| Site | Start date | Title | Description |
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ML24270A004 | FitzPatrick | 2 October 2024 | Fitpatrick Pre-submittal Meeting Slides, October 2, 2024 | |
ENS 57343 | Hatch | 27 September 2024 07:46:00 | Manual Reactor Trip on Lowering Condenser Vacuum | The following information was provided by the licensee via phone:
At 0346 EDT on 9/27/24, with Unit 1 in mode 1 at 54 percent power, the reactor was manually tripped due to degrading condenser vacuum secondary to environmental conditions. The trip was not complex with all systems responding normally post trip. Closure of containment isolation valves (CIVs) in multiple systems occurred. Operations responded and stabilized the plant.
The reactor protection system actuation while critical event is being reported as a 4-hour non-emergency notification per 10 CFR 52.72(b)(2)(iv)(B). Additionally, it is reportable under 10 CFR 52.72(b)(3)(iv)(a) as an event that results in a valid actuation of the CIVs.
There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Decay heat removal is via steam bypass to the main condenser. Unit 2 was not affected. |
BW240053, Revised 2022 Annual Radioactive Effluent Release Report | Braidwood | 6 September 2024 | Revised 2022 Annual Radioactive Effluent Release Report | |
IR 05000277/2024002 | Peach Bottom | 14 August 2024 | Integrated Inspection Report 05000277/2024002 and 05000278/2024002 | |
IR 05000321/2024002 | Hatch | 8 August 2024 | Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002 | |
IR 05000259/2024002 | Browns Ferry | 2 August 2024 | Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 | |
ML24213A085 | Vogtle | 31 July 2024 | Final RO Written Exam Vogtle, Units 3 and 4, 2024-301 Combined (Redacted for Public Release) | |
ML24204A071 | Limerick | 29 July 2024 | Issuance of Amendment Nos. 263 and 225 Technical Specifications for Main Steam Line Tunnel Temperature | |
ENS 57233 | Calvert Cliffs | 18 July 2024 19:24:00 | Automatic Reactor Trip | The following information was provided by the licensee via phone and email:
At 1524 (EDT) on 07/18/2024, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex, with all systems responding normally post-trip.
Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves.
Unit 1 implemented AOP-7K (abnormal operating procedure), overcooling event, due to a grid transient. Operations responded and stabilized Unit 1 in Mode 1 at 100 percent power.
Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
There was no impact on the health and safety of the public or plant personnel.
The NRC resident inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
All rods fully inserted. There were no other specified system actuations. |
ML24145A177 | Salem Hope Creek | 15 July 2024 | and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary | |