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| Start date | Title | Reporting criterion | |
|---|---|---|---|
| ENS 54979 | 3 November 2020 05:11:00 | Both Trains of Salt Water Inoperable | 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor |
| ENS 52640 | 25 March 2017 05:42:00 | Refueling Water Tank Level Inadvertently Lowered Below Ts | 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| ENS 50752 | 22 January 2015 22:45:00 | Unanalyzed Heat Exchanger Lineup Could Exceed Design Basis Temperatures | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition |
| ENS 50502 | 1 October 2014 05:24:00 | Partial Loss of Communications in Emergency Operations Facility and Joint Information Center | 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness |
| ENS 48367 | 3 October 2012 04:10:00 | Unanalyzed Condition Due to High Energy Line Break Barrier Being Partially Open | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition |
| ENS 47619 | 23 January 2012 18:00:00 | Breach in High Energy Line Break Barrier | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition |
| ENS 47512 | 8 December 2011 22:55:00 | Unanalyzed Condition Potentially Could Affect the Common Control Room | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition |
| ENS 47413 | 3 November 2011 22:00:00 | Diesel Generator Starting Air Not Compliant with Appendix R Requirements | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition |
| ENS 45737 | 2 March 2010 12:30:00 | Pressurizer Safety Nozzle Weld Degradation | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded |
| ENS 43830 | 8 December 2007 05:50:00 | Reactor Power Inadvertently Increased Above Accident Analysis Limit | 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition |