ML17263B031
| ML17263B031 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/26/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17263B033 | List: |
| References | |
| NUDOCS 9505010236 | |
| Download: ML17263B031 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ROCH STER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
59 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 March 13,
- 1995, 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.
D.
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; 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 2.
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:
9505010236 950426 PDR ADQCK 05000244 P
3.
(2)
Technic 1
S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
59
, 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
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 26, 1995 Ledyard B. Harsh, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove 4.4-7 Insert 4.4-7
b.
If repairs are not completed and conformance to the C ~
acceptance criterion of 4.4.2.2 is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion.
.If it is determined that the leakage through a
mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and plans for corrective action developed.
4.4.2.4 Test Fre uenc
'a 0 b.
Except as specified in b.
and c. below, individual penetrations and containment isolation valves shall be tested in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.
The containment equipment
- hatch, fuel transfer
- tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.
Amendment No. gp,pg 59
- 4. 4-7