ML19343C111
| ML19343C111 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/12/1981 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM LOD-81-40-21, NUDOCS 8102180661 | |
| Download: ML19343C111 (2) | |
Text
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Commonwealth Edison one First National Plaza. Chicago. Ilhnois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 February 12, 1981 Mr.
B.
J. Youngblood, Chief Licensing Branch 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.
C.
20555
Subject:
LaSalle County Station Unit 1 and 2 Safety /
Relief Valve Testing NUREG-0737 Item II.D.1 NRC Docket Nos. 50-373/374 LOD 81-40-21
Dear Mr. Youngblood:
As you are aware, Commonwealth Edison is a member in the BWR Owners Group and is a participant in the generic safety /
relief valve testing program sponsored by that group.
The testing, in accordance with agreements reached between the Owners Group and the NRC Staff in November 1980, is scheduled to be completed in July 1981 by the testing contractor - EPRI Labs.
In order to clarify the Commonwealth Edison position with respect to this testing as it relates to the safety review of LaSalle County Station, the following commitments are offered:
- 1. All of the requirements specified in Item II.D.1 of NUREG-0737 related to the LaSalle County S/RV's will be met in the manner agreed upon between the BWR Owners Group and the NRC Staff.
- 2. This S/RV Test Program conducted by the BWR Owners Group will be formulatt;d in such a way that the functionality of the LaSalle County safety relief valve (Crosby) and discharge pipe for expected operating and accident conditions is confirmed directly or by correlation or other evidence to substantiate applicability to the as-installed design including the effect of as-built discharge piping on valve operability.
- 3. If, upon completion of the review of the Owners Group program, the NRC Staff requires additional information for pressures and temperatures in excess of those provided in the low pressure test program, Commonwealth Edison will participate in the development of the additional information 81021s0%(
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Mr. B. J. Youngblood Page Two February 12, 1981 requested related to valve operability and system functionality on a schedule consistent with that agreed to between the BWR Owners Group and the NRC Staff.
In the event you have any further questions in this regard, please direct ther. to this of fice.
Very truly yours, 4
L. O. DelGeorge Nuclear Licensing Administrator cc: NRC Resident Inspector-LSCS
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