensedatedSeptember 19,1969,issuperseded byFacilityOperating LicenseNo.DPR-18herebyissuedtoRochester Gasand.ElectricCorporation toreadasfollows:

A.ThelicenseappliestotheR.E.GinnaNuclearPowerPlant,aclosedcycle,pressurized, light-water-moderated andcooledreactor,andelectricgenerating equipment (hereinreferredtoas"thefacility"

)whichisownedbytheRochester GasandElectricCorporation (hereinafter "thelicensee" or"RG&E").Thefacility.

islocatedonthelicensee's siteonthesouthshoreofLakeOntario,WayneCounty,NewYork,about16mileseastoftheCityofRochester and,isdescribed inlicenseapplication Amendment No.6,"FinalFacilityDescription andSafetyAnalysisReport",andsubsequent amendments thereto,andintheapplication forpowerincreasenotarized February2,1971,and.Amendment Nos.1through4thereto(hereincol-lectively referredtoas"theapplication"

).B.Subjecttotheconditions andrequirements incorporated herein,theCommission herebylicensesRG&E:(1)PursuanttoSection104boftheActand10CFRPart50,"Domestic Licensing ofProduction andUtilization Facilities",

topossess,use,andoperatethefacilityatthedesignated locationinWayneCounty,NewYork,inaccordance withtheprocedures andlimitations setforthinthislicense;(2)PursuanttotheActand10CFRPart70,toreceive,possess,anduseatanytimespecialnuclearmaterialorreactorfuel,inaccordance withthelimitations forstorageandamountsrequiredforreactoroperation asdescribed intheFinalSafetyAnalysisReport,asamended,andCommission SafetyEvaluations datedNovember15,1976,October5,1984,and.November14,1984.(a)PursuanttotheActand10CFRPart70,toreceiveand.storefour(4)mixed.oxidefuelassemblies inaccordance withthelicensee's application datedDecember14,1979(transmitted byletterdatedDecember20,1979);(b)PursuanttotheActand10CFRPart70,topossessandusefour(4)mixedoxidefuelassemblies inaccordance withthelicensee's application datedDecember14,1979transmitted byletterdatedDecember20,1979),assupplemented February20,1980andMarch5,1980;(3)PursuanttotheActand10CFRParts30,40,and.70,toreceive,possess,anduseatanytimeanybyproduct, source,andspecialnuclearmaterialassealed.neutronsources.forreactorstartup,sealedsourcesforreactorinstrumentation andradiation monitoring equipment cali-bration,andasfissiondetectors inamountsasrequired; (4)PursuanttotheActand10CFRParts30,40,and70,toreceive,possess,anduseinamountsasrequiredanybyproduct, source,orspecialnuclearmaterialwithoutrestriction tochemicalorphysicalform,forsampleanalysisorinstrument calibration orassociated withradioactive apparatus orcomponents; and(5)PursuanttotheActand10CFRParts30and70,topossess,butnotseparate, suchbyproduct andspecialnuclearmaterials asmaybeproducedbytheoperation ofthefacility.

C.Thislicenseshallbedeemedtocontainandissubjecttotheconditions specified inthefollowing Commission regulations in10CFRPart20,Section30.34ofPart30,Section40.41ofPart40,Sections50.54and50.59ofPart50,and.Section70.32ofPart70;andissubjecttoallapplicable provisions oftheActand.rules,regulations andordersoftheCommission noworhereafter ineffect;andissubjecttotheadditional conditions specified below:(1)MaximumPowerLevel.RGGEisauthorized tooperatethefacilityatsteady-state powerlevelsuptoamaximumof1520megawatts (thermal)

.(2)Technical Secifications TheTechnical Specifications contained, inAppendixAareherebyincorporated inthelicense.Thelicenseeshalloperatethefacilityinaccordance withtheTechnical Specifications.

(3)FireProtection (a)Thelicenseeshallmaintainineffectallfireprotection featuresdescribed inthelicensee's submittals referenced inandasapprovedormodi-fiedbytheNRC'sFireProtection SafetyEvaluation (SE)datedFebruary14,1979andSEsupplements datedDecember17,1980,February6,1981andJune22,1981,orconfigurations subsequently approvedbytheNRC,subjecttoprovisions (b)and(c)below.(b)Thelicenseemaymakenochangetotheapprovedfireprotection featureswhichwould.decreasetheleveloffireprotection intheplantwithoutpriorapprovaloftheCommission.

Tomakesuchachangethelicenseemustsubmitanapplication forlicenseamendment pursuantto10CFR50.90.

