ML20207Q908
| ML20207Q908 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/04/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2NRC-7-039, 2NRC-7-39, TAC-62936, NUDOCS 8703100188 | |
| Download: ML20207Q908 (3) | |
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2NRC-7-039 Beaver Va' ley No. 2 Unit Project Organization Telecopy (
32 Ext.160 S.E.G. Building P.O. Box 328 March 4, 1987 Shippingport, PA 15077 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412 10 CFR 50.55a(h) Schedular Exemption Steam Generator High Level Trip Gentlemen:
We have reviewed the Reactor Systems' Branch (RSB) position on the steam generator high level trip for the increased feedwater event which was forwarded by your letter dated February 20, 1987.
Notwithstanding our past position on the approoriateness of applying the IEEE-279 requirements, for reactor protection systems to this design feature, we have evaluated our options and selected a modification on the feedwater control circuits that should resolve this and other issues. We will modify the three steam generator level control circuits to incorporate a median-select function.
This will provide circuit discrimination for the high and low level signals, selecting the mid-range input from the three protection steam genera-tar level channels. This modification will be inst 111ed at the first refueling outage and will require a schedular exemption to 10 CFR 50.55a(h) for the Oper-ating License pursuant to the requirements of 10 CFR 50.12.
The following items are submitted in support of this request:
1.
With the expected issuance of the Operating License in April 1987, exigent circumstances exist which do not provide a sufficient timeframe to design, procure and install this modification.
2.
The hypothetical downscale failure of the controlling steam generator level channel, in conjunction with an "as-is" failure of one of the remaining level channels is a very low probability event.
It has not been shown, nor can it be reasonably conceived, to be an accident that would result in a significant fission product release and on this basis, would not represent an undue risk to the public health and safety.
3.
Duquesne Light has trained all licensed personnel on the potential conse-quences of the steam generator overfill and included this transient, coupled with a failure of the main regulating valve to respond in manual, as part of their simulator training.
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J Beaver Valley Power Station, Unit No. 2 Docket No. 50-412 10CFR 50.55a(h)
Page 2 We believe this modification will fully resolve the RSB exception to this design and enable closure of the confirmatory item referenced in the Supplemen-tary Safety Evaluation Report 2, Sections 7.3 and 15.1.2.
DUQUESNE LIGHT COMPANY l
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By J. YK ayey
(/ T Senior (rice PreM dent REM /ans cc: Mr. J. Beall, NRC Sr. Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Par.\\ Avenue King of_ Prussia, PA _19406 Mr. Peter S. Tan U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 340 Addressee only t
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,1 Beaver Valley Power Station, Unit No. 2 Docket No. 50-412 10CFR 50.55a(h)
Page 3 COMMONWEALTH OF PENNSYLVANIA )
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COUNTY OF BEAVER
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On this N day of
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, before me, a Notary Public ' in and for said Commonwealth and County, ' personally appeared J. J. Carey, who being duly sworn, deposed and said that (1) he is Senior Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge.
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