ML20062H322

Interim Deficiency Rept Re Deleterious Effects Corrosion Inhibitors Have on Solder Used to Stake Locking Nuts on Thermostatic Valve Override Assemblies.Initially Reported on 820702.Final Rept Expected by 820924

ML20062H322
Person / Time
Site:	Hope Creek, 05000355
Issue date:	08/02/1982
From:	Martin T Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8208160016
Download: ML20062H322 (2)

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e ODR 08 -07 Thomas J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430B316 Vice Presient Engineering and Construction August 2, 1982 Mr. Ronald C. Ilaynes, 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 HOPE CREEK GENERATING STATION On July 2, 1982, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. R. Keimig, advising of a potential significant construction deficiency concerning the deleterious effects corrosion inhibitors may j have on solder used to stake locking nuts on thermostatic valve override assemblies. The following information is provided in accordance with the requirements of 10CFR50.55 (e) .

By letter dated June 28, 1982, Colt Industries reported to the NRC in accordance with 10CFR21 that solder used to stake nuts on the override assembly of Robertshaw thermostatic valves, used in the cooling system of Colt's diesel engines, can be attacked by corrosion inhibitors. This could result in valve failure.

Bechtel Power Corporation is investigating the safety implica-i tions of this condition postulating valve failure. Colt's concerns are based on possible engine damage due to over cooling if a thermostatic valve " fails safe" to its full cooling position.

Bechtel has requested additional information from Colt Industries for their study. Bechtel has committed to complete their safety analysis by September 10, 1982.

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8208160016 820802 16 PDR ADOCK 05000354 S PDR

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i R. - C. Ilaynes 2 8/2/82 L

A final report conveying the requisite safety analysis and full details concerning our corrective actions will be submitted to your office by September 24, 1982. l

< Very truly yours,  !

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

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

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