ML17264B095
| ML17264B095 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/10/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264B096 | List: |
| References | |
| NUDOCS 9711180217 | |
| Download: ML17264B095 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.O. 2055&4001 ROCHESTER GAS AND ELECT IC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
69 License No.
DPR-18 The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated August 19,
- 1997, as supplemented September 17, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 2.
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-18 is hereby amended to read as follows:
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3.
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
69
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
~ This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 10, 1997
ATTACHMENT TO LICENSE AMENDMENT NO.
69 FACILITY OPERATING LICENSE NO. DPR-18 DOCKET NO. 50-244 Replace the fol owing page of the Appendix A Technical Specifications with the attached page.
The revised page are identified by Amendment number and contain vertical lines indicating the area of change.
Remove 3.5-2 Insert'.5-2
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Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1. 1 Verify each accumulator motor operated isolation valve is fully-open.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.1.2 Verify borated water volume in each accumulator is z 1111,cubic feet (50%%u) and s 1139 cubic feet (82%%u).
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is ~ 700 psig and s 790 psig.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.1.4 Verify boron concentration in each accumulator is ~ 2100 ppm and s 2600 ppm.
31 days on a
STAGGERED TEST BASIS SR 3.5.1.5 Verify power is removed from each accumulator motor operated isolation valve operator when pressurizer pressure is
> 1600 psig.
31 days R.E; Ginna Nuclear Power Plant 3.5-2 Amendment No. gg, 69