Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 54262 | 7 September 2019 12:01:00 | On September 09, 2019 at 0824 EDT, with St. Lucie Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped on Low Reactor Coolant System Flow due to a trip of the 1A1 reactor coolant pump. The trip was uncomplicated with all systems responding normally post-trip. Operators responded and stabilized the plant in Mode 3. The cause of the loss of the 1A1 reactor coolant pump is currently under investigation. St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100 percent power. This report is submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip. Decay heat removal is being accomplished by main feed water and the main condenser using the turbine steam bypass valves. The licensee notified the NRC Resident Inspector. |
| ENS 54253 | 1 September 2019 17:44:00 | EN Revision Text: NOTIFICATION OF UNUSUAL EVENT DUE TO DECLARATION OF HURRICANE WARNING A hurricane warning is in effect for St. Lucie County including the plant site. A hurricane warning was confirmed with the State Watch Office at 1717 EDT. As a matter of procedure, St. Lucie Nuclear Power Plant entered an Unusual Event classification for the hurricane warning. State and local officials have been notified by the licensee. The NRC Resident Inspector was notified of this by the licensee. This report is submitted in accordance with 10 CFR 50.72(a)(2)(i) due to the Notice of Unusual Event and 10 CFR 50.72(b)(2)(xi) due to the offsite notification.
The Hurricane Warning was downgraded to a Tropical Storm Warning by the National Weather Service for St. Lucie County including the Plant Site. At time 1818 EDT on 9/3/19, St. Lucie Nuclear Power Plant has terminated from the Unusual Event Classification. There are no changes in plant status for either unit. Both units are stable at 100 percent power. The NRC Resident Inspector was notified. Notified the R2DO (Shaeffer), IRDMOC (Kennedy), NRR EO (Walker), R2RA (Dudes via email), NRR (Nieh via email), DHS SWO, FEMA Ops Ctr., DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), FEMA NRCC (email). |
| ENS 53703 | 29 October 2018 16:47:00 | On October 29, 2018 at 1317 EDT, with St. Lucie Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to inadequate feedwater flow to both 1A and 1B Steam Generators (S/Gs). The trip was uncomplicated with all systems responding normally post-trip. (All control rods fully inserted and there were no specified system actuations.) Operators responded and stabilized the plant in Mode 3. The cause of the inadequate feed flow to the 1A and 1B Steam Generators is currently under investigation. Decay Heat removal is being accomplished through forced circulation with stable conditions from Main Feedwater and the Steam Bypass Control System to the Main Condenser. Currently maintaining Pressurizer pressure at 2250 psia and Reactor Coolant System temperature at 532 degrees F. St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100% power. This report is submitted in accordance with 10CFR50.72(b)(2)(iv)(B) for the reactor trip. The NRC Senior Resident Inspector has been notified. |
| ENS 50290 | 21 July 2014 08:09:00 | On July 21, 2014 at 0800 EDT, the Unit 2 Radiation Monitoring Computer System will be inoperable and unavailable due to pre-planned maintenance to implement an upgrade to the system. Alternate methods for monitoring are being utilized. The Radiation Monitor Computer System is expected to be restored to available status at approximately 1900 EDT on July 21, 2014. This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii), as any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update will be provided once the Radiation Monitoring Computer System has been restored to normal operation. The NRC Resident Inspector has been notified.
The Unit 2 Radiation Monitoring Computer System is restored to an available status as of July 21, 2014 at 1955 EDT. The NRC Resident Inspector has been notified. Notified R2DO (McCoy). |
| ENS 49688 | 2 January 2014 12:14:00 | This report is being made under 10 CFR 50.73(a)(2)(iv)(A) as an invalid actuation of Emergency Diesel Generator (EDG) 1A in lieu of a 60-day LER. Per NUREG-1022, the following information is provided: The specific train and system that were actuated: At 0323 hours (EST) on November 3, 2013, the St. Lucie Unit 1 train 'A' EDG automatically started. Troubleshooting revealed that the ESF-A group 7 actuation relay (K507A) failed, providing an invalid Engineered Safety Feature (ESF) 'start' signal to EDG 1A, and the EDG started and operated in the standby mode. The failed relay was replaced, and the post maintenance test was successful. Was train actuation complete or partial? This was a partial actuation of the 'A' train emergency power system as the 1A EDG output breaker did not close, by design, with power on the emergency busses. Did the system start and function correctly? The failed 7A actuation relay provided an invalid start signal to EDG 1A that properly responded to the start signal. The EDG output breaker closing logic prevented closure because the 4160 VAC emergency bus was energized at the time the actuation relay failed. The system started and functioned as would be expected for the existing plant conditions. The licensee informed the NRC Resident Inspector. Notified R2DO (Haag). |
| ENS 48882 | 3 April 2013 14:13:00 | A licensed employee was arrested for possession of a controlled substance while off-duty. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector. |
| ENS 48306 | 14 September 2012 11:20:00 | A non-licensed contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details. The licensee has notified the NRC Resident Inspector. |
| ENS 47657 | 10 February 2012 07:31:00 | On February 10, 2012, with Unit 1 in Mode 5, while performing scheduled maintenance, a technician inadvertently made contact with a component that caused an undervoltage condition on an essential bus, resulting in the automatic start and loading of the 1B Emergency Diesel Generator (EDG). Prior to the event the 1B EDG was inoperable and not required by Technical Specifications; however, the 1B EDG was available. All equipment responded as expected. Currently maintaining the plant in Mode 5. Decay heat removal is being supplied by the 1A Shutdown Cooling train and was never interrupted. There was no impact on the Shutdown Safety Assessment. Unit 2 was unaffected and remains in Mode 1 at 100% power. This event is reportable pursuant to 10CFR 50.72(b)(3)(iv(A). The licensee notified the NRC Resident Inspector. |