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Category:ACRS Summary Report
MONTHYEARML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C2071974-09-25025 September 1974 Letter Responding to a September 17, 1974 Letter Requesting a Response to Two ACRS Identified Items Concerning Main Steam Isolation Valve Leakage and Inservice Inspection of the Reactor Pressure Vessel and Advising That Inform. ML17037C4801974-09-13013 September 1974 Letter Transmitting ACRS Report Dated September 10, 1974, on the Application for Conversion of the Provisional Operating License to a Full-Term Operating License for the Nine Mile Point Nuclear Station Unit ML17037C4901974-02-20020 February 1974 Letter Submitting Copy of Report of the Advisory Committee on Reactor Safeguards Dated February 12, 1974 on Expected Performance of General Electric 8x8 Fuel Design for Reload Use ML17037C3691971-03-12012 March 1971 Letter Responding to a February 11, 1971 Forwarding an ACRS Report Pertaining to the Request for an Increase from 1538 to 1850 Thermal Megawatts in the Licensed Power Level ML17037C3501970-06-19019 June 1970 Letter Authorizing the Return to Operation of Unit 1 in Accordance with Your Documented Program and Subject to Conditions Defined and Enclosing an ACRS Report Dated June 16, 1970 1974-09-25
[Table view] Category:Letter
MONTHYEARIR 05000220/20244022024-11-20020 November 2024 Material Control and Accounting Program Inspection Report 05000220/2024402 and 05000410/2024402 (Cover Letter Only) IR 05000410/20240032024-11-0808 November 2024 Integrated Inspection Report 05000220/1014003 and 05000410/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations 2024-09-04
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v'EB201974DocketNo.50-220M.agaraR)hawkPowerCorporation ATlM:R.PhilipD.RaymondVicePresident
-sneering300ErieBoulevard WestSyracuse, NewYork13202Gentlel1)en:
AcopyofthereportoftheAdvisoryCommittee onReactorSafeguards datedFebruary12,1974,isenclosedforyourinformation.
ThereportreflectstheCoamhtee's reviewofthedesignandexpectedperfora)ance ofGenera1E1ectric8x8fuelbundlestobeusedinpart;ialandflQ1corereloadsforboilirgwaterreactorssuchasyourNineM.lePointNuclearStationUrd.tl.Youwillbeadvisedwhenwehaveconyleted ourreviewofyourrequestforoperation with8x8fuel.Sincerely, DonaldJ.SkovholtAssistant DirectorforOperating ReactorsDirectorate ofLicensing
Enclosure:
ACHSReportRNDiggsNDubecc:Seenext;pagel4JinksBsch~f(ig)SKariSVargaHBoydECaseDistribution DocketFileAECPDRLocalPDRRPReadingBranchReadingJRBuchanan, OHNL93Abernathy, DTIEWNoore,LDTSkovholt, L:ORTJCarter, L:ORRO(3)OGCVStelloJGalloJSaltzman FLIngramHINueller JWagner,OCWOM.lier, DRAPCollins, L:OLBDLZiemann, L:ORBg2.82........
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FormhFC-318(Rev.9.53)LCM0240CRI3C@31311423I320204 II i;,'iagarn lfohawkPowerCorporation February20,1974ccw/enclosure:
J.BruceHacDonald, EsquireDeputyCommissioner andCounsel.NewYorkStateDepartment ofCommerceandCounseltotheAtomicEnergyCouncil99Washington AvenueAlbany,NewYork12210ArvinE.Upton,EsquireLeBoeuf,Larry,Leiby6HacRae.1757NStreet',N.W.Washington, D.C.20036AnthonyZ.Roisman,EsquireBerlin,RoismanandKessler1712NStreet,N.W.Washington, D.C.20036Hr.DonaldX.Gleason,ChairmanCountyOfficeBuilding/>6EastBridgeStreetOswego,NewYork13126Hr."Robert P.Jones,Supervisor TownofScribaR.D.II4Oswego,NewYork13126OswegoCityLibrary~~
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ADVISORYCOMMITTEE ONREACTORSAFEGUARDS UNlTEDSTATESATOMlCENERGYCOMMlSSlON WASHINGTON, D.C.R054bFebruary12,1974Hanorable DixyLeeRayChaiznsnU.S.AtaoiaEmmgyGmni'ssion 545458dxJect:HEX'ORCCNGENEBALELECXREC8XSPGELXESX(ÃK)RHEZQADUSE'earDx'.BaysAtits166thmeeting,XhhemLxy7<<9,1974ttheAdvisoryCGHlAittee anReactorSafeguazds campleted agexxericreviewofthedesignandex.-pandpeeiarxtlaxxce ofGeneralElectric8xSfuelbuncllestobesplayedinpartialandfullcarereloadsinboilingwaterreaclurs.
