ML20212D842
| ML20212D842 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/24/1987 |
| From: | Allen C COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2658K, NUDOCS 8703040217 | |
| Download: ML20212D842 (2) | |
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Address Reply to: Post Once Box 757 Chece00,lenois 80000 0767 '
February 24, 1987 U.S. Nuclear Regulatory Cossaission
. ATTN: Doctseent control Desk
' Washington, D.C._
.20555
Subject:
LaSalle County Station Units 1 and 2 Proposed Technical. Specification for
~
Diesel Generator "O" MRC Docket Nos. 50-373 and 50-374 Reference (a): January 19,~1987 letter from C.M. Allen proposing amendment to NPF-11 and NPF-18 to allow D/G "O" out-of-service for up to 7 days for preplanned preventative maintenance activities.
Dear Sir:
The following discussion is to provide documentation of a telecon between Dr. A. Bournia and myself held on February 4, 1987. During that telecon a discussion was held regarding meeting specific conditions called out in Reference (a) would be controlled. Also discussed were the effects of the cross-tie between buses 142Y and 242Y on the Emergency Safeguard Features (RSF) power supply design.
The conditions discussed are quoted from the January 19, 1987 amendment request (Reference (a)).
We have concluded that the proposed change will not endanger the health and safety of the public provided that the following conditions are met before the "o" diesel generator is taken out of service for completion of surveillance requirements 4.8.1.1.2d.1 and/or 4.8.1.1.2f.1:
1.
One of the units must be in cold shutdown, the refueling mode or defueled.
2.
Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to removal of the "O" diesel generator from service, surveillance requirements 4.8.1.1.la and 4.8.1.1.2a.4 must be successfully completed for the offsite power circuits and for the 1A and 2A diesel generators.
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No maintenance is performed on the offsite power circuits or the 1A and 2A diesel generators while the "O" diesel generator is out of service.
4.
Technical Specification surveillance requirement 4.8.1.1.la is performed daily.
5.
The control circuit for the unit cross-tie circuit breakers between buses 142Y and 242Y are temporarily modified to allow the breakers to be closed with a diesel generator feeding one of the buses.
In the event that the above conditions cannot be met, the appropriato Technical Specification action statement requirements will be met.
r These conditions will be controlled by the Shift Control Room Engineer (SCRE). The SCRE will receive direction from two procedures, one of which will specify the surveillances to be conducted to ensure the conditions above are met and the other will prescribe loads on buses 142Y and 242Y while cross-tied. These procedures will be essentially the same as the temporary procedures utilized in the Unit 1 Refuel Outage to support D/G "O" out-of-service. This was approved by Amendment 16 to NPF-18.
These new procedures will be written and approved prior to invoking this technical specification change.
The cross-tie procedure will control the loads carried on the two buses to ensure the D/G does not become overloaded from non-essential loads.
This ensures sufficient margin to carry the ESF design loads and ensures the design basis for the FSAR accident analysis is maintained.
If you have any additional questions regarding this matter, please contact this office.
V truly your C. M. Allen Nuclear Licensing Administrator im Attachments cc:
Dr. A. Bournia - NRR Regional Administrator - RIII M.C. Parker - IDNS Resident Inspector - LSCS 2658K