ML17264A502
| ML17264A502 | |
| Person / Time | |
|---|---|
| Site: | Ginna  (DPR-18-A-064, DPR-18-A-64) |
| Issue date: | 05/23/1996 |
| From: | Jeffrey Mitchell NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264A503 | List: |
| References | |
| NUDOCS 9605290075 | |
| Download: ML17264A502 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> O.C. 205554001 ROCH STER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 G
NNA UCLEAR POW P
AN AMENDM NT TO FACI TY OPERATING LICENSE Amendment No. 64 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 February 9,
- 1996, as supplemented March 15,
- 1996, and April 22,
- 1996, 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; O.
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:
'&05290075 960523 PDR ADOCK 05000244 P
PDR 3.
(2)
S ecific tions The Technical Specifications contained in Appendix A, as revised through Amendment No.
64
, 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
),~.c ~~
Jocelyn A. Mitchell, Acting 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:
Nay 23, 1996
C S
AM 64 OP RATING LIC NSE N
DPR-8 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.
J~ove 5.0-22 Insert 5.0-22
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6.
~PT (continued) c ~
d.
The RCS pressure and temperature and LTOP limits shall be those previously reviewed and approved by the NRC.
The acceptability of the P/T and LTOP limits are documented in NRC letter dated May 23, 1996.
Specifically, the limits and methodology are described in the following documents:
1.
Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RG8E), to Document Control Desk,
- NRC, Attention: A.R. Johnson, "Application for Facility Operating License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR),"
April 22, 1996.
2.
Letter from C. I. Grimes, NRC, to R.A. Newton, Westinghouse Electric Corporation, "Acceptance for Referencing Topical Report WCAP-14040, Revision 1,
'Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves'," October 16, 1995.
3.
Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RGEE), to Document Control
- Desk, NRC, Attention A.R. Johnson, "Technical Specifications Improvement
- Program, Reactor Coolant System (RCS)
Pressure and Temperature Limits Report (PTLR),"
December 8,
1995.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for revisions or supplement thereto.
R.E.
Ginna Nuclear Power Plant 5.0-22 Amendment No. Pf, 64