ML20079P721
| ML20079P721 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 11/06/1991 |
| From: | Chrzanowski D COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19353B277 | List: |
| References | |
| IEB-88-002, IEB-88-2, NUDOCS 9111130265 | |
| Download: ML20079P721 (3) | |
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Downers Grove, Illinois 60515 November 6,1991 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Transmittal of WCAPs Providing Fatigue Evaluation of Byron and Braidwood Steam Generator Tubes for Bulletin 88-02 Byron Units 1 and 2, NRC Docket Numbers 50-454/455 Braidwood Units 1 and 2, NRC Docket Numbers 50-456/457 (b)
NRC Bulletin 88-02, dated Februay 5,1988.
References:
a)
(
W. Morgan (CECO) letter to A. Davis (NRC), dated April 18, 1988.
(c)
W. Morgan (CECO) letter to A. Davis (NRC), dated July 20, 1988 (d)
M. Richter (CECO) letter to NRC dated October 17,1989
Dear Dr. Murley:
Reference (a) requested that holders of operating licenses or construction aermits for Westinghouse designed nuclear power reactors with steam generators laving carbon steel support plates implement actions to minimize the potential for a steam generator tube rupture event caused by a rapidly propagatir.g iatigue crack such as occurred at North Anna Unit 1. References (b) and (c) presented Commony.ealth Edison's (Edison's) previous responses for Byron and Braldwood Stations to Reference (a). Reference (d) provided information regarding the definition of denting in Byron /Braidwood steam generators. This letter is transmitting the results of the Westinghouse analysis and the subsequent corrective actions related to the Byron and Braidwood steam generators.
Enclosed are:
1.
2 copies of WCAP-12608," Byron Unit 1 and Braidwood Unit 1 Evaluation for Tube Vibration Induced Fatigue"(Proprietary).
2.
1 copy of WCAP-12609," Byron Unit 1 and Braidwood Unit 1 Evaluation for Tube Vibration Induced Fatigue"(Non-Proprietary).
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Dr. Thomas E. Murlay Novemb:r 6 1991 As a result of this analysis, two tubes were found to be susceptible to potential fatigue at the top support p; ate as a result of misplaced anti-vibration bars.
These tubes are R12C8 in steam generator C of Byron Unit 1 and R12C5 In steam generator B of Braidwood Unit 1. Based upon the requirements of I&E Bulletin 88 02, a modification was initiated to assure that these tubes will not fall in service nor be allowed to interact with adjacent tubes.
This modification invoved installing a cable damper in the tubes and removing the tubes from service by plugging. This modification is complete at Byron and Braldwood. The report and follow up modificatlun fulfills the Commonwealth Edison requirements identified by the NRC in l&E Bulletin 88-02 for Byron and Braidwood.
Also enclosed are a Westinghouse authorization letter, CAW-91-221, accompanying affidavit, Proprietary Information Notice, and Copyright Notice.
As item 1 contains ir.'ormation 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 address 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 ot the Commission's regulations.
Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-91-221 and should be addressed to R.P. DiPla:c, Manager of Nuclear Safety Licensing, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
If there are any questions or comments, please contact me at (708) 515 7292.
Sincerely, I
l wy David J. Chrzanowski Nuclear Licensing Administrator Generic issues
- Westinghouse Authorization Letter CAW-91-221 - WCAP-12608 - WCAP-12609 cc: A. Bert Davis, Regional Administrator - Rlli w/o attachment R. Pulsifer, F toject Manager - NRR/PDlll-2 w/o attachment act Manager - NRR/PDill 2 w/o attachment A. Hsia, Pro'oject Manager - NRR/PDlli 2 w/o attachment R. Elliott, Pr S. DuPont, Senior Resident inspector (Braidwood) w/o attachment W. Kropp, Senior Resident inspector (Byron) w/o attachment ch:1066/6
ATTACliMENT 1 WESTINGiiOUSE LETTER CAW-91-221 8
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