ENS 54932
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ENS Event | ||
|---|---|---|
22:49 Aug 6, 2020 | ||
| Title | 60-Day Optional Telephonic Notification of an Invalid Actuation of a General Containment Isolation Signal Affecting More than One System | |
| Event Description | This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and10 CFR 50.73(a)(1) to describe an invalid actuation of a general containment isolation signal affecting more than one system.
On August 6, 2020, at approximately 1749 CDT, Browns Ferry Nuclear Plant (BFN), Unit 2 experienced a loss of Reactor Protection System (RPS) Bus 2A. Primary Containment Isolation System (PCIS) Groups 2, 3, 6, and 8 isolated in response to this event. The PCIS isolations caused the initiation of Standby Gas Treatment (SBGT) trains A, B, and C, and Control Room Emergency Ventilation (CREV) subsystem A. Unit 2 declared RCS leakage detection instrumentation inoperable and entered TS LCO 3.4.5 condition A, B, and D with required action D.1 to enter LCO 3.0.3 immediately. Unit 2 entered TS LCO 3.0.3 with required actions to be in Mode 2 within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, Mode 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, and Mode 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. Upon investigation, it was discovered that an age-related overheating condition resulted in the failure of the 2A RPS Motor Generator (MG) set, causing the feeder beaker from the 2A 480v Remote Motor-Operated Valve distribution board to trip. On August 6, 2020, at approximately 1808 CDT, Operations personnel commenced restoration of Unit 2 to normal after transferring 2A RPS to its alternate power supply. The 2A RPS MG Set drive motor was replaced on August 24, 2020. Plant conditions which initiate PCIS Group 2 actuations are Reactor Vessel (RV) Low Water Level or Drywell High Pressure. Plant conditions which initiate PCIS Group 3 actuations are RV Low Water Level or Reactor Water Cleanup Area High Temperature. Plant conditions which initiate PCIS Group 6 actuations are RV Low Water Level, High Drywell Pressure, or Reactor Building Ventilation Exhaust High Radiation. Plant conditions which initiate PCIS Group 8 actuations are Reactor Vessel (RV) Low Water Level or Drywell High Pressure. At the time of the event, these conditions did not exist; therefore, the actuation of the PCIS was invalid. All affected safety systems responded as expected. There were no safety consequences or impact to the health and safety of the public as a result of this event. This event was entered into the Corrective Action Program as Condition Report 1628707. The NRC Resident Inspector has been notified of this event. | |
| Where | |
|---|---|
Browns Ferry  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+1431.6 h59.65 days <br />8.521 weeks <br />1.961 months <br />) | |
| Opened: | Casey Cartwright 14:25 Oct 5, 2020 |
| NRC Officer: | Jeffrey Whited |
| Last Updated: | Oct 5, 2020 |
| 54932 - NRC Website
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WEEKMONTHYEARENS 556602021-10-20T13:05:00020 October 2021 13:05:00 10 CFR 50.73(a)(1), Submit an LER Invalid Actuation of a General Containment Isolation Signal Affecting More than One System ENS 552872021-04-01T18:02:0001 April 2021 18:02:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Telephonic Notification of Invalid Actuation of a General Containment Isolation Signal Affecting More than One System ENS 549322020-08-06T22:49:0006 August 2020 22:49:00 10 CFR 50.73(a)(1), Submit an LER | 60-Day Optional Telephonic Notification of an Invalid Actuation of a General Containment Isolation Signal Affecting More than One System ENS 549312020-08-06T06:28:0006 August 2020 06:28:00 10 CFR 50.73(a)(1), Submit an LER | 60-Day Optional Telephonic Notification of an Invalid Specified System Actuation ENS 547092020-03-16T06:02:00016 March 2020 06:02:00 10 CFR 50.73(a)(1), Submit an LER Invalid Specified System Actuation ENS 546972020-03-09T01:21:0009 March 2020 01:21:00 10 CFR 50.73(a)(1), Submit an 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Notification of Invalid Specified System Actuation ENS 480062012-04-11T20:15:00011 April 2012 20:15:00 10 CFR 50.73(a)(1), Submit an LER Invalid System Actuation Resulting from Post Maintenance Testing ENS 474502011-09-19T16:00:00019 September 2011 16:00:00 10 CFR 50.73(a)(1), Submit an LER Invalid Group 6 Isolation Signal ENS 470032011-05-01T07:44:0001 May 2011 07:44:00 10 CFR 50.73(a)(1), Submit an LER Invalid Rps (Scram) Actuation ENS 468802011-03-30T19:43:00030 March 2011 19:43:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Telephonic Notification of Invalid Rps Signal Due to Loss of Variable Leg of Level Transmitter ENS 468812011-03-27T01:05:00027 March 2011 01:05:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Telephonic Notification of Invalid Primary Containment Isolation Signal Due to Maintenance ENS 466562011-01-03T21:15:0003 January 2011 21:15:00 10 CFR 50.73(a)(1), Submit an LER 60 Day Telephone Notificaton Concerning Invalid Containment Isolation System Actuations ENS 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00:58:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System (Pcis) Actuation ENS 428672006-08-09T14:51:0009 August 2006 14:51:00 10 CFR 50.73(a)(1), Submit an LER Invalid Eecw Pump Actuation During Testing ENS 428372006-07-18T09:47:00018 July 2006 09:47:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System Actuation Due to Loss of Power to One Reactor Protection System Bus ENS 423892006-01-13T17:57:00013 January 2006 17:57:00 10 CFR 50.73(a)(1), Submit an LER Unplanned, Invalid Actuation of Emergency Diesel Generator ENS 422152005-11-15T14:05:00015 November 2005 14:05:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System (Pcis) Actuation ENS 411812004-09-28T18:02:00028 September 2004 18:02:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System Actuation from Loss-Of-Power to Reactor Protection System (Rps) Bus 2A ENS 411802004-09-25T23:14:00025 September 2004 23:14:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System Actuation from Loss-Of-Power to Reactor Protection System (Rps) Bus 3B 2021-04-01T18:02:00 [Table view] | |
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