ENS 45888
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ENS Event | |
|---|---|
21:48 Apr 30, 2010 | |
| Title | Light Socket Short Causes Isolation Systems to Actuate |
| Event Description | At 1648 CDT, while the Control Bay AUO [Auxiliary Unit Operator] was attempting to change a light bulb for 1-IL-99-1AA, 1A [Reactor Protection System] RPS [Motor Generator] MG Set available light, the light socket shorted causing the loss of 1A RPS. The loss of 1A RPS resulted in Groups 2, 3, 6, and 8 primary containment isolations and initiated Standby Gas Treatment and Control Room Emergency Ventilation. All systems responded as designed. The Control Room operators entered the appropriate abnormal operating instruction, 1-AOI-99-1, to restore the affected systems. Operations entered TS LCO 3.3.1.1 conditions A.1 (place channel in Trip in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) and C.1 (restore RPS trip capability in 1 hr). At 1734 CDT, Operations exited TS LCO 3.3.1.1 upon restoration of 1A RPS per 1-AOI-99-1.
This event is reportable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per 10CFR 50.72(b)(3)(iv)(A) 'Any event or condition that results in a valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) [b. General Containment Isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs)], except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' This event also requires an LER within 60 days per 10CFR 50.73(a)(2)(iv)(A). The NRC Resident Inspector has been notified.
Retraction of an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-emergency notification for invalid Primary Containment Isolation System (PCIS) actuation from a loss of power to the Reactor Protection System (RPS) 1A. Browns Ferry Nuclear Plant (BFN) is retracting the 10 CFR 50.72(b)(3)(iv)(A) eight-hour non-emergency report made on April 30, 2010, at 2131 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.108455e-4 months <br /> Central Daylight Time. BFN's initial report was categorized as a valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B). The loss of power to RPS 1A resulted in PCIS Groups 2, 3, 6, and 8 primary containment isolations and initiation of Standby Gas Treatment and Control Room Emergency Ventilation. However, plant conditions which require PCIS actuations and system initiations (e.g., low reactor water level, high drywell pressure, abnormal area radiation level, high area temperature) did not exist, therefore, the actuation was invalid. As a consequence, TVA has concluded that this event does not meet the reporting requirements of 10 CFR 50.72. The event is reportable under 10 CFR 50.73(a)(2)(iv)(A). A 60-day phone call will be made in accordance with 10 CFR 50.73(a)(1). [See EN #46054] TVA's evaluation of this event is documented in the Corrective Action Program (PER 227662). TVA has notified the NRC Resident Inspector. Notified R2DO (Desai). |
| Where | |
|---|---|
Browns Ferry  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+0.72 h0.03 days <br />0.00429 weeks <br />9.86256e-4 months <br />) | |
| Opened: | Tim Taylor 22:31 Apr 30, 2010 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Jun 29, 2010 |
| 45888 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 572982024-08-30T15:51:00030 August 2024 15:51:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Automatic Start of Diesel Generators ENS 570902024-04-25T03:15:00025 April 2024 03:15:00 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 Scram with Eccs Actuation ENS 569902024-02-24T08:19:00024 February 2024 08:19:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Emergency Diesel Generator ENS 565312023-05-20T08:15:00020 May 2023 08:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 545592020-03-03T10:16:0003 March 2020 10:16:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation ENS 543022019-10-01T08:07:0001 October 2019 08:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram During Reactor Startup ENS 539232019-03-10T04:59:00010 March 2019 04:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Resulting in Rps and Eccs Actuation ENS 532692018-03-18T16:58:00018 March 2018 16:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Turbine Control Valve Closure ENS 531622018-01-10T15:28:00010 January 2018 15:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Turbine Control Valve Fast Closure Scram Signal ENS 526482017-03-29T23:44:00029 March 2017 23:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Initiated During Startup ENS 518782016-04-22T18:59:00022 April 2016 18:59:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Partial Loss of Power Experienced During Electrical Bus Transfer ENS 513332015-08-20T15:32:00020 August 2015 15:32:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of an Emergency Diesel Generator on Low Bus Voltage ENS 504042014-08-26T22:30:00026 August 2014 22:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Generator Neutral Overvoltage Causes a Reactor Scram ENS 500902014-05-06T13:30:0006 May 2014 13:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Low Reactor Water Level During Instrument Testing ENS 499282014-03-19T03:52:00019 March 2014 03:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Failure to Control Main Turbine Moisture Separator Level ENS 488292013-03-19T09:02:00019 March 2013 09:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Lowering Condenser Vacuum ENS 487822013-02-25T19:13:00025 February 2013 19:13:00 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)(i), Tech Spec