ENS 55390
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ENS Event | |
|---|---|
21:46 Jul 31, 2021 | |
| Title | Manual Reactor Trip of Unit 1 |
| Event Description | At 1646 [CDT] on 7/31/21, with Unit 1 in Mode 1 at 100 percent power, the reactor was manually tripped due to control board indications of a Unit 1 'B' Main Feed Pump trip. After the reactor trip, one of the Condenser Steam Dump valves cycled to intermediate and remained stuck. The Condenser Steam Dump Valve was isolated locally using manual isolation valves. The 'B' Feed Regulating Bypass Valve did not control in automatic and was taken to manual to control the level in 'B' Steam Generator. The Auxiliary Feedwater System automatically actuated as designed when the valid actuation signal was received. Operations stabilized the plant in Mode 3. Decay heat is being removed by atmospheric dump valves due to condenser unavailability. Unit 2 is unaffected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).
The NRC Resident Inspector has been notified. During the transient, all control rods inserted into the core. There is no known primary to secondary leakage. During the transient, no relief valves or safeties lifted. The plant is currently maintaining normal operating temperature and pressure with all safety equipment available. The plant is in its normal shutdown electrical lineup. |
| Where | |
|---|---|
Point Beach  Wisconsin (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:+-0.15 h-0.00625 days <br />-8.928571e-4 weeks <br />-2.0547e-4 months <br />) | |
| Opened: | Dan Heidel 21:37 Jul 31, 2021 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Jul 31, 2021 |
| 55390 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Point Beach with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 553902021-07-31T21:46:00031 July 2021 21:46:00
[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 of Unit 1 ENS 537792018-12-05T06:00:0005 December 2018 06:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip on Loss of Main Condenser Vacuum ENS 515702015-11-29T01:12:00029 November 2015 01:12:00 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 Generator Lockout After Voltage Regulator Malfunction ENS 515062015-10-29T08:48:00029 October 2015 08:48:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of the Auxiliary Feedwater System Due to Main Transformer Lockout ENS 506492014-12-03T02:50:0003 December 2014 02:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Failure of Condensate Pump ENS 487222013-02-06T17:43:0006 February 2013 17:43:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event - Loss of Offsite Power to Essential Buses for Greater than 15 Minutes ENS 481892012-08-15T01:31:00015 August 2012 01:31:00 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 in Anticipation of an Automatic Turbine Trip ENS 480532012-06-28T01:46:00028 June 2012 01:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to 100% Load Reject ENS 474782011-11-27T08:38:00027 November 2011 08:38:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Due to a Loss of Offsite Power During Switching Operations ENS 469572011-06-14T00:24:00014 June 2011 00:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip During Startup Physics Testing ENS 464822010-12-15T07:48:00015 December 2010 07:48:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 2 Manual Reactor Trip During Startup ENS 461292010-07-27T01:01:00027 July 2010 01:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Condenser Vacuum ENS 460802010-07-09T11:47:0009 July 2010 11:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to a Feedwater Regulating Valve Failure ENS 460322010-06-19T11:36:00019 June 2010 11:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Generator Lockout ENS 434072007-06-05T20:17:0005 June 2007 20:17:00 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 Feedwater Valve Failure ENS 421992005-12-13T09:39:00013 December 2005 09:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Loss of Condenser Vacuum ENS 407542004-05-15T16:54:00015 May 2004 16:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Diver Entangled in Intake Crib 2021-07-31T21:46:00 | |
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