ML20138C816

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Suppls 850927 Submittal Re Generic Ltr 85-15 & Responds to Telcon Questions.Protective Devices Consist of Ite Circuit Breakers for Control Circuits & Klockner-Moeller molded-case Circuit Breakers for Power Feeds
ML20138C816
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 10/09/1985
From: Massin H
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
0759K, 759K, GL-85-15, NUDOCS 8510230053
Download: ML20138C816 (2)


Text

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g Commonwealth Edison C ) one First National Plaza. Chicago. lilinois G Address Reply to: Post Office Box 7W Chicago. Illinois 60690 October 9, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Units 1 and 2 Environmental Qualification of Electrical Equipment - Supplemental Information -

NRC Docket Nos. 50-373 and 50-374

Reference:

September 27, 1985 letter from H. L. Massin to H. R. Denton responding to Generic Letter 85-15.

Dear Mr. Denton:

The referenced letter apprised the NRC of certain test activities, associated with the requirements of 10 CFR 50.49, which are still in oroaress. It also provided a reevaluation of the Comsip analyzers. This letter supplements that September 27, 1985 submittal with responses to the questions you asked during our telecon today.

QUESTION 1: On page 3 of the submittal, reference is made to " protective devices". What is the qualification status of these devices?

RESPONSE: These protective devices consist of ITE Circuit Breakers for the control circuits and Klockner-Moeller Molded-Case Circuit Breakers for the power feeds. These devices are located in MCC's 1(2)AP71E and 1(2)AP78E for Analyzers 1(2)PL76J and 1(2)PL773, respectively. The KC's are located in the reactor building in a potentially harsh environment and are included in the EQ program. Recall that the qualification status of these items was also provided in the referenced letter under the discussion on the Klockner-Moeller Motor Control Center.

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QlESTION 2: On page 4 of the submittal, reference to " core damaging event" should be clarified to eliminate potential operator confusion.

l RESPONSE: We will revise LOA-HG-01 to specifically include DBA-LOCA.  ;

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H. R. Denton October 9, 1985 If you have any questions concerning this matter, please direct them to this office.

One signed original and ten (10) copies of this transmittal are enclosed for you use.

Very truly yours, Y

H. L. Massin Nuclear Licensing Admininstrator 1m cc: Dr. A. Bournia - NRR Resident Inspector - LSCS 0759K l

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