ML19330B281

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Potential Significant Deficiency Rept Re Primary Containment Relief Valves Supplied by Gpe Controls.Bechtel Has Completed Review of Revised Stress Analysis Calculations.Expected Completion Date of Actions Is 800815
ML19330B281
Person / Time
Site: Hope Creek  PSEG icon.png
Issue date: 06/25/1980
From: Martin T
Public Service Enterprise Group
To:
Shared Package
ML19330B279 List:
References
NUDOCS 8007310293
Download: ML19330B281 (1)


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O Thomas J. Martin Public Service Electric and Gas Company 80 Park Pir.ce Newark, N.J. 07101 201/430-8316 Vice Fresdent Engineenng and Construction June 25, 1980 Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforch'ent Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

PRIMARY CONTAINMENT RELIEF VALVES 10 CFR50. 55 (e), POTENTIAL SIGNIFICANT DEFICIENCY NO. 1 UNIT HOPE CREEK GENERATING STATION On March 26, 1980 a verbal report was made to Region 1, Office of Inspection and Enforcement representative, Mr. A. Cerne advising of a potential significant item regarding the primary containment relief valves supplied by GPE Controls.

Supplemental information was submitted in writing to Region 1, Office of Inspection and Enforcement on April 25, 1980 and May 23, 1980 with the indication that the analysis of the potential problem was continuing.

The following is an interim report concerning the potential design defici,'cy in the primary containment relief valves, GPE Controls Model LD240-447.

Bechtel Power Corporation, PSE&G's Architect Engineer, has completed a review of the revised stress analysis calculation submitted by GPE Controls.

Results of the review revealed calculation assumptions which require further justification by GPE Controls.

The expected completion date of actions to finalize the review of the potential significant deficiency is August 15, 1980.

Very truly yours, 7

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l CC: Office of Inspection & Enforc ent Div. of Reactor Const. Inspe tion Washington, D.C.

, 8007310273 t

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