ML20062D729
| ML20062D729 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/30/1982 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| 4611N, NUDOCS 8208060199 | |
| Download: ML20062D729 (2) | |
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\\ O ' 7 Address Reply to: Post Office Box 767 (j/ Chicago Illinois 60690 July 30, 1982 Mr. A. Schwencer, Chie f Licensing Branch #2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Unit 1 Seismic and Loss-o f-Coolant Accident Loads NRC Docket No. 50-373 Reference (a):
License NPF-ll dated April 17, 1982, Condition 2.C. (12), Seismic and Lo ss-o f-Coolant Ac cident Lo ads.
(b):
NEDE-21175-3 P, Clas s III, July, 1982, BWR Fuel As sembly Evaluation o f Combined SSE and LOCA Loadings
( Amendmen t No. 3).
(c):
J.. F. Quirk letter to Hal Bernard dated July 27, 1982, transmitting NEDE-2117 5-3 P.
Dear Mr. Schwencer:
Re ference (a) states, in part, that:
"By July 30, 1982, the licensee shall submit to NRC a 4
complete description of the analytical methods along with all analytical results necessary to show that LaSalle fully meets the criteria of Appendix A to the Standard Review Plan, Section 4.2 (NUREG-0800) with regard to fuel assembly liftoff.
General Electric Company has prepared a proprietary licensing topcial report, Reference (b), which summarizes the method, model, and inputs used to evaluate the LaSalle BWR fuel assemblies when subjected to seismic (SSE) and hydrodynamic loads (LOCA, SRV discharge, annulus pressurization, condensation oscillation, etc.).
The model development procedure and the methodology for evaluating gap openings are described for fug,1 assemblies applicable to BWR/4/5/6.
Details are given to
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account for the non-linear behavior of the fuel assembly under the influence of the combined dynamic load inputs.
A statistical method was used to yield resultant response having a non-exceedance probability (NEP) of 84 percent for the combined response quantities at a 50 percent confidence level; this method is consistent with the requirements of NUREG-0484 Rev. I and the Kennedy-Newmark Criteria (NED0-24010-03) which ere used for combination of responses from two or more dynamic loads.
RPOmn65199 820730 DR ADOCK 050003
A. Schwencer July 30, 1982 For LaSalle, the results show that the amount o f fuel bundle gap opening is very small (0.035 inch under the most limiting postulated load combinations).
That gap opening is acceptable compared with the 0.520 inch gap required to disengage the lower tie plate from the fuel support casting.
By separate transmittal on July 27, 1982, three copies of the subject report were provided directly to the NRC by Reference (c).
This submittal fulfills the Reference (a) dated requirements.
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 employees and contractor personnel.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
If you have any further questions in this matter, please contact this office.
Very truly yours, 7 / 30lBL C. W. Schroeder Nuclear Licensing Administrator 1m cc:
NRC Resident Inspector - LSCS 1/0 4611N i