ENS 55856
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ENS Event | |
|---|---|
06:24 Apr 23, 2022 | |
| Title | Manual Reactor Trip During Control Rod Testing |
| Event Description | The following information was provided by the licensee via fax or email:
On April 23, 2022, at 0224 [EDT] hours, with Unit 2 in Mode 1 at 100 percent power, two control rods dropped during control rod testing resulting in misalignment, which required a manual reactor trip in accordance with plant procedure. All safety systems functioned as expected. The Auxiliary Feedwater system actuated as designed to provide makeup flow to the steam generators. Operations responded and stabilized the plant. Decay heat is being removed by the steam generator power operated relief valves. 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). The automatic start of the Auxiliary Feedwater system is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The cause of the dropped rods is being investigated. Unit 1 is not affected. 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: Electrical power is in normal off-site arrangement. All emergency electrical supplies are available. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| 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:+-0.33 h-0.0138 days <br />-0.00196 weeks <br />-4.52034e-4 months <br />) | |
| Opened: | Wil Fowler 06:04 Apr 23, 2022 |
| NRC Officer: | Thomas Herrity |
| Last Updated: | Apr 23, 2022 |
| 55856 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Catawba with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 570262024-03-13T01:11:00013 March 2024 01:11:00
[Table view]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 548882020-09-08T13:25:0008 September 2020 13:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Over Power Delta Temperature ENS 545232020-02-12T23:00:00012 February 2020 23:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip 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 2024-03-13T01:11:00 | |
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