ENS 53336
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ENS Event | |
|---|---|
14:40 Apr 14, 2018 | |
| Title | Automatic Reactor Scram and Emergency Core Cooling System Injection |
| Event Description | At 1040 EDT, Fermi 2 automatically scrammed on RPV [Reactor Pressure Vessel] Level 3 following a loss of the Division 1 Station System Transformer (SST) #64. All control rods fully inserted. HPCI [High Pressure Coolant Injection] and RCIC [Reactor Core Isolation Cooling] automatically started as designed on Reactor Water Level (RWL) 2 and restored RWL. The lowest RWL reached was 101.8 inches [above Top of Active Fuel]. HPCI injected for approximately 35 seconds. RWL is currently being maintained in the normal level band with RCIC. No Safety Relief Valves (SRVs) actuated. All isolations and actuations for RWL 3 and 2 occurred as expected. Investigation into loss of SST #64 continues. At the time of the scram, all Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDGs) were operable, and no 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 the actuation of the Reactor Protection System (RPS) when the reactor is critical. Following the loss of power and reactor scram, the Division 2 EECW [Emergency Equipment Cooling Water] Temperature Control Valve (TCV) controller was in Emergency Manual and maintaining max cooling. Operators placed the controller in Auto and the TCV is controlling normally. The NRC Senior Resident has been notified. Decay heat is being removed via Division 2 steam dumps to the condenser. The plant is in a modified shutdown electric lineup with offsite power available and stable. Emergency diesel generators did automatically start and load.
This update provides additional clarification of the applicable reporting criteria for this event associated with Primary Containment Isolation Actuations. All isolations and actuations for RWL (Groups 4, 13, and 15) and RWL 2 (Groups 2, 10, 11, 12, 14, 16, 17, and 18) occurred as expected. This report is also being made in accordance with 10CFR50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any systems listed in paragraph (b)(3)(iv)(B): RPS, HPCI, and RCIC. RPV pressure is being maintained by the bypass valves to the main condenser. All actuations that occurred were fully completed and restored. The licensee notified the NRC Resident Inspector. Notified R3DO (Stone).
This update provides additional information regarding the specified system actuations and an additional applicable reporting criteria. The loss of Division 1 Station System Transformer (SST) #64 at 1040 EDT on 4/14/2018 resulted in the automatic initiation of Emergency Diesel Generators (EDG) 11 and 12. The EDGs started as expected and continue to supply their associated busses. This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), as an event or condition that resulted in a valid actuation of any system listed in paragraph (b)(3)(iv)(B), including EDGs. In addition, the loss of the Division 1 SST #64 resulted in the expected transfer from the normal to alternate power source for the Low Pressure Coolant Injection (LPCI) swing bus, rendering LPCI loop select inoperable. The alternate power source continued to energize the LPCI swing bus throughout the event until the system was realigned to the normal power source at 1239 EDT on 4/14/2018. This condition is reportable pursuant to 10CFR50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector. Notified R3DO (Stone). |
| 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 10 CFR 50.72(b)(3)(iv)(A), ECCS Actuation 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+-0.1 h-0.00417 days <br />-5.952381e-4 weeks <br />-1.3698e-4 months <br />) | |
| Opened: | Jeff Myers 14:34 Apr 14, 2018 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Apr 15, 2018 |
| 53336 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Fermi with 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 | |
WEEKMONTHYEARENS 559642022-06-25T03:38:00025 June 2022 03:38:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor SCRAM Due to Main Turbine Trip ENS 558942022-05-11T22:14:00011 May 2022 22:14:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection Inoperable ENS 557322022-02-04T22:00:0004 February 2022 22:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor SCRAM ENS 554232021-08-22T09:29:00022 August 2021 09:29:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident HPCI Declared Inoperable ENS 554032021-08-11T10:34:00011 August 2021 10:34:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident HPCI Inoperability ENS 555582021-06-03T06:41:0003 June 2021 06:41:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection Inoperable Due to LOW Level Instrumentation ENS 547612020-07-02T03:05:0002 July 2020 03:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Power - 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Mitigate the Consequences of an Accident High Pressure Coolant Injection Declared Inoperable ENS 534352018-05-31T18:20:00031 May 2018 18:20:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Reactor Water Cleanup System Declared Inoperable ENS 534292018-05-27T10:30:00027 May 2018 10:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Reactor Water Cleanup System Declared Inoperable 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 529582017-09-09T14:00:0009 September 2017 14:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Mechanical Draft Cooling Tower Fans Declared Inoperable ENS 523312016-10-28T19:00:00028 October 2016 19:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Standby Liquid Control Technical Specification Not Met ENS 516762016-01-23T00:35:00023 January 2016 00:35:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Low Pressure Coolant Injection Pump Isolation Valve Would Not Reopen ENS 517552016-01-06T20:14:0006 January 2016 20:14:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Power Reduction Due to Automatic Opening of the Turbine Bypass Valves 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 508742015-03-09T19:21:0009 March 2015 19:21:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Swing Bus Automatic Throwover Failure ENS 517562015-02-21T05:30:00021 February 2015 05:30:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Power Reduction Due to Automatic Opening of a Turbine Bypass Valve ENS 498012014-02-06T17:54:0006 February 2014 17:54:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Emergency Equipment Cooling Water in Manual Override Due to Human Performance Error ENS 488862013-04-03T14:53:0003 April 2013 14:53:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Cooling Water Makeup Pump Failed to Start During a Surveillance Test 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 478682012-04-26T14:12:00026 April 2012 14:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of the Reactor Protection System During Testing ENS 472422011-09-06T05:04:0006 September 2011 05:04:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Indication of Hpci Minimum Flow Valve Position Lost ENS 465152010-12-28T17:20:00028 December 2010 17:20:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection System Inoperable Due to Inoperable Minimum Flow Valve 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 450352009-04-30T14:39:00030 April 2009 14:39:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Hpci Declared Inoperable Due to Failure of Test Line Pressure Control Valve During Surveillance Test 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 448112009-01-28T12:30:00028 January 2009 12:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Coolant Injection System Inoperable ENS 446982008-12-05T02:18:0005 December 2008 02:18:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Unplanned Hpci Inoperability ENS 440992008-03-26T14:45:00026 March 2008 14:45:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Pressure Boundary Door Blocked Open ENS 440622008-03-13T18:45:00013 March 2008 18:45:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Reactor Building to Torus Vacuum Breaker Pressure Switches May Not Perform Design Function 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 427832006-08-17T23:00:00017 August 2006 23:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Emergency Diesel Generators Inoperable Due to Undersized Breaker Control Transformers 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 426222006-06-06T20:00:0006 June 2006 20:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Failure to Meet Emergency Equipment Service Water Surveillance Requirement ENS 422242005-12-23T03:25:00023 December 2005 03:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Eecw Temperature Control Valve Not Fully Open ENS 417802005-06-16T13:23:00016 June 2005 13:23:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Rhr Lpci Divisions Inoperable Due to Valve Failure 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 ENS 402102003-10-01T00:50:0001 October 2003 00:50:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required by Technical Specifications Due to Inoperable Control Center Hvac 2022-06-25T03:38:00 | |
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