ML20003C358
| ML20003C358 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/03/1980 |
| From: | Martin T Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20003C315 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8102270823 | |
| Download: ML20003C358 (2) | |
Text
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mes J. Martin Public Service Electric and Gas Company 80 Park P4ce Newark,.;.J. G/101 201/430-8316 Vice Pres 4ent Engineering and Construction December 3, 1980 Mr. Boyce H. Grier, Director U.
S. Nuclear Regulatory Commission Office of Inspection & 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 Op March 26, 1980, a verbal report was made to Region 1, Office of Incoection and Enforcement representhtive, Mr. A. Cerne, advising of & potential significant item regarding the primary containment vacuum relief valves supplied by GPE Controls.
Supplemental infor-mation has been submitted in writing to your office indicating that the analysis of this potential deficiency was continuing.
The rost recent submittal was dated October 24, 1980.
The following addresses the question of reportability in accordance with 10CFR50.55(e):
Bechtel Power Corporation's Engineering Department has assessed the subject potential design deficiency and specification nonconformance identified by GPE Controls in their Model LD240-447 primary contain-ment vacuum relief valyes supplied to Hope Creek.
This potential deficiency was discovered during a review of their design analysis report and involved the bolting on the pallet hinge mounting block.
This bolting is subjected to shear stresses during LOCA conditions, concurrent with a seismic event, which might exceed stress allowables.
Bechtel requested that GPE Controls submit certified stress / seismic analysis for the mounting block bo?. ting, which was not included in prior vendor document submittals.
The requested documentation was 3102 270 gg _y
Boyce H.
Grier 12/3/80 received and' reviewed and it was concluded thdt the subject bolting is designed within appropriate stress allowables and in conformance with Specification 10855-M-150(Q).
Therefore, safe plant operation is not adversely affected and no further corrective action is required.
As such, PSE&G withdraws the item as not reportable under 10CFR50.5S(e) and therefore. considers this matter closed.
Should additional information be desired, we will be pleased to further discuss it with you.
Very truly yours, l
CC Office of Inspection & Enforcement Div. of Reactor Construction Inspection Washington, DC l
l L