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| -GINNAPLANT-Criticality SafetyAnalysisfortheNewFuelStorageRacksbyThomasR.RobbinsPickard,LoweandGarrick,Inc.July19838309ih0056 8309i2PDRADOCK05000244PPDR7011R0706835 | | -GINNA PLANT-Criticality Safety Analysis for the New Fuel Storage Racks by Thomas R.Robbins Pickard, Lowe and Garr ick, Inc.July 1983 8309ih0056 8309i2 PDR ADOCK 05000244 P PDR 7011R0706835 |
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| Introduction ThenewfuelstorageracksfortheGinnaPlantaccommodate 44fuelassemblies in4rowsof11assemblies. | | Introduction The new fuel storage racks for the Ginna Plant accommodate 44 fuel assemblies in 4 rows of 11 assemblies. |
| Althoughnewfuelassemblies arealwaysstoredinadrycondition inthese,racks,thecondition ofoptimummoderation isconsidered inthisanalysiseventhoughitisinconceivable thatsuchacondition couldbeachievedintheseracks.'escri tionoftheAnalsisAplanviewofthenewfuelstorageracksisshowninFigure1.Althoughthecentertocenterspacingbetweenallfuelassemblystoragelocations isnotuniformintheEast-Nest Direction, aminimumuniformspacingwasconservatively assumedintheanalysis.
| | Although new fuel assemblies are always stored in a dry condition in these, racks, the condition of optimum moderation is considered in this analysis even though it is inconceivable that such a condition could be achieved in these racks.'escri tion of the Anal sis A plan view of the new fuel storage racks is shown in Figure 1.Although the center to center spacing between all fuel assembly storage locations is not uniform in the East-Nest Direction, a minimum uniform spacing was conservatively assumed in the analysis.Figure 1 also shows the conservative symmetric geometry model chosen to calculate the effects of radial neutron leakage from the racks in the North-South direction. |
| Figure1alsoshowstheconservative symmetric geometrymodelchosentocalculate theeffectsofradialneutronleakagefromtheracksintheNorth-South direction.
| | Symmetry boundary conditions (i.e., zero neutron current)are imposed on the North, East, and i<est boundaries of the model, and a zero neutron flux boundary condition is imposed at the outer edge of the assumed water reflector on the South boundary.The detailed dimensions and geometry of this model are shown in Figure 2.The'uel assembly characteristics utilized for the analysis are shown in Table 1.A uniform'axial enrichment distribution of 4.25 w/o U-235 was assumed for each fuel rod in the assembly.The k of the fuel pin cell used to generate cross sections for the rack criticality analysis is shown as a function of water density in Figure 3.For the normal dry storage condition, the fuel assembly k will be essentially the same as or lower than the fuel pin cell Q, and therefore an upper limit for the k ff of the rack for dry conditions may be obtained by extrapolation of the fuel pin cell k: to zero water density.The resulting k is about 0.72, and the k ff of the finite rack will be substantially less than that value.7011R0706831 I'C If it is assumed the entire rack area is surrounded by a full density water reflector, then the water density in the resulting enclosed area can be varied, and the k of the rack can be determined from edits which combine the void-water and fuel assembly regions of the model shown in Figure 2.The resulting fuel rack k is also shown in Figure 3.At water densities below 0;1 gm/cc,'n optimum moderation condition is approached. |
| Symmetryboundaryconditions (i.e.,zeroneutroncurrent)areimposedontheNorth,East,andi<estboundaries ofthemodel,andazeroneutronfluxboundarycondition isimposedattheouteredgeoftheassumedwaterreflector ontheSouthboundary.
| | The apparent, optimum moderator density is quite low because of the large volume fraction of the void-water region (0.994)as compared to that of the fuel region (;006)." However, these large k's at low water densities are not of concern as shown by the k ff values from the eff same calculations. |
| Thedetaileddimensions andgeometryofthismodelareshowninFigure2.The'uelassemblycharacteristics utilizedfortheanalysisareshowninTable1.Auniform'axialenrichment distribution of4.25w/oU-235wasassumedforeachfuelrodintheassembly.
| | The neutron multiplication factor, which includes neutron leakage effects in the North-South direction only, is shown as a function of water density in Figure 4.The maximum neutron multiplication factor is seen to be about 0.94 at an optimum water density of about:045 gm/cc.'owever, these calculations assumed zero neutron leakage in both the East-West radial direction and the axial direction. |
| Thekofthefuelpincellusedtogeneratecrosssectionsfortherackcriticality analysisisshownasafunctionofwaterdensityinFigure3.Forthenormaldrystoragecondition, thefuelassemblykwillbeessentially thesameasorlowerthanthefuelpincellQ,andtherefore anupperlimitforthekffoftherackfordryconditions maybeobtainedbyextrapolation ofthefuelpincellk:tozerowaterdensity.Theresulting kisabout0.72,andthekffofthefiniterackwillbesubstantially lessthanthatvalue.7011R0706831 I'C Ifitisassumedtheentirerackareaissurrounded byafulldensitywaterreflector, thenthewaterdensityintheresulting enclosedareacanbevaried,andthekoftherackcanbedetermined fromeditswhichcombinethevoid-water andfuelassemblyregionsofthemodelshowninFigure2.Theresulting fuelrackkisalsoshowninFigure3.Atwaterdensities below0;1gm/cc,'noptimummoderation condition isapproached.
