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| Entered date | Event description | |
|---|---|---|
| ENS 48354 | 28 September 2012 09:00:00 | This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. On September 28, 2012, the EOF/TSC air handler chiller unit was removed from service to perform planned maintenance. This maintenance activity will not affect the air filtration portion of the system and these facilities remain available for use during an emergency. This maintenance activity will be performed in a manner to minimize the time that the air handler chiller is out of service. This maintenance activity impacts the ability to maintain ambient air temperature in the facilities. The (estimated) duration of this activity is planned to be 4 hours. If an emergency condition occurs that requires activation of the emergency response facilities, the EOF and TSC will be utilized. The Emergency Response Organization team members have the ability to relocate to alternate locations in accordance with emergency implementing procedures based on conditions. Alternate emergency response facilities will remain available in the event that relocation is necessary. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update message will be provided when the emergency response facilities are restored. The licensee notified the NRC Resident Inspector, the State of South Carolina and the local counties of Lee, Chesterfield and Darlington.
The EOF/TSC Chiller is back in service as of 1102 (EDT) on 9/28/12. The ability to maintain ambient air temperature in the EOF/TSC facilities has been restored. The licensee notified the NRC Resident Inspector. Notified the R2DO (Nease). |
| ENS 47781 | 28 March 2012 17:14:00 | At 1503 hours EDT on March 28, 2012, with the unit in Mode 1 at 55% power, an automatic reactor trip occurred. The reactor trip was the result of a turbine trip from a 'B' Steam Generator Hi Level. All Reactor Coolant Pumps (RCP) remained running. The Auxiliary Feeedwater (AFW) System automatically actuated due to both main feedwater pump breakers opening from a valid feedwater isolation signal. Steam Generator Levels were then controlled by Auxiliary Feedwater pumps. Steam Generator Blowdown was automatically isolated with the AFW actuation. The RCS Code Safety valves, Pressurizer Power Operated Relief Valves (PORVs), Steam Generator PORVs or the Main Steam Safety valves (MSSVs) did not open during the event. All control rods fully inserted following the reactor trip. The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently in Mode 3 and stable. There were no radiological consequences or releases as a result of this event. The cause of the Steam Generator Hi Level is under investigation. The Resident NRC Inspector has been informed. |