05000390/LER-2025-002, Automatic Reactor Trip Due to Main Turbine Trip
| ML25077A032 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 03/18/2025 |
| From: | Reneau W Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| WBL-25-011 LER 2025-002-00 | |
| Download: ML25077A032 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| 3902025002R00 - NRC Website | |
text
l\\'4 TENNESSEE VALLEY AUTHORITY Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381 WBL-25-011 March 18, 2025 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-96 NRC Docket No. 50-390 10 CFR 50.73
Subject:
Licensee Event Report 390/2025-002-00, Automatic Reactor Trip Due to Main Turbine Trip Pursuant to the reporting requirements of 10 CFR 50. 73, attached is the subject Licensee Event Report (LER) concerning the automatic reactor trip due to a main turbine trip for Watts Bar Nuclear Plant, Unit 1, which occurred on January 17, 2025.
There are no new regulatory commitments contained in this letter. Please direct any questions concerning this matter to Jonathan Johnson, WBN Licensing Manager, at jtjohnsonO@tva.gov.
William C. Renea Site Vice President Watts Bar Nuclear Plant
U.S. Nuclear Regulatory Commission WBL-25-011 Page 2 March 18, 2025 Enclosure: LER 390/2025-002-00, Automatic Reactor Trip Due to Main Turbine Trip cc (w/Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Region II
WBL-25-011 E1 of 1 ENCLOSURE Tennessee Valley Authority Watts Bar Nuclear Plant Unit 1 LER 390/2025-002-00, Automatic Reactor Trip Due to Main Turbine Trip
Abstract
While operating at 100% steady state power, the Watts Bar Unit 1 reactor experienced an automatic reactor trip at 0203 EST on January 17, 2025, in response to a turbine trip.
All control and shutdown bank rods inserted properly in response to the reactor trip. All safety systems including the auxiliary feedwater (AFW) system actuated in response to the trip, as expected. All systems actuated as required and there were no complications with the trip. The plant was stabilized with decay heat removed initially through AFW and then through standby main feedwater (MFW) and the steam dump system.
Notification to the NRC of the reactor trip was made by operations at 0418 EST (Event Notification 57500). The actuation of the reactor protection system (RPS) was reported as a four hour report under 10 CFR 50.72 (b)(2)(iv)(B). The actuation of the AFW system (an engineered safety feature (ESF)) was reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).
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VII. Previous Similar Events at the Same Site
None
VIII. Additional Information
None IX.
Commitments
None