ENS 42974
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ENS Event | |
|---|---|
17:06 Nov 8, 2006 | |
| Title | Specified System Actuation - Emergency Diesel Generator Auto Start |
| Event Description | {{#Wiki_filter:On November 8, 2006, at approximately 11:06 Central Standard Time (CST) a valid actuation of Fort Calhoun station (FCS) Unit 1 Emergency Diesel Generator 2 (DG-2) occurred as a result of undervoltage on its respective safety bus (1A4). DG-2 started as a result from manually deenergizing bus 1A4 during the performance of the Bus Ground Fault Locator Function Test. The DG-2 output breaker was disabled as part of the test and therefore did not close onto the bus. The procedure was deficient in ensuring that DG-2 was not in automatic.
No loads were being supplied from Bus 1A4 at the time and thus no loads were lost. No other Safeguards systems or equipment were actuated. Fort Calhoun Station is currently in a refueling outage, Mode 5 with the core offloaded to the Spent Fuel Pool. No Technical Specifications were entered as a result of this actuation due to plant being less than 300�F. Emergency Diesel Generator 2 was taken out of automatic, lockout relays reset and the engine was shutdown. The licensee notified the NRC Resident Inspector. }} |
| Where | |
|---|---|
Ft Calhoun  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-2.6 h-0.108 days <br />-0.0155 weeks <br />-0.00356 months <br />) | |
| Opened: | Ken Kingston 14:30 Nov 8, 2006 |
| NRC Officer: | Bill Gott |
| Last Updated: | Nov 8, 2006 |
| 42974 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
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 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 2016-06-22T13:41:00 | |
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