ENS 43784
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ENS Event | |
|---|---|
08:13 Nov 15, 2007 | |
| Title | Reactor Scram - Initiation of Ari Caused by Level 2 Signal |
| Event Description | At 03:13 EST 11/15/2007, a reactor scram occurred due to initiation of ARI caused by a Level 2 signal from Div 1 level instrumentation. The reactor mode switch was taken to shutdown in response to the trip of the recirc pumps initiated by ARI as directed by our Abnormal Operating procedures. All control rods fully inserted into the core. The lowest reactor vessel water level reached was 183 inches. The MSIV's were manually closed to control cooldown rate. Reactor water level is being controlled by CRD and reactor water cleanup blowdown.
At the time of the scram, protective tagging was being hung on the Division I Reference Leg Backfill system. At the time of the scram all ECCS systems and Emergency Diesel Generators were operable. This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), any event that results in actuation of the reactor protection system (RPS) when the reactor is critical. The licensee is investigating the cause of the scram. There was no ECCS injection. Primary plant pressure is 400 psig, and primary plant temperature is 335 degrees Fahrenheit. The scram is uncomplicated. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Fermi  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000341/LER-2007-002 |
| Time - Person (Reporting Time:+-1.65 h-0.0688 days <br />-0.00982 weeks <br />-0.00226 months <br />) | |
| Opened: | George Miller 06:34 Nov 15, 2007 |
| NRC Officer: | Joe O'Hara |
| Last Updated: | Nov 15, 2007 |
| 43784 - NRC Website
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WEEKMONTHYEARENS 570462024-03-23T04:04:00023 March 2024 04:04:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 559642022-06-25T03:38:00025 June 2022 03:38:00 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 Main Turbine Trip ENS 557322022-02-04T22:00:0004 February 2022 22:00:00 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 533362018-04-14T14:40:00014 April 2018 14:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram and Emergency Core Cooling System Injection ENS 513912015-09-14T03:05:00014 September 2015 03:05:00 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)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Manual Scram Due to Loss of Turbine Building Closed Cooling Water ENS 509032015-03-19T11:02:00019 March 2015 11:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to an Oscillation Power Range Monitor Upscale Actuation ENS 484872012-11-07T14:21:0007 November 2012 14:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Shutdown Due to Hydrogen In-Leakage to Stator Water Cooling System ENS 483092012-09-14T20:03:00014 September 2012 20:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to the Loss of the 120 Kv Switchyard ENS 480472012-06-25T17:30:00025 June 2012 17:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Feed Pump Trip Results in Manual Reactor Scram ENS 463592010-10-24T20:41:00024 October 2010 20:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to a Turbine Trip Resulting from a Low Condenser Vacuum ENS 459792010-06-06T06:38:0006 June 2010 06:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Automatic Reactor Scram Due to Partial Loss of Offsite Power ENS 457892010-03-25T20:27:00025 March 2010 20:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Shutdown Due to Main Turbine Trip ENS 453942009-09-30T15:09:00030 September 2009 15:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Shutdown Due to Hydrogen In-Leakage to Stator Water Cooling System ENS 449422009-03-28T05:46:00028 March 2009 05:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram Due to Mode Switch Being Placed in Shutdown Following High Vibration on Main Turbine #1 Bearing ENS 439482008-01-31T20:44:00031 January 2008 20:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram in Response to Trip of Both Reactor Recirc Pumps ENS 437842007-11-15T08:13:00015 November 2007 08:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram - Initiation of Ari Caused by Level 2 Signal ENS 427382006-07-29T19:50:00029 July 2006 19:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram and Eccs Injection Due to Loss of Feedwater ENS 426432006-06-15T14:53:00015 June 2006 14:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Turbine Trip ENS 413542005-01-24T21:10:00024 January 2005 21:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Due to Unidentified Leakage Greater than 10 Gpm ENS 412432004-12-04T09:17:0004 December 2004 09:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to an Auto Voltage Regulator Trip ENS 410172004-09-04T03:45:0004 September 2004 03:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation 2024-03-23T04:04:00 | |
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