ML17262B121
| ML17262B121 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/29/1992 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17262B122 | List: |
| References | |
| NUDOCS 9212300259 | |
| Download: ML17262B121 (4) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No.
DPR-18 1.
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 June 22, 1992 complies with the standard 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 set forth in 10 CFR Chapter I; 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.
- 2. 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:
(2) Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
50
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 29, 1992 Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
50 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Remove 4.3-1 4.3-1a Insert 4.3-1
4.3 Reactor Coolant S stem A licabilit Applies to surveillance of the reactor coolant system and its components.
To ensure operability of the reactor coolant system and its components.
S ecifications:
4.3.1 4.3.1.1 Reactor Vessel Material Surveillance Testing The reactor vessel material surveillance specimens shall be removed and examined to determine changes in their material properties, as required by Appendix H to 10 CFR 4.3.2 Part SO.
Pressurizer 4.3.2.1 The pressurizer water level shall be verified to be within its limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during power operation and hot shutdown.
Amendment No: f$,
50 4.3-1