| | To determine the effect of" axial neutron leakage on the multiplication factor, flux weighted cross sections representing the fuel assembly and void-water regions of the radial model were used in one-dimensional axial calculations, and the results are also shown in I Figure 4.The maximum neutron multiplication factor is now seen to be about 0.70 at a water density of about.075 gm/cc.This low multiplication factor even at optimum moderation conditions makes it unnecessary to evaluate the neutron leakage effects in the East-West radial direction which would result in some further small but significant reduction in the neutron multiplication factor.In addition to the other conservatisms in the calculations, no credit was taken for neutron streaming effects at low water densities. |
| Theapparent, optimummoderator densityisquitelowbecauseofthelargevolumefractionofthevoid-water region(0.994)ascomparedtothatofthefuelregion(;006)."However,theselargek'satlowwaterdensities arenotofconcernasshownbythekffvaluesfromtheeffsamecalculations.
| | Considering the large distances separating fuel assemblies in the rack, such effects would be expected to significantly increase neutron leakage from the racks and thereby further reduce the neutron multiplication factor.7011R0706832 I |
| Theneutronmultiplication factor,whichincludesneutronleakageeffectsintheNorth-South direction only,isshownasafunctionofwaterdensityinFigure4.Themaximumneutronmultiplication factorisseentobeabout0.94atanoptimumwaterdensityofabout:045gm/cc.'owever, thesecalculations assumedzeroneutronleakageinboththeEast-West radialdirection andtheaxialdirection.
| | Figure 4 also demonstrates the acceptability of the new fuel storage racks in the flooded condition which corresponds to a water density of 1.0 gm/cc.As shown, the neutron multiplication factor is somewhat less than 0;88 for the fully flooded condition and therefore clearly acceptable. |
| Todetermine theeffectof"axialneutronleakageonthemultiplication factor,fluxweightedcrosssectionsrepresenting thefuelassemblyandvoid-water regionsoftheradialmodelwereusedinone-dimensional axialcalculations, andtheresultsarealsoshowninIFigure4.Themaximumneutronmultiplication factorisnowseentobeabout0.70atawaterdensityofabout.075gm/cc.Thislowmultiplication factorevenatoptimummoderation conditions makesitunnecessary toevaluatetheneutronleakageeffectsintheEast-West radialdirection whichwouldresultinsomefurthersmallbutsignificant reduction intheneutronmultiplication factor.Inadditiontotheotherconservatisms inthecalculations, nocreditwastakenforneutronstreaming effectsatlowwaterdensities.
| | Because of the conservative techniques and assumptions used to evaluate the maximum possible neutron multiplication factor, there is more than reasonable assurance that no significant hazards based on criticality safety are involved in storing fuel assemblies of up to 4.25 w/o U-235 in the Ginna.new fuel storage racks.7011R0706833 Table 1 FUEL ASSEMBLY CHARACTERISTICS Number of rods containing U02 Rod pitch (in)Overall envelope dimensions (in)Weight of U (Kg U)Active fuel length (in)Enriched uranium region Length (in)Enrichment (w/o)Natural uranium blanket region Length (in)Enrichment (w/o)Instrument tube Material O.D;(in)I.D.(in)Guide tubes 179 0."5560 7.763 350;5 141.4 128.98 4.25 12.42 0.711 Zr-4 0.4015 0.3499 Material O.D.(in), O.D.(in), I.D.(in), I.D.(in), Fuel pellet Material Density (X O.D.(in)Cladding O.D.(in)I.D.(in)Spacer Grids Number above dashpot in dashpot above dashpot in dashpot theoretical) |
| Considering thelargedistances separating fuelassemblies intherack,sucheffectswouldbeexpectedtosignificantly increaseneutronleakagefromtheracksandtherebyfurtherreducetheneutronmultiplication factor.7011R0706832 I | | Zr-4 0.5280 0.4825 0.4900 0.4425 U02 95+"-1.5 0.3444 0.0019.400.3514 i<eights of materials* |
| Figure4alsodemonstrates theacceptability ofthenewfuelstorageracksinthefloodedcondition whichcorresponds toawaterdensityof1.0gm/cc.Asshown,theneutronmultiplication factorissomewhatlessthan0;88forthefullyfloodedcondition andtherefore clearlyacceptable.