(c)Thelicenseemaymakechangestoapprovedfireprotection featureswhichdonotdecreasetheleveloffireprotection withoutpriorCommission approvalprovidedsuchchangesdonototherwise involveachangeinalicensecondition ortech-nicalspecification orresultinanunreviewed safetyquestion(see10CFR50.59).However,thelicenseeshallmaintain, inanauditable form,acurrentrecordofallsuchchangesincluding ananalysisoftheeffectsofthechangeontheleveloffireprotection andshallmakesuchrecordsavailable toNRCinspectors uponrequest.Allchanges,totheapprovedfeaturesmadewithoutpriorCommission approvalshallbereportedannuallytotheDirectoroftheOfficeofNuclearReactorRegulation.

(4)SecondarWaterChemistrMonitorin ProramThelicenseeshallimplement asecondary waterchemistry monitoring programtoinhibitsteamgenerator tubedegra-dation.Thisprogramshallbedescribed.

intheplantprocedures andshallinclude:(a)Identification ofasamplingscheduleforthecriticalparameters and.controlpointsfortheseparameters; (b)Identification oftheprocedures usedtomeasurethevaluesofthecriticalparameters; (c)Identification ofprocesssamplingpoints;(d)Procedure fortherecording andmanagement ofdata;(e)Procedures definingcorrective actionsforoffcontrol.pointchemistry conditions; and(f)Aprocedure identifying (i)theauthority respon-siblefortheinterpretation ofthedata,and(ii)thesequenceand.timingofadministrative eventsrequiredtoinitiatecorrective action.(5)SstemsInteritThelicenseeshallimplement aprogramtoreduceleakagefromsystemsoutsidecontainment thatwouldorcouldcontainhighlyradioactive fluidsduringaserioustransient oraccidenttoaslowasreasonably achiev-ablelevels.Thisprogramshallincludethefollowing:

(a)Provisions establishing preventive maintenance andperiodicvisualinspection requirements; and

(b)Leaktestrequirements foreachsystematafrequency nottoexceedrefueling cycleintervals.

(6)IodineMonitorin Thelicenseeshallimplement aprogramwhichwillensurethecapability toaccurately determine theairborneiodineconcentration invitalareasunderaccidentconditions.

Thisprogramshallincludethefollowing:

(a)Trainingofpersonnel; (b)Procedures formonitoring; and(c)Provisions formaintenance ofsamplingandanalysisequipment.

D.Thefacilityrequiresexemptions fromcertainrequirements of10CFR50.46(a)(1),

50.48(c)(4),,

andAppendixJto10CFRPart50.Theseinclude:(1)anexemption from50.46(,a)(1),

thatECCSperformance becalculated inaccordance withanaccept-ablecalculational modelwhichconformstotheprovisions inAppendixK(SERdated,April18,1978).Theexemption willexpireuponreceiptandapprovalofrevisedECCScalcula-tions;(2)certainexemptions fromAppendixJto10CFRPart50sectionIII.A.4(a) maximumallowable leakagerateforreducedpressuretests,sectionIII.B.1acceptable technique forperforming local(TypeB)leakageratetests,sectionIII.D.1scheduling ofcontainment integrated leakageratetests,and.sectionIII.D.2testingintervalforcontain-mentairlocks(SERdatedMarch28,1978);and(3)anexemption totheschedular requirements forthealternative shutdownsystemassetforthin10CFR50.48(c)(4)

(NRCletterdated,May10,1984).Theexemption iseffective untilstartupfromthe1986refueling outage.Theaforementioned exemptions areauthorized bylawandwillnotendangerlifeorpropertyorthecommondefenseandsecurityandareotherwise inthepublicinterest.

Therefore, theexemptions areherebygranted,pursuantto10CFR50.12.E.PhysicalProtection

-Thelicenseeshallmaintainineffectandfullyimplement allprovisions ofthefollowing Commission-,

approveddocuments, including amendments andchangesmadepursuanttotheauthority of10CFR50.54(p),

whicharebeingwithheldfrompublicdisclosure pursuantto10CFR73.21:(1)SecurityPlancollectively titled"R.E.GinnaNuclearPowerPlantUnit1SecurityPlan",datedJanuary18,1978,asrevisedDecember8,.1978,March27,1979,June29,1979,December14,1979,andSeptember 10,1980.

