ML20217G569
| ML20217G569 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/23/1998 |
| From: | Krich R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217G571 | List: |
| References | |
| NUDOCS 9804290166 | |
| Download: ML20217G569 (2) | |
Text
i Commonwealth rdiwn Company l*K) Opus Pl.u e Dow nen Gan e, IL 60515-5 01 l
April 23,1998 1
U. S. Nuclear Regulatory Commission Washington, D.C. ' 20555 Attention: Document Control Desk
Subject:
Annual 10 CFR 50.46 Report Byron Nuclear Power Station Units 1 and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 Braidwood Nuclear Power Station Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457 This letter fulfills the Annual reporting requirement of 10 CFR 50.46(a)(3)(ii) for Units 1 and 2 of the Braidwood and Byron Nuclear Power Stations. Per the reporting requirements this report is being submitted by April 23,1998. provides updated information regarding the Peak Cladding Temperature (PCT) of the limiting Small Break and Large Break Loss of Coolant Accident analysis evaluations for Braidwood and Byron Stations. Attachment 1 includes all assessments as of April 1,1998. Attachment 2 contains a detailed description for each change or error reported. Attachment 3 contains a brief description ofitems that were evaluated and are not included in the PCT rack up sheets.
Westinghouse has notified Comed that there are no new issues, with the exception of the 31 ant specific evaluations in attachment 3 that affect PCT for both the large and small areak LOCA analyses for Braidwood and Byron Stations. Comed has reviewed the Westinghouse annual 1997 letter and concurs with Westinghouse's conclusions. For all the discrepancies contained in this report, Westinghouse and Comed have determined that these issues do not constitute substantial safety hazards, and that all Comed plants continue to comply with the requirements of 10 CFR 50.46 and 10 CFR 50 Appendix K acceptance criteria. Because compliance with 10 CFR 50.46 is maintained with existing PCT penalties, no near term reanalysis is planned for these Units.
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USNRC April 23,1998 Please direct any questions to this omce.
Sincerely, R.M. Knch Vice President Nuclear Regulatory Services i
. Attachments cc:
- Regional Administrator-Region 111 Senior Resident inspector - Braidwood Senior Resident inspector - Byron Omce of Nuclear Safety -IDNS j
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