ML20211H384
| ML20211H384 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/05/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| (CDR-83--14), (CDR-83-00-14), SBN-1091, NUDOCS 8606230498 | |
| Download: ML20211H384 (3) | |
Text
.
W r"S SFABROOK STATION Enginrering Offico PENHI June 5, 1986 SBN-1091 Public Service of New Hampshire T.F.
Q2.2.2 NEW HAMPSHIRE YANKEE DIVISION 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 July 14, 1983, A. L. Legendre (YAEC) to Eugene Kelley (NRC, Region I)
(c) PSNH Letter (SBN-669), dated June 19, 1984,
" Interim 10CFR50.55(e) Report:
Service Air System NNS Supports", J. DeVincentis to R. W.
Starostecki Subj ect :
Final 10CFR50.55(e) Report:
Service Air System NNS Supports (CDR 83-00-14)
Dear Sir:
In Reference (b), we reported a potential 10CFR50.55(e) deficiency regarding supports for the Service Air System and other systems which carry a Non-Nuclear Safety (NNS) designation.
Because of the proximity to safety-related equipment, the proper classification should have been Non-Nuclear Seismic (NNS-1), whereby the structural integrity of a support during seismic / operating event is assured.
The following corrective action for all pipe supports that did not meet NNS-1 pipe support criteria has been completed:
1.
All affected lines were reviewed to determine whether the supports should be NNS or NNS-1.
Basic criteria used in this review was to avoid any adverse impact on the safety related systems, components or structures.
gRO6230498 860605 8
ADDCK 05000443 PDR Seabrook Station Construction Field Office. P.O. Box 700 Seabrook, NH 03874 $('
'j
'o 2,
United States Nuclear Regulatory Commission Attention:
Mr. R. W. Starostecki Page 2 2.
Pipe analysis was reviewed and/or revised using the latest available design information such as ARS, field change etc.,
to assure that the stresses are within the allowable limits.
New support loads were generated when reanalysis was required.
3.
Support designs were reviewed using the following information:
a) Latest loads and classification based on piping analysis and review.
4 I
b) All change documents.
4.
Where required, the support classification was changed, support modifications were made, and drawings were issued for construction.
As such, this is considered our final report on this item.
l Very truly yours, 3
ohn DeVincentis Director of Engineering cc: Atomic Safety and Licensing Board Service Lis t 4
Director, Of fice of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 1
1 i
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