(2)Safeguards Contingency PlanincludedasrevisedChapter8(Revisions 12and13),submitted pursuantto10CFR73.40bythelicensee's letterdatedApril3,1980,asrevisedbyletterdatedJuly24,1980,tothe"R.E.GinnaNuclearPowerPlantUnit1SecurityPlan",datedJanuary18,1978,asrevisedApril3,1980,July24,1980,andSeptember 10,1980.(3)Thelicenseeshallfullyimplement andmaintainineffectallprovisions oftheCommission-approved GuardTrainingandQualification Plan,including amendments andchangesmadepursuanttotheauthority of10CFR50.54(p).

ThisapprovedPlanconsistsofadocumentwithheldfrompublicdisclosure pursuantto10CFR73.21identified as"R.E.GinnaNuclearPowerPlant,UnitNo.1TrainingandQuali-ficationPlan",datedApril23,1981(transmitted byletterdatedMay4,1981),including revisedpagesdatedJuly29,1981(transmitted byletterdatedJuly30,1981).F.Thisamendedlicenseiseffective asofthedateofissuanceandshallexpireatmidnight, September 18,2009.FORTHENUCLEARREGULATORY COMMISSION

Attachment:

AppendixA-Technical Specifications DateofIssuance:

ATTACHMENT BReasonsforChane:ThecurrentOperating Licenseexpiration date(April25,2006)is40yearsfromthedateofissuanceoftheConstruction Permit.Becauseapproximately 29monthswererequiredtoconstruct theR.E.GinnaNuclearPowerPlanttothepointoffuelloadingandstartuptesting,theeffective periodofthelicenseisapproxi-mately37yearsand7months.CurrentNRCpolicyistoissueoperating licensesfora40-yearperiodbeginning withthedateofissuance.

Therequested changeinexpiration dateoftheR.E.GinnaNuclearPowerPlantOperating Licensewouldprovideforthe40-yearperiod'ofoperation.

Rochester Gasand.ElectricCorporation believesthattheusefullifeoftheR.E.GinnaNuclearPowerPlantissignificantly morethanthe40yearsrequested inthislicenseamendment application.

Wearecurrently involvedinaPlant.LifeExtension Program(PLEX)fortheGinnaplant.Thepurposeofthisprogramistodetermine theoptimumsafeoperating lifeofthefacilityandestablish aprogramofsurveillance, testing,andplanned,replacement/refur-bishmenttosupportthisgoal.Determination ofSiificantHazardsConsiderations:

TheproposedchangetotheOperating Licensehasbeenevaluated todetermine whetheritconstitutes asignificant hazardscon-sideration asrequiredby10CFRPart50,Sections50.91usingthestandards providedinSection50.92.Thisanalysisisprovidedbelow:,1.Theproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated..

TheR.E.GinnaNuclearPowerPlantwasdesignedandconstructed primarily onthebasisof40yearsofplantoperation.

Forexample,thereactorvesselwasdesignedandfabricated fora40-year,life.Acomprehensive vesselmaterials surveillance programismaintained inaccordance with10CFRPart50,AppendixH.Analyseswereperformed todemonstrate compliance withtheNRCpressurized thermalshockscreening criteria.

AlloftheRTvaluesremainbelowtheNRCscreening valuesforPTSusingtheprojected fluenceexposurethrough32EFPY.Attheprojected capac-ityfactorof80%thiscorresponds tothe40-yearlifeoftheplant.Thisinformation wascontained.

inWCAP-11026 whichwastransmitted totheNRConJanuary13,1986asanattachment toaletterfromR.KoberofRG&EtoG.Lear.Theanalysescontained intheR.E.GinnaNuclearPowerPlantFinalSafetyAnalysisReportwereperformed onthebasisofnotlessthan40yearsofexpected.

plantlife.

Attachment BAnalysesandinformation presented intheR.E.GinnaNuclearPowerPlantEnvironmental Report,ingeneral,werenotdependent onanyspecificperiodofplantoperation.

Procedures andprogramsareinplacetodetectabnormaldeterioration andaging,ofcriticalplantcomponents.

Examplesinclude:a.Plantpressureretaining vessels,piping,andsupportsystemsareinspected inaccordance withSectionXIoftheASMEBoilerandPressureVesselCodeand10CFRPart50,Section50.55a(g),

exceptwherespecificwrittenreliefhasbeengrantedbytheNRCpursuantto10CFR50,Section50.55a(g)(6)(i).

Safety-related pumpsand'alves areincludedinatestprogrammeetingtherequirements ofSectionXI.oftheCodeand.theplantTechnical Specifications.

b.Safety-related electrical equipment hasbeenenviron-mentallyqualified inaccordance withtherequirements of10CFRPart50,Section50.49.Aginganalysesestablish requiredintervals forequipment replacement.

