ENS 41027
ENS Event | |
|---|---|
18:45 Sep 8, 2004 | |
| Title | Emergency Feedwater System Actuation |
| Event Description | At 1445 on September 8, 2004, while in Mode 3 after an unplanned reactor trip during tropical storm Frances, Crystal River Unit 3 experienced a re-actuation of the B-Train of the Emergency Feedwater System. The Emergency Feedwater System had previously actuated during a Loss of Offsite Power experienced during Hurricane Frances and the B-Train actuation had procedurally been bypassed as part of the plant recovery. While In the process of restoring a Main Feedwater Pump to an operating condition, the signal bypassing the B-Train Emergency Feedwater actuation was momentarily removed due to unusual plant conditions present during recovery from the loss of power This resulted in the re-actuation of the B-Train of Emergency Feedwater. This condition is 8-Hour reportable per 10CFR50.72(b)(3)(iv)(B)(6). The re-actuation of the B-Train of Emergency Feedwater did not have a significant impact on plant operation and the associated equipment has been returned to a standby condition.
The licensee informed the NRC Resident Inspector.
The following information was provided by the licensee via facsimile: At 1823 [hrs. EDT] on 9/8/04, Crystal River Unit 3 made an 8-hour ENS notification in accordance with 10CFR50.72(b)(3)(iv)(A) and 50.72(b)(3)(iv)(B)(6) concerning re-actuation of the B-train of the Emergency Feedwater System. The Emergency Feedwater System had previously actuated during a Loss of Offsite Power experienced during Hurricane Frances and the B-Train actuation had procedurally been bypassed as part of the plant recovery. While in the process of restoring a Main Feedwater Pump to an operating condition, the signal bypassing the B-Train Emergency Feedwater actuation was momentarily removed due to unusual plant conditions present during recovery from the loss of power. This allowed for a re-actuation of the B-Train of Emergency Feedwater based on a loss of Main Feedwater Pump signal. However, the two Main Feedwater Pumps had not been operating since the loss of offsite power that occurred on 9/6/04. The A-Train Emergency Feedwater System had been operating continuously since the initial actuation on the loss of offsite power and continued to operate during and after the re-actuation of the B-Train. Re-actuation of the B-Train has been determined to be an invalid actuation in accordance with the guidance of NUREG-1022, and therefore EN 41027 is retracted. The licensee has informed the NRC resident inspector. R2DO (Lesser) notified. |
| Where | |
|---|---|
Crystal River  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.37 h-0.0154 days <br />-0.0022 weeks <br />-5.06826e-4 months <br />) | |
| Opened: | Jon Huecker 18:23 Sep 8, 2004 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Sep 30, 2004 |
| 41027 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
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 | |