ML20004B037
| ML20004B037 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/21/1981 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105270142 | |
| Download: ML20004B037 (2) | |
Text
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O One First Nat:onal Plaza. Chicago.11tino Commonwealth Edison Address Reply to: Post Office Box 767 Chicago, lilinois 60690
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Mr. A.
Schwencer, Chief Licensing Branch 2 4 /,y / ',
Division of Licensing
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U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
LaSalle County Station Units 1 and 2 Supplemental Information in Response to Informal NRC Questions on S/RV Performance Review Program NRC Docket Nos. 50-373/374 Reference (1):
L. O. DelGeorge letter to A.
Schwencer dated May 19, 1981.
Dear Mr. Schwencer:
The purpose of this letter is to supplement information provicea in Reference (1) relative to the S/RV Performance Review Program to be implemented at LaSalle County Station.
Specifically, Commonwealth Edison will make a good faith effort to promote the development of a multi-utility program to accumulate, consoliaate and commumnicate significant maintenance operating information related to the Crosby main Steam line safety / relief valve.
In the event an acequate program alreaay exists to process such information, such as the Nuclear Plant Reliability Data system, Commonwealth Edison will make a 9000 faith effort to promote tne participation by other Crosby valve owners in such a program.
As was inaicatea in Reference (1), pertinent information, incluaing but not limitea to LER reported failures, will be recorded at LaSalle County Station and maae available as input to such a group program.
The LaSalle County records will include the following types of information:
1.
Initial valve records 2.
Leak Detection Device Records 3.
Scheaulea Maintenance Records 4.
Unscneaulea Maintenance Records The program will be structured to collect sufficient data to allow identification of potentially generic safety-relief valve problems ranging from excessive wear observec curing normal inspection to complete failures of the valve.
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Mr. A. Schwencer May 21, 1981 If there are any further questions in this regard, please direct them to this office.
Very truly yours, L. O. DelGeorge Nuclear Licensing Department i
cc:
NRC Resident Inspector - LSCS A
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