ENS 56373
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ENS Event | |
|---|---|
06:05 Feb 19, 2023 | |
| Title | Specified System Actuation |
| Event Description | The following information was provided by the licensee via fax or email:
At 0105 EST on February 19, 2023, with the James A. FitzPatrick Nuclear Power Plant (JAF) at 100 percent power, a valid high main steam line radiation signal was received. An actuation of a fire protection foam system caused migration of high conductivity water into a low conductivity sump. Organic compounds were introduced into the primary coolant and resulted in a temporary increase in nitrogen-16 which was detected by main steam line radiation monitors and actuated primary containment isolation signals in more than one system. The reactor water recirculation sample system isolated. The signal also went to the normally isolated main steam line drain system and condenser air removal system. The event is reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A). The elevated radiation condition no longer exists. Health and safety of the public was not impacted by this event. The NRC Resident Inspector was notified. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+2.85 h0.119 days <br />0.017 weeks <br />0.0039 months <br />) | |
| Opened: | Michael Lewis 08:56 Feb 19, 2023 |
| NRC Officer: | Eric Simpson |
| Last Updated: | Feb 19, 2023 |
| 56373 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 563732023-02-19T06:05:00019 February 2023 06:05:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation ENS 561192022-09-26T07:06:00026 September 2022 07:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 520422016-06-24T16:15:00024 June 2016 16:15:00 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 Reactor Recirculation Pumps Degradation ENS 486762013-01-16T02:12:00016 January 2013 02:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of a 4160 Volt Bus While Performing Testing ENS 483862012-10-05T17:03:0005 October 2012 17:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Rps and Pciv Actuation Due to Loss of Offsite Power ENS 445462008-10-07T10:35:0007 October 2008 10:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation Due to Loss of Power During Testing ENS 437522007-10-28T04:59:00028 October 2007 04:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Lowering Intake Level ENS 436352007-09-12T10:35:00012 September 2007 10:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Following Intake Structure Traveling Screen Fouling ENS 419872005-09-14T06:13:00014 September 2005 06:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram on Low Reactor Vessel Water Level During Planned Maintenance ENS 400722003-08-14T20:26:00014 August 2003 20:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to a Loss of Offsite Power. 2023-02-19T06:05:00 | |
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