ENS 47847
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ENS Event | |
|---|---|
20:11 Apr 18, 2012 | |
| Title | Unit Two Automatic Reactor Scram on High Reactor Pressure |
| Event Description | On April 18, 2012, at 1511 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.749355e-4 months <br /> (CDT), an automatic scram occurred on high reactor pressure. The pressure increase occurred during post-modification testing on the main generator automatic voltage regulator, which had been upgraded during the recent refueling outage.
Following the reactor scram, reactor water level decreased to approximately zero inches, which resulted in automatic Group II and III isolations (Reactor Water Clean Up and Secondary Containment Isolation) as expected. All systems responded properly to the event. The cause of the event is still under investigation. Unit 1 was unaffected by the event and remains at 100% power. This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). All Control Rods fully inserted, decay heat is being removed through the bypass steam valves to the main condenser, and the plant remains in a normal shutdown electrical alignment. The high reactor pressure appears to have been caused by a load rejection associated with the main generator voltage regulator testing. The licensee has informed the NRC Resident Inspector. |
| Where | |
|---|---|
Quad Cities  Illinois (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:+-2.07 h-0.0863 days <br />-0.0123 weeks <br />-0.00284 months <br />) | |
| Opened: | James Cox 18:07 Apr 18, 2012 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Apr 18, 2012 |
| 47847 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (20 %) |
| After | Hot Shutdown (0 %) |
Quad Cities with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 566762023-08-11T08:29:00011 August 2023 08:29:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 562102022-11-04T19:00:0004 November 2022 19:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Due to Rising Water Level ENS 559752022-07-04T06:04:0004 July 2022 06:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Manual Scram Due to Lowering Reactor Water Level ENS 551462021-03-20T01:30:00020 March 2021 01:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Unit 1 Emergency Diesel Generator ENS 542392019-08-25T16:02:00025 August 2019 16:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Main Generator Ground Fault Relay ENS 536932018-10-24T05:00:00024 October 2018 05:00:00 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 1/2 Edg Auto Started and Lpci/Core Spray Inoperable Due to Loss of Safety Bus ENS 536262018-09-26T05:00:00026 September 2018 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Generator Output Breaker Trip ENS 509492015-04-03T02:33:0003 April 2015 02:33:00 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 Steam Leak ENS 499882014-04-02T18:40:0002 April 2014 18:40:00 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 Alert Declared Due to Fire in Unit 2 Turbine Building ENS 478472012-04-18T20:11:00018 April 2012 20:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit Two Automatic Reactor Scram on High Reactor Pressure ENS 469512011-06-13T10:10:00013 June 2011 10:10:00 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 Steam Leak in Turbine Building ENS 461842010-08-17T19:14:00017 August 2010 19:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Initiated Due to Recirculation Pump Trip ENS 461692010-08-12T08:58:00012 August 2010 08:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Reactor Automatic Scram Due to Turbine Trip ENS 431982007-02-28T07:20:00028 February 2007 07:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 2 Reactor Manually Scrammed Due to Decreasing Condenser Vacuum ENS 425742006-05-14T14:57:00014 May 2006 14:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Automatic Start ENS 423562006-02-22T07:22:00022 February 2006 07:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Valid Main Turbine Load Reject Signal ENS 417822005-06-17T16:20:00017 June 2005 16:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Ehc Malfunction ENS 406252004-03-30T13:40:00030 March 2004 13:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram During Turbine Thrust Bearing Wear Detector Testing 2023-08-11T08:29:00 | |
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