ML20076K912

Forwards Evaluation of NUREG-0808 Load Definition, Per Condition 2.C(16) of License NPF-11 &

ML20076K912
Person / Time
Site:	LaSalle
Issue date:	09/13/1983
From:	Schroeder C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20076K915	List: ML20076K912 ML20076K920
References
RTR-NUREG-0808, RTR-NUREG-808 7302N, NUDOCS 8309150310
Download: ML20076K912 (2)

Text

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c -

C C:mmonwrith Edison

• one First National Plaza Chicago. %nois O Address Reply to: Post Office Box 767 Chicago, Illinois 60690 September 13, 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 Evaluation of NUREG-0808 Load Definition NRC Docket Nos. 50-373 and 50-374 References (a): License NPF-11, Condition 2.C.(16).

(b): A. Schwencer letter to D.L. Farrar dated April 13, 1983.

(c): C.W. Schroeder letter to Director of

. Nuclear Reactor Regulation dated July 27, 1983.

Dear Mr. Denton:

Reference (a) stated:

" Prior to October 1, 1982, the licensee shall submit its confirmatory assessment of the containment design adequacy for pool dynamic loads (chugging, vent lateral and diaphram reverse pressure) developed in conjunction with the Long Term Program and reported in NUREG-0808."

Reference (b) stated that prior submittals germane to the license condition were inadequate and that Commonwealth Edison must provide a detailed design review to demonstrate structural adequacy.

Enclosed is the report entitled " Evaluation of NUREG-0808 Load

Definition for LaSalle County Station Units 1 and 2" which provides l

positive confirmation of the design adequacy of the LaSalle plant piping and supports due to NUREG-0808 high frequency excitation. This report supercedes information provided in reference (c). Errors in calculating increased loads have been corrected and four subsystems previously not evaluated were found adequate. It is our understanding that the enclosed report addresses the issues most recently discussed with Mr. D. Terao of your staff during recent meetings at the offices of Sargent and Lundy on this topic, i This submitral should therefore allow closure of References (a) and (d).

e3o9150310 B30913 f ,[ol t

PDR ADOCK 05000373 p PDR

s H. R. Denton September 13, 1983 To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct. In some respects these statements are not based on my personal knowledge but upon infor-mation furnished by other Commonwealth Edison and contractor employees.

Such information has been reviewed in accordance with Company practice and I believe it to be reliable.

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

Very truly yours, l- /

C. W. roeder Nuclear Licen 'ng Admin strator 1m cc: NRC Resident Inspector - LSCS 1/0 7302N

l l

EVALUATION OF NUREG-0808 LOAD DEFINITION LA SALLE COUNTY STATION UNITS 1 AND 2 Commonwealth Edison Company SARGENT4 LUNDY Calculation No. EMC-045075

-ruoiueras. Project No. 6728-37