ML20132E431
| ML20132E431 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/18/1985 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| (CDR-85--5), (CDR-85-00-05), SBN-830, NUDOCS 8507170704 | |
| Download: ML20132E431 (2) | |
Text
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SEABROOK STATION Engineering Office Pub 5c Service of New HampeNro Now Hampshire Yankee Division June 18, 1985 S BN-830 T.F. Q2.2.2 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention:
Mr. Richard W. Starostecki, Director Division of Project and Resident Programs
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Telecon of March 15, 1985, V. L. K111 pack, Jr. (YAEC) to J. Beall (Region I)
(c) PSNH Letter SBN-792, dated April 18,1985, " Interim 10CFR50.55(e) Report, Limit Switch Brackets for Valves 1-SI-V-89, 90 and 93," J. DeVincentis to R. W. Starostecki (d) PSNH Letter SBN-813, dated June 3,1985, " Interim 10CFR50.55(e) Report, Limit Switch Brackets for Valves 1-SI-89, 90 and 93," J. DeVincentis to R. W. Starostecki (e) Westinghouse Letter NAH-U-3351, dated May 9,1985, "SI Valve Limit Switch Brackets," D. R. Gregg to D. D. Boyle
Subject:
Final 10CFR50.55(e) Report, Limit Switch Brackets for Valves 1-SI-V-89, 90 and 93 (CDR-85-00-05)
Dear Sir:
We previously reported [ Reference (d)], a potential 10CFR50.55(e) item to Region I regarding the perceived uncertain structural integrity of the limit switch brackets on three Westinghouse valves.
Per Reference (e), Westinghouse has performed detailed calculations which have indicated that, contrary to the initial judgment, the subject brac ke t s are capable of performing their safety-related function with the as-delivered j
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PER P.O. Box 300 + Seabrook NH 03874. Telephone (603)474-9521 Lg 8' j
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United States' Nuclear Regulatory Commission June 18, 1985 Attention:
Mr. Richard W. Starostecki, Director Page 2 design. Therefore, based on the results' of Westinghouse's investigation, we have determined that this item is not a reportable deficiency in accordance
- with 10CFR50.55(e) criteria.
This is our final report on this item.
Very truly yours, 49 4 John DeVincentis, Director Engineering and Licensing cc: Atomic Safety and Licensing Board Service List Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 L