ENS 46661
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ENS Event | |
|---|---|
07:40 Mar 7, 2011 | |
| Title | Inadvertant Auto-Start Signal to the 1B Diesel Generator During Testing |
| Event Description | Farley Unit One was conducting FNP-1-STP-80.8, [test procedure for] 1B DG [Diesel Generator] 1000 KW load rejection. After successfully completing the load rejection portion of the procedure, the control room staff was restoring the 1B diesel to a normal auto start alignment. With the 1B diesel running, the plant operator was required to reset the 1B DG loading sequencer. He incorrectly pressed the Emergency Start reset push-button instead of the Sequencer reset push-button. As a result, the Emergency Diesel generator stop light illuminated for a brief few seconds and then extinguished. Subsequently due to the test configuration, the 1B diesel received an auto-start signal and returned to the running condition prior to the Emergency Start reset. Although further investigation is continuing, this report is being made due to an apparent valid actuation of ESF equipment.
This event had no impact on other equipment or the plant electrical alignment. The Sequencer reset push-button and the Emergency Start reset push-button are not in close proximity to each other. The plant operator was assessed for fatigue and it was determined that fatigue was not a factor. The plant operator was removed from duties pending remedial training and assessment. The licensee has notified the NRC Resident Inspector.
The 8-hour non-emergency report (EN#46661) per 10CFR50.72(b)(3)(iv)(A) was conservatively reported based on the potential for a valid actuation of an Emergency Diesel Generator (EDG) during a 1000 KW load rejection surveillance test. During the restoration phase of the load rejection test to align the 1B EDG to a normal shutdown configuration, a plant operator incorrectly pressed the Emergency Start Reset (ESR) push-button instead of the Sequencer Reset push-button. As a result, the 1B EDG stop light illuminated momentarily and then extinguished. The 1B EDG received a momentary shutdown signal, but remained in a running condition. Upon completion of the 1B EDG circuit analysis, It was determined that the 1B EDG did not receive a valid actuation of the EDG safety function. Depressing the ESR push-button caused the emergency start relays to deenergize and remain de-energized. The emergency start relays energize on receipt of valid signals in response to actual plant conditions or parameters satisfying the requirements for the initiation of the safety function of the EDG. Therefore per section 3.2.6 of NUREG-1022, the 1B EDG did not receive a valid actuation signal. The NRC Resident Inspector has been notified. Notified R2DO(Musser) |
| Where | |
|---|---|
Farley  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+2.85 h0.119 days <br />0.017 weeks <br />0.0039 months <br />) | |
| Opened: | Alton Deweese 10:31 Mar 7, 2011 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Mar 9, 2011 |
| 46661 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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 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 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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