Noitemswouldbeaffectedbytheextension.

c~Anumberofspecialinspections andinvestigations havebeenperformed bytheR.E.GinnaNuclearPowerPlanttechnical staffproviding additional assurance thatabnormalorunanticipated degradation willnotoccurincomponents requiredforsafeandreliableplantoperation.

Theseinspections haveincludedsuchitemsaspipe,valve,andfittingwallthick-nessmeasurements insteam,feedwater andcondensate

'linessubjecttoerosion..

Asanexampleofthisongoingeffort,amotoroperatedvalvediagnostic programisbeingimplemented atGinna.Thisprogramisproviding valuabledatatoinsurecontinued reli-abilityandperformance ofthemotoroperatedvalves.Additional inspections ofthisnature'ill beidenti-fiedaspartoftheR.E.Ginnaplant-specific PLEXProgram.Therequested extension ontheR.E.GinnaNuclearPowerPlantlicensewillallowtheplanttooperateforthelengthoftimecontemplated duringthedesignprocess.Thestationhasprogramsandprocedures inplacetomonitorthepowerplanttogivereasonable assurance thatequipment andsystemswillcontinuetomeettheirdesignparameters.

Theextension ofthelicensedoperating period,therefore, willnotsignificantly increasetheprobability orconsequences ofaccidents thathavebeenpreviously evaluated.

Attachment B2.Theproposedamendment willnotcreatethepossibility ofanewordifferent.

kind.ofaccidentfromanyaccidentpreviously analyzed.

Theproposedamendments involveonlyachangeintheexpiration dateoftheOperating License.Nosafetyanalysesareaffected.

Nonewordifferent accidenttypeiscreated..

Theaccidentanalysespresented intheUpdated.FinalSafetyAnalysisReportremainhounding.

3.Theproposed, amendment willnotinvolveasignificant reduction inthemarginofsafety.Theproposedamendment involvesonlyachangeintheexpiration dateoftheOperating License.Nosafetymarginsareaffected.

Thelicensing basesoftheplant,asdescribed intheUpdatedFinalSafetyAnalysisReportandtheEnviron-mentalReport,areapplicable for40yearsofplantoperation.

Forthereasonsstatedabove,wehaveconcluded thattheselicenseamendments donotinvolveasignificant.

hazardsconsideration.

ReviewofR.E.GinnaNuclearPowerPlantEnvironmental ReortWehavereviewedtheoriginalR.E.GinnaNuclearPowerPlantEnvironmental Report,andthe1982update.Wehaveconcluded thattheenvironmental impactassociated withoperation oftheR.E.GinnaNuclearPowerPlantfora40-yearperiod.ofoperation wasconsidered inthisreport.TheEnvironmental Report,assupplemented, doesnotgenerally useordiscussaspecificperiod.ofplant.operation intheevaluations presented..

Intheapproximately 5yearsofplantoperation sincetheEnvi-ronmental Reportwasupdated,anumberofmodifications havebeenmadetotheR.E.GinnaNuclearPowerPlantandsurrounding siteandfacilities.

Thesemodifications, ingeneral,hadtheeffectofimproving thereliability andsafetyoftheplantorreducingtheenvironmental impactofplantoperation.

Theyinclude:a.Facilities Manymodifications totheplanthavebeenmadesincetheoriginalOperating Licensehasbeenissued.Sig-nificantmodifications.

aredescribed in,theR.E.GinnaUpdatedFinalSafetyAnalysisReport.Modifications madewithoutpriorNRCapprovalinaccordance withtheprovisions of10CFRPart50,Section50.59,were Attachment BreportedtotheCommission.

Modifications requiring priorNRCapprovalweremadefollowing receiptofanNRCSafetyEvaluation Report.Nomodification wasfoundtoaffecttheconclusions oftheR.E.GinnaNuclearPowerPlantEnvironmental Report.During1978aDeepBedCondensate Polishing SystemwasbroughtonlineatGinnaStationforthepurposeofimproving thesecondary sidesteamgenerator waterchem-istry.Thissystemwashousedina6,000ftadditionattachedtotheturbinebuilding.

