05000296/LER-2024-004, Browns Ferry Nuclear Plant, Unit 3, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping
| ML24339B794 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/04/2024 |
| From: | Komm D Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LER 2024-004-00 | |
| Download: ML24339B794 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2962024004R00 - NRC Website | |
text
Post Office Box 2000, Decatur, Alabama 35609-2000 December 4, 2024 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
Licensee Event Report 50-296/2024-004-00 The enclosed Licensee Event Report provides details of the Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping. The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.73(a)(2)(i)(B), as any operation or condition which was prohibited by the plants Technical Specifications.
There will be a supplement to this Licensee Event Report to provide additional time to complete the cause evaluation.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David J. Renn, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, Daniel A. Komm Site Vice President Enclosure: Licensee Event Report 50-296/2024-004 Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant
ENCLOSURE Browns Ferry Nuclear Plant Unit 3 Licensee Event Report 50-296/2024-004-00 Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping See Enclosed
Abstract
On June 3, 2024, an increase in Browns Ferry (BFN) Unit 3 Drywell Unidentified Leakage was identified.
This condition was monitored and trended from June 3, 2024, to October 4, 2024. The unidentified leakage came from two different sources. Prior to shutdown, total drywell unidentified leakage was approximately 1.0 gallon per minute.
On October 5, 2024, at 0456, during the initial drywell entry of BFN Unit 3 Planned Outage 13 for replacement of a suspected defective fuel bundle, the drone operator observed water leaking from the elbow near the 1-inch sensing line off the 3B recirculation pump. In addition to this, the drone operator also observed water leaking from near the 3A recirculation pump vent line on a 3/4-inch elbow.
There will be a supplement to this Licensee Event Report to provide additional time to complete the cause evaluation.
Page 7 of 7 VI.
Corrective Actions
Corrective Actions are being managed by the TVAs Corrective Action Program (CAP) under Condition Reports (CRs) 1963793, 1963794, and 1965828.
A. Immediate Corrective Actions
The leak source documented by CR 1963793 was repaired by WO 124871621, and the other leak source documented by CR 1963794 was repaired by WO 124871622.
B. Corrective Actions to Prevent Recurrence or to reduce the probability of similar events occurring in the future There will be a supplement to this Licensee Event Report to provide additional time to complete the cause evaluation.
VII. Previous Similar Events at the Same Site
A review of the BFN Licensee Event Reports (LERs) for Units 1, 2, and 3 over the last four years revealed three (3) previous, similar events. (LERs 259/2022-001-01, 260/2023-001-01, and 296/2022-003-01).
VIII. Additional Information
There is no additional information.
IX.
Commitments
There are no new commitments.