ML20138R243
| ML20138R243 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/20/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-5-150, TAC-62936, NUDOCS 8512310106 | |
| Download: ML20138R243 (1) | |
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'a=SNIE Pittsburgh, PA 15205 December 20, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Steam Generator Level Control
REFERENCES:
a) NRC letter dated Novenber 22, 1985, fran Mr. H.
Thompson to Mr. J. Carey b) NRC letter dated June 25 1985, fran Mr. Victor Nerses, May 9,,
1985, Backfit Meeting on Stean
" Meeting Summary of Generator Fourth Channel '
c) NRC letter dated Novenber 25, 1985, fran Mr. D. Crutchfield to Backfitting Activities - October 1985" port on Plant Specific Mr. Hugh Thanpson, " Monthly Status Re Gentlemen:
In Reference (a), the NRC requested that the Beaver Valley Power Station Unit No. 2 (BVPS-2) Final Safety Analysis Report (FSAR) be revised to eliminate the inconsistency of representing the stean generator high level trip systen as part of the Emergency Safety Features (ESF) Actuation Systen.
Duquesne Light Conpany has reviewed the BVPS-2 FSAR and has now detennined that only one change is needed.
Table 15.0-6 in the FSAR will be revised to refer to the stean generator high level trip function as a non-required actuation function. The use of the high stean generator level is not required for protection but is used only as a convenient ending point for the analysis in Section 15.1.2 of the FSAR.
This revision is expected to be incorporated in Anendment No.11 to the BVPS-2 FSAR, which is scheduled to be issued in January, 1986.
This infonnation should allow you to conplete your additional review of a p)licability to 10CFR50.55(a)(h) in accordance with References (a), (b),
and c DUQUESNE LIG COMPANY
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