ML17264B134
| ML17264B134 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/09/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17264B135 | List: |
| References | |
| NUDOCS 9712170025 | |
| Download: ML17264B134 (4) | |
Text
y ing REGS
."o Cy A.
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-000I ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
70 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 September 29,
- 1997, as supplemented October 8,
- 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:
97i2i70025 971209 PDR ADQCK 05000244 POR
3.
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
70
, 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 S.
Si gh Bajwa, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 9,
1997
ATTACHMENT TO LICENSE AMENDMENT NO.
70 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 are identified by Amendment number and contain vertical lines indicating the area of change.
Remove 5.0-22 nsert 5.0-22
eporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 PTLR (continued)
C.
The analytical methods used to determine the RCS pressure and temperature and LTOP limits shall be those previously reviewed and approved by the NRC in NRC letter, "R.E. Ginna
- Acceptance for Referencing of Pressure Temperature Limits
- Report, Revision 2
(TAC No. M96529)," dated November 28, 1997.
Specifically, the methodology is described in the following documents:
1.
Letter from R.C. Mecredy, Rochester Gas and Electric Corporation (RGBE), to Document Control Desk,
- NRC, Attention:
Guy S. Vissing, "Application for Facility Operating
- License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
Administrative Controls Requirements,"
Attachment VI, September 29,
- 1997, as supplemented by letter from R.C. Mecredy, RG&E, to'uy S. Vissing,
- NRC, "Corrections to Proposed Low Temperature Overpressure Protection System Technical Specification," October 8, 1997.
2.
WCAP-14040-NP-A, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," Sections 1 and 2, January, 1996.
d.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for revisions or supplement thereto.
R.E.
Ginna Nuclear Power Plant 5.0-22 Amendment No. g, PP, 70