ML20077J018

Forwards Assessment Against RHR Safety/Relief Valve Discharge Steam Condensation Loads, Constituting Revised Response to NRC Questions.Rhr Safety Valve Load Combination Confirms Design Basis Adequacy

ML20077J018
Person / Time
Site:	LaSalle
Issue date:	08/05/1983
From:	Schroeder C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20077J019	List: ML20077J018 ML20077J031
References
CON-7099N NUDOCS 8308120178
Download: ML20077J018 (1)

Text

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[2h Commonwealth ) One First National Plaza. Edison Chcago, flhnois

('q,/OChicago, '7 AddrIss R; ply to: Put Offica Box 767 Illinois 60690 August 5, 1983 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Units 1 and 2 Concerns Regarding the Adequacy of Design Margins of the Mark I and II Containment Systems NRC Docket Nos. 50-373 and 50-374 Reference (a): C.W. Schroeder letter to A. Schwencer dated August 30, 1982.

Dear Mr. Denton:

Questions regarding possible RHR system safety valve discharge loads were answered in Reference (a). That submittal used infurmation contained in NEDO 21061 " Mark II Containment Dynamic Forcing Functions Information Report (DFFR)" Rev. 2. General Electric Company notified Commonwealth Edison in a letter dated February 25, 1983 of errata in the DFFR which invalidate our previous load definition. The enclosed report

" Assessment Against RHR Safety / Relief Valve Discharge " team Condensation Loads" is a revised response to part 3.1.C of the referenced submittal.

The results of this assessment clearly show that the RHR safety valve load combination is bounded by the LaSalle design basis and confirms design basis adequacy.

To the best of my knowledge and belief the statements contained herein and in the enclosure are true and correct. In some respects these statements are not based on my personal knowledge but upon information furnished by other Commonwealth Edison employees and consultants. Such information has been reviewed in accordance with Company practice and I believe it to be reliable.

Enclosed please find one (1) signed original and forty (40) copies of this letter and the enclosure.

If there are any further questions in this matter, please contact this office.

Very truly yours, W b k J ~ sjgje3 C. W. Schroeder Nuclear Licensing Administrator im Enclosure i cc: NRC Resident Inspector - LSCS 1/0 9300120178 830005 [

PDR ADOCK 05000373 7099N P PDR

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