Semantic search
Entered date | Event description | |
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ENS 51318 | 13 August 2015 16:52:00 | A licensed, non-supervisory employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector as well as the NRC Region 3 Office Safeguards Inspector. |
ENS 50464 | 17 September 2014 09:21:00 | This telephone notification is provided in accordance with 10CFR50.72(b)(3)(xiii), 'Major Loss of Emergency Preparedness Capabilities.' On September 17th, 2014, at 0800 (CDT), the Exelon LaSalle Station Technical Support Center (TSC) ventilation system was removed from service for planned TSC ventilation system maintenance. The removal of the ventilation system potentially affects the TSC habitability during a declared emergency requiring activation. The Emergency Response Organization (ERO) team has been notified of the maintenance and the possible need to relocate during an emergency. If an emergency is declared and the TSC ERO activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological, or other conditions. If relocation of the TSC staff becomes necessary, the Station Emergency Director will relocate the staff to an alternate TSC location in accordance with applicable site procedures. The ventilation system is expected to be out of service for approximately 4 hours. The licensee has notified the (NRC) Senior Resident Inspector of the issue.
The scheduled TSC ventilation system maintenance is expected to be out of service for approximately an additional 7 hours. The licensee has notified the NRC Senior Resident Inspector of the issue. Notified R3DO (Dickson) |
ENS 46605 | 9 February 2011 19:59:00 | At 1830 CST on 02/09/11, LaSalle Unit 1 commenced a Technical Specification required plant shutdown, due to identification of pressure boundary leakage. At 1804 CST on 02/09/11, it was identified that 1E51-F076, Reactor Core Isolation Cooling System Steam Supply Inboard Isolation Bypass Warmup Valve, had a one inch crack in a weld on the pressure seal joint. This qualifies as pressure boundary leakage, which requires entry into Tech Spec 3.4.5, RCS Operational Leakage, Required Action C, to be in Mode 3, Hot Shutdown, by 0604 on 02/10/11, and Mode 4, Cold Shutdown, by 0604 on 02/11/11 . At the time of discovery, Unit 1 was in startup mode following a forced outage. A repair plan is being prepared at this time and the Unit will remain in cold shutdown until repairs are complete. This is an unisolable leak. Reactor pressure is 913 psig. The licensee notified the NRC Resident Inspector. |