ENS 48964
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ENS Event | |
|---|---|
18:11 Apr 24, 2013 | |
| Title | Valid Actuation of an Emergency Diesel Generator Due to a Loss of Train a Reserve Feed to the Site |
| Event Description | On 4/24/13 at 1411 EDT, a fault occurred on the Unit 1 101 CD Reserve Auxiliary Transformer causing the 12 CD 34kV Reserve Feed Breaker to open resulting in a loss of Train A Reserve Feed to Unit 1 and Unit 2. The cause of the fault is still under investigation.
Unit 2 remains stable in 100% power. Unit 2 entered LCO 3.8.1, AC Source - Operating, Condition A, one required offsite circuit inoperable Restore Unit 2 reserve feed to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Unit 1 is currently in a refueling outage and offline. Unit 1 CD Emergency Diesel Generator (EDG) automatically started and loaded as expected. North Spent Fuel Pit Cooling Train lost power due to a load shed, which resulted in a 2 degree Fahrenheit rise in the Spent Fuel Pool Temperature. The North Spent Fuel Pit Cooling Pump was restarted on 1 CD EDG at 1447 EDT. South Spent Fuel Pool Cooling Train remained in-service the entire time. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Cook  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000315/LER-2013-002 |
| Time - Person (Reporting Time:+-0.93 h-0.0388 days <br />-0.00554 weeks <br />-0.00127 months <br />) | |
| Opened: | Randy Rose 17:15 Apr 24, 2013 |
| NRC Officer: | Charles Teal |
| Last Updated: | Apr 24, 2013 |
| 48964 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 571952024-06-27T12:04:00027 June 2024 12:04:00
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November 2011 10:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Aux Feedwater Pump Start After Main Feedwater Pump Trip ENS 472472011-09-07T12:54:0007 September 2011 12:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Main Turbine Trip from 100% Power ENS 464772010-12-14T02:19:00014 December 2010 02:19:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Auxiliary Feedwater System in Response to Loss of One Main Feedwater Pump ENS 463112010-10-06T04:08:0006 October 2010 04:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Auxiliary Feedwater System in Response to Valid Steam Generator Low-Low Level Signals ENS 458932010-05-02T12:58:0002 May 2010 12:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Auxiliary Feedwater System in Response to Loss of One Main Feedwater Pump ENS 452282009-07-26T19:06:00026 July 2009 19:06:00 10 CFR 50.72(b)(2)(iv)(B), 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421252005-11-08T08:58:0008 November 2005 08:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Reactor Coolant Pump Bus Undervoltage ENS 416392005-04-26T04:02:00026 April 2005 04:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip with Afw Actuation ENS 406602004-04-09T02:16:0009 April 2004 02:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Feedwater Flow Transient ENS 406222004-03-29T19:04:00029 March 2004 19:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Reactor Trip Bypass Breaker Manipulation Test ENS 404192003-12-30T18:30:00030 December 2003 18:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Tripped from 100% Power Due to Low Steam Generator 2024-06-27T12:04:00 | |
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