ENS 44024
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ENS Event | |
|---|---|
09:27 Mar 1, 2008 | |
| Title | Emergency Feedwater Actuation While Shutting Down |
| Event Description | On 03/01/2008 a pre-planned unit shutdown was in progress to repair a reactor coolant pump seal. At approximately 20% reactor power, a main feedwater flow perturbation occurred. This flow perturbation resulted in an Emergency Feedwater actuation at 0427 [EST]. Both Emergency Feedwater system trains started automatically on low levels in the Once Through Steam Generators as designed. Main feedwater system recovered and continued to supply inventory with levels stabilized at the required low level setpoint. Following plant stabilization, Emergency Feedwater was secured and the pre-planned unit shutdown was resumed. This event is reportable under the requirements of 10 CFR 50.72 (b)(3)(iv)(A).
The cause of the feedwater flow perturbation is still under investigation. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Crystal River  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+0.42 h0.0175 days <br />0.0025 weeks <br />5.75316e-4 months <br />) | |
| Opened: | Bryan Wooten 09:52 Mar 1, 2008 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Mar 1, 2008 |
| 44024 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (20 %) |
| After | Power Operation (20 %) |
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 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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