| | Inconel grids (2), lbs total Zircaloy grids (7), lbs total 3.00 19.46*Does not include weight of the stainless steel sleeves or inserts.7Allun7n~n~n a 5 5c 5g/-'8"/'-8"/'-8"/'-8" 2.4"/'-8"/'8" 2'O/'8''-8"/-'8"/-'8"/'-8" Il.8 TYP.I I t!f II NENI FUEL RACKS (7YP.4 R0M/5)SEE ENLARGEO PLAAI A-8~5EE ELEV.2&Oed.O.51 8 0'ru).O32 L2~2 COhlTINVOJ5 8=7u<EFN d<s FOR SUPPORT STEEL W THIS AREA-SEE OM/CI.D-522-G'32 CON ERVA FOR RADI VE N lj LEA DEL 0 GE RACK FOR OET4/2$OF OOOO SFE'/dl 072 |
| Becauseoftheconservative techniques andassumptions usedtoevaluatethemaximumpossibleneutronmultiplication factor,thereismorethanreasonable assurance thatnosignificant hazardsbasedoncriticality safetyareinvolvedinstoringfuelassemblies ofupto4.25w/oU-235intheGinna.newfuelstorageracks.7011R0706833 Table1FUELASSEMBLYCHARACTERISTICS Numberofrodscontaining U02Rodpitch(in)Overallenvelopedimensions (in)WeightofU(KgU)Activefuellength(in)EnricheduraniumregionLength(in)Enrichment (w/o)NaturaluraniumblanketregionLength(in)Enrichment (w/o)Instrument tubeMaterialO.D;(in)I.D.(in)Guidetubes1790."55607.763350;5141.4128.984.2512.420.711Zr-40.40150.3499MaterialO.D.(in),O.D.(in),I.D.(in),I.D.(in),FuelpelletMaterialDensity(XO.D.(in)CladdingO.D.(in)I.D.(in)SpacerGridsNumberabovedashpotindashpotabovedashpotindashpottheoretical)
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| Zr-40.52800.48250.49000.4425U0295+"-1.50.34440.0019.400.3514i<eightsofmaterials* | |
| Inconelgrids(2),lbstotalZircaloygrids(7),lbstotal3.0019.46*Doesnotincludeweightofthestainless steelsleevesorinserts.7Allun7n~n~n a55c5g/-'8"/'-8"/'-8"/'-8"2.4"/'-8"/'8"2'O/'8''-8"/-'8"/-'8"/'-8"Il.8TYP.IIt!fIINENIFUELRACKS(7YP.4R0M/5)SEEENLARGEOPLAAIA-8~5EEELEV.2&Oed.O.5180'ru).O32L2~2COhlTINVOJ5 8=7u<EFNd<sFORSUPPORTSTEELWTHISAREA-SEEOM/CI.D-522-G'32CONERVAFORRADIVENljLEADEL0GERACKFOROET4/2$OFOOOOSFE'/dl072
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| ~~Figure2SYNNETRIC HODELTOCONSERVATIVELY REPRESENT RADIALLEAKAGEOFTHEGINNANEMFUELSTORAGERACKS117.071.892107.064.108VOID-WATER7.784FUELASSEMBLIES 7.784'MATER 4'tFigure3GINNANEWFUELRACKWITHOFAAT4.25W/0U-235INFINITEMULTIPLICATION FACTORVSWATERDENSITY4>>>>444~~4+MtI>>t~1.6"'>>t<<tt+<<t~4~>>2>>%toot~M+22M~24~2224WtW4<<44~\4'~2-OOn2ttO4IOGL41.41.21.00.8O.o~222i":2'ar~it4~4<<EwZ4>>t~4+t424>>~t44~\>>W4C~ot~otQt>>4+~4<<~>>4+~4~>>WoI'4+2EEit.t2~+<<tl44Ott+2'>>~tl2'KIool~ttttitiI>>24Pi4~\rFIE~~tt~t4+Ztt4>>+4HHE~tt28Lttt4~+4+tootal~4=HT2H+tt~4<<44444++t+t4to~tlttt4>>:223K3144+224tto~444>>4>>tt>>+tt<<.24I+t4t444IP>>R~tlt>>1~+to44+\4442<<1Pi'.llIttt>>~>><<>>4NewFuelRackModel."=."~~;,FuelPinCell-:.0.442244ttttttttot4~4+4~4>>t>>~++4tg+~tt>>4~<<4Ittt44~444444>>4+>>4~tLI1~~to4+>>~tlt+4~~<<4ttt44>>>>44~ltoC~2"t~4444>>~t'I~KiIK-=- | | ~~Figure 2 SYNNETRIC HODEL TO CONSERVATIVELY REPRESENT RADIAL LEAKAGE OF THE GINNA NEM FUEL STORAGE RACKS 117.0 71.892 107.0 64.108 VOID-WATER 7.784 FUEL ASSEMBLIES 7.784'MATER 4't Figure 3 GINNA NEW FUEL RACK WITH OFA AT 4.25 W/0 U-235 INFINITE MULTIPLICATION FACTOR VS WATER DENSITY 4>>>>444~~4+Mt I>>t~1.6"'>>t<<tt+<<t~4~>>2>>%toot~M+22M~2 4~2224 Wt W 4<<4 4~\4'~2-O O n2 tt O 4I O GL 4 1.4 1.2 1.0 0.8 O.o~222 i": 2'a r~it 4~4<<EwZ 4>>t~4+t4 24>>~t 44~\>>W 4C~ot~ot Qt>>4+~4<<~>>4+~4~>>Wo I'4+2 EE it.t 2~+<<t l4 4 Ott+2'>>~tl 2'K I ool~ttttiti I>>24 Pi 4~\rFI E~~tt~t 4+Ztt 4>>+4 HHE~tt 28 L tt t 4~+4+to otal~4=HT2 H+tt~4<<44 44 4++t+t4 to~t ltt t4>>:22 3K3 144+224t to~444>>4>>tt>>+tt<<.2 4 I+t 4 t 444 IP>>R~tlt>>1~+to 44+\444 2<<1 Pi'.ll I ttt>>~>><<>>4 New Fuel Rack Model."=."~~;,Fuel Pin Cell-:.0.4 4224 4 tttt ttt tot 4~4+4~4>>t>>~++4 tg+~tt>>4~<<4I ttt4 4~4 444 4 4>>4+>>4~t LI1~~to 4+>>~tlt+4~~<<4 tt t4 4>>>>44~l to C~2"t~444 4>>~t'I~KiIK-=- |
