ENS 51678
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ENS Event | |
|---|---|
22:03 Jan 23, 2016 | |
| Title | Partial Loss of Power Results in Emergency Diesel Generators Starting |
| Event Description | At 1703 [EST] on 1/23/16, with Unit 1 and Unit 2 operating at 100% power, the North Anna 34.5 kv Bus 3, off-site power feed to the 'C' Reserve Station Service Transformer, was lost which resulted in the loss of power to the Unit 1 'H' Emergency Bus and the Unit 2 'J' Emergency Bus. Loss of 34.5kV Bus 3 resulted from feeder breaker L102 opening. As a result of the power loss, the 1H Emergency Diesel Generator and the 2J Emergency Diesel Generator automatically started as designed and restored power to the associated emergency bus. During this event, the Unit 1 'B' Charging Pump, 1-CH-P-18 automatically started as designed due to the loss of power event.
The valid actuation of these ESF components due to the loss of electrical power is reportable per 10 CFR 50.72 (b)(3)(iv)(A). The Unit 1 'H' Emergency Bus off-site power source was restored to service and the 1H Emergency Diesel Generator was secured and returned to Automatic. The Unit 2 'J' Emergency Bus power feed continues to be from the 2J Emergency Diesel Generator. Restoration of offsite power to operable status is currently being pursued. The Unit 1 'B' Charging Pump has been secured and returned to automatic. Both units are in a stable condition. An investigation is underway to determine the cause of the L102 feeder breaker opening resulting in the 34.5 kv Bus 3 loss of power. The licensee notified the NRC Resident Inspector |
| Where | |
|---|---|
North Anna  Virginia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-2.25 h-0.0938 days <br />-0.0134 weeks <br />-0.00308 months <br />) | |
| Opened: | Shaun Mchugh 19:48 Jan 23, 2016 |
| NRC Officer: | Vince Klco |
| Last Updated: | Jan 23, 2016 |
| 51678 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (99 %) |
| After | Power Operation (97 %) |
WEEKMONTHYEARENS 571482024-05-29T10:24:00029 May 2024 10:24:00
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ECCS Discharge Reactor Trip and Spurious Safety Injection ENS 432172007-03-07T08:05:0007 March 2007 08:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Autostart on Loss of "B" Reserve Station Service Transformer ENS 430722007-01-03T23:03:0003 January 2007 23:03:00 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 Card Failure ENS 429962006-11-16T07:26:00016 November 2006 07:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip ENS 424832006-04-08T02:31:0008 April 2006 02:31:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Group Step Counter Failure During Reactor Startup ENS 418982005-08-06T02:28:0006 August 2005 02:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Apparently Due to Lightning Strike ENS 408042004-06-10T17:13:00010 June 2004 17:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip While Performing Scheduled Solid State Protection Testing ENS 407842004-05-29T06:02:00029 May 2004 06:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Rod Position Indication Failure During Hot Rod Drop Test 2024-05-29T10:24:00 | |
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