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| | issue date = 01/26/1996 | | | issue date = 01/26/1996 |
| | title = Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading | | | title = Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 6 | | | page count = 6 |
| | | project = |
| | | stage = Request |
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| {{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterof))RochesterGasandElectricCorporation)(R.E.GinnaNuclearPowerPlant)DocketNo.50-244APPLICATIONOFAMENDMENTTOOPERATINGLICENSEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RGE<E"),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheLicensePart2SectionB.(2)andtheTechnicalSpecificationsSection5.4setforthinAppendixAtothatLicensebeamended.Thisrequestforamendmentissubmittedtoincorporatechangesnecessarytoreflectrevisednuclearfuelloading.TheproposedlicensechangeissetforthinAttachmentAtothisApplication.TheproposedTechnicalSpecificationchangeissetforthinAttachmentB.AsafetyevaluationissetforthinAttachmentC.Thisevaluationdemonstratesthattheproposedchangedoesnotinvolveasignificant.changeinthetypesorasignificantincreaseintheamountsofeffluentoranychangeintheauthorizedpowerlevelofthefacility.AsdemonstratedinAttachmentC,theproposedchangedoesnotinvolveasignificantsafetyhazard.9601300307960l26PDRADOCK05000244pPDR I,i< | | {{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ) |
| Wherefore,ApplicantrespectfullyrequeststhattheFacilityOperatingLicenseNo.DPR-18andAppendixAtothatlicensetoamendedintheformattachedheretoasAttachmentAandAttachmentBrespectively.RochesterGasandElectricCorporationByRobertC.MecredyVicePresidentNuclearOperationsSubscribedandsworntobeforementhis26thdayoanuary,1996.NotaryPblicDEBORAHA.PIPERNINotaryPublicmtheStateofNnvYorkONTARIOCOUNTYCommrsaonExprresNov.23,]9,fg | | ) |
| <gaAft;~<cNfpW*1r~aUNITEDSTATESLEARREGULATORYCOMMISSIO5%FWASKINGTON,O.C.20555ATTACHMEMTAROCHESTERGASANDELECTRICCORPORATIONDOCKETNO.50-244R.E.GINNANUCLEARPOWERPLANTFACILITYOPERATINGLICENSELicenseNo.DPR-18(pI.TheNuclearRegulatoryCommission(theCommission)hasfoundthat:IA.TheapplicationcomplieswiththerequirementsoftheAtomicEnergyActof1954,asamended(theAct),andtheregulationsoftheCommissionsetforthin10CFRChapter'Iandallrequirednotifica-tionstootheragenciesorbodieshavebeendulymade;8.ConstructionoftheR.E.GinnaNuclearPowerPlant(thefacility)hasbeensubstantiallycompletedinconformitywithConstructionPermitNo.CPPR-19,asamended,andtheapplication,theprovisionsoftheAct,andtherulesandregulationsoftheCommission;C.Thefacilitywill.operateinconformitywiththeapplication,theprovisionsoftheAct,andtherulesandregulationsoftheCommiss10nD.E.Thereisreasonableassurance(i)thatthefacilitycan-beoperatedatpowerlevelsupto1520megawatts(thermal)withoutendangeringthehealthandsafetyofthepublic;and(ii)thatsuchactivitieswillheconductedincompliancewiththeregulationsoftheCommission;TheapplicantistechnicallyandfinanciallyqualifiedtoengageintheactivitiesauthorizedbythisoperatinglicenseinaccordancewiththerulesandregulationsoftheCommission;TheapplicanthasfurnishedproofoffinancialprotectionttIatsatisfiestherequirementsof10CFRPart140;andG.Theissuanceofthislicensewillnotbpinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic.2.TheProvisionalOperatingLicensedatedSeptember19,1969,issupersededbyFacilityOperatingLicenseNc.DPR-18herebyissuedtoRochesterGasandElectricCorporaiontoreadasfollows:A.ThislicenseappliestotheR.E.GinnaNuclearPowerPlant,aclosedcycle,pressurized,light-water-moderatedandcooledreactor,andelectricgeneratingeauipment(hereinreferredtoas"the | | Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant) |
| ~~ | | APPLICATION OF AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S. |
| AttachmentAfacility")whichisownedbytheRochesterGasandElectricCorporation(hereinafter"thelicensee"or"RGLE".Thefacilityislocatedonthelicensee'ssiteonthesouthshoreofLakeOntario,WayneCounty,NewYork,about16mileseastoftheCityofRochesterandisdescribedinlicenseapplicationAmendmentNo.6,"FinalFacilityDescriptionandSafetyAnalysisReport,"andsubsequentamendmentsthereto,andintheapplicationforpowerincreasenotarizedFebruary2,1971,andAmendmentNos.1through4thereto(hereincollectivelyreferredtoas"theapplication").Subjecttotheconditionsandrequirementsincorporatedherein,theCommissionherebylicensesRG&E:(1)PursuanttoSection104boftheActand10CFRPart50,"DomesticLicensingofProductionandUtilizationFacilities,"topossess,useandoperatethefacilityatthedesignatedlocationinWayneCounty,NewYork,inaccordancewiththeproceduresandlimitationssetforthinthislicense;(2)PursuanttotheActand10CFRPart70,toreceive,possess,anduseatanytimespecialnuclearmaterialorreactorfuel,inaccordancewiththelimitationsforstorageandamountsrequiredforreactoroperationasdescribedintheFinalSafetyAnalysisReport,asamended,andCommissionSafetyEvaluationsdatedNovember15,1976,October5,-1984,November14,1984,andAugust30.1995.(a)PursuanttotheActand10CFRPart70,toreceiveandstorefour(4)mixedoxidefuelassembliesinaccordancewiththelicensee'sapplicationdatedDecember14,1979(transmittedbyletterdatedDecember20,1979);(b)PursuanttotheActand10CFRPart70,topossessandusefour(4)mixedoxidefuelassembliesinaccordancewiththelicensee'sapplicationdatedDecember14,1979(transmittedbyletterdatedDecember20,1979),assupplementedFebruary20,1980andMarch5,1980;(3)PursuanttotheActand10CFRParts30,40,and70toreceive,possess,anduseatanytimeanybyproduct,source,andspecialnuclearmaterialassealedneutronsourcesforreactorstartup,sealedsourcesforreactorinstrumentationandradiationmonitoringequipmentcalibration,andasfissiondetectorsinamountsasrequired;(4)PursuanttotheActand10CFRParts30,40,and70,toreceive,possess,anduseinamountsasrequiredanybyproduct,source,orspecialnuclearmaterialwithoutrestrictiontochemicalorphysicalform,forsampleanalysisorinstrumentcalibrationorassociatedwithradioactiveapparatusorcomponents;and}}
| | Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGE<E"), holder of Facility Operating License No. DPR-18, hereby requests that the License Part 2 Section B.(2) and the Technical Specifications Section 5.4 set forth in Appendix A to that License be amended. This request for amendment is submitted to incorporate changes necessary to reflect revised nuclear fuel loading. |
| | The proposed license change is set forth in Attachment A to this Application. The proposed Technical Specification change is set forth in Attachment B. A safety evaluation is set forth in Attachment C. This evaluation demonstrates that the proposed change does not involve a significant. change in the types or a significant increase in the amounts of effluent or any change in the authorized power level of the facility. As demonstrated in Attachment C, the proposed change does not involve a significant safety hazard. |
| | 9601300307 960l26 PDR ADOCK 05000244 PDR p |
| | |
| | I, i< |
| | |
| | Wherefore, Applicant respectfully requests that the Facility Operating License No. DPR-18 and Appendix A to that license to amended in the form attached hereto as Attachment A and Attachment B respectively. |
| | Rochester Gas and Electric Corporation By Robert C. Mecredy Vice President Nuclear Operations Subscribed and sworn to before me n this 26th day o anuary, 1996. |
| | Notary P blic DEBORAH A.PIPERNI Notary Public m the State of Nnv York ONTARIO COUNTY Commrsaon Exprres Nov. 23, ]9,fg |
| | |
| | <ga Aft;~ |
| | <cN fp UNITED STATES LEAR REGULATORY COMMISSIO5%F WASKINGTON, O. C. 20555 W*1r ATTACHMEMT A |
| | ~ |
| | a ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT FACILITY OPERATING LICENSE License No. DPR-18 p |
| | I. The Nuclear Regulatory Commission (the Commission) has found that: |
| | I A. The application complies with the requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission set forth in 10 CFR Chapter'I and all required notifica-tions to other agencies or bodies have been duly made; |
| | : 8. Construction of the R. E. Ginna Nuclear Power Plant (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-19, as amended, and the application, the provisions of the Act, and the rules and regulations of the Commission; |
| | ( C. The facility will .operate provisions of the Act, and in conformity with the application, the the rules and regulations of the Commiss10n D. There is reasonable assurance (i) that the facility can -be operated at power levels up to 1520 megawatts (thermal) without endangering the health and safety of the public; and (ii) that such activities will he conducted in compliance with the regulations of the Commission; E. The applicant is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission; The applicant has furnished proof of financial protection ttIat satisfies the requirements of 10 CFR Part 140; and G. The issuance of this license will not bp inimical to the common defense and security or to the health and safety of the public. |
| | : 2. The Provisional Operating License dated September 19, 1969, is superseded by Facility Operating License Nc. DPR-18 hereby issued to Rochester Gas and Electric Corpora ion to read as follows: |
| | A. This license applies to the R. E. Ginna Nuclear Power Plant, a closed cycle, pressurized, light-water-moderated and cooled reactor, and electric generating eauipment (herein referred to as "the |
| | |
| | ~ ~ |
| | Attachment A facility") which is owned by the Rochester Gas and Electric Corporation (hereinafter "the licensee" or "RGLE". The facility is located on the licensee's site on the south shore of Lake Ontario, Wayne County, New York, about 16 miles east of the City of Rochester and is described in license application Amendment No. 6, "Final Facility Description and Safety Analysis Report," and subsequent amendments thereto, and in the application for power increase notarized February 2, 1971, and Amendment Nos. 1 through 4 thereto (herein collectively referred to as "the application" ). |
| | Subject to the conditions and requirements incorporated herein, the Commission hereby licenses RG&E: |
| | (1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use and operate the facility at the designated location in Wayne County, New York, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material or reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as amended, and Commission Safety Evaluations dated November 15, 1976, October 5, -1984, November 14, 1984, and August 30. 1995. |
| | (a) Pursuant to the Act and 10 CFR Part 70, to receive and store four (4) mixed oxide fuel assemblies in accordance with the licensee's application dated December 14, 1979 (transmitted by letter dated December 20, 1979); |
| | (b) Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the licensee's application dated December 14, 1979 (transmitted by letter dated December 20, 1979), as supplemented February 20, 1980 and March 5, 1980; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and}} |
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High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
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Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
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Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant)
APPLICATION OF AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGE<E"), holder of Facility Operating License No. DPR-18, hereby requests that the License Part 2 Section B.(2) and the Technical Specifications Section 5.4 set forth in Appendix A to that License be amended. This request for amendment is submitted to incorporate changes necessary to reflect revised nuclear fuel loading.