| 442-g30.2)4<<X+3~t~+4+t>>t~~o'.IIi22=~4>>4~~444444\4~4>>22I4+t4tttttottol44otto<<444~4>>t>>4~4~4~4~t>>t14Ž44+tot~~4~+440~~40>>4>>t~o~~0.4'.60.81.00.2WaterDensity(gm/cc)I~~II4~~I~~~ll>>~~I~>>4~oil Figure40.9i!!iii!!!li!!i!!I!Iij,'jGINNANEWFUELSTORAGERACKSWITHOFAAT4.25W/0U-235NEUTRON}}ULTIPLICATiON FACTORVSWATERDENSITYiil!)jj'!!ll'i!iiiiji!'II!I~Ill!j!Il!))ljll!i)iillI'!i!ill!Ii)fill!lilitel!i)fl!!Ti!!l"ll)iiIlljlI!li):IQi'ili!:.i'I'll)'ll)i.!i!hl!i!jll!!!!i!!!!li:I!Il!'Ill:IWITHCONSERVATIVE HOOELOFRADIALLEAKAGEj))i....,,...,.~..!'!l!)il!)!illII'jjIIIIIIl!!'!!i!;I!!!j!)!I!)!OWITHCONSERVATIVE HODELOFRADIALANDAXIALLEAKAGE!l!Ijii!!1I"..Iiil'!!ii!i!!!ll!IIIjij!Ij!j!I'!j!),')jj)ijiEJ+0':!tii!iiit!!:ii!iii:jt;L'(I!!il!I!I!,Nj!Ii!iliai!l!!!i!j!i':i!i:!i!!':i | | 442-g3 0.2)4<<X+3~t~+4+t>>t~~o'.IIi 22=~4>>4~~444 444\4~4>>22 I 4+t4 ttttt otto l 44 otto<<4 4 4~4>>t>>4~4~4~4~t>>t 14Ž4 4+to t~~4~+4 4 0~~4 0>>4>>t~o~~0.4'.6 0.8 1.0 0.2 Water Density (gm/cc)I~~I I 4~~I~~~ll>>~~I~>>4~oil Figure 4 0.9 i!!i ii!!!li!!i!!I!I ij,'j GINNA NEW FUEL STORAGE RACKS WITH OFA AT 4.25 W/0 U-235 NEUTRON}}ULTIPLICATiON FACTOR VS WATER DENSITY iil!)jj'!!ll'i!i iiij i!'I I!I~I ll!j!Il!))l jll!i)ii ll I'!i!i ll!Ii)f ill!lili tel!i)fl!!Ti!!l" l l)i i I ll jl I!li):I Qi'i li!:.i'I'll)'ll)i.!i!h l!i!jll!!!!i!!!!li:I!Il!'Ill:I WITH CONSERVATIVE HOOEL OF RADIAL LEAKAGE j))i....,,...,.~..!'!l!)il!)!ill II'jj I II II Il!!'!!i!;I!!!j!)!I!)!O WITH CONSERVATIVE HODEL OF RADIAL AND AXIAL LEAKA GE!l!Iji i!!1 I"..Ii il'!!ii!i!!!ll!I I I jij!I j!j!I'!j!),')jj)iji EJ+0':!t ii!i iit!!:i i!ii i:j t;L'(I!!il!I!I!, Nj!Ii!ilia i!l!!!i!j!i': i!i:!i!!':i)I!!j')I!!i i!!1)!)ll O t 0.6!'ii!!!!i iii: I)I I I jij L':t j j!:Ij.Ij!!!!)j)ii:il!li i!!j i!!i P)~':.: 0.4 0 0.1 ljl!)l(!i!!t (l"'i'I[0.2 0.3 0.4 0.5 0.6 0.2 0.8 0.9 1.0 Water Density (gm/cc) |
| )I!!j')I! | | ~~~C a h K l' September 2, 1983 DISTRIB UTION Docket ORB Reading GDick HSmith ELD attorney DOCKET NO(S).50-244 Nr.John E.Mlier, Vice President Electric and Steam Production Rochester,.Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 I R.E.GINNA PLANT-OPPORTUNITY FOR HEARING (APPLICATIONS 1"1,/24/81, SNUBBER REQUIREMENTS: |
| !ii!!1)!)llOt0.6!'ii!!!!iiii:I)IIIjijL':tjj!:Ij.Ij!!!!)j)ii:il!lii!!ji!!iP)~':.:0.400.1ljl!)l(!i!!t(l"'i'I[0.20.30.40.50.60.20.80.91.0WaterDensity(gm/cc) | | 9/28/82, STAFF REORGANIZATION) |
| ~~~CahKl' September 2,1983DISTRIBUTIONDocketORBReadingGDickHSmithELDattorneyDOCKETNO(S).50-244Nr.JohnE.Mlier,VicePresident ElectricandSteamProduction Rochester,.Gas andElectricCorporation 89EastAvenueRochester, NewYork14649IR.E.GINNAPLANT-OPPORTUNITY FORHEARING(APPLICATIONS 1"1,/24/81, SNUBBERREQUIREMENTS: | | The following documents concerning our review of the subject facility are transmitted for your information.'otice of Receipt of Application. |
| 9/28/82,STAFFREORGANIZATION) | | Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No., dated Notice of Hearing on Application for Construction Permit.Notice of Consideration of Issuance of Facility Operating License.Application and Safety Analysis Report, Volume Amendment No.to Application/SAR dated Construction Permit No.CPPR-, Amendment No., dated Facility Operating License No., Amendment No., dated Order Extending Construction Completion Date, dated El Other(Specify) |
| Thefollowing documents concerning ourreviewofthesubjectfacilityaretransmitted foryourinformation.'otice ofReceiptofApplication.
