ML19318C198

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Ack Receipt of 800515 Final Deficiency Rept Re Undetected Failure in Engineered Safety Features Actuation Sys
ML19318C198
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 06/06/1980
From: Robert Carlson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Tallman W
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
References
NUDOCS 8007010182
Download: ML19318C198 (1)


Text

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IN UNITED STATES Spirro f

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NUCLEAR REGULATORY COMMISSION

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g MING OF PRUSSI A. PENNSYLVANI A 19406 Docket Nos. 50-443 JUli 0 01111 50-444 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 SBN-120 of May 15,1980)

Thank you for your letter, referenced above, which forwarded a final report pursuantto10CFR50.55(e)regardingthesubjectmatter.

Your report will be reviewed and evaluated, and should we require additional information concerning this matter, we will contact you.

Your cooperation with us is appreciated.

Sincerely, Robert T. Carlson, Chief Reactor Construction and Engineering Support Branch cc:

John DeVincentis, Project Manager S

8007010/gx

.. W PUBLIC SERVICE Compartyof New Hamr3eher e SEABROCK STATION Engineering Omce:

20 Turnpike Road Westborough, MA 01581 May' 15, 1980 SBN-120

,T.F. Q 2.2.2 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania-19406 Attention: Office of Inspection and Enforcement

Reference:

1.

Docket No. 50-443 and 50-444 2.

Telecen of 11/8/79 between Stewart Ebneter (NRC) and David Maidrand (YAEC) 3.

Westinghouse letter No. NS-TMA-2150 dated 11/7/79 to Victor Stello, Jr. NRC 4.

Public Service of New Hampshire letter No. SBN-108 dated 1.2/6/79 to Region I NRC 5.

Westinghouse letter No. NS-TMA-2204 dated 2/15/80 to Victor Stello, Jr. NRC

Subject:

10 CFR 50.55 (e) Final Report on Undetected Failure in Engineered Safety Features Actuation System

Dear Sir:

In accordance with the requirements of 10 CFR 50.55 (e), Reference 4 forwarded to the NRC an Interim Report entitled, " Undetected Failure in Engineered Safety Features Actuation System."

In that report we stated that we were continuing to work with Westinghouse on how to best resolve the issue for Seabrook Station.

We have now completed our review and have decided to implement the pro-cedures described by Westinghouse in Reference 5.

Application of these procedures will assure that a failure in the engineered safety feature actuation system will not go undetected.

T)u 3

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-1 U.S. Nuclear Regulctory CommiEOion Page 2 SBN-120

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Should you require additional infor: nation on this matter, please contact us.

Very truly yours, s

John Devincentis Project Manager DAM: tan cc:

Director of Inspection and Enforcement Washington, D.C.

20555

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