ENS 50688
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ENS Event | |
|---|---|
16:14 Dec 17, 2014 | |
| Title | Automatic Reactor Trip Due to Loss of Load |
| Event Description | At 1014 [CST] on 12/17/2014, the reactor automatically tripped due to loss of load on RPS [Reactor Protection System]. Preliminary information indicates turbine-generator trip caused an uncomplicated reactor trip . All safety functions are met. Currently maintaining Mode 3, Hot Shutdown. At time of trip, non-safety related house transformers, T1A1 and T1A2 became inoperable as expected due to generator trip. Entered Technical Specification 2.7 (2)a, 72 hr LCO [for the inoperable T1A1 and T1A2 transformers].
All control rods fully inserted. All busses are energized via offsite power. Decay heat is being released via AFW and the condenser bypass valves. The unit is stable in Mode 3. Cause of the loss of load is being investigated. The NRC Resident Inspector has been informed. |
| Where | |
|---|---|
Fort Calhoun  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-3.3 h-0.138 days <br />-0.0196 weeks <br />-0.00452 months <br />) | |
| Opened: | Laurel Ketcham 12:56 Dec 17, 2014 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Dec 17, 2014 |
| 50688 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Fort Calhoun with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 520332016-06-22T13:41:00022 June 2016 13:41:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip ENS 506882014-12-17T16:14:00017 December 2014 16:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Loss of Load ENS 499262014-03-17T17:02:00017 March 2014 17:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip Initiated by Loss of Stator Cooling Water ENS 497172014-01-12T09:23:00012 January 2014 09:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following Control Rod Position Deviation ENS 469882011-06-26T05:00:00026 June 2011 05:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Both Emergency Diesel Generators Supplying Plant Emergency Buses Per Plant Procedure ENS 465062010-12-23T16:50:00023 December 2010 16:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Uncomplicated Reactor Trip from 100% Power ENS 458282010-04-08T21:22:0008 April 2010 21:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Steam Generator Inlet Isolation Valve ENS 440662008-03-15T13:33:00015 March 2008 13:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Turbine Trip ENS 429742006-11-08T17:06:0008 November 2006 17:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Emergency Diesel Generator Auto Start ENS 414462005-02-27T03:34:00027 February 2005 03:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Plant Had a Reactor Trip from 16.1% Power Due to a Loss of Turbine Load Signal ENS 401562003-09-13T01:55:00013 September 2003 01:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Unanticipated Negative Axial Shape Index (Asi). 2016-06-22T13:41:00 | |
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