| | C August 23, 1983 (see 48 FR 38421);the intervention period expires Dt |
| Draft/Final Environmental Statement, datedNoticeofAvailability ofDraft/Final Environmental Statement, datedSafetyEvaluation Report,orSupplement No.,datedNoticeofHearingonApplication forConstruction Permit.NoticeofConsideration ofIssuanceofFacilityOperating License.Application andSafetyAnalysisReport,VolumeAmendment No.toApplication/SAR datedConstruction PermitNo.CPPR-,Amendment No.,datedFacilityOperating LicenseNo.,Amendment No.,datedOrderExtending Construction Completion Date,datedElOther(Specify) | |
| CAugust23,1983(see48FR38421);theintervention periodexpiresDt
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| ==Enclosures:== | | ==Enclosures:== |
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| Asstatedcc:w/enclosures:
| | As stated cc: w/enclosures: |
| SeeSnextpage/gZ~/8Office,ofNuclearReacorRegulation Division-of.'icensing Operating ReactorsBranch85AOFF/cE>L:0iF5SURNAME/g~COATEP/7NROFORM318{10/80)NRCM0240OFF(CIALRECOROCOPY
| | SeeSnext page/g Z~/8 Office, of Nuclear Reac or Regulation Division-of.'icensing Operating Reactors Branch 85 A OFF/cE>L: 0 iF5 SURNAME/g~C OATE P/7 NRO FORM 318{10/80)NRCM 0240 OFF(CIAL RECORO COPY |
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| Mr.JohnE.MaierCC'arryH.Voigt,EsquireLeBoeuf,Lamb,LeibyandMacRae1333NewHampshire Avenue,N.W.Suite1100Washington, D.C.20036Mr.MichaelSlade12Trailwood CircleRochester, NewYork14618EzraBialikAssistant AttorneyGeneralEnvironmental Protection BureauNewYorkStateDepartment ofLaw2WorldTradeCenterNewYork,NewYork10047ResidentInspector R.E.GinnaPlantc/oU.S.NRC1503LakeRoadOntario,NewYork14519StanleyB.Klimberg, EsquireGeneralCounselNewYorkStateEnergy'ffice AgencyBui-lding 2'mpireStatePlazaAlbany,NewYork12223Dr.EmmethA.LuebkeAtomicSafetyandLicensing BoardU.S.NuclearRegulatory Comnission Washington, D.C.20555Dr.RichardF.ColeAtomicSafetyandLicensing BoardU.S.NuclearRegulatory Coomission Washington, D.C.20555Dr.ThomasE.Murley,RegionalAdministrator NuclearRegulatory Coomission, RegionI631ParkAvenue'ingofPrussia,Pennsylvania 19406U.S.Environmental Protection AgencyRegionIIOfficeATTN:RegionalRadiation Representative 26FederalPlazaNewYork,NewYork10007HerbertGrossman, Esq.,ChairmanAtomic.SafetyandLicensing BoardU.S.NuclearRegulatory Commission Washington, D.C.20555Supervisor oftheTownofOntario107RidgeRoadWestOntario,NewYork14519JayDunkleberger NewYorkStateEnergyOffice.AgencyBuilding2EmpireStatePlazaAlbany,NewYork12223}} | | Mr.John E.Maier CC'arry H.Voigt, Esquire LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue, N.W.Suite 1100 Washington, D.C.20036 Mr.Michael Slade 12 Trailwood Circle Rochester, New Yor k 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.Ginna Plant c/o U.S.NRC 1503 Lake Road Ontario, New York 14519 Stanley B.Klimberg, Esquire General Counsel New York State Energy'ffice Agency Bui-lding 2'mpire State Plaza Albany, New York 12223 Dr.Emmeth A.Luebke Atomic Safety and Licensing Board U.S.Nuclear Regulatory Comnission Washington, D.C.20555 Dr.Richard F.Cole Atomic Safety and Licensing Board U.S.Nuclear Regulatory Coomission Washington, D.C.20555 Dr.Thomas E.Mur ley, Regional Administrator Nuclear Regulatory Coomission, Region I 631 Park Avenue'ing of Prussia, Pennsylvania 19406 U.S.Environmental Protection Agency Region II Office ATTN: Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq., Chairman Atomic.Safety and Licensing Board U.S.Nuclear Regulatory Commission Washington, D.C.20555 Supervisor of the Town of Ontario 107 Ridge Road West Ontario, New York 14519 Jay Dunkleberger New York State Energy Office.Agency Building 2 Empire State Plaza Albany, New York 12223}} |
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Rev 1 to Design Verification Ginna Station Containment Foundation Mat Analysis.
