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{{#ask: [[Originated by::Mark Dodds]] [[Category:ENS Notification]]
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{
    "query_string": "[[Originated by::Mark Dodds]] [[Category:ENS Notification]]",
    "query_source": "SMWSQLStore",
    "query_time": "0.0109",
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}

	Entered date	Event description
ENS 46218	31 August 2010 17:45:00	The licensee discovered a potential prohibited substance in the protected area. The substance has been removed from the facility. The licensee has notified the NRC Resident Inspector, the Illinois Emergency Management Agency and the DeWitt County Sheriff Office. Contact the Headquarters Operations Officer for additional details.
ENS 48765	18 February 2013 11:35:00	On February 18, 2013, at 0318 hours (CST), the Main Control Room received an alarm associated with a transfer of the Division 4 Nuclear System Protection System (NSPS) inverter to the alternate source. Plant Technicians were performing a Technical Specification (TS) Surveillance, 'Average Power Range Monitor Flow Biased/Neutron Flux Response Time Test,' when a test cable connector contacted a fuse block staple jumper, causing the transfer of the Division 4 NSPS bus from normal inverter source to its alternate source. TS 3.8.7, 'Inverters - Operating' Surveillance Requirement 3.8.7.1 is not met with the inverter on the alternate source, and Condition C, requires High Pressure Core Spray (HPCS) system to be declared inoperable immediately since the Division 4 NSPS bus was not energized from the inverter. Since HPCS is an emergency core cooling system and is a single train safety system, this is a condition that could have prevented fulfillment of a safety function and is reportable under 10 CFR 50.72(b)(3)(v)(D), system needed to mitigate the consequences of an accident. At 0925 CST, the Division 4 NSPS bus has been restored to service on the normal source. At 0925 CST, HPCS has been declared Operable. The NRC Resident has been notified.
ENS 49632	13 December 2013 20:07:00	During a feed pump shift from the motor driven reactor feed pump to the 'A' turbine driven reactor feed pump during power ascension, reactor pressure vessel (RPV) water level was approaching the Reactor Protective System (RPS) automatic scram set point when a manual reactor scram was inserted. All control rods fully inserted. RPV water level is being maintained by the normal condensate booster / feedwater systems. RPV pressure is being maintained via normal main steam system. There were no actuations of any Emergency Core Cooling System and no Safety Relief Valves actuations. All systems responded as expected. The licensee notified the NRC Resident Inspector.

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