ML021210583
| ML021210583 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/25/2002 |
| From: | Bergendahl H FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2768 | |
| Download: ML021210583 (3) | |
Text
FENOC Davis-Besse Nuclear Power Station 5501 North State Route 2 S~
Oak Harbor, Ohio 43449-9760 FirstEnergy Nuclear Operating Company Howard W. Bergendahl 419-321-8588 Vice President - Nuclear Fax: 419-321-8337 Docket Number 50-346 License Number NPF-3 Serial Number 2768 April 25, 2002 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 Thirteenth Refueling Outage 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. License Condition 2.C(7) requires the FirstEnergy Nuclear Operating Company (FENOC) to report to the Nuclear Regulatory Commission (NRC) information related to specific indications identified during inservice inspection of steam generator tubes. This letter satisfies License Condition 2.C(7) in its entirety for the inspections performed during the recent thirteenth refueling outage. No supplemental report will be provided. The information specified by the license condition is provided below:
- a. No License Condition 2.C(7) indications were found inboard of any installed repair roll.
- b. Three tubes had License Condition 2.C(7) indications in the heat affected zone adjacent to the tube-to-tubesheet seal weld in the upper tubesheet. These three tubes were repaired by repair roll in accordance with Technical Specification 4.4.5.4 requirements.
- c. Based on the License Condition 2.C(7) indications identified, no leakage from any such indication in the original tube-to-tubesheet rolls, tube-to-tubesheet re-roll repairs, and heat affected zones of seal welds would be expected following a large-break loss-of-coolant accident (LBLOCA).
The best-estimate primary-to-secondary leakage following a LBLOCA has been determined to be 0.00 gpm. Accordingly, the off-site dose consequences from a LBLOCA would be below 10 CFR Part 100 limits.
Docket Number 50-346 License Number NPF-3 Serial Number 2768 Page 2 Should you have any questions or require additional information, please contact Mr. David H.
Lockwood, Manager - Regulatory Affairs, at (419) 321-8450.
Very truly yours, MAR Enclosure cc:
J. E. Dyer, Regional Administrator, NRC Region III S. P. Sands, DB-1 NRC/NRR Project Manager C. S. Thomas, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 Serial Number 2768 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-BESSE NUCLEAR POWER STATION (DBNPS) IN THIS DOCUMENT. ANY OTHER ACTIONS DISCUSSED IN THE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY THE DBNPS. THEY ARE DESCRIBED ONLY FOR INFORMATION AND ARE NOT REGULATORY COMMITMENTS. PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8450) AT THE DBNPS OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.
Commitment Due Date None N/A