05000260/LER-2023-001, Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line
| ML23109A362 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/19/2023 |
| From: | Sivaraman M Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LER 2023-001-00 | |
| Download: ML23109A362 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
| 2602023001R00 - NRC Website | |
text
Post Office Box 2000, Decatur, Alabama 35609-2000 April 19, 2023 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260 Subject:
Licensee Event Report 50-260/2023-001-00 Reference:
Non-Emergency Event Notification 56371 - Degraded Condition The enclosed Licensee Event Report provides details of a pressure boundary leak on Browns Ferry Nuclear Plant, Unit 2. 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; and 10 CFR 50.73(a)(2)(ii)(A), as any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
There will be a supplement to this Licensee Event Report to provide additional time to obtain failure analysis results for the drain line associated with 2-FCV-68-3.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Christopher L. Vaughn, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, Manu Sivaraman Site Vice President Enclosure: Licensee Event Report 50-260/2023-001 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line p
y,
U.S. Nuclear Regulatory Commission Page 2 April 19, 2023 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 2 Licensee Event Report 50-260/2023-001-00 Pressure Boundary Leak on Recirculation Pump Discharge Isolation Valve Drain Line See Enclosed
Abstract
On February 17, 2023, during a drywell entry for leak identification, BFN personnel discovered a cracked weld on the 2A Recirculation Pump discharge isolation valve drain line. On February 18, 2023, at 0439, it was determined that this drain line was classified as American Society of Mechanical Engineers Code Class I piping and constitutes part of the BFN, Unit 2 Reactor Coolant System pressure boundary. Operations personnel maintained BFN, Unit 2 in Mode 4 or 5 until the leak was repaired. On February 18, 2023, at 1025 CST, eight-hour Event Notification 56371 was made to the NRC. On March 19, 2023, work was completed to remove and replace the drain line.
There will be a supplement to this Licensee Event Report to provide additional time to obtain failure analysis results for the drain line associated with 2-FCV-68-3.
Page 7 of 7 This event was reported to the NRC under Licensee Event Report (LER) 50-259/2022-001 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line.
- 2. On December 2, 2022, at 2330 CST, during a drywell entry for leak identification, BFN Engineering personnel discovered a through-wall piping leak on a test line between the two RHR Shutdown Cooling test line isolation valves. On December 3, 2022, at 1000, it was determined that this test line was classified as ASME Code Class 1 piping and constitutes part of the BFN, Unit 3 RCS pressure boundary.
The root cause of the event has not yet been determined.
This event was reported to the NRC under LER 50-296/2022-003 Pressure Boundary Leak on Residual Heat Removal System Low Pressure Coolant Injection Test Line VIII. Additional Information There is no additional information.
IX.
Commitments There are no new commitments.