ML17262A4691991-04-25025 April 1991
Rev 0 Summary Exam Rept for 1991 Steam Generator Eddy Current Insp.
ML17262A4521991-04-22022 April 1991
Control Room Heatup Analysis.
ML17262A3781991-02-28028 February 1991
Nonproprietary Re Ginna Low Temp Overpressure Protection Sys Setpoint Phase II Evaluation, Final Rept
ML17262A4141991-02-26026 February 1991
Safety Analysis,Ginna Station Updated FSAR Section 6.2.4 & Tables 6.2-13,6.2-14 & 6.2-15 Changes.
ML17262A3681991-02-15015 February 1991
Simulation Facility Certification Rept.
ML17262A4431990-10-0404 October 1990
Rev 0 to Design Analysis Ginna Station Containment Mat Design Water Level Elevation 265 ft,0 Inches.
ML17262A4401990-10-0404 October 1990
Rev 0 to Design Verification Ginna Station Containment Foundation Mat Analysis.
ML17262A1931990-10-0303 October 1990
Rev 1 to Safety Analysis Ginna Station Updated FSAR Table 6.2-13 Changes.
ML17262A1761990-08-30030 August 1990
Voltage Simulation for Case EOF LOC4 LOCA Simulation for 50/50 Mode - Circuit 767 Details 12B Transformer Feeding Bus 12B.
ML17262A1771990-07-27027 July 1990
Rev 1 to Design Analysis EWR 4525-1, Fault Current Analysis of Power Distribution Sys.
ML17262A1781990-07-24024 July 1990
Rev 1 to Design Analysis EWR 4525-2, Adequacy of Electric Sys Voltages.
ML17250B1761990-05-0808 May 1990
Rev 1 Summary Exam Rept for 1990 Steam Generator Eddy Current Insp.
ML17261B0201990-03-14014 March 1990
Design Criteria Ginna Station Steam Generator Containment Penetration.
ML17251A4811989-02-28028 February 1989
Ultrasonic Indication Sizing Technique Development. Related Info Encl
ML17251A4771988-06-17017 June 1988
Rev 0 to Differential Pressure Thrust Calculation Methodology.
ML17261A6571987-10-31031 October 1987
Steam Generator Tube Plugging Increase Licensing Rept for Ginna Nuclear Power Station.
ML17261A5521987-07-14014 July 1987
Supplemental Rept to Dcrdr Final Summary Rept for Re Ginna Station.
ML17251A4741987-04-0101 April 1987
Rev 0 to Safety Analysis,Ginna Station PORV Block Valves.
ML17251A4721987-03-10010 March 1987
Rev 0 to Design Criteria,Ginna Station PORV Block Valves Replacement.
ML17251A9191986-12-18018 December 1986
Rev 0 to Implementation Rept EWR 2799, Reactor Vessel Level Monitoring Sys.
ML17251A6171986-03-0101 March 1986
1986 Steam Generator Eddy Current Exam Summary Rept.
ML17254A7031985-12-31031 December 1985
Vols 1 & 2 to Dcrdr Final Summary Rept Program Implementation,Re Ginna Nuclear Power Plant.
ML17254A6911985-12-16016 December 1985
Reinforced Masonry Wall Evaluation,Evaluation of Control Bldg Reinforced Walls.
1997-08-29
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999
Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis
ML17265A7621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr
ML17265A7531999-09-23023 September 1999
Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped
ML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7471999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7341999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7131999-07-22022 July 1999
Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7211999-07-19019 July 1999
ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp.
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A7661999-06-30030 June 1999
1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr
ML17265A7011999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17265A6681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation.
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr
ML17265A5951998-12-31031 December 1998
Rg&E 1998 Annual Rept.
ML17265A5001998-12-21021 December 1998
Rev 26 to QA Program for Station Operation.
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4761998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4531998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A4291998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr
1999-09-30
[Table view] |
Text
for Rochester Gas and Electric Corporation
-GINNA PLANT-Criticality Safety Analysis for the New Fuel Storage Racks by Thomas R.Robbins Pickard, Lowe and Garr ick, Inc.July 1983 8309ih0056 8309i2 PDR ADOCK 05000244 P PDR 7011R0706835
Introduction The new fuel storage racks for the Ginna Plant accommodate 44 fuel assemblies in 4 rows of 11 assemblies.
Although new fuel assemblies are always stored in a dry condition in these, racks, the condition of optimum moderation is considered in this analysis even though it is inconceivable that such a condition could be achieved in these racks.'escri tion of the Anal sis A plan view of the new fuel storage racks is shown in Figure 1.Although the center to center spacing between all fuel assembly storage locations is not uniform in the East-Nest Direction, a minimum uniform spacing was conservatively assumed in the analysis.Figure 1 also shows the conservative symmetric geometry model chosen to calculate the effects of radial neutron leakage from the racks in the North-South direction.
