ML17251A303
| ML17251A303 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/03/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A304 | List: |
| References | |
| NUDOCS 8810100166 | |
| Download: ML17251A303 (4) | |
Text
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0 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.
31 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated May 13, 1988 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; 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:
8810100166. 881003 PDR
- DOCK 05000244 P
PNU (2)
Technical S ecifications The Technical Specifications contained in Appendix A as revised through Amendment No.
31
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective. as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II Date of Issuance:
October 3, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.
31 FACILITY'PERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A as follows:
REMOVE page 3.13-1 INSERT page 3.13-1
~
3.13 Sho Su pressors (Snubbers)
A licabilit Applies to the operability of all safety-related shock suppressors (snubbers) listed in Table 3.13-1.
N To specify the reauirements for operability of shock suppressors (snubbers)..
3.13.1 3.13.2 S ecifications:
The reactor shall not be made critical unless (1) all shock suppressors (snubbers) listed in Table 3.13.1 are operable.
Continued hot shutdown or power operation is permitted for a period up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> without the conditions of 3.13.1 being met. If the conditions of 3.13-1 are not met in that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period, then the reactor shall be in a cold shutdown condition within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Basis Shock suppressors (snubbers) are required to be operable to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers may be replaced by rigid structural supports (bumpers) provided an analysis is performed to demonstrate that appropriate acceptance criteria are satisfied for design basis seismic and pipe break events and provided that the bumpers are inspected periodically in a manner appropriate for rigid structural supports.
3 ~ 1 3 1
Amendment No.
31