ENS 43179
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ENS Event | |
|---|---|
00:15 Feb 22, 2007 | |
| Title | |
| Event Description | At 1915 on February 21, 2007, Crystal River Unit 3 was at reduced power (71%) for planned maintenance on one of four condenser waterboxes when the Integrated Control System (ICS) for Main Feedwater became erratic causing a feedwater transient that underfed the once thru steam generators. The reactor protection system (RPS) actuated on high Reactor Coolant System pressure causing a reactor trip. CR3 also received an Emergency Feedwater Actuation (EFIC) on low steam generator levels. This event is reportable as a 4-Hour Non-Emergency Notification per 10CFR50.72 (b)(2)(iv)(B) for Reactor Protection System Actuation and as an 8-Hour Non-Emergency Notification per 10CFR50.72 (b)(3)(iv)(A) for Emergency Feedwater Actuation and for Reactor Protection System actuation. All systems responded as designed and the plant remains stable with Emergency Feedwater in MODE 3.
The licensee informed the NRC Resident Inspector. |
| Where | |
|---|---|
Crystal River  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000302/LER-2007-002 |
| Time - Person (Reporting Time:+-2.07 h-0.0863 days <br />-0.0123 weeks <br />-0.00284 months <br />) | |
| Opened: | Ricky E. Rawls 22:11 Feb 21, 2007 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Feb 21, 2007 |
| 43179 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (71 %) |
| After | Hot Standby (0 %) |
Crystal River with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 490862013-06-02T01:29:0002 June 2013 01:29:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Emergency Diesel Generator ENS 452862009-08-24T15:00:00024 August 2009 15:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Loss of Power to Control Rods ENS 448072009-01-27T15:17:00027 January 2009 15:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Loss of 4160V Bus ENS 444382008-08-24T19:57:00024 August 2008 19:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Feedwater Flow Oscillations ENS 440242008-03-01T09:27:0001 March 2008 09:27:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Feedwater Actuation While Shutting Down ENS 431792007-02-22T00:15:00022 February 2007 00:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on High Rcs Pressure Following a Feedwater Transient ENS 420942005-10-29T05:26:00029 October 2005 05:26:00 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 Loss of Feedwater Pumps ENS 410272004-09-08T18:45:0008 September 2004 18:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Feedwater System Actuation ENS 410232004-09-06T15:50:0006 September 2004 15:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Partial Loss of Offsite Power ENS 406082004-03-24T08:31:00024 March 2004 08:31:00 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 ENS 402992003-11-05T22:34:0005 November 2003 22:34:00 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 High Reactor Coolant System Pressure 2013-06-02T01:29:00 | |
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