ML20205B110
| ML20205B110 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/20/1987 |
| From: | Allen C COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2886K, NUDOCS 8703270549 | |
| Download: ML20205B110 (2) | |
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a se i ; One First Nabonal Pisza. Checago, IEncis Address Reply tx Post Omco Box 767 Chica00. IWnois 60690 0767 March 20, 1987 4
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 l
1.
Subject:
LaSalle County Station Units 1 and 2 Safety Parameter Display System, Validyne CM-249 Isolator - NRC Request for Additional Information NRC Docket Nos. 50-373 and 50-374
Reference:
Letter front A. Bournia to D.L. Farrar, I
dated March 4, 1987 concerning " Request for Additional Information on Safety Parameter Display System Isolation for LaSalle County Station, Units 1 & 2".
Dear Sir:
The following is Commonwealth Edison Company's understanding of proposed actions as a result of the conference call between the Nuclear Regulatory Comunission, commonwealth Edison Company and Sargent & Lundy on March 10, 1987, related to the above subject and reference letter.
Following the Detroit Edison meeting dated March 19, 1987, the NRC indicated that it would take a short period of time to resolve internal questions and publish a final safety evaluation report. Therefore, the following have been or will be done:
1.
Commonwealth Rdison Company and Sargent & Lundy met with the Nuclear Regulatory Commission on March 19, 1987 at the Fermi 2 Nuclear Plant to hear the Detroit Edison discussion regarding:
(a) SPDS design utilizing the Validyne CM 249 Isolator.
(b) An agreeable definition of Maximum Credible Fault (MCF) as applied to the Validyne Isolator usage in SPDS.
2.
Within two (2) weeks following the issuance of a final SER to Detroit Edison, CECO will notify the NRC of the decision of Commonwealth Edison as to the actions which will be taken regarding Validyne CM 249 Isolators installed in the SPDS system at LaSalle.
i, B703270549 870320 DR ADOCK 05000373 0\\
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3
.,.o Y Commonwealth Edison Company questioned the necessity for disconnecting SPDS (identified in the reference letter) in view of the plant risks and associated costs with disconnection. Obviously, this would remove a valuable tool from service which was specifically designed to assist in assessment of conditions during an accident. The NRC responded that SPDS need not be disconnected at this time as long as timely resolution of this issue is being pursued by Commonwealth Edison. Based on this concurrence and our time line identified in item 2 above, the SPDS will remain in operation until this issued is resolved.
If you have any additional questions regarding this matter, please contact this office.
Very truly yours, C. M. Allen Nuclear Licensing Administrator 1m Attachments cc:
Dr. A. Bournia - NRR Regional Administrator - RIII NRC Resident Inspector - LSCS 2886K