ENS 57026
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ENS Event | |
|---|---|
01:11 Mar 13, 2024 | |
| Title | Loss of Power to Containment Radiation Monitors |
| Event Description | The following information was provided by the licensee via phone and email:
On March 12, 2024, at 2111 EDT, a valid containment ventilation isolation train 'A' and 'B' signal was received due to a spurious loss of power to 1EMF-38 (containment particulate radiation monitor) and 1EMF-39 (containment gas radiation monitor). The power to 1EMF-38 and 1EMF-39 was restored. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: There were no plant evolutions ongoing at the time of the event and the cause of the loss of power is under investigation. There was no impact to Unit 2.
After further review of the event, it was determined the actuation of the associated containment ventilation isolation train 'A' and 'B' was not valid. This is due to the loss of power being associated with the control room modules for 1EMF-38 and 1EMF-39, and not a result of an actual sensed parameter or plant condition. Therefore, this event notification is being retracted. The NRC Resident Inspector has been notified. Notified R2DO (Miller) |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+1.3 h0.0542 days <br />0.00774 weeks <br />0.00178 months <br />) | |
| Opened: | Joshua Gower 02:29 Mar 13, 2024 |
| NRC Officer: | Kerby Scales |
| Last Updated: | Mar 13, 2024 |
| 57026 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 573442024-09-27T11:46:00027 September 2024 11:46:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Condenser Vacuum ENS 570262024-03-13T01:11:00013 March 2024 01:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Power to Containment Radiation Monitors ENS 561772022-10-24T12:57:00024 October 2022 12:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Auxiliary Feedwater System Actuation ENS 558562022-04-23T06:24:00023 April 2022 06:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Control Rod Testing ENS 555492021-10-27T18:29:00027 October 2021 18:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the 1B EDG Load Sequencer on Bus Undervoltage Condition ENS 552292021-05-01T11:55:0001 May 2021 11:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Actuation of the Auxiliary Feedwater System ENS 543072019-10-02T08:15:0002 October 2019 08:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Containment Spray System ENS 532712018-03-19T07:29:00019 March 2018 07:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Actuation of Auxiliary Feedwater System During Maintenance ENS 467802011-04-23T13:21:00023 April 2011 13:21:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Auxiliary Feedwater Pump Start While Cooling Down Reactor ENS 435972007-08-25T14:58:00025 August 2007 14:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Autostart of All Emergency Diesel Generators Due to a Grid Disturbance ENS 412462004-12-06T02:35:0006 December 2004 02:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip/Reactor Trip Due to Moisture Separator Reheater (Msr) High Level Trip Signal. ENS 411542004-10-28T04:52:00028 October 2004 04:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip After Shutdown Bank Dropped Into Core ENS 405382004-02-22T22:30:00022 February 2004 22:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped After the "B" Sg Feedwater Isolation Valve Failed Closed ENS 401142003-08-29T06:03:00029 August 2003 06:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Catawba Unit 1 Automatic Reactor Trip Due to Reactor Protection System Actuation 2024-09-27T11:46:00 | |
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