ENS 57075
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ENS Event | |
|---|---|
04:35 Apr 13, 2024 | |
| Title | Automatic Reactor Trip |
| Event Description | The following information was provided by the licensee via phone and email:
At 0035 EDT on April 13, 2024, with Unit 1 at 97 percent power, the reactor automatically tripped due to 1 of 3 reactor coolant pump (RCP) low flow reactor trip [signal] associated with a loss of the A and B 4160 volt normal buses. Auxiliary feedwater and the 1-1 emergency diesel generator (EDG) automatically started on valid actuation signals. The 1-1 EDG sequenced on to supply all required loads per plant design. All control rods fully inserted and the trip was not complex with all systems responding normally post-trip. Operators have responded and stabilized the unit in Mode 3 [Hot Standby]. Decay heat is being removed by discharging steam to the main condenser via the condenser steam dump system with steam generators being supplied by the main feedwater system. Unit 2 is not affected by the event. 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). Due to the valid actuations of auxiliary feedwater and the 1-1 EDG, this event is reportable in accordance with 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 senior resident inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Power for the A-E Bus is on the 1-1 EDG. The D-F Bus is on offsite power. One electrical train of offsite power is down. |
| Where | |
|---|---|
| Beaver Valley Pennsylvania (NRC Region 1) | |
| 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:+-0.67 h-0.0279 days <br />-0.00399 weeks <br />-9.17766e-4 months <br />) | |
| Opened: | James (Jake) Davis 03:55 Apr 13, 2024 |
| NRC Officer: | Thomas Herrity |
| Last Updated: | Apr 13, 2024 |
| 57075 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (97 %) |
| After | Hot Standby (0 %) |
Beaver Valley with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 571322024-05-19T04:30:00019 May 2024 04:30:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 570752024-04-13T04:35:00013 April 2024 04:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 565272023-05-19T12:52:00019 May 2023 12:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System (AFW) ENS 559432022-06-15T11:24:00015 June 2022 11:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Automatic Auxiliary Feedwater Actuation ENS 555862021-11-17T18:13:00017 November 2021 18:13:00 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 Automatic Auxiliary Feedwater Actuation ENS 555722021-11-12T15:07:00012 November 2021 15:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Increasing Steam Generator Water Levels ENS 555072021-10-05T10:32:0005 October 2021 10:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Auxiliary Feedwater Actuation ENS 543692019-11-04T10:35:0004 November 2019 10:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Steam Dump Transient ENS 530562017-11-07T10:04:0007 November 2017 10:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip Due to Main Unit Generator Over Current ENS 501242014-05-20T12:35:00020 May 2014 12:35:00 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 Reactor Startup ENS 496972014-01-06T21:59:0006 January 2014 21:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Main Transformer Fault ENS 495052013-11-05T23:28:0005 November 2013 23:28:00 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 Notification of Unusual Event Due to Explosion and Fire in the Turbine Building ENS 493922013-09-30T06:38:00030 September 2013 06:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Start of Motor Driven Auxiliary Feedwater Pump ENS 467442011-04-10T07:45:00010 April 2011 07:45:00 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)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip While Performing a Technical Specification Required Shutdown ENS 450002009-04-20T05:15:00020 April 2009 05:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Actuation on Valid Steam Generator Hi-Hi Signal During Shutdown ENS 442392008-05-24T13:38:00024 May 2008 13:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Steam Generator Level Excursion ENS 428342006-09-08T01:57:0008 September 2006 01:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Spurious Opening of a Reactor Trip Breaker ENS 424672006-04-02T18:02:0002 April 2006 18:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Main Generator Trip ENS 403202003-11-13T16:35:00013 November 2003 16:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from 100% Power with Cause Being Investigated ENS 402472003-10-15T03:55:00015 October 2003 03:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Low "B" Steam Generator Water Level. 2024-05-19T04:30:00 | |
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