The proposed license change is set forth in Attachment A to this Application. The proposed Technical Specification change is set forth in Attachment B. A safety evaluation is set forth in Attachment C. This evaluation demonstrates that the proposed change does not involve a significant. change in the types or a significant increase in the amounts of effluent or any change in the authorized power level of the facility. As demonstrated in Attachment C, the proposed change does not involve a significant safety hazard.
9601300307 960l26 PDR ADOCK 05000244 PDR p
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Wherefore, Applicant respectfully requests that the Facility Operating License No. DPR-18 and Appendix A to that license to amended in the form attached hereto as Attachment A and Attachment B respectively.
Rochester Gas and Electric Corporation By Robert C. Mecredy Vice President Nuclear Operations Subscribed and sworn to before me n this 26th day o anuary, 1996.
Notary P blic DEBORAH A.PIPERNI Notary Public m the State of Nnv York ONTARIO COUNTY Commrsaon Exprres Nov. 23, ]9,fg
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<cN fp UNITED STATES LEAR REGULATORY COMMISSIO5%F WASKINGTON, O. C. 20555 W*1r ATTACHMEMT A
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a ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT FACILITY OPERATING LICENSE License No. DPR-18 p
I. The Nuclear Regulatory Commission (the Commission) has found that:
I A. The application complies with the requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission set forth in 10 CFR Chapter'I and all required notifica-tions to other agencies or bodies have been duly made;
- 8. Construction of the R. E. Ginna Nuclear Power Plant (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-19, as amended, and the application, the provisions of the Act, and the rules and regulations of the Commission;
( C. The facility will .operate provisions of the Act, and in conformity with the application, the the rules and regulations of the Commiss10n D. There is reasonable assurance (i) that the facility can -be operated at power levels up to 1520 megawatts (thermal) without endangering the health and safety of the public; and (ii) that such activities will he conducted in compliance with the regulations of the Commission; E. The applicant is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission; The applicant has furnished proof of financial protection ttIat satisfies the requirements of 10 CFR Part 140; and G. The issuance of this license will not bp inimical to the common defense and security or to the health and safety of the public.
- 2. The Provisional Operating License dated September 19, 1969, is superseded by Facility Operating License Nc. DPR-18 hereby issued to Rochester Gas and Electric Corpora ion to read as follows:
A. This license applies to the R. E. Ginna Nuclear Power Plant, a closed cycle, pressurized, light-water-moderated and cooled reactor, and electric generating eauipment (herein referred to as "the
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Attachment A facility") which is owned by the Rochester Gas and Electric Corporation (hereinafter "the licensee" or "RGLE". The facility is located on the licensee's site on the south shore of Lake Ontario, Wayne County, New York, about 16 miles east of the City of Rochester and is described in license application Amendment No. 6, "Final Facility Description and Safety Analysis Report," and subsequent amendments thereto, and in the application for power increase notarized February 2, 1971, and Amendment Nos. 1 through 4 thereto (herein collectively referred to as "the application" ).
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses RG&E:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use and operate the facility at the designated location in Wayne County, New York, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material or reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as amended, and Commission Safety Evaluations dated November 15, 1976, October 5, -1984, November 14, 1984, and August 30. 1995.
(a) Pursuant to the Act and 10 CFR Part 70, to receive and store four (4) mixed oxide fuel assemblies in accordance with the licensee's application dated December 14, 1979 (transmitted by letter dated December 20, 1979);
(b) Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the licensee's application dated December 14, 1979 (transmitted by letter dated December 20, 1979), as supplemented February 20, 1980 and March 5, 1980; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and