ENS 41782
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ENS Event | |
|---|---|
16:20 Jun 17, 2005 | |
| Title | Automatic Reactor Scram Due to Ehc Malfunction |
| Event Description | At 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br /> (CDT) on June 17, 2005, the Unit 1 reactor automatically scrammed from 85% power due to a valid high reactor pressure signal. The maximum reactor pressure was approximately 1044 psig during the event. All control rods inserted to their full-in position. Initial indications are that the reactor pressure increase was caused by a malfunction in the Electro-Hydraulic Control (EHC) system, which resulted in closure of the main turbine control valves. The main turbine bypass valves (nine) opened as expected in response to the pressure increase. No reactor pressure vessel safety or relief valves were required to actuate during the event. Reactor water level decreased to approximately -20 inches, which resulted in automatic Group 2 and 3 isolations as expected. All systems responded properly to the event. Unit 1 is in Mode 3 with a cooldown in progress and reactor water level in the normal level band. An investigation into the Unit 1 scram is in progress.
Unit 2 remains at 94% power. This report is being made in accordance with 10CFR 50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). The licensee notified 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:+-1.3 h-0.0542 days <br />-0.00774 weeks <br />-0.00178 months <br />) | |
| Opened: | Jim Stortz 15:02 Jun 17, 2005 |
| NRC Officer: | Bill Gott |
| Last Updated: | Jun 17, 2005 |
| 41782 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (85 %) |
| 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 571412024-05-23T16:46:00023 May 2024 16:46:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Turbine Trip Signal ENS 570582024-03-28T01:46:00028 March 2024 01:46:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Reactor Protection System ENS 566762023-08-11T08:29:00011 August 2023 08:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram 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 2024-05-23T16:46:00 | |
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