ML20246D996

Forwards Proprietary WCAP-12305 & Nonproprietary WCAP-12306, Evaluation of Thermal Statification for Seabrook Unit 1 Pressurizer Surge Line, in Response to NRC Bulletin 88-011. Proprietary Rept Withheld (Ref 10CFR2.790(b)(4))

ML20246D996
Person / Time
Site:	Seabrook
Issue date:	06/30/1989
From:	Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19312B348	List: ML20246D996 ML20246E027 ML20246E045
References
IEB-88-011, IEB-88-11, NYN-89077, NUDOCS 8907120061
Download: ML20246D996 (4)

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N$w Hampshire Ted C. Feigenbaum Vice President NYN-89077 June 30, 1989 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

References:

a) Facility Operating License NPF-67. Docket No. 50-443 b) NRC Bulletin 88-11 dated December 20, 1988, " Pressurizer Surge Line Thermal Stratification" c) NHY Letter NYN-89023 dated March 7, 1989, " Response to NRC Bulletin 88-112 Pressurizer Surge Line Thermal Stratification," G. S. Thomas to USNRC

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Subject:

- Follow-up Response to NRC Bulletin 88-11: Pressurizer Surge Line Thermal Stratification Gentlemen:

• This letter presents the results of a detailed quantitative plant-specific stress analysis of the Seabrook Station pressurizer surge line in response to NRC Bulletin 88-11, and as committed to by New Hampshire Yankee (NHY) in Reference (c). This analysis is based upon plant-specific operating procedurer, thermal rncnitoring data, sur.y line piping and pipe support danign, and incitides the effects of therral stratification and q

striping. The proprietary report which provides the results of this strear analys;it, Westinghouse WCAPe 12305, " Evaluation cf Thermal Stratification for the inbrook Unit 1 Pressw.dze.* Surge Line" is provided in Enclosure 1.

Encitare 2. Westinghouse WCAP-12306, " Evaluation of Thermal Stratification for the Seabrook Unit 1 Pressurizer Surge Line" is the non-proprietary version of this sehe report.

The results of this strces aoslysis, which addresses the effects cf thermal stratif$ cation and striping, demonstrate that l

the Seabrook Station surge lirie pipe stresses are below the ASME Code allowable limits.

all elements of the Seabrook Station surge line meet the ASME Code fatigue limits.

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modifications'are not required to the Seabrook Station surge line pipe supports and whip restraints.

l 8907120061 890630 ~

JEJo PDR 0 ADOCK 05000443 FDC

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OWCe : isoft New Hampshire Yankee Division of Public Service Company of New Hampshire ^'M P.O. Box 300

• Seabrook, NH 03874

• Te'ephone (603) 474-9521 ^"O g

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United States Nuclear Regulatory Commission June 30, 1989 Attention: Document Control Desk Page 2 During the two most recent plant heatup operations, Seabrook Station surge line temperature and displacement data were recorded and provided to Westinghouse for evaluation. Westinghouse has compiled monitoring data on

five other nuclear units, exclusive of Seabrook Station, from which they have developed a bounding transient set defining the stratification phenomenon. This bounding transient set is utilized to develop the thernal stresses in the enclosed report. The Seabrook Station plant-specific data are within the envelope established by the bounding transient. set.

During the power ascension phases of the Startup Testing Program, the surge line temperature and displacement will be recorded and the data will be provided to Westinghouse to confirm that the plant-specific temperature and displacement measurements during various operating transients remain within the limits of the bounding transient set.

The stress analysis provided in Enclosures 1 and 2 will serve as the basis for updating the record ASME Code Class 1 stress and fatigue analysis.

-This update is scheduled to be completed by April 30, 1990, in compliance with Reference (b.'.

In summary, the enclosed plant-specific stress analysis demonstrates that thermal' stratification does not effect the integrity of the Seabrook Station pressurizer surge line. The surge line design complies with the ASME Code requirements for the life of the plant.

'l Westinghouse authorization letter, CAW-89-083. Proprietary Information Notice, and accompanying Affidavit are provided in Enclosure 3.

As Westinghouse 9 Report WCAP-12305 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidt.vit signed by Westinghsase, the owner of the information. The affidavit Jets forth the basis on which the inforaction umy be withheld from public Gas:losure by the Commission and addresses with specificity the considerations listed in paragraph (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-69-083 and should be addressed to R. A. Wiesemann, Manager of Regulatory & Legislative Affairs, Westinghouse Electric Corporation, P.O.

Box 355, Pittsburgh, Pennsylvania 15230-0355.

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' United States Nuclear Regulatory Commission - June.-30, 1989-n '. Attentions- Document Control Desk. Page 31 L

. Should you have any questions regarding~this matter, please contact

Mr. Joe Vargas at (603) 474-9521, extension 2776.

Very truly yours, i.

9 \

Ted C. Feigenbaum Enclosures.

cc - Mr. William T.; Russe 11' 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-Washington..DC 20555

'NRC Senior Resident Inspector P.O.-Box 1149 Seabrook Station, NH 03874 f

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ENCLOSURE 2 TO NYN-89077 WCAP-12306

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