ML20137V233

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Significant Const Deficiency Rept Re Heat Buildup in Emergency Diesel Generator Cabinets.Initially Reported on 850403.Design Change Package 7079 Prepared to Increase & Redirect Airflow.Next Rept Will Be Submitted by 851101
ML20137V233
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/13/1985
From: Martin T
Public Service Enterprise Group
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8510030422
Download: ML20137V233 (2)


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Pubhc Service Electric and Gas Company Thomas J. Martin 80 Par k Plaza, Nw. ark, NJ 07101 201-430-831G Mailing Address. P.O. Box 670, Newark, NJ 07101 Vice President Engineenng and Construction September 13, 1985 i

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i Dr. Thomas E.

Murley, Administrator U.

S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue j

King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

i SIGNIFICANT CONSTRUCTION DEFICIENCY HEAT BUILD-UP IN EDG CABINETS HOPE CREEK GENERATING STATION I

On April 3, 1985, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr.

E.

l Kelly, advising of a significant construction deficiency I

concerning heat build-up due to three (3) transformers mounted inside the Generator Control Cabinets.

On May 6 and August 7, 1985, interim reports were sent to your 1

office.

The following interim report is provided in i

accordance with 10CF250.55(e).

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Onsite tests confirm that temperatures within the Hope Creek generator potential and excitation control panels, as designed, would exceed the qualified limits of the exciter 4

i transformer insulation.

Failure of the insulation would short circuit the transformer coil resulting in loss of j

excitation current to the generator.

Loss of power from the j

Emergency Diesel Generators would adversely affect safe i

shutdown of the plant under emergency conditions.

We there-j fore consider the subject condition to be reportable in accordance with 10CFR50.55(e).

In accordance with Colt Industries' recommendations, we plan to replace the center current transformer (CT) with a CT that presents a larger surface area to the airf1qw and Bechtel has prepared Design Change Package No. 7079 to increase and redirect the airflow through the control

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panel.

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Dr.

T.

E.

Murley 2

9/13/85 We expect to provide you with a final report on this issue by November 1, 1985.

Very truly yours, C

Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D.

C.

20555 NRC Resident Inspector - Hope Creek P.

O.

Box 241 Hancocks Bridge, NJ 08038 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339 l