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| Entered date | Event description | |
|---|---|---|
| ENS 56784 | 9 October 2023 21:52:00 | The following information was provided by the licensee via email: A non-licensed employee supervisor failed a test specified by the fitness for duty testing program. The individual's authorization for site access has been terminated. The NRC Resident Inspector has been notified. |
| ENS 54040 | 1 May 2019 21:03:00 | EN Revision Text: MANUAL REACTOR TRIP DUE TO MISALIGNED CONTROL ROD At 1643 (CDT), with Unit 2 in Mode 2 during low power physics testing, the reactor was manually tripped per procedure due to a misaligned control rod. 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 atmosphere using the atmospheric relief valves. Unit 1 is not affected. Due to the Reactor Protection System actuation, 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.
This Event Notification is being updated to clarify that the reactor was not critical when this event occurred. Therefore, the reporting requirement is changed from 10 CFR 50.72(b)(2)(iv)(B) to 10 CFR 50.72 (b)(3)(iv)(A). The reactor was tripped during low power physics testing. The misaligned rod was encountered during rod group insertion and the affected bank had been inserted to the extent that the reactor was subcritical when the operators tripped the reactor. The licensee notified the NRC Resident Inspector. Notified R2DO (Lopez) |
| ENS 54002 | 16 April 2019 02:59:00 | At 2355 CDT on 4/15/19, life-saving activities by offsite medical personnel for a Farley employee were terminated. The coroner declared the individual deceased at the plant site at 0130 CDT. The fatality is not believed to be work-related and the individual was inside of the Radiological Controlled Area. This is a four-hour notification, non-emergency for a notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified. The licensee will be notifying the Occupational Safety and Health Administration due to the on-site fatality. The licensee will perform a radiological survey of the individual prior to transportation offsite. |
| ENS 53159 | 9 January 2018 23:38:00 | On January 9, 2018, at 1759 CST, during review of NFPA 805 requirements and circuit analysis, it was determined that the NFPA 805 analysis and Fire Safe Shutdown Modeling did not consider all fire-induced failures. As such, a condition could possibly exist during a postulated fire where both safety related electrical trains could be impacted. This notification is to report a condition involving the fire safe shutdown analysis. The condition could result in an adverse impact on the ability of operators to respond to a postulated fire in these areas. Therefore, this notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(B), any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. Compensatory fire watches have been established in the affected areas. The licensee notified the NRC Resident Inspector.
Following additional refinements to the NFPA 805 Fire PRA Model, the circuits which initiated the initial report of an unanalyzed condition have now been evaluated and have proven that no significant degradation to plant safety existed. Therefore, EN 53159 is being retracted. The NRC Resident Inspector has been notified. Notified R2DO (Michel). |