Whilethissystemhashadabeneficial effectonsteamgenerator chemistry, additional wasteproductshavebeenproducedwhichrequirechemicaltreatment priortodischarge intoLakeOntario.Thedischarges areacceptable totheNYStateDepartment ofEnvironmental Conservation andareincludedintheCompany's SPDESpermitdiscussed inSectionc.below.b.RandUseWhilesomeconstruction (e.g.,thecondensate polisherbuilding) hastakenplaceontheGinnasitesincethe1982EISupdate,siteboundaries andacreagehavenotchanged.Noneofthenewfacilities willresultinanyadditional impactuponlocallanduseorterrestrial ecosystems andtherefore theimpactsdescribed in.theEISremainvalid.c.WaterQualityandThermalDischarge-Related.

ImpactsTheGinnaStationcirculating coolingwatersystemisregulated bytheStatePollutant Discharge Elimi-nationSystem(SPDES)Permitting ProgramwhichisanEPA-initiated program(subsequently.

transferred totheStateofNewYork)whichauthorizes andmonitorsdis-charges'o waterbodiesinordertoensuretheprotection oftheenvironment fromchemical,

physical, andbiological degradation.

InMay1985theNewYorkStateDepartment ofEnvironmental Conservation issuedSPDESPermitNo.NY-0000493forthe.GinnaStation.Thispermitisrenewable onafiveyearbasis.Allwaterqualityissuesincluding chem-icaldischarges, discharge flows,thermaldischarge, and.biological impactscomeunderthejurisdiction ofthispermit.Additionally, thispermitauthorized variances fortheexistingcoolingwaterintakeanddischarge.

systemspursuanttoSections316(a)and.(b)oftheCleanWaterActforthefiveyearlifeofthepermit.Becausethispermitwasissuedsubsequent tothe1982EISupdate,impactssincethattimehavebeen,andwillcontinuetobe,thoroughly reviewedintheSPDESprocess.

Attachment BAsignificant changetothecirculating coolingwatersystemdescription whichhasbeenmadesincethe1982EISupdateistherevisionoftotaldailydischarge flowfrom576milliongallonsperdayto490milliongallonsperday.Thisrevisionwasmadein1985andwasbasedonrecalculated heatrejection ratesfortheStation.Additionally, sincethe1982EISupdateanumberofreportsrelatedtotheaquaticecological impactsofGinnaStationoperation havebeenprepared.

Following isalistofthesignificant aquaticecological reportspreparedforGinnaStationsincethe1982EISupdate.RG&EREPORTNO.B-13-289TITLE1977-1981 Entrainment ProgramSummaryReport,GinnaNuclearPowerStation,1985B-13-2901978-1983 FishProgramSummaryReport,GinnaNuclearPowerStation,1986B-13-293GinnaNuclearPowerStation,Impingement ProgramPlanofStudy,1985B-13-328FishImpingement Program,1982through1986AnalysisReport,GinnaNuclearPowerStation,1987Theapplicant believesthattheSPDESPermitting ProgramisadequatetomonitorpresentandfuturewaterqualityimpactsofGinnaStation.Therefore, noadditional waterqualityimpactanalysesarenecessary inthisapplication.

d.Radiological Effects-and RadwasteTreatment SystemsReleasesofradioactive liquidandgaseouswastesfromGinnahaveremainedamongthelowestofU.S.generating plantsduringthepastdecade.Volumeofradwasteshipped,isamongthelowestofU.S.nucleargenerating plants.Thefollowing tableisasummaryofthemostrecentGinnaoffsiteradiation doseassessment whichcoverstheperiodofJanuary1throughDecember31,1986.Theseannualdosesaresubstantially lower-thanthosereportedintheFinalEnvironmental ImpactStatement (FEIS).

Attachment BGaseousReleaseCalculated DoseBasedonReleaseData10CPR50AppendixIGuidelines PerUnitPerYearMaximumSiteBoundaryGammaAirDose(mrad)0.002210MaximumSiteBoundaryBetaAirDose(mrad.)0.005420TotalMaximumOffsiteDosetoAnyOrgan(mrem)0.0060Liid.ReleasesTotalMaximumOffsiteWholeBodyDose(mrem)0.172TotalMaximumOffsiteOrganDose(mrem)0.19310Therehavebeennolandusechangeswhichhavesignifi-cantlyaffectedoffsitedosecalculations.