Symmetry boundary conditions (i.e., zero neutron current)are imposed on the North, East, and i<est boundaries of the model, and a zero neutron flux boundary condition is imposed at the outer edge of the assumed water reflector on the South boundary.The detailed dimensions and geometry of this model are shown in Figure 2.The'uel assembly characteristics utilized for the analysis are shown in Table 1.A uniform'axial enrichment distribution of 4.25 w/o U-235 was assumed for each fuel rod in the assembly.The k of the fuel pin cell used to generate cross sections for the rack criticality analysis is shown as a function of water density in Figure 3.For the normal dry storage condition, the fuel assembly k will be essentially the same as or lower than the fuel pin cell Q, and therefore an upper limit for the k ff of the rack for dry conditions may be obtained by extrapolation of the fuel pin cell k: to zero water density.The resulting k is about 0.72, and the k ff of the finite rack will be substantially less than that value.7011R0706831 I'C If it is assumed the entire rack area is surrounded by a full density water reflector, then the water density in the resulting enclosed area can be varied, and the k of the rack can be determined from edits which combine the void-water and fuel assembly regions of the model shown in Figure 2.The resulting fuel rack k is also shown in Figure 3.At water densities below 0;1 gm/cc,'n optimum moderation condition is approached.
The apparent, optimum moderator density is quite low because of the large volume fraction of the void-water region (0.994)as compared to that of the fuel region (;006)." However, these large k's at low water densities are not of concern as shown by the k ff values from the eff same calculations.
The neutron multiplication factor, which includes neutron leakage effects in the North-South direction only, is shown as a function of water density in Figure 4.The maximum neutron multiplication factor is seen to be about 0.94 at an optimum water density of about:045 gm/cc.'owever, these calculations assumed zero neutron leakage in both the East-West radial direction and the axial direction.
To determine the effect of" axial neutron leakage on the multiplication factor, flux weighted cross sections representing the fuel assembly and void-water regions of the radial model were used in one-dimensional axial calculations, and the results are also shown in I Figure 4.The maximum neutron multiplication factor is now seen to be about 0.70 at a water density of about.075 gm/cc.This low multiplication factor even at optimum moderation conditions makes it unnecessary to evaluate the neutron leakage effects in the East-West radial direction which would result in some further small but significant reduction in the neutron multiplication factor.In addition to the other conservatisms in the calculations, no credit was taken for neutron streaming effects at low water densities.
Considering the large distances separating fuel assemblies in the rack, such effects would be expected to significantly increase neutron leakage from the racks and thereby further reduce the neutron multiplication factor.7011R0706832 I
Figure 4 also demonstrates the acceptability of the new fuel storage racks in the flooded condition which corresponds to a water density of 1.0 gm/cc.As shown, the neutron multiplication factor is somewhat less than 0;88 for the fully flooded condition and therefore clearly acceptable.
Because of the conservative techniques and assumptions used to evaluate the maximum possible neutron multiplication factor, there is more than reasonable assurance that no significant hazards based on criticality safety are involved in storing fuel assemblies of up to 4.25 w/o U-235 in the Ginna.new fuel storage racks.7011R0706833 Table 1 FUEL ASSEMBLY CHARACTERISTICS Number of rods containing U02 Rod pitch (in)Overall envelope dimensions (in)Weight of U (Kg U)Active fuel length (in)Enriched uranium region Length (in)Enrichment (w/o)Natural uranium blanket region Length (in)Enrichment (w/o)Instrument tube Material O.D;(in)I.D.(in)Guide tubes 179 0."5560 7.763 350;5 141.4 128.98 4.25 12.42 0.711 Zr-4 0.4015 0.3499 Material O.D.(in), O.D.(in), I.D.(in), I.D.(in), Fuel pellet Material Density (X O.D.(in)Cladding O.D.(in)I.D.(in)Spacer Grids Number above dashpot in dashpot above dashpot in dashpot theoretical)
Zr-4 0.5280 0.4825 0.4900 0.4425 U02 95+"-1.5 0.3444 0.0019.400.3514 i<eights of materials*
