ML18095A929

Provides plant-specific Analysis & Addl Evaluations Necessary to Complete Response to NRC Bulletin 88-11 Re Pressurizer Surge Line Thermal Stratification

ML18095A929
Person / Time
Site:	Salem
Issue date:	05/15/1991
From:	Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-011, IEB-88-11, NUDOCS 9105220118
Download: ML18095A929 (3)

Text

• Public Service Electric and Gas Company Thomas M. Crimmins, Jr. Public Service Electric and Gas Company P.O. Box 236, HancocksBridge. NJ 08038 609-339-4700 Vice President - Nuclear Engineering

. MAY 1 5 1991 NLR-N91083 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NRC BULLETIN 88-11 PRESSURIZER SURGE LINE THERMAL S~RATIFICATION SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311

~y letter dated March 27, 1991, the NRC transmitted to Public Service Electric & Gas Company (PSE&G),* .the Safety Evaluation Related to Westinghouse Owners Group Pressurizer Surge Line Thermal Stratification .Generic Detailed Analysis, WCAP-12639.

Salem Unit Nos. 1 and 2 were two of the plants noted that demonstrated acceptable stress fatigue in the surge line. PSE&G hereby submits the plant specific analysis and additional evaluations necessary to complete our response to NRC Bulletin 88-11.

The required analys.is has been completed by *westinghouse Electric Corporation and is documented in WCAP~12913. (non-proprietary) and WCAP-12914 (proprietary), structural Evaluation of Salem Nuclear Plant Units 1 and 2 Pressurizer Surge Lines, Considering the Effects of Thermal Stratification.

The- existing configurations for both Salem Unit Nos. 1 and 2 have been analyzed. The results indicate small contacts at one pipe whip restraint and "bottoming out" of variable spring-.hangers for the 320°F differential temperature. ASME Code allowables were shown to be exceeded for both Salem units under the existing configurations. However, by taking credit for insulation crushability and modifying spring hangers to avoid bottoming out", the ASME Code stress limits and cumulative usage factor

-requirements have been shown to _be acceptable for the remainder of the licensed operation for both units. No whip restraint gap modifications are necessary to show Code acceptance, if the spring can travel allowances are _satisfied.

9105220118 910515 PDR ADOCK 05000272 P PDR

atty 1 '5 1991 Document Control Desk 2 NLR-N91083 The analysis has concluded that Salem Nos. 1 .and 2 are in full compliance with the requirements of NRC Bulletin 88-11, provided the required spring hanger modifications are implemented. PSE&G will submit _within 30 days, a schedule for completion of the required modifications.

In view of the Salem specific analysis, the existing Justification for Continued Operation (JCO), dated May 31, 1989, (ref: NLR-N89069) which was based on the assessment without detailed reanalysis, is still valid. The modifications will be completed prior to exceeding the ten heatup and cooidown cycles referenced in the JCO.

• contains WCAP-12913 and Enclosure 2 contains WCAP-12914. Enclosure 2 contains Westinghouse proprietary information and should therefore be withheld from public

• disclosure and should not be reproduced, pursuant to 10CFR2.790.

An affidavit declaring Enclosure 2 information proprietary is contained as Attachment 1.

Should there be any questions with regard to this submittal, please do not hesitate to contact us.

Sincerely, Attachment Enclosures (2)

mA'Y' 115~ 199\

Document Control Desk 3 NLR-N91083 c Mr. J. c. stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625