ENS 48869
ENS Event | |
|---|---|
15:33 Mar 31, 2013 | |
| Title | Notification of Unusual Event Declared Due to a Breaker Explosion in the Protected Area |
| Event Description | At 0750 [CDT] on 3/31/2013, during movement of the Unit 1 Main Turbine Generator Stator (~500 tons), the Unit 1 turbine temporary lift device failed. This caused a loss of all off-site power on Unit 1. The ANO Unit 1 #1 and #2 EDG [Emergency Diesel Generator] have started and are supplying A-3 4160V switchgear and A-4 4160V switchgear. P-4A Service Water pump and P-4C Service Water pump has been verified running. Unit 1 has entered [procedures] 1202.007 - Degraded Power, 1203.028 - Loss of Decay Heat, and 1203.050 - Spent Fuel Emergencies. Unit 1 is in MODE 6.
ANO-1 entered TS 3.8.2 A, 'One Required Offsite Circuit Inoperable'. All required actions are complete. The event caused a loss of decay heat removal on ANO Unit 1 which was restored in 3 minutes and 50 seconds. Unit 2 tripped and is in MODE 3. Emergency Feed Water was initiated on Unit 2 and Unit 2 was in [Technical Specification] 3.0.3 from 0817 [CDT] to 0848 [CDT] due to Emergency Feedwater. Unit 2 is being powered by off-site. Unit 2 Startup 3 [transformer] lock out at 0921 [CDT]. [Bus] 2A1 is on Start up 2 [transformer] and [bus] 2A3 is on #2 EDG. 10CFR50.72 (b)(3)(iv)(A) - 4-hr. notification due to the ES [Engineered Safeguard Feature] actuation on both Unit 1 and Unit 2. 10CFR50 72 (b)(2)(iv)(B) - 4-hr. notification due to RPS [Reactor Protection System] actuation on Unit 2. 10CFR50.72 (b)(2)(xi) - 4-hr. notification due to Government Notification. 29CFR1904.39a - [OSHA] 8-hr. notification due to death on site. At 1033 [CDT] on 3/31/2013, Unit 2 entered a Notification of Unusual Event based on EAL HU4 due to damage in 2A1 switchgear. Notification of the NUE will be made lAW Emergency Plan requirements. Follow-up notifications will be made as appropriate. At this time, the full extent of structural damage on Unit 1 is not known. There was one known fatality and 4 known serious injuries to workers. The local coroner is on site for the fatality and the injured personnel have been transported offsite to local hospitals. Investigation into the cause of the failure and extent of damage is ongoing. On Unit 2, all rods inserted during the trip. The core is being cooled via natural circulation. Decay heat is being removed via steam dumps to atmosphere. There is no known primary to secondary leakage. The licensee has notified the State of Arkansas, local authorities, OSHA and the NRC Resident Inspector. Notified DHS SWO, DHS NICC, FEMA and Nuclear NSSA (via email).
The licensee terminated the NOUE at 1821 CDT. The basis for termination was that the affected bus (2A2) is de-energized and no other equipment on Unit 2 was damaged. The licensee has notified the state and local authorities and will be notifying the NRC Resident Inspector. Notified R4DO (Pick), NRR EO (Howe), IRD (Gott), DHS SWO, DHS NICC, FEMA and Nuclear SSA (via email).
The licensee made the following edits to the third paragraph of their original report (edits in quotes): Unit 2 tripped and is in MODE 3. Emergency Feed Water initiated on Unit 2. Unit 2 was in [Technical Specification] 3.0.3 from 0817 [CDT] to 0848 [CDT] due to Emergency Feedwater "being procedurally overridden." Unit 2 "was initially" being powered by off-site. Unit 2 Startup 3 Lock out occurred at 0921. 2A1 is now on Startup 2, and "2A4" is on #2 EDG. Notified R4DO (Kellar) via email. |
| Where | |
|---|---|
Arkansas Nuclear  Arkansas (NRC Region 4) | |
| Reporting | |
| Emergency class: | Unusual Event |
| 10 CFR 50.72(a) (1) (i), Emergency Class Declaration 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release | |
| Time - Person (Reporting Time:+-3.6 h-0.15 days <br />-0.0214 weeks <br />-0.00493 months <br />) | |
| Opened: | Phillip Fore 11:57 Mar 31, 2013 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Apr 2, 2013 |
| 48869 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Arkansas Nuclear with 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 563512023-02-14T17:03:00014 February 2023 17:03:00
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Notification of Onsite Chemical Spill ENS 516072015-12-15T11:44:00015 December 2015 11:44:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Feed to One Steam Generator ENS 507392015-01-15T21:45:00015 January 2015 21:45:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Offsite Notification Due to Hospitalized Injured Employee ENS 501382014-05-24T15:09:00024 May 2014 15:09:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Offsite Notification Due to Individual Requiring Assistance from Offsite Emergency Personnel ENS 500632014-04-28T01:12:00028 April 2014 01:12:00 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 an Auxiliary Trip on Core Protection Calculator ENS 499952014-04-03T18:01:0003 April 2014 18:01:00 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Reactor Coolant System Pressurizer Pressure ENS 478242012-04-11T17:40:00011 April 2012 17:40:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Drill Message Inadvertently Mistaken for Actual Event ENS 465552011-01-20T02:58:00020 January 2011 02:58:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Notice of Unusual Event Due to a Security Event ENS 458722010-04-26T05:00:00026 April 2010 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 1 Experienced an Automatic Reactor Trip During an Ni Calibration ENS 458542010-04-18T18:57:00018 April 2010 18:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Reactor Startup ENS 455492009-12-08T14:42:0008 December 2009 14:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Low Steam Generator Level Caused by Loss of Main Feed Water Pump ENS 453672009-09-20T10:11:00020 September 2009 10:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Auto Start During Surveillance Testing ENS 449062009-03-14T02:51:00014 March 2009 02:51:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Feedwater Regulating Valve Failure Leads to Manual Reactor Trip ENS 448372009-02-07T16:59:0007 February 2009 16:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to a Fire Onsite ENS 448312009-02-05T21:24:0005 February 2009 21:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 1 Manually Tripped Due to Control Rod Drive Motor High Temperatures ENS 447362008-12-20T18:12:00020 December 2008 18:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip When Control Rod Bank Inserted Without Operator Action ENS 447162008-12-12T14:55:00012 December 2008 14:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 1 Was Manually Tripped from 32% Power Due to an Abnormal Rod Pattern ENS 441252008-04-07T18:45:0007 April 2008 18:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Core Element Assembly Calculators Declared Inoperable ENS 437422007-10-24T04:05:00024 October 2007 04:05:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Alert Declared Due to Electrical Fire in the Auxiliary Building ENS 429492006-10-30T19:04:00030 October 2006 19:04:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Alert Declaration Due to Electrical Fire Affecting One Esf Train ENS 422292005-12-26T16:47:00026 December 2005 16:47:00 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 Turbine Trip ENS 419072005-08-10T13:15:00010 August 2005 13:15:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Spurious Activation of Off-Site Emergency Plan Sirens ENS 414752005-03-09T19:04:0009 March 2005 19:04:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Offsite Notification Due to Investigation of Inadvertent Siren Activation ENS 410562004-09-19T14:34:00019 September 2004 14:34:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Offsite Notification Due to Siren Activation ENS 402042003-09-28T05:13:00028 September 2003 05:13:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release Offsite Notification Due to Report of Emergency Siren Actuation ENS 401192003-08-29T19:28:00029 August 2003 19:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on High Rcs Pressure 2023-02-14T17:03:00 | |