Resultsofthe1986offsitedosecalculations forthecriticalreceptorareprovidedbelow.This1985dataistypicalandisexpectedtobetypicalofdoseassessments through2009.CriticalRecetor-for1986:SectorDistancePathwayAgeGroupThyroidDoseE670MetersGround.,Inhalation, Vegetation Child0.006mremOccupational radiation exposureattheR.E.GinnaplanthasbeenreducedtolessthantheU.S.averageforPWRsforthelastfouryears.Thishasbeenachieveddespiteanearlyhistoryoffuelleakageandalaterhistoryofincreasing steamgenerator inspection andrepairrequire-ments.Theexposurereduction isattributed toamanage-mentcommitment to"AsLowAsReasonably Achievable (ALARA)"exposures, andanexperienced.

and,motivated radiation protection supportgroup.Theprogramreceives Attachment Bconstantattention throughtheCorporate ALARACommittee andwasrecentlyenhancedbyadoptionbytheEngineering Department oftheALARA/Radiation SafetyDesignReviewprocedure.

Theannualpersonnel dosereceivedatGinnaforeachofthelastfiveyearsissummarized below.The"averageannualdoseforthatperiodisapproximately 487man-remandforthelastfouryearsapproximately 368man-rem.Doseratesarestableandarenotexpectedtoincreasesignificantly inthefuture,infact,adecreaseispossibleduetorecentlydeveloped dilutechemicaldecontamination techniques.

Theincreased useofroboticsinmaintenance willalsotendtoreducetheannualdose.Annualmaintenance activities arenotexpectedtochangesignificantly duetotheincreaseinplantlife.Overall,theGinnaannualdoseisnotexpectedtoexceed.thelastfouryearsofoperation andbeapproximately 350man-remperyearfortheperiod.of2006to2009.YearTotalDose(man-rem) 19831984198519861987960370410363330*Includes 180man-remforseismicsupports, 110man-remfornozzledaminstallation, 130forsteamgenerator tubesleevesand.135forsteamgenerator channelheaddecontamination.

Inadditiontooperational methodsandprocedures whichareemployedtoreduce.publicandoccupational doses,manymodifications havebeenmadetotheplanttoreduceeffluents, radwasteshipments andpersonnel exposure.

Majorchangesincludeinstallation ofacharcoalfilter.intheauxiliary buildingventilation system,theadditionofpolishing demineralizers fortheliquidradwastesystemandtheuseofasupercompactor tore-ducethenumberofradwaste.

shipments.

Installation ofareactorheadshieldanduseofroboticequipment forinspection andrepairhavereducedoccupational doseso Attachment.

BTheR.E.GinnaNuclearPower.Plantspentfuelstoragepoolhasbeenrerackedtomaximumcapacity, butwillnotprovideadequatestoragetotheendofthecurrentlicensedoperation.

Therodconsolidation processisbeingexploredandademonstration programhasbeenconducted.

Rodconsolidation wouldprovideforoperation beyondtheyear2009withfullcoredischarge capability.

IfaFederalrepository isnotavailable bythen,othermethodsofonsitestorage,suchasdrycaskstorage,couldbeemployed.

e.Population Recentpopulation densities havebeencomparedwiththe1970U.S.CensusBureaustatistics usedintheoriginalEIS.Theapplicant hasobtained1984population dataforthethirteencountyareaincludedinthe50mileradiusoftheplant.Thi;sinformation indicates thatthepopulation inthisthirteencountyareahasincreased byonly3%overall.Sincethisincreaseissubstantially belowboththeoriginalRG&EandNRCestimates for1984,theresultant impactsuponpopulations shouldactuallybelessthanthoseoriginally estimated intheEIS.The1980population fora2mileradiusaroundthe.Ginnasiteis1078people.Thispopulation isestimated toincreaseto1390bytheyear2015basedonthe1980-1985 population growthrateforWayneCounty.Population centerswith'populations greaterthan25,000people,withinthe50mileradiusoftheplant,includeMonroeCountywiththeCityofRochester (Rochester 1984popu-lation:243,000),

andtheCityofAuburn,N.Y.Theseareidentified below,alongwithpopulation projections fortheyear2015,basedonthe1970-1980 population growthratesfortheseareas.POPULATION CENTERLOCATION1984POPULATION 2015MonroeCountyAuburn,N.Y.20miWSW45miESE711,20032,000742,10035,500Weconcludethattheenvironmental impactscausedbythepresenceoftheR.E.GinnaNuclearPowerPlantareminimalandthattherehavebeennosignificant negativechangescaused,bymodifications whichhavebeenmadetotheplant.Thisrecordprovidesabasistoshowthattheenvironmental costofcontinued operation oftheplant,atleasttotheSeptember 2009date,isminimalin,compari-sontothesocietalbenefitsoftheuseof.,relatively inexpensive energywhichisgenerated attheplant.

0~t