| | Site | Start date | Title | Description |
|---|
| ENS 55964 | Fermi | 25 June 2022 03:38:00 | Automatic Reactor SCRAM Due to Main Turbine Trip | The following information was provided by the licensee via email:
At 2338 EDT, on June 24, 2022, with the unit in Mode 1 at 100 percent power, the reactor automatically scrammed due to an RPS actuation following a Main Turbine Trip. The cause of the turbine trip is not known at this time. The scram was not complex, with systems responding normally post-scram.
Operations responded and stabilized the plant. Reactor water level has been recovered and maintained at the normal level. Decay Heat is being removed by the Main Steam system to the main condenser using the Turbine Bypass Valves. All Control Rods inserted into the core. The transient occurred with no surveillances or activities in progress. Investigation into the cause of the Turbine Trip is in progress.
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). The low reactor water level caused an isolation of Primary Containment (Groups 4/13/15) as expected. The Primary Containment Isolation Event is being reported under 10 CFR 50.72(b)(3)(iv)(A). There was no impact to the health and safety of the public or plant personnel. The NRC resident has been notified. |
| RS-22-082, Defueled Safety Analysis Report Update, Revision 11 | Dresden | 22 June 2022 | Defueled Safety Analysis Report Update, Revision 11 | |
| ENS 55943 | Beaver Valley | 15 June 2022 11:24:00 | Manual Reactor Trip and Automatic Auxiliary Feedwater Actuation | The following information was provided by the licensee via email:
At 0724 EDT on 6/15/2022, with Unit 1 in Mode 1 at 100 percent power, the reactor was manually tripped due to lowering Steam Generator levels due to a secondary plant perturbation in the Heater Drain System. All control rods fully inserted into the core and the Auxiliary Feedwater System automatically started as designed in response to the full power reactor trip. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response.
Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Unit 2 is not affected and remains at 100 percent power and stable.
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). Additionally, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| IR 05000382/2022501 | Waterford | 11 June 2022 | Emergency Preparedness Inspection Report 05000382/2022501 and Preliminary White Finding | |
| ML22145A000 | | 10 June 2022 | Rulemaking: Proposed Rule: Consolidated Preliminary Rule Language for the Part 53 Rulemaking - Framework B, Subparts N Through U | |
| ML22153A508 | 05000418 | 8 June 2022 | GG2022013-RFI-GAG POV Inspection | |
| L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis | Perry | 1 June 2022 | Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis | |
| ENS 55910 | Cook | 24 May 2022 08:14:00 | Manual Reactor Trip Following Manual Turbine Trip from High Vibrations on Main Turbine | The following information was provided by the licensee via email:
On May 24, 2022, at 0414 EDT, while rolling the Unit 1 main turbine during the Unit 1 Cycle 31 refueling outage, the Unit 1 main turbine experienced high vibrations and the main turbine was manually tripped with reactor power at 12 percent. Main turbine vibrations persisted and the reactor was manually tripped, Main Steam Stop Valves were closed, and main condenser vacuum was broken.
This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook Resident NRC Inspector has been notified.
Unit 1 is being supplied by offsite power. All control rods fully inserted. Both Motor Driven Auxiliary Feedwater Pumps started properly. Decay heat is being removed via Steam Generator Power Operated Relief Valves. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event. |
| ML22144A144 | Diablo Canyon | 23 May 2022 | FAQ 22-02 - Diablo Canyon Scram | |
| ML22151A141 | Wolf Creek | 18 May 2022 | 5 to Updated Safety Analysis Report, Chapter 11, Radioactive Waste Management | |