ENS Event | |
|---|---|
05:00 Jun 26, 2011 | |
| Title | Both Emergency Diesel Generators Supplying Plant Emergency Buses Per Plant Procedure |
| Event Description | At approximately 0125 [hrs. CDT], the AquaDam providing enhanced flood protection for FCS [Ft. Calhoun Station] Unit 1 failed. At 0221, as a precautionary measure, DG-2 [Diesel Generator] was automatically started per plant procedure to divorce bus 1A4 from offsite power. At 0250, DG-1 was automatically started to divorce bus 1A3. Both Emergency Diesel Generators loaded on buses as designed. 345KV and 161KV offsite power remain available.
This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), 'System Actuation of the Emergency Diesel Generators'. All safety related flood protection barriers remain in place. Current river level is 1006.5' MSL and stable. FCS remains in a NOUE [Notification of Unusual Event] due to high river level. NRC personnel stationed onsite for flood monitoring have been informed. |
| Where | |
|---|---|
Fort Calhoun  Nebraska (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+2.97 h0.124 days <br />0.0177 weeks <br />0.00407 months <br />) | |
| Opened: | Amy Burkhart 07:58 Jun 26, 2011 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Jun 26, 2011 |
| 46988 - NRC Website
Loading map... | |
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 | |