Thesetopicswerediscussed atthe165thACRSmeetingonJanuary10-12,1974t555'te',,~,5574,andinDenver,Colorado, anJanuary24,1974.DuringitsravinestheOmmi.ttee hadthebermCit.ofdiscussians withrepresentatives oftheGenamlZXa~icGxnpxxzy, theAECRegu3atozy Staff,andofthedocu-maxtslistedbeld.TheGeneralElectricSxSfuelassalhlyconsistsof63fuelxoclsplusoneunfueled; water-fle@,spacex"~ptxxre xodinasctuareSx8bundlearraywithina-squaxmchannelbox.ThedesignofthefuelxcdsandfuelxcdbundleintheSxSreloadfuelassemblyis,exceptfardiffexencesinthelength.ofthefuelandgasplenam,thesameasinthe8x8fuelBSSHllbly used3Ilthe~6bo113LIlg waterxitorconceptreferredtointheCaanittee's n~ofSex~her21,1972.TheSxSfuelbundlesareinterchangeable inGeneralElectricboilingwaterreactorswiththepeeviously used7x7bundles.Xhgeneral,thethexualmarginstofueldamagedesignbasesaregreaterfarSxSfuelthanfar'x7fuel.%hedesignvalueafthelinearheatgemmation ratefarnormalopexmtion is33.4kw/ftfarSxSfueland17.5to18.5lee/ftfar.7x7fuelspecificpowerisslightlygreaterfarthe8xSfuelthanforthe7x7fuel.TheGenera.ElectricCatapanybelievesthe3xeerlinearheatgeneration rateandslightlygreaterratioofcladtlxxc1cness toxaddietershouMresultinfeweefailuresinSxSftxelthanin7x7fuel.AlthoughthehyQraulic resistaxxce ofSx8bunDesisslightlygreaterthanthatof7x7buxxllm,thethecal-hydraulic pex-faxmanceofboxeseitherpartially orfullyloadedwithSxSassemblies isnotchsgnlded relativetocaresloadedwith7x7assemblies.
EmeableicyLee.RayFebruary12,1974SincetheU-235enrichnents fortheindivMmQ.
fuelrods,thenumberl~tlh~lllggtlhd, Ithratioaresimilax'n theSxSand7x7designs,theneutnnicbehaviorofthetsmdesignsisnotsignificantly diffanmt.
Theintexnally locatedwaterxodintheSxSdesignreducesxod-to-xod powerpeaking.Sincethenextmania andthemal~rauLic characteristics ofSxSand7x7fuelhuxG.esaresimilar,thoraxbehaviorunderahnoxnsloperatianal t'\PlbWbl.
Ih~fl'hdcantxolxoddrop,'uel
- handling, andsteamlinebreakacx68ents arenatexitedtobesignificantly different forthetwofueldesigns.II~51'WWW,'lkU'tV~h~waterreactors, andtheRegulatory Staffhaveperfamtect analysesofthebehaviorof8x8fuelinseveralmixedandfullyreloadedcca~undertxansient andaccidentcxmditions.
TheseanalysesymBictthat,,farboilingwatermectxuwwhichhavejetpumps,thepeakcladtemperatures duringapo.~~tedlarge-break IQCAusingtheXnterimAcceptance CriteriaaxelessforSxSthanfor7x7assariblies.
ERwmrer,forlargepostulated breaksinnan-)etpumpplantsandfarsmallandintexaectiate sizebreaksfarallplants,thepr~x8peakcladtemperatures areinthesamerangefarbothSxSa+i7x7fuel.Consequently, indivtitual reviewsbytheRegu-latoryStaffoftheequiperfarmmce ofSxSreloadfuel,incluKLng plantmpecific systemeffectsazxlanysignificant corefuelloadLingil1bIIfhIfwHth8xSfueltodeteexnine limitsanreactoroperating conditiorm.
TheCce-mitteewishestobeirdhraedconcerning theresultsofthesereviewsfortheinitialSxSfuelload:tngs ineachoftheseveralGeneralElectricboilingwaterreactarproductlines.TheRegulatory Staffplanstousetheresultsofrecentlycanducted N~~~8~~~I'llanalytical nedelsfarSxBfuel.TheQanaittee wishestobekeptinfcemd.IlE!fS16 andhun31eswhosedesignsbrac]setthedimensians oftheSxSfuelandantheperfarmance ofcarescantaining mixbmesofassaablies withdifferent rmobersandsizesoffuelrcds.Althoughmechanical testshavebeenperfaxned'an 8xSfuelassemblies anRcampanents todaaanstrate theirintegri.ty, additional teststovex'ifyspacergridstrengthhavebeenrequested bytheRegulatory Staff.Thismattershouldberesolvedinaninersatisfactary totheRecpQatoxy Staff.
~~lyRIMmableDixyLeeHayFehrum~12,1974TheAneealElectricCaqxmyhasplannedaprecgamofbothpre-andpost-inmHatian enauninatians tomonitortheperformance of8xSfuel!!!!~!.1lprogramandwishestobekeptinformed.
TheHegulatory Staffiscurrently revhm9xgthetreatment.
ofuncextaintiesintheestablishment andmmi;toring ofoperating limitsfarboilingwaterreactors.