Required Shutdown Automatic Scram Due to a Turbine Trip from a Loss of Condenser Vacuum ENS 489042013-02-11T11:13:00011 February 2013 11:13:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Initiation of Reactor Core Isolation Cooling System ENS 486232012-12-22T17:52:00022 December 2012 17:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Loss of Power to the Reactor Protection System ENS 479722012-05-29T08:31:00029 May 2012 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 Scram Due to Main Generator Load Reject Signal ENS 479552012-05-24T11:39:00024 May 2012 11:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram During Startup ENS 479422012-05-22T07:49:00022 May 2012 07:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Reactor Protection System Being De-Energized ENS 472992011-09-28T09:14:00028 September 2011 09:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to a Turbine Trip ENS 471302011-08-06T11:17:0006 August 2011 11:17:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Initiation of Technical Specification Required Shutdown ENS 468722011-05-22T22:37:00022 May 2011 22:37:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Reactor Protection System (Rps) Actuation Signal - Scram Discharge Volume (Sdv) High Water Level ENS 468052011-05-02T11:26:0002 May 2011 11:26:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation Due to a Emergency Diesel Generator Output Breaker Trip ENS 468012011-04-29T04:38:00029 April 2011 04:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Primary Containment Isolation System Actuation Due to Loss of Power from a Diesel Generator ENS 465112010-12-26T22:20:00026 December 2010 22:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to High Vibration on Main Generator Exciter ENS 459902010-06-09T08:31:0009 June 2010 08:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Closure of Main Steam Isolation Valves ENS 458882010-04-30T21:48:00030 April 2010 21:48:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Light Socket Short Causes Isolation Systems to Actuate ENS 453912009-09-30T04:23:00030 September 2009 04:23:00 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 Unit 2 Manually Scrammed After Trip of an Operating Condensate Pump and Rapidly Lowering Rvwl ENS 452902009-08-24T23:50:00024 August 2009 23:50:00 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 Condensate Booster Pump Trip Resulting in a Manual Reactor Scram ENS 448602009-02-18T09:51:00018 February 2009 09:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Due to Power Load Unbalance Signal on Main Generator Resulting in Reactor Scram ENS 448542009-02-16T11:13:00016 February 2009 11:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Loss of Stator Cooling Water ENS 445402008-10-05T03:08:0005 October 2008 03:08:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Following Reverse Power Signal on Main Generator ENS 441872008-05-05T08:32:0005 May 2008 08:32:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Power to Esf Buses During Transfer of Offsite Power Source ENS 438782008-01-01T03:40:0001 January 2008 03:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 3 Automatic Scram Due to Main Generator Load Reject Signal ENS 437182007-10-12T13:02:00012 October 2007 13:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Turbine Trip ENS 436132007-09-03T07:14:0003 September 2007 07:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Electro-Hydraulic Control (Ehc) System Leak ENS 435602007-08-11T22:51:00011 August 2007 22:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Neutron Monitoring Trip Signal ENS 434142007-06-09T16:00:0009 June 2007 16:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due Turbine Trip as a Result of High Moisture Separator Reheater Tank Level ENS 433812007-05-24T07:11:00024 May 2007 07:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Electro-Hydraulic Control (Ehc) System Leak ENS 430922007-01-11T14:16:00011 January 2007 14:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram When Turbine Output Breakers Opened ENS 428132006-08-30T03:25:00030 August 2006 03:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Electro-Hydraulic Oil Leak ENS 427872006-08-19T16:05:00019 August 2006 16:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram of Unit 3 Due to the Loss of Both Reactor Recirculation Pumps ENS 421022005-10-31T19:18:00031 October 2005 19:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Trip of Main Turbine ENS 419972005-09-17T16:29:00017 September 2005 16:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to Maintenance ENS 418962005-08-05T22:08:0005 August 2005 22:08:00 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 Rps Actuation Due to Low Reactor Water Level Caused by Loss of Reactor Feed Pumps ENS 415952005-04-13T15:53:00013 April 2005 15:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Rps Actuation Due to an Invalid Atws Logic Actuation ENS 414042005-02-11T22:29:00011 February 2005 22:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to a Load Rejection ENS 412192004-11-23T16:02:00023 November 2004 16:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Turbine Trip ENS 408622004-07-11T03:35:00011 July 2004 03:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to an Upscale Trip on Intermediate Range Monitors ENS 408582004-07-09T03:32:0009 July 2004 03:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Due to a Turbine Generator Load Rejection Signal 2024-08-30T15:51:00 | |
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