Inconel grids (2), lbs total Zircaloy grids (7), lbs total 3.00 19.46*Does not include weight of the stainless steel sleeves or inserts.7Allun7n~n~n a 5 5c 5g/-'8"/'-8"/'-8"/'-8" 2.4"/'-8"/'8" 2'O/'8-8"/-'8"/-'8"/'-8" Il.8 TYP.I I t!f II NENI FUEL RACKS (7YP.4 R0M/5)SEE ENLARGEO PLAAI A-8~5EE ELEV.2&Oed.O.51 8 0'ru).O32 L2~2 COhlTINVOJ5 8=7u<EFN d>>>444~~4+Mt I>>t~1.6"'>>t<<tt+<<t~4~>>2>>%toot~M+22M~2 4~2224 Wt W 4<<4 4~\4'~2-O O n2 tt O 4I O GL 4 1.4 1.2 1.0 0.8 O.o~222 i": 2'a r~it 4~4<<EwZ 4>>t~4+t4 24>>~t 44~\>>W 4C~ot~ot Qt>>4+~4<<~>>4+~4~>>Wo I'4+2 EE it.t 2~+<<t l4 4 Ott+2'>>~tl 2'K I ool~ttttiti I>>24 Pi 4~\rFI E~~tt~t 4+Ztt 4>>+4 HHE~tt 28 L tt t 4~+4+to otal~4=HT2 H+tt~4<<44 44 4++t+t4 to~t ltt t4>>:22 3K3 144+224t to~444>>4>>tt>>+tt<<.2 4 I+t 4 t 444 IP>>R~tlt>>1~+to 44+\444 2<<1 Pi'.ll I ttt>>~>><<>>4 New Fuel Rack Model."=."~~;,Fuel Pin Cell-:.0.4 4224 4 tttt ttt tot 4~4+4~4>>t>>~++4 tg+~tt>>4~<<4I ttt4 4~4 444 4 4>>4+>>4~t LI1~~to 4+>>~tlt+4~~<<4 tt t4 4>>>>44~l to C~2"t~444 4>>~t'I~KiIK-=-
442-g3 0.2)4<<X+3~t~+4+t>>t~~o'.IIi 22=~4>>4~~444 444\4~4>>22 I 4+t4 ttttt otto l 44 otto<<4 4 4~4>>t>>4~4~4~4~t>>t 14Ž4 4+to t~~4~+4 4 0~~4 0>>4>>t~o~~0.4'.6 0.8 1.0 0.2 Water Density (gm/cc)I~~I I 4~~I~~~ll>>~~I~>>4~oil Figure 4 0.9 i!!i ii!!!li!!i!!I!I ij,'j GINNA NEW FUEL STORAGE RACKS WITH OFA AT 4.25 W/0 U-235 NEUTRONULTIPLICATiON FACTOR VS WATER DENSITY iil!)jj'!!ll'i!i iiij i!'I I!I~I ll!j!Il!))l jll!i)ii ll I'!i!i ll!Ii)f ill!lili tel!i)fl!!Ti!!l" l l)i i I ll jl I!li):I Qi'i li!:.i'I'll)'ll)i.!i!h l!i!jll!!!!i!!!!li:I!Il!'Ill:I WITH CONSERVATIVE HOOEL OF RADIAL LEAKAGE j))i....,,...,.~..!'!l!)il!)!ill II'jj I II II Il!!'!!i!;I!!!j!)!I!)!O WITH CONSERVATIVE HODEL OF RADIAL AND AXIAL LEAKA GE!l!Iji i!!1 I"..Ii il'!!ii!i!!!ll!I I I jij!I j!j!I'!j!),')jj)iji EJ+0':!t ii!i iit!!:i i!ii i:j t;L'(I!!il!I!I!, Nj!Ii!ilia i!l!!!i!j!i': i!i:!i!!':i)I!!j')I!!i i!!1)!)ll O t 0.6!'ii!!!!i iii: I)I I I jij L':t j j!:Ij.Ij!!!!)j)ii:il!li i!!j i!!i P)~':.: 0.4 0 0.1 ljl!)l(!i!!t (l"'i'I[0.2 0.3 0.4 0.5 0.6 0.2 0.8 0.9 1.0 Water Density (gm/cc)
~~~C a h K l' September 2, 1983 DISTRIB UTION Docket ORB Reading GDick HSmith ELD attorney DOCKET NO(S).50-244 Nr.John E.Mlier, Vice President Electric and Steam Production Rochester,.Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 I R.E.GINNA PLANT-OPPORTUNITY FOR HEARING (APPLICATIONS 1"1,/24/81, SNUBBER REQUIREMENTS:
9/28/82, STAFF REORGANIZATION)
The following documents concerning our review of the subject facility are transmitted for your information.'otice of Receipt of Application.
Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No., dated Notice of Hearing on Application for Construction Permit.Notice of Consideration of Issuance of Facility Operating License.Application and Safety Analysis Report, Volume Amendment No.to Application/SAR dated Construction Permit No.CPPR-, Amendment No., dated Facility Operating License No., Amendment No., dated Order Extending Construction Completion Date, dated El Other(Specify)
C August 23, 1983 (see 48 FR 38421);the intervention period expires Dt
Enclosures:
As stated cc: w/enclosures:
SeeSnext page/g Z~/8 Office, of Nuclear Reac or Regulation Division-of.'icensing Operating Reactors Branch 85 A OFF/cE>L: 0 iF5 SURNAME/g~C OATE P/7 NRO FORM 318{10/80)NRCM 0240 OFF(CIAL RECORO COPY
Mr.John E.Maier CC'arry H.Voigt, Esquire LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue, N.W.Suite 1100 Washington, D.C.20036 Mr.Michael Slade 12 Trailwood Circle Rochester, New Yor k 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.Ginna Plant c/o U.S.NRC 1503 Lake Road Ontario, New York 14519 Stanley B.Klimberg, Esquire General Counsel New York State Energy'ffice Agency Bui-lding 2'mpire State Plaza Albany, New York 12223 Dr.Emmeth A.Luebke Atomic Safety and Licensing Board U.S.Nuclear Regulatory Comnission Washington, D.C.20555 Dr.Richard F.Cole Atomic Safety and Licensing Board U.S.Nuclear Regulatory Coomission Washington, D.C.20555 Dr.Thomas E.Mur ley, Regional Administrator Nuclear Regulatory Coomission, Region I 631 Park Avenue'ing of Prussia, Pennsylvania 19406 U.S.Environmental Protection Agency Region II Office ATTN: Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq., Chairman Atomic.Safety and Licensing Board U.S.Nuclear Regulatory Commission Washington, D.C.20555 Supervisor of the Town of Ontario 107 Ridge Road West Ontario, New York 14519 Jay Dunkleberger New York State Energy Office.Agency Building 2 Empire State Plaza Albany, New York 12223}}
