Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 50310 | 25 July 2014 14:02:00 | On July 25th, 2014 at 1129 EDT, during investigation of a small leak inside Saint Lucie Unit 2 containment, a defect was identified on a valve (V3811, Safety Injection Tank 281 Outlet Vent Valve). This valve is within the Q-Group A (ASME Class 1 equivalent) boundary of the safety injection line. The leak is currently isolated from the reactor coolant system by a Technical Specification credited isolation check valve. The affected Safety Injection Tank has been declared inoperable and the unit has entered 24 hour shutdown (Technical Specification) action statement 3.5.1.b. Unit shutdown is currently being planned for repair of the flaw. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The licensee has notified the NRC Resident Inspector.
On July 26, 2014 at 0002 EDT, Saint Lucie Unit 2 commenced shutdown to repair the identified leak. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(2)(i). The NRC Resident Inspector has been notified. Unit 2 current power is 88% at 0105 EDT and expect to trip the unit at approximately 0400 EDT. Notified the R2DO (Musser). |
| ENS 50303 | 24 July 2014 07:44:00 | On July 24, 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 1700 EDT on July 24, 2014. This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii), as an 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 has been restored to an operable status as of July 24, 2014 at 1650 EDT. The NRC Resident Inspector has been notified. Notified R2DO(Musser) |
| ENS 47915 | 11 May 2012 07:07:00 | On May 11, 2012, a failure of the High Power Feed Regulating Valve FCV-9011 resulted in '2A' S/G water level lowering. Manual operator control of the Main Feed Regulating system was unsuccessful in stabilizing S/G water level. '2A' S/G level lowered to the procedurally required manual reactor trip criteria. The crew inserted a manual trip. All CEAs fully inserted into the core. Following the trip, Auxiliary Feedwater actuated as designed and decay heat removal was via Auxiliary Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently, Unit 2 is maintaining pressurizer pressure at 2250 psia, temperature at 532 degrees F on Main Feedwater (using Low Power Feed Regulating Valves LCV-9005/9006) and Steam Bypass Control. 'Unit 1 was unaffected and remains in Mode 1 at 29% power. This event is reportable pursuant to 10CFR50.72(b)(2)(iv)(B) for the Reactor Trip, as well as 10CFR50.72(b)(3)(iv)(A) for specified system actuation (Auxiliary Feedwater). The licensee has notified the NRC Resident Inspector. |
| ENS 47793 | 31 March 2012 03:42:00 | At 0022 (EDT) on 03/31/12 while maintaining power stable at 10% for Steam Bypass Control System testing, Unit 1 was manually tripped due to an uncontrolled cooldown caused by PCV-8802 (Steam Bypass Control Valve) unexpectedly opening. Following the trip, PCV-8802 closed and the secondary was isolated by closing the Main Steam Isolation Valves per Standard Post Trip Actions. Following isolation of the steam demand, the trip was uncomplicated with all CEAs fully inserted. No automatic safety system actuations were required and none occurred. The cause of the unexpected opening of the Steam Bypass Control System valve is under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Auxiliary Feedwater and Atmospheric Dump Valves. The Offsite power grid is available and stable. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to manual RPS actuation with the reactor at power. The RCS cooled down from 532 degree to 515 degrees over a period of approximately 2 minutes and 40 seconds. The reactor was manually tripped when RCS temperature reached 515 degrees and the lowest RCS temperature observed after the trip was 505 degrees. The licensee has notified the NRC Resident Inspector. |