ENS 47628
ENS Event | |
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01:30 Feb 1, 2012 | |
Title | Manual Trip Due to a Primary to Secondary Leak Greater than 30 Gal/Hr |
Event Description | At 1505 PST, Unit 3 entered Abnormal Operation Instruction S023-13-14 'Reactor Coolant Leak' for a steam generator leak exceeding 5 gallons per day.
At 1549 PST, the leak rate was determined to be 82 gallons per day. At 1610 PST, a leak rate greater than 75 gallons per day with an increasing rate of leakage exceeding 30 gallons per hour was established and entry into S023-13-28 'Rapid Power Reduction' was performed. At 1630 PST, commenced rapid power reduction per S023-13-28 'Rapid Power Reduction'. At 1731 PST, with reactor power at 35% the Unit was manually tripped. At 1738 PST, Unit 3 entered Emergency