ENS 45946
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ENS Event | |
|---|---|
21:34 May 22, 2010 | |
| Title | Manual Reactor Trip Due to Loss of Steam Generator Water Level Control |
| Event Description | Unit 2 was operating at 100% power in the normal operating procedure, FNP-2-UOP-3.1, Power Operation, when multiple alarms were received associated with 2C Steam Generator (S/G) level, and a process cabinet failure. The control room team noticed there was no power or control capability on the 2C S/G Feedwater Regulating Control Valve (FRV), and 2C S/G level was decreasing. The control room team attempted to take manual control of the 2C FRV, which did not respond. The reactor was manually tripped when 2C S/G narrow range level reached 40%. The automatic trip set point for S/G level is 28%. All systems responded properly for the reactor trip and there were no complications.
The investigation indicates there was an Nuclear Controller Driver (NCD) card failure in Process Control Cabinet 8. The controller card controls the 2C S/G FRV controller, which prevented any automatic, or manual control of the 2C S/G FRV, or 2C S/G level. There were no safety or relief valves that lifted and decay heat is being removed via steam dump control valves. Auxiliary feedwater pumps are maintaining level in the steam generators. Electrical lineup is normal. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Farley  Alabama (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: | 05000364/LER-2010-002 |
| Time - Person (Reporting Time:+-2.4 h-0.1 days <br />-0.0143 weeks <br />-0.00329 months <br />) | |
| Opened: | Rick Lulling 19:10 May 22, 2010 |
| NRC Officer: | John Knoke |
| Last Updated: | May 22, 2010 |
| 45946 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Farley with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 569712024-02-16T11:34:00016 February 2024 11:34:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Automatic Actuation of Auxiliary Feedwater System ENS 568522023-11-14T16:41:00014 November 2023 16:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 563292023-02-01T15:56:0001 February 2023 15:56:00 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 and Automatic Actuation of Auxiliary Feedwater System ENS 560282022-08-03T17:58:0003 August 2022 17:58:00 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 Power to START-UP Transformer ENS 542872019-09-21T13:00:00021 September 2019 13:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip Due to Reactor Coolant Pump Vibration Alarm ENS 540402019-05-01T21:43:0001 May 2019 21:43:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation En Revision Imported Date 5/9/2019 ENS 523952016-11-27T06:26:00027 November 2016 06:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip with Automatic Auxiliary Feedwater System Actuation Due to Voltage Oscillations ENS 523562016-11-08T06:00:0008 November 2016 06:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Steam Generator Reduced Feedflow ENS 522742016-10-01T10:12:0001 October 2016 10:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip Due to Inadvertent Closure of Main Steam Isolation Valve ENS 519182016-05-11T11:53:00011 May 2016 11:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Farley Unit 2 Trip on Hi Hi Steam Generator Level ENS 510432015-05-05T09:22:0005 May 2015 09:22:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Pump Auto Start Signal Initiated During Startup ENS 506182014-11-15T09:53:00015 November 2014 09:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of the Reactor Protection System for Abnormal Rod Position Indication ENS 505332014-10-14T08:41:00014 October 2014 08:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of a Start-Up Transformer ENS 491062013-06-12T02:05:00012 June 2013 02:05:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip Due to the Loss of a Start-Up Transformer ENS 478132012-04-06T19:44:0006 April 2012 19:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Load Shed Signal Occurred Due to Loss of the 1B Startup Transformer ENS 478092012-04-05T17:20:0005 April 2012 17:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Systems Actuations While Performing a Surveillance Test ENS 466612011-03-07T07:40:0007 March 2011 07:40:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertant Auto-Start Signal to the 1B Diesel Generator During Testing ENS 459462010-05-22T21:34:00022 May 2010 21:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Steam Generator Water Level Control ENS 458892010-05-01T02:00:0001 May 2010 02:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent System Actuation Occurred During a Surveillance Test ENS 448552009-02-16T22:55:00016 February 2009 22:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Relay Actuation Results in Auto Start of 1C Emergency Diesel Generator ENS 446662008-11-19T10:25:00019 November 2008 10:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 436872007-10-03T19:10:0003 October 2007 19:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip on Loss of Forced Flow to Rcs Loop "a ENS 411752004-11-05T15:11:0005 November 2004 15:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Loss of "B" Train Site Power During Testing ENS 406672004-04-12T08:47:00012 April 2004 08:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 2 Experienced a Reactor Trip During Startup Due to an Invalid Sr Trip Signal ENS 406662004-04-11T16:05:00011 April 2004 16:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip for Unknown Reasons During Plant Startup ENS 405582004-03-01T11:22:0001 March 2004 11:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Experienced a Reactor Trip on Turbine Trip Due to a Feedwater System Problem ENS 403092003-11-10T16:36:00010 November 2003 16:36:00 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 False Rcp Breaker Open Signal 2024-02-16T11:34:00 | |
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