ML17263A707: Difference between revisions

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{{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof))hesterGasa'cCorporation
{{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of))hester Gas a'c Corporation
)(R.E.aNuclearPowerPlan))DocketNo.50-244APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"
)(R.E.a Nuclear Power Plan))Docket No.50-244 APPLICATION FOR 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
),Rochester GasandElectricCorporation
("RG&E"), holder of Facility Operating License No.DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that license be amended.This request for change in Technical Specifications is to increase allowable reactor coolant activity levels to the Improved Technical Specification values (NUREG-1431).
("RG&E"),
A description of the amendment request, necessary background information, justification of the requested change, safety evaluation and no significant hazards and environmental considerations are provided in Attachment A.A marked up copy of the current Ginna Station Technical Specifications which shows the requested change is set forth in Attachment B.The proposed revised Technical Specifications are provided in Attachment C.These changes are consistent with Westinghouse Improved Technical Specifications (NUREG 1431)3.4.16.a,b and figure 3.4.16-1.940b240200'40bl5,'
holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatlicensebeamended.ThisrequestforchangeinTechnical Specifications istoincreaseallowable reactorcoolantactivitylevelstotheImprovedTechnical Specification values(NUREG-1431).
PDR~ADOCK 05000244 P, PDR WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No.DPR-18 be amended in the form attached hereto as Attachment C.Rochester Gas and Electric"Corporation Robert C.Mecred Vice President Ginna Nuclear Production Subscribed and sworn to before me on this 15th day of June, 1994.C GM A.PPKRNI tarot pPuY~i" 6StnhdNnr Yarh Oc'TAPJ0 COUN1Y Ce-.''.--"-Hov 2S, 19+>}}
Adescription oftheamendment request,necessary background information, justification oftherequested change,safetyevaluation andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.AmarkedupcopyofthecurrentGinnaStationTechnical Specifications whichshowstherequested changeissetforthinAttachment B.TheproposedrevisedTechnical Specifications areprovidedinAttachment C.Thesechangesareconsistent withWestinghouse ImprovedTechnical Specifications (NUREG1431)3.4.16.a,b andfigure3.4.16-1.
940b240200'40bl5,'
PDR~ADOCK05000244P,PDR WHEREFORE, Applicant respectfully requeststhatAppendixAtoFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment C.Rochester GasandElectric"Corporation RobertC.MecredVicePresident GinnaNuclearProduction Subscribed andsworntobeforemeonthis15thdayofJune,1994.CGMA.PPKRNItarotpPuY~i"6StnhdNnr YarhOc'TAPJ0COUN1YCe-.''.--"-Hov2S,19+>}}

Revision as of 13:02, 7 July 2018

Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity
ML17263A707
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/15/1994
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A706 List:
References
NUDOCS 9406240200
Download: ML17263A707 (2)
v • d • e


Text

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of))hester Gas a'c Corporation

)(R.E.a Nuclear Power Plan))Docket No.50-244 APPLICATION FOR 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

("RG&E"), holder of Facility Operating License No.DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that license be amended.This request for change in Technical Specifications is to increase allowable reactor coolant activity levels to the Improved Technical Specification values (NUREG-1431).

A description of the amendment request, necessary background information, justification of the requested change, safety evaluation and no significant hazards and environmental considerations are provided in Attachment A.A marked up copy of the current Ginna Station Technical Specifications which shows the requested change is set forth in Attachment B.The proposed revised Technical Specifications are provided in Attachment C.These changes are consistent with Westinghouse Improved Technical Specifications (NUREG 1431)3.4.16.a,b and figure 3.4.16-1.940b240200'40bl5,'

PDR~ADOCK 05000244 P, PDR WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No.DPR-18 be amended in the form attached hereto as Attachment C.Rochester Gas and Electric"Corporation Robert C.Mecred Vice President Ginna Nuclear Production Subscribed and sworn to before me on this 15th day of June, 1994.C GM A.PPKRNI tarot pPuY~i" 6StnhdNnr Yarh Oc'TAPJ0 COUN1Y Ce-..--"-Hov 2S, 19+>

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