ML17262A412: Difference between revisions

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| issue date = 03/08/1991
| issue date = 03/08/1991
| title = Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs
| title = Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs
| 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 = 3
| page count = 3
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Rochester Gas and Electric Corporation (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
{{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of                             )
("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 submitted to remove the table of Containment Isolation Valves and provide a reference to the UFSAR.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.
Rochester Gas and Electric Corporation       )  Docket No. 50-244 (R.E. Ginna Nuclear Power Plant)             )
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.The proposed Technical Specification change is set forth in Attachment A to this Application.
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
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.
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 submitted to remove the table of Containment Isolation Valves and provide a reference to the UFSAR. 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.
9i03i400i4 9i0308 PDR ADOCK 05000244 P PDR  
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.
~~e 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.Mecre Vice President Ginna Nuclear Production Subscribed and sworn to before me on this 8th day of March, 1991 otary Pu lic SAMUEL H.BROSNE NARY PUBUC, Stete d New Yak Regtetnttion No.49004$Gu6fied in Moeoe Cly.l 1hhyne Ce.Mt Oxamahn Bptnooeo,2tt,19~~
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~ ~ e WHEREFORE,           Applicant respectfully requests that Appendix A to Facility Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation By Robert C. Mecre Vice President Ginna Nuclear Production Subscribed and sworn to before                 me on this 8th day of March, 1991 otary         Pu     lic SAMUEL H.BROSNE NARY PUBUC, Stete d New Yak Regtetnttion No. 49004$
Gu6fied in Moeoe Cly.l 1hhyne Ce.
Mt Oxamahn Bptnooeo,2tt,19~~
 
a 4 ~
9NNOAS J>> JBU~A~
toV eSI b ~,OLLAYP4I5'f tent% dA rN~W
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Latest revision as of 08:15, 10 November 2019

Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs
ML17262A412
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/08/1991
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A411 List:
References
NUDOCS 9103140014
Download: ML17262A412 (3)
v • d • e


Text

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 ("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 submitted to remove the table of Containment Isolation Valves and provide a reference to the UFSAR. 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.

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.

9i03i400i4 9i0308 PDR ADOCK 05000244 P PDR

~ ~ e 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. Mecre Vice President Ginna Nuclear Production Subscribed and sworn to before me on this 8th day of March, 1991 otary Pu lic SAMUEL H.BROSNE NARY PUBUC, Stete d New Yak Regtetnttion No. 49004$

Gu6fied in Moeoe Cly.l 1hhyne Ce.

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