ML20028D661

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Interim Potential Const Deficiency Rept Re Emergency Diesel Generator O Rings.Initially Reported on 821213.Colt Industries Reported Potential Problem If Cooling Sys Contaminated W/Diesel Fuel.Also Reportable Per Part 21
ML20028D661
Person / Time
Site: Hope Creek, 05000355  PSEG icon.png
Issue date: 01/11/1983
From: Martin T
Public Service Enterprise Group
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8301190343
Download: ML20028D661 (2)


Text

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Thomas J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430B316 Vice Prwdent E ngineering and Construction January ll, 1983 Mr. Ronald C. Haynes, Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

POTENTIAL CONSTRUCTION DEFICIENCY EMERGENCY DIESEL GENERATORS - "0" RINGS HOPE CREEK GENERATING STATION On December 13, 1982, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. L. Tripp, advising of a potentially significant construction deficiency concerning our Emergency Diesel Generators. The following information is provided in accordance with the requirements of 10CFR50.55(e).

By letter dated October 6, 1982, Robertshaw Controls Company reported this problem to Colt Industries and the NRC in accord-ance with 10CFR21. Colt Industries indicated to us that a potential problem exists with Robertshaw thermostatic valves used in the cooling system for diesel generators. If the cooling water becomes contaminated with diesel fuel, an "0" ring in the valve poppet swells and may cause sluggish operation or jamming of the valve.

Bechtel Power Corporation is evaluating the safety implications of this condition postulating cooling water contamination by diesel fuel. Determination of corrective action is pending receipt of detailed instructions from Colt Industries, the manufacturer of our diesel generators.

8301190343 830111 PDR ADOCK 05000354 S PDR p 'g

R. C. Haynes 2 1/11/83 A final report conveying the results of our safety analysis and full details concerning our corrective actions will be submitted to your office by March 15, 1983.

Very truly yours, lI

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

NRC Resident Inspector - Hope Creek P. O. Box 241 Hancocks Bridge, NJ 08038

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