ML20072N089

Interim Deficiency Rept Re Possible Lack of Heat Treatment on Stainless Steel Flanges Mfg by Tube-Line Corp.Initially Reported on 830601.Affected Flanges Removed from Svc. Bechtel Providing Analysis.Next Rept by 830815

ML20072N089
Person / Time
Site:	Hope Creek, 05000355
Issue date:	06/30/1983
From:	Martin T Public Service Enterprise Group
To:	Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8307150199
Download: ML20072N089 (2)

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• b& ~ *dCY arf Thomas J. Martin Public Service Ek:ctric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/4304316 Vice Prea. dent Engineering and Constructic,n June 30, 1983 b

Mr. James M. Allgn, Acting Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Allen:

POTENTIAL CONSTRUCTION DEFICIENCY HEAT TREATMENT OF STAINLESS STEEL FLANGES HOPE CREEK GENERATING STATION On June 1, 1983, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. E . C . M cCabe ,

advising of a potentially significant construction deficiency concerning stainless steel flanges manufactured by Tube-Line Corporation that may not have received the requisite heat treat-ment. The following interim report is provided in accordance with the requirements of 10CFR50.55 (e) .

Description of Deficiency Guvon Alloys, Inc. advised Bechtel Power Corporation, our architect / engineer and constructor, that sixty-five (65) stainless steel flanges, manufactured by Tube-Line Corporation, may not have received the required heat treatment (solution anneal). Two (2) heat numbers were affected.

l Corrective Action Bechtel has initiated Nonconformance Report No. 2260 to control the hardware and to document the possible nonconforming condition.

Our current plans call for the removal of the affected flanges from service. No firm date has been established for completing their removal.

8307150199 830630 PDR ADOCK 05000354 S

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i J. M. Allen 2 6/30/83 Analysis of Safety Implications e

A representative sample of each heat will be sent to Bechtel Project Engineering for testing to determine if safe operation of the plant could have been adversely affected, had the condi-tion gone undetected.

A further report will be provided you by August 15, 1983, indicating the status of our investigation, actions taken or scheduled and safety analysis.

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Very truly yours, K

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 I

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