ML20235Y315
| ML20235Y315 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/07/1989 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19302D655 | List: |
| References | |
| IEB-88-011, IEB-88-11, NYN-89023, NUDOCS 8903140065 | |
| Download: ML20235Y315 (5) | |
Text
.
George S. Thomas '
Vice President Nucleor Production a
L1
' Pubuc Service of New Hampshire
, NGw Hampshire Yankee Division NYN-89023 March 7, 1989 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
References:
(a)
Facility Operating License NPF-56, Docket No. 50-443 (b) NRC Bulletin No. 88-11 dated December 20, 1988,
" Pressurizer Surge Line Thermal Stratification" (c)
PSNH Letter NYN-88163 dated December 27, 1988, ' Interim Response to NRC Bulletin 88-11:
Pressurizer Surge Line Thermal Stratification," G. S. Thomas to USNRC i
(d)
PSNH Letter NYN-88164 dated December 30, 1988, " Interim Response to NRC Bulletin 88-11:
Pressurizer Surge Line Thermal Stratification," G. S. Thomas to USNRC
Subject:
Response to NRC Bulletin 88-11:
Pressurizer Surge Line Thermal Stratification f
Gentlemen This letter presents the results of a study to estinate the effect of thermal stratification on the Seabrook Station pressurizer surge line and to qualitatively evaluate ASME Code compliance of the Seabrook surge line under I
thermal stratification loading conditions. The study reviewed Seabrook Station operating procedures', thermal monitoring data, and the details of surge line piping, support and restraint design and compared these to several other plants which have undergone detailed analysis.
In addition, a limited plant-specific piping structural analysis was completed.
The study was performed by Westinghouse Electric Co., a firm which has considerable experience in pressurizer surge line thermal stratification definition and stress analysis.
The proprietary report which provides the results of the study, Westinghouse WCAP 12151: Assessment of Thermal Stratification for the Seabrook Unit 1 Pressurizer Surge Line, is provided in Enclosure 1.
Enclosure 2, Westinghouse WCAP 12152: Assessment of Thermal Stratification for the Seabrook Unit 1 Pressurizer Surge Line, is the non-proprietary version of this same report.
A g,[
8903140065 89030 ADOCK0500g443 b
y[
DC 0
/N DR lI O
/ /y P O. Box 300. Seabrook, NH 03874. Te.
.one (603) 474-9574 i
i United States Nuclear Regulatory Commission March 7, 1989 Attention:
Document Control Desk Page 2 The review of Seabrook Station operating procedures and thermal monitoring data has resulted in the conclusion that the expected thermal transient severity for the Seabrook surge line will not exceed the parameters used to perform plant-specific analyses for other nuclear units. The review of the Seabrook surge line piping configuration and related design details res'alted in the conclusion that pipe expansion stresses under stratification should not exceed the limits of the ASME Code.
The review of the Seabrook surge line support and whip restraint design resulted in the judgment that support capacities will not be exceeded and that whip restraints will not impede vertical motion due to thermal stratification.
Additionally, the results of the limited plant-specific piping structural analysis provided the bases to conclude that a detailed analysis of the Seabrook surge line should o result in pipe stresses below the ASME Code allowable limits, o demonstrate that limiting element (o) of the surge line would be shown to be acceptable for fatigue, and o indicate that support modifications are not needed.
I During the next heatup, Seabrook surge line temperature and displacement data will be recorded. This data will be provided to Westinghouse for use in the Westinghouse Owner's Group Surge Line Stratification Generic Program. As discussed recently with the NRC Staff, two additional temperature monitoring locations have been instrumented with four temperature detectors. A revised isometric drawing showing the location of all surge line monitoring and displacement points is provided in Enclosure 3.
A detailed quantitative plant-specific surge line piping structural analysis which considers the effects of thermal stratification and striping will be submitted by June 30, 1989. This analysis will serve as the basis for updating the record ASME Code Class 1 stress and fatigue analysis.
The update will be completed within one year following issuance of a low power license.
In summary, NHY believes that the enclosed qualitative evaluation and limited plant-specific structural analysis demonstrate that the Seabrook surge line will meet ASME code limits for the life of the plant.
The detailed quantitative plant-specific structural analysis considering the effects of l
thermal stratification and striping will confirm that fatigue and stresses are in compliance with ASME code limits.
Westinghouse authorization letter, CAW-89-025, Proprietary Information Notice, and accompanying Affidavit are provided in Enclosure 4.
United States Nuclear Regulatory Commission March 7, 1989 Attention:
Document Control Desk Page 3 As Westinghouse Report WCAP 12151 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragragh (b)(4) of Section 2.790 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse Affidavit should reference CAW-89-025 and should be addressed to R. A. Wiesemann, Manager of Regulatory &
Legislative Affairs, Westinghouse Electric Corporation P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Should you have any questions regarding this matter, please contact Mr. Joe Vargas at (603) 474-9574, extension 2776.
Very truly yours,
- W -t m
Georg S. Thomas Enclosures cc Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects i
Washington, DC 20555 l
l Mr. David G. Ruscitto i
NRC Senior Resident Inspector l
P.O. Box 1149 Seabrook, NH 03874 1
l STATE OF NEW HAMPSHIRE l
1 Rockingham, s8.
March 7, 1989 Then personally appeared before me, the above-named George S. Thomas who,
.being duly sworn, did state that he is Vice President - Nuclear Production of j
Public S;rvice Company of New Hampshire, that he is duly authorized to execute and file the foregoing information in the name and on the behalf of Public-Service Company of New Hampshire, and that the statements therein are true to the best of his knowledge and belief.
iiutlo b DMutu.A Beverly E. S4jloway, Notary Pubj)ic My Commission Expires: ' March 6, 1990 i
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