ENS 55732
ENS Event | |
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22:00 Feb 4, 2022 | |
Title | Automatic Reactor Scram |
Event Description | The following information was provided by the licensee via email:
At 1700 EST, on February 4, 2022 with the unit in Mode 1 at 58 percent power, the reactor automatically scrammed due to low Reactor water level due to a transient on the Feedwater System while preparing to shutdown for a refueling outage. The scram was not complex, with systems responding normally post-scram. Operations responded and stabilized the plant. Reactor water level has been recovered and maintained at normal level. Decay Heat is being removed by the Main Steam system to the main condenser using the Turbine Bypass Valves. All Control Rods inserted into the core. The transient occurred while in the process of removing the South Reactor Feed Pump from service. While reducing speed on the South, the North Reactor Feed Pump increased in speed and tripped on low suction. The plant was preparing to shut down for a refueling outage when the trip occurred. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Additionally, in preparation of plant shutdown, Primary Containment De-Inerting was in progress. The low Reactor water level caused an isolation of Primary Containment (Groups 4/13/15). The Primary Containment Isolation Event is being reported under 10 CFR 50.72(b)(3)(iv)(A). There was no impact to the health and safety of the public or plant personnel. The NRC resident has been notified. |
Where | |
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Fermi Michigan (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+-1.5 h-0.0625 days <br />-0.00893 weeks <br />-0.00205 months <br />) | |
Opened: | Whitney Hemingway 20:30 Feb 4, 2022 |
NRC Officer: | Brian Lin |
Last Updated: | Feb 4, 2022 |
55732 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (58 %) |
After | Hot Standby (0 %) |
Fermi with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 570462024-03-23T04:04:00023 March 2024 04:04:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 559642022-06-25T03:38:00025 June 2022 03:38:00 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 Turbine Trip ENS 557322022-02-04T22:00:0004 February 2022 22:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 547612020-07-02T03:05:0002 July 2020 03:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Power - Auto Initiation of Emergency Diesel Generator ENS 533362018-04-14T14:40:00014 April 2018 14:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 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 and Emergency Core Cooling System Injection ENS 513912015-09-14T03:05:00014 September 2015 03:05:00 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)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Manual Scram Due to Loss of Turbine Building Closed Cooling Water ENS 509032015-03-19T11:02:00019 March 2015 11:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to an Oscillation Power Range Monitor Upscale Actuation ENS 484872012-11-07T14:21:0007 November 2012 14:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Shutdown Due to Hydrogen In-Leakage to Stator Water Cooling System ENS 483092012-09-14T20:03:00014 September 2012 20:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to the Loss of the 120 Kv Switchyard ENS 480472012-06-25T17:30:00025 June 2012 17:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Feed Pump Trip Results in Manual Reactor Scram ENS 478682012-04-26T14:12:00026 April 2012 14:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of the Reactor Protection System During Testing ENS 463592010-10-24T20:41:00024 October 2010 20:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to a Turbine Trip Resulting from a Low Condenser Vacuum ENS 459792010-06-06T06:38:0006 June 2010 06:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Automatic Reactor Scram Due to Partial Loss of Offsite Power ENS 457892010-03-25T20:27:00025 March 2010 20:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Shutdown Due to Main Turbine Trip ENS 453942009-09-30T15:09:00030 September 2009 15:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Shutdown Due to Hydrogen In-Leakage to Stator Water Cooling System ENS 449422009-03-28T05:46:00028 March 2009 05:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram Due to Mode Switch Being Placed in Shutdown Following High Vibration on Main Turbine #1 Bearing ENS 439482008-01-31T20:44:00031 January 2008 20:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram in Response to Trip of Both Reactor Recirc Pumps ENS 437842007-11-15T08:13:00015 November 2007 08:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram - Initiation of Ari Caused by Level 2 Signal ENS 427382006-07-29T19:50:00029 July 2006 19:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram and Eccs Injection Due to Loss of Feedwater ENS 426432006-06-15T14:53:00015 June 2006 14:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Turbine Trip ENS 413542005-01-24T21:10:00024 January 2005 21:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Due to Unidentified Leakage Greater than 10 Gpm ENS 412432004-12-04T09:17:0004 December 2004 09:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to an Auto Voltage Regulator Trip ENS 410172004-09-04T03:45:0004 September 2004 03:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation 2024-03-23T04:04:00 | |