ML051230212
| ML051230212 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/29/2005 |
| From: | Bezilla M FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3147 | |
| Download: ML051230212 (2) | |
Text
FENOC FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, Ohio 43449 Mark B. Bezilla Oce President - Nuclear 419-321-7676 Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 3147 April 29, 2005 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
Subject:
Davis-Besse Nuclear Power Station License Condition 2.C(7) Report for the Mid-Cycle 14 Steam Generator Inspection Ladies and Gentlemen:
This letter is submitted in accordance with the requirements of the Operating License for the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1. DBNPS License Condition 2.C(7) requires FENOC to demonstrate by evaluation that the primary-to-secondary leakage following a large-break loss of coolant accident (LBLOCA), if any, as described in Appendix A to Topical Report BAW-2374, July 2000, continues to be acceptable, based on the as-found condition of the steam generators. The following provides a written summary of this evaluation.
A best estimate evaluation of leakage during a postulated LBLOCA event was performed for all circumferential crack indications discovered during the inspection. There were 11 of these indications estimated to leak in Steam Generator 1 and one in Steam Generator 2. All potential leak paths from these indications were limited by the interfaces between the expanded portions of tubing and the tubesheets. The combined postulated leak rates for these indications were 0.66 gpm for Steam Generator 1 and 0.06 gpm for Steam Generator 2. This leakage would not result in a radionuclide release in excess of 10 CFR Part 100 limits.
- AgoI
Docket Number 50-346 License Number NPF-3 Serial Number 3147 Page 2 No regulatory commitments are made in this letter. Should you have any questions or require additional information, please contact Mr. Henry L. Hegrat, Supervisor - Licensing, at (330) 315-6944.
Very truly yours, MAR cc:
J. L. Caldwell, Regional Administrator, NRC Region III J. B. Hopkins, DB-l NRC/NRR Senior Project Manager C. S. Thomas, DB-I NRC Senior Resident Inspector Utility Radiological Safety Board