ML20094B299

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Provides Revised Commitment Re Schedule for Installation of Fire Hazards Panel Described in Util .Rev Provided to Resolve NRC Concern Re Deadline for Completion of Mods Required by Condition 6(f) in Draft License
ML20094B299
Person / Time
Site: Byron Constellation icon.png
Issue date: 10/26/1984
From: Tramm T
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
9384N, NUDOCS 8411070096
Download: ML20094B299 (1)


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Commonwealth Edison s

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O j one First National Pirza Checigo. Ilknois

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j Chicago, Illinois 60690 October 26, 1984 Mr. Harold-R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject:

Byron Generating Station Unit 1 Fire Protection NRC Docket Nos. 50-454 References (a):

June 17, 1983 letter from T. R. Tramm to H. R. Denton.

(b):

October 18, 1984 letter from T. M. Novak to D. L. Farrar.

Dear Mr. Denton:

This is to provide Commonwealth Edison's revised commitment regarding the schedule for installation of the Byron 1 fire hazards panel described in reference (a).

This revision is provided at the request of the NRC Staff to resolve their concern regarding the deadline for

. completion of the modifications required by Condition 6(f) in the draft

. license issued in reference (b).

In reference (a) we indicated that additional instrumentation would.be provided which can operate after a fire in the auxiliary electric equipment room or the control room to assure that the plant can be safely shutdown.

We committed to installation of this equipment on Byron 1 by the end of the first refueling outage.

It now appears that this instrumentation will be installed and operational prior to exceeding 5% power.

This schedule is contingent upon timely delivery of various components and successful completion of testing.

It has been developed upon a "best efforts" basis and does not allow for any significant unexpected delays.

It will not, however, be altered without prior NRC approval.

In the unlikely event that this instrumentation cannot be made operational prior to exceeding 5% power, appropriate compensatory measures will be proposed.

These could involve a continuous fire watch or the use of portable test instrumentation.

Please address further questions regarding this matter to this

. office.

Very truly yours, f, f{

43 DOC O

T. R. Tramm Nuclear Licensing Administrator 1m

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