ML17262B020

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

ML17262B020
Person / Time
Site:	Ginna
Issue date:	09/15/1992
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262B019	List: ML17262B018 ML17262B020 ML17262B021
References
REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9210050354
Download: ML17262B020 (4)

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) )

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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 satisfy Rochester Gas and. Electric Corporation's commitment to revise the Technical Specifications consistent with our April 18, 1991, response to Generic Letter 90-06, "Resolution of Generic Issue 70, 'Power-Operated Relief Valve and Block Valve Reliability,'nd Generic Issue 94,

'Additional Low-Temperature Overpressure Protection for Light-Water Reactors,'ursuant to 10CFR50.54(f)." The proposed Amendment revises Technical Specifications Sections 3.1.1.4, 3.1.1.6, 4.3.4 and adds site specific basis sections to address the generic letter.

Technical Specification 3.1.1.4 was deleted and relocated under the provisions of proposed Specification 3.1.1.6. This revision continues to ensure that the existing and proposed limiting conditions of operation are met. The proposed revision also eliminates the need to duplicate identical requirements under two individual specifications. Similarly, Surveillance Requirement 4.3.5.6 will be renumbered and relocated under the provisions of Specification Section 4.3.4, Relief Valves. This administrative change also p21PPgp DR 5$

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ensures consistency with proposed Specification 3.1.1.6. Specification section 3.1.1.3 will be revised to address limiting conditions for operation above cold shutdown. This proposed change is conservative and considered to be an administrative change.

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 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 Robert C. Mec edy Vice President, Ginna Nuclear Production Subscribed and sworn to before me on this ~X~day of 1992.

klARtE C. VfLLEf)EUVE bootery Public, State of New York f'lonroe County

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