ML20133B222
| ML20133B222 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/30/1985 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GN-701, NUDOCS 8510030089 | |
| Download: ML20133B222 (2) | |
Text
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Georgia Power Company Routs 2, Box 299A -
Waynisboro, Georgia 30830 Telephone 404 554-9%1 404 724-8114-Southern Company Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Proj.ect September 30, 1985 Director.of Nuclear Reactor Regulation File: X6BB06 Attention:
Ms. Elinor G. Adensam, Chief Log: GN-701 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0 GILE ELECTRIC GENERATING PLANT-UNITS 1 AND 2 FIRE PROTECTION SAFE SHUTDOWN ANALYSIS
Dear Mr. Denton:
During discussions with the NRC staff, Georgia Power Company committed to completing an analysis of the safe shutdown capability for Plant Vogtle by September 30, 1985. This analysis will also address the alternate or dedicated shutdown capability and the question of associated circuits and spurious actuations caused by a fire. To complete the analysis to the level of detail necessary has required more time than originally estimated.
It is expected that the analysis of the safe shutdown capability, alternate shutdown and associated circuits / spurious actuations will.be completed and submitted for NRC review by March 1986.
As discussed in the September 26, 1985, telephone conversation with the NRC staff, the safe shutdown analysis performed to date has shown that the sprinkler system inside the containment is not needed to assure safe shutdown. The system as presently designed is not operable until the manual containment isolation valve is opened. Therefore automatic sprinkler coverage is not provided for the containment. The ability to achieve safe shutdown for a fire inside containment will'be assured by providing separation of redundant safe shutdown components in accordance with the require v ts of 10 CFR 50 Appendix R Section III.G.2 for non-inerted containment..
This change in plant design will be reflected in a future FSAR amendment.
8510030009 850930 ADOCK O5000424 PDR PDR F
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Director of Nuclear Reactor Regulation Page 2 September 30, 1985 If your' staff requires any additional information, please do not hesitate to contact me.
Sincerely, J. A. Bailey Project Licensing Manager JAB /rik/caa Attachment-xc:
D. O. Foster
.R. A. Thomas J. E. Joiner, Esquire B. "W.
Churchill, Esquire M. A. Miller (2)
B. Jones (w/o att.)-
L. T. Gucwa G. Bockhold, Jr.
T.' Johnson (w/o att.)
D. C. Teper (w/o att.)
L. Fowler W. C. Ramsey Vogtle Project File 4
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