ML20080P874
| ML20080P874 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/28/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9503080162 | |
| Download: ML20080P874 (2) | |
Text
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s i
ROCHESTER GAS AND ELECTRIC CORK) RATION
- 89 EAST AVENUE, ROCHESTER, N Y 14649-0001 N AREA CODE 716 546200 ROBERT C. MECREDY i d.
V ce Pres,d.e, February 28, 1995 f
3j N*.or oo.,anoni U.S. Nuclear Regulatory Commission Document Control Desk l
Attn:
Allen R. Johnson a
Project Directorate I-3
/
Washington, D.C.
20555
Subject:
Submittal of Summary Description of the Vehicle Control Measures in Compliance with 10 CFR 73.55 R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
The enclosed document is Rochester Gas and Electric Corporation's Summary Description of measures to comply with the amended 10 CFR 73, " Physical Protection of Plants and Materials." It is submitted in accordance with 10 CFR 73.55(c) (9).
This document provides a description of the proposed vehicle control measures for the R.E.
Ginna Nuclear Power Plant and establishes that these measures provide adequate protection against the design basis explosion and meets the design goals and criteria i
specified by the rule.
In accordance with the established compliance schedule of 10 CFR
]
- 73. 55 (c) (9) (ii), all vehicle control measures are required to be installed by February 29, 1996.
Rochester Gas and Electric is currently involved in preparations for replacement of the steam generators at Ginna Station, and construction activities associated with this effort will be ongoing from March 1995 through June 1996.
At the present time, it is envisioned that only a portion of the existing jersey barrier system on the south end of the perimeter will require removal to allow for steam generator replacement activities and that new vehicle barriers, when installed, will not create any interferences.
- However, there is some uncertainty regarding the capability to transport the steam generators and lifting crane to their setup areas without dismantling a portion of the new vehicle barrier system.
The attached sketch shows these barriers in the area of interest.
An additional concern exists in that it is possible that the existing jersey barriers, which meet the anchored jersey barrier design provided in NUREG/CR-6190, Vol.
2, may not be judged adequate by the NRC.
The design adequacy is dependent on the NRC's decision regarding their recent concerns with the design.
Based on the timing of this decision and if new vehicle barriers must be installed in place of the existing barriers identified on the sketch, it may be necessary to request an extension.of the full implementation date for a short duration to redesign and construct a replacement for the existing system at the south en.1.
^
9503080162 950228 PDR ADOCK 05000244 1
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i 1 id Future correspondence will address this issue once RG&E receli,eW-additional information regarding this design.
Od" '
Very ruly yours, l
\\
1 i
Robert C. Mecr dy 1
PSbi370 1
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xc:
Mr. Allen R. Johnson (Mail.Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 i
U.S. Nuclear Regulatory Commission Regio!t I 475 Allendale Road i
King of Prussia, PA 19406 i
i Ginna Senior Resident Inspector.
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