ML19323G423
| ML19323G423 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/23/1980 |
| From: | Martin T Public Service Enterprise Group |
| To: | |
| References | |
| NUDOCS 8006020407 | |
| Download: ML19323G423 (2) | |
Text
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.o Thomes J. Martin Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-8316 Vice President Enginenng and Construction May 23, 1980 Mr. Boyce H. Grier, Director U.
S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
PRIMARY CONTAINMENT RELIEF VALVES 10CFR50.55(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 with the indication that the analysis of the potential problem was continuing.
It was reported that expected completion date for the investigation was May 22, 1980.
The following is a second interim report concerning the potential design deficiency in the primary containment relief valves Model LD240-447, supplied by GPE Controls.
The deficiency was discovered during review of the stress analysis report and involved pallet hinge mounting block bolting.
Initial analysis by GPE Controls indicates that hinge block mounting studs have been found not to be stressed above ASME Code allowable stresses, when loaded to design and faulted load limits, specified in the-applicable specification.
GPE Controls is proposing a revised g
stress analysis.
Upon receipt of this analysis, the design adequacy of the mounting bolts and subsequently the reportability under 10CFR50.55(e) will be assessed.
4 79 sik i
8006020401
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Mr. Boyce H. Orier 5/23/80 I
The expected completion date of the review of the potential significant deficiency is June 30, 1980 at which time a report will be made to the NRC.
i Very truly yours, CC:
Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C.
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