TheCcxanittee wishestobekeptinfarneQ.
He-evaluation ofcareoperating limitswillbenecessary asaresultoftherecentlygcanulgated Accephmce CriteriaforEmergency CoreCoolingSystems.TheGanmittee vrishestobekeptinfarrneci.
The~tteebelievesthat,withduereganltotheabavecomments, incluQiLng theindividual reloadreviewsbytheHegulatory Staffwhichwilladdressspecificplantfeatures, theGenera.Electric8x8fuelassanblies areacceptable foruseinthereloadofGeneralElectricboilingwaterxeactxam.
&E.m.H.StrattonChaixaenStBefezences attached.
Honorable DDTLeeRayPebruary12,1974203Q45.6."Dresden3NuclearPowerStation,SecondReloadLicenseSuhnittal",
GeneralElectricCo.,NuclearPuelD@lartment, SepteInber 1973@andSuppleIRRIt AgRR%6her17~1973~Supplement B~DeceH58K' p1973Supplatent C,Decanber6,1973;Supplement D,Deliber17,1973;Supplement EcDe~Mr17'973'upplement PrJanuazp's 1974'upplement G,Januaxy9~1974)Supplement H,January'23, 1974"NineMilePointUnit1-SemndRefueling",
P.D.RayIImdtoA.Giambusso, September 14,1973'NineMi1ePointUnit1SafetyAnalysisforType5andType6ReloadPuelgNiagaraHat'uvr8c Power~aratiang October15,1973"NineMilePointUnitlrPartlcNan<<Proprietary ResponseandPart2,Proprietary Respanse,"
Jamlary15,1974Monticello NuclearGenerating PlalltgPexlIBnent PlantChangestoAccamncdate F~ilibrium CoreScramReactivity Insertian Charac-teristics",
January23,1974NED0-20103, "QerumalDesignInfoxIoatian forGeneralElectricBoilingWaterReactorReloadFuelCamellcing inSpriIlg,'74",September 1973H.E.Wi11iamsan aIldD.C.Ditmore,"Experience with.HWRFuel9hroughSeptarher 1971",NED0-10505, May1972GEAP-4059, "Vibration ofPuelRodsinP~elPlow",E.P.Quinn,July1962708Letter,J.A.HindstoV.Nmre,'ebruary 4,1974,"P~lrietary Infoxmation, SxSPuelWearTests"X~.JA,HindstoVMoorePehnlary41974SXSPue1Sur-veillance PIugramNEM-10735, "Densification Cansiderations inHNRFuelDesignandPerfoxmallce",
D.C.DitmareandRB.E13dns,Decaaber1972/Supplement 2,"Response toAECQuestions, NEW&-10735 Apri11973"(Proprietary) gSupplement 2,"Response toAK'.Questions, NEDDY-10735 Supplement 1",May1973'Proprietary),
Supplement 3,"Respanse toAECQuestions, NEDH10735@Supplement 1gJune,1973(Proprietary),
Supplement 4g"Responses toAECQuestions NEXT-10735",
tuly1973,(Proprietary) fSupplement 5'g',DensifxcatiaIl.
Consideratians 1nHNRFuel'gJuly1973(Proprietary).g SUpplements 6j7gaIKlSgFuelDensificatiaIl EffectsanGeneIzLElectricHoiUingWaterPpm~Fuel"~
a~'v~~
~~Q~Hceozab3a Dixy'eeRayFebruary12,1974,References
'contend)
NEDO20181'uppl6fMlt 1gDecember3t1973(Pxoprj~~)
g~GAPIII"AJ4xM.forthePrediction ofPelletConductance inBNRFuelRods"10."Technical ReportanDensification ofGm~ElectricReat'~Fuels",U.S~AtomicEntryCamaission, August23,1973,and"Supple>rent 1totheTechnical ReportonDensification ofCanexalElectricReactorFuels",December14,197311."Sensitivity Stayon~6FuelBuntsResponsetoaPoshQated IDGE,C.M.MaserandR.W.Grume,Deaeaher197312.NEIPr10801,"Mod~theE+/6Los~&Dcelant Accident" CoreSprylyandBottxxnFloodix@HeatTransferEffectiveness",
J..D.DuncanandJ.E.Leenaxd,'Maxch1973,and"Response toAECRet:gmstforAdditional Information anNEDE-10801",
May19739'mpa5.etary),
13,.ME0-10993, "CoreSprayandBottcmFloodingEffectiveness inthe~6"gJ.D.DurbanandJ.E.Leceard,Segteaher 197314."CoreTkmenal'Analyses ofaStainless SteelCladHeaterRodBundle",C.M.userandR.W.Griebe,December197315."StatusRepI~'ntheGeneralElectricCompanySx8FuelAssembly",
January18,1974,USAECRegu1atory Staff16."Technical ReportontheGeneralElectricOarttpany SxSFuelAssembly",
February5,1974,USMCRegulatory Staff~ff~~L~A 0