ML19257C191
| ML19257C191 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/28/1979 |
| From: | Robert Carlson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Tallman W PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| References | |
| NUDOCS 8001250191 | |
| Download: ML19257C191 (1) | |
Text
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UNITED STATES EN,)s-(I,$
NUCLEAR REGULATORY COMMISSION a g'N j REGION I oA g
631 PARK AVENUE
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KING OF PRUSSIA, PENNSYLVANIA 19406
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Docket Nos. 50-443 50-444 DEC 2 81979 Public Service Company of New Hampshire ATTN:
Mr. W. C. Tallman President 1000 Elm Street Manchester, New Hampshire 03105 Gentlemen:
Subject:
Undetected Failure in Engineered Safety Features Actuation System (Your letter of December 6,1979)
Thank you for your letter, referenced above, which forwarded an interim report pursuant to 10 CFR 50.55(e) regarding the subject matter.
Your report will be reviewed and evaluated, and should we require additional infonnation concerning this matter, we will contact you.
Your cooperation with us is appreciated.
Sincerely, 42d$
er Carlson, Chief (Reactor Construction and Engineering Support Branch cc:
John DeVincentis, Project Manager 1810 094 J
8001250 / 9 /
PUBLIC SERVICE camp.nyof m.w s.mp.we.
SEABROOK STATION Engineering Office:
20 Turnpike Road Westborough, MA 01581 December 6, 1979 SBN-108 T.F. Q 2.2.2 U.S. Nuclear Regulatory enmmission Region I 631 Park Avenue King of ? russia, Pennsylvania 19406 Attention: Office of Inspection and Enforcement
Reference:
1.
Docket No. 50-443 and 50-444 2.
Telecon of 11/8/79 between Stewart Ebneter NRC and David Maidrand YAEC 3.
Westinghouse letter No. NS-TMS-2150 dated 11/7/79 to Victor Stello, Jr. NRC
Subject:
10 CFR 50.55 (e) Interim Report on Undetected Failure in Engineered S3faty Features Actuation System
Dear Sir:
The following is submitted in accordance with the requirements of 10 CFR 50.55 (e).
This deficiency was reported to the Region I Inspection and Enforcement Office, by telephone, on 11/8/79.
Westinghouse has identified an undetectable failure which potentially could exist in a circuit associated with Engineered Safeguards and which is required for reactor protection.
The specific circuit is d6 scribed below.
The design function of the circuit is a permissivo to provide the operator, depending on plant conditions, the capability to manually reset and block Safety Injection.
A failure analysis, which assumed a failure of the affacted circuit in both of the redundant protection trains (per ability to automatically initiate the pr certain conditions.
PLICATE DOCUMENT Entire document previously entered into system under:
xNoM/Alfo 363 1810 095 y
N o. of pages:
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