ENS 48309
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ENS Event | |
|---|---|
20:03 Sep 14, 2012 | |
| Title | Automatic Reactor Scram Due to the Loss of the 120 Kv Switchyard |
| Event Description | At 1603 EDT, Fermi 2 automatically scrammed due to onsite loss of 120 kV switchyard. All control rods fully inserted. The lowest Reactor Water Level (RWL) reached was 98 inches. Division I diesels, EDG-11 and EDG-12, automatically started and loaded. HPCI and RCIC automatically started and restored RWL. RWL is currently being maintained in the normal level band with Condensate/Feed and Control Rod Drive (CRD) systems. No Safety Relief Valves (SRV) actuated. All isolations and actuations for RWL 3 and 2 occurred as expected. Investigation into loss of 120 kV switchyard continues.
At the time of the scram, all Emergency Core Cooling (ECCS) and Emergency Diesel Generators (EDG) were operable with the exception of EDG-11 which was available vice operable due to ventilation work, and no other safety related equipment was out of service. This report is being made in accordance with 10CFR50.72(b)(2)(iv)(A), any event that results in ECCS discharge into the reactor coolant system as a result of a valid signal and 10CFR50.72(b)(2)(iv)(B), any event that results in actuation of the reactor protection system (RPS) when the reactor is critical. EDG-11 and EDG-12 are performing all of their functions and providing power to the Division I AC buses. Temperatures are being monitored in the room containing EDG-11 and the room is not approaching any temperature limits. The MSIVs are open with decay heat being removed via steam to the main condenser using the bypass valves. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Fermi  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000341/LER-2012-005 |
| Time - Person (Reporting Time:+-0.6 h-0.025 days <br />-0.00357 weeks <br />-8.2188e-4 months <br />) | |
| Opened: | Brett Jebbia 19:27 Sep 14, 2012 |
| NRC Officer: | Dong Park |
| Last Updated: | Sep 14, 2012 |
| 48309 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (68 %) |
| After | Hot Shutdown (0 %) |
Fermi with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge | |
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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