ML19270G035

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Forwards 790515 Rept, Addl Info on Justification of Mark II Lead Plant Safety Relief Valve Load Definition by S&W,In Response to NRC 790427 Request
ML19270G035
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 05/30/1979
From: Novarro J
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19270G036 List:
References
REF-GTECI-A-08, REF-GTECI-CO, TASK-A-08, TASK-A-8, TASK-OR SNRC-396, NUDOCS 7906010201
Download: ML19270G035 (1)


Text

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  • WADING RIVER, N.Y.11792 May 30, 1979 SNRC-396 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

" ADDITIONAL INFORMATION ON JUSTIFICATION OF MARK II LEAD PLANT SRV LOAD DEFINITION", by Stone & Webster Engineering Corporation, dated May 15, 1979. This report is provided in response to a telephone conference call on April 27, 1979 between the NRC Staff and representatives of the Mark II Lead Plants.

During that telephone conversation, the NRC Staff requested that Shoreham complete Table 2 of the SRV Load Definition Report, and submit a discussion on the effect of modal partici-pation on low frequency piping system responses.

The detailed analysis results support the conclusion that the design basis Ramshead Load definition provides conservative results even when the fundamental mode of a piping system is low enough for a few modes to occur in the frequency range where the tee quencher amplified response spectra (ARS) is greater than the ramshead ARS. This is because the contri-bution to total stress from the law frequency range modes is only a small part of the total. This document therefore further reinforces the justification of the use of the rams-head SRV load definition as the Mark II Lead Plant SRV load definition for plant component design.

We trust that this information is responsive to the Staff's request regarding the response of low frequency piping systems, and completes the documentation of the load definition described in our March 30, 1979 submittal (SNRC-374). g Very truly yours, g

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))bb 22h J. P. Novarro, Project Manager Shoreham Nuclear Power Station 7 9 0 6 010 2cy FC 8935