ML17262A372: Difference between revisions

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{{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMI'SSION 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 COMMI'SSION In the Matter of                                 )
("RGGE"), holder of Facility Operating License'o.
                                                  )
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 provide clarification of which quality assurance activities are subject to audit considerations, through reference to the NRC endorsed Quality Assurance Program for R.E.Ginna Nuclear Power Plant.The proposed amendment also changes the audit frequency, described in Technical Specification 6.5.2.8d, from"at least once per year" to"at least once per 24 months." This proposed change is consistent with the required audit frequency of 24 months identified in NUREG-0452,"Standard Technical Specifications for Westinghouse Pressurized Water Reactors." 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 also demonstrates that the proposed 9102250101 910215 PDR ADOCK 05000244 p PDR 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. Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGGE"), holder of Facility Operating License'o. 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 provide clarification of which quality assurance         activities are subject to audit considerations, through reference to the NRC endorsed Quality Assurance Program for R. E. Ginna Nuclear Power Plant.
WHEREFORE, Applicant respectfully reguests 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.'ecre Vice President, Ginna.Nuclear Production Subscribed and sworn to before me on this J5+0 day of~~ts~ssg gpst J SAMUEL R BROWNE NOTARY PUBLIC, State of New Yotft RegIsttation No.4917041 Quatdiott in Monroe Cly.I Wayne Cftt.Mtt Commission Expin60tc,28,19+)}}
The proposed amendment also changes       the audit frequency, described in Technical Specification 6.5.2.8d, from "at least once per year" to "at least once per 24 months." This proposed change is consistent with the required audit frequency of 24 months identified in NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors."
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 also demonstrates that the proposed 9102250101 910215 PDR   ADOCK 05000244 p               PDR
 
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 reguests 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.'ecre Vice President, Ginna. Nuclear Production Subscribed and sworn to before me on this J5+0 day of ~~ts~ssg gpst J SAMUEL R BROWNE NOTARY PUBLIC, State of New Yotft RegIsttation No. 4917041 Quatdiott in Monroe Cly. I Wayne Cftt.
Mtt Commission Expin60tc,28,19+)}}

Revision as of 18:42, 29 October 2019

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
ML17262A372
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/15/1991
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A371 List:
References
NUDOCS 9102250101
Download: ML17262A372 (2)
v • d • e


Text

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMI'SSION 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 ("RGGE"), holder of Facility Operating License'o. 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 provide clarification of which quality assurance activities are subject to audit considerations, through reference to the NRC endorsed Quality Assurance Program for R. E. Ginna Nuclear Power Plant.

The proposed amendment also changes the audit frequency, described in Technical Specification 6.5.2.8d, from "at least once per year" to "at least once per 24 months." This proposed change is consistent with the required audit frequency of 24 months identified in NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors."

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 also demonstrates that the proposed 9102250101 910215 PDR ADOCK 05000244 p PDR

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 reguests 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.'ecre Vice President, Ginna. Nuclear Production Subscribed and sworn to before me on this J5+0 day of ~~ts~ssg gpst J SAMUEL R BROWNE NOTARY PUBLIC, State of New Yotft RegIsttation No. 4917041 Quatdiott in Monroe Cly. I Wayne Cftt.

Mtt Commission Expin60tc,28,19+)

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