ML17263A318: Difference between revisions

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| issue date = 07/13/1993
| issue date = 07/13/1993
| title = Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS
| title = Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS
| 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 =  
Line 14: Line 14:
| 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 = 4
| page count = 4
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:1\~~y UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of))Rochester Gas and Electric Corporation
{{#Wiki_filter:1
)(R.E.Ginna Nuclear Power Plant))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
\
("RGEE"), 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 submitted to remove the table of Containment Isolation Valves and provide a reference in the bases to the Ginna Station procedure containing the list of valves.The containment isolation requirements during refueling operations are also revised consistent with industry standards.
~ ~ y UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of                           )
Temporary notes associated with the containment purge and mini-purge systems are being removed since the purge valve flanges and the mini-purge system have been installed.
                                                )
Also, surveillance testing requirements in Section 4.4 associated with containment leakage acceptance criteria are clarified and requirements for the new steam generator inspection/maintenance penetration are provided.9307220175 9307i5 PDR ADQCK 05000244 p PDR I f I,'(%V I The proposed Technical Specification change is set forth in Attachment A to this Application.
Rochester Gas and Electric Corporation       )   Docket No. 50-244 (R.E. Ginna Nuclear Power Plant)           )
A safety evaluation is set forth in Attachment B.This evaluation demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.As demonstrated in Attachment B, the proposed change does not involve a significant hazards consideration.
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
WHEREFORE, Applicant respectfully requests that Appendix A to, Facility Operating License No.DPR-18 be amended in the form attached hereto as Attachment A.Rochester Gas and Electric Corporation By Robert C.Mecr dy Vice President Nuclear Production Subscribed and sworn to before me on this 13th day of July Notary Public h'IARIE C.t,'ILLENEUVE Notary Public;State of New York Moitroe County commission'hpire".
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGEE"), 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 submitted to remove the table of Containment Isolation Valves and provide a reference in the bases to the Ginna Station procedure containing the list of valves.
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The containment isolation requirements during refueling operations are also revised consistent with industry standards.       Temporary notes associated with the containment purge and mini-purge systems are being removed since the purge valve flanges and the mini-purge system     have been   installed. Also, surveillance testing requirements in Section 4.4 associated with containment leakage acceptance criteria are clarified and requirements for the new steam generator inspection/maintenance penetration are provided.
9307220175 9307i5 PDR ADQCK 05000244 p               PDR
 
I f
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    %V I
 
The proposed             Technical Specification change is set forth in Attachment A to         this Application.       A safety evaluation is set forth in Attachment         B.       This evaluation demonstrates     that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. As demonstrated in Attachment B, the proposed change does not involve a significant hazards consideration.
WHEREFORE,         Applicant respectfully requests that Appendix A to, Facility Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation By Robert C. Mecr dy Vice President Nuclear Production Subscribed and sworn to before               me on this 13th day of July Notary Public h'IARIE C. t,'ILLENEUVE Notary Public; State of New York Moitroe County commission'hpire". octouez 3J )9+$ 4
 
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Latest revision as of 10:36, 4 February 2020

Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS
ML17263A318
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/13/1993
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A317 List:
References
NUDOCS 9307220175
Download: ML17263A318 (4)


Text

1

\

~ ~ y UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

)

Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant) )

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 ("RGEE"), 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 submitted to remove the table of Containment Isolation Valves and provide a reference in the bases to the Ginna Station procedure containing the list of valves.

The containment isolation requirements during refueling operations are also revised consistent with industry standards. Temporary notes associated with the containment purge and mini-purge systems are being removed since the purge valve flanges and the mini-purge system have been installed. Also, surveillance testing requirements in Section 4.4 associated with containment leakage acceptance criteria are clarified and requirements for the new steam generator inspection/maintenance penetration are provided.

9307220175 9307i5 PDR ADQCK 05000244 p PDR

I f

I,'(

%V I

The proposed Technical Specification change is set forth in Attachment A to this Application. A safety evaluation is set forth in Attachment B. This evaluation demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. As demonstrated in Attachment B, the proposed change does not involve a significant hazards consideration.

WHEREFORE, Applicant respectfully requests that Appendix A to, Facility Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.

Rochester Gas and Electric Corporation By Robert C. Mecr dy Vice President Nuclear Production Subscribed and sworn to before me on this 13th day of July Notary Public h'IARIE C. t,'ILLENEUVE Notary Public; State of New York Moitroe County commission'hpire". octouez 3J )9+$ 4

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