ML19254D951

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Forwards Second Suppl to Justification of Mark II Lead Plant Safety Relief Valve Load Definition Equipment Evaluation
ML19254D951
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 10/23/1979
From: Novarro J
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19254D952 List:
References
SNRC-438, NUDOCS 7910300357
Download: ML19254D951 (1)


Text

1*

LONG ISLAND LIGHTING COMPANY 7 FLd'O Jaarauawa,-

SHOREHAM NUCLEAR POWER STA' TION P.O. BOX 618. NORTH COUNTRY ROAD + WADING RIVER, N.Y.11792 October 23, 1979 SNRC-438 Mr. Harold R.

Denton, Director Office of Nuclear Reactor Regulation U.

S.

Nuclear Regulatory Commission Washington, D. C.

20555 SHOREHAM NUCLEAR POWER STATION - UNIT 1 DOCKET NO. 50-322

Dear Mr. Denton:

Enclosed herewith are fifteen (15) copies of a report entitled "Second Supplement to Justification of Mark II Lead Plant SRV Load Definition - Equipment Evaluation" by Stone & Webster Engineering Corporation, dated September 28, 1979.

This report is provided in rasponse to a meeting July 26, 1979 between NRC Staff and representatives of the Mark II Lead Plants.

During that meeting, the NRC Staff requested that Shoreham provide assurance that the low frequency portion of the T-quencher SRV load definition would be bounded by the design-basis Ramshead Load definition not only for piping systems, as satisfactorily demonstrated in the May 30, 1979 submittal, but also for equipment.

The detailed results summarized herein support the conclusion that low frequency equipment in general has been designed to conservative seismic loads which bound both Ramshead and T-quencher results.

We trust that this information completes the documentation requests by NRC Staff for the load definition described in our March 30, 1979 submittal (SNRC-374).

Very 1

yours, f

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{p.P. Noyarro, cc:

J.

Higgins

" Project Manager Shoreham Nuclear Power Station o\\

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Encls.

7910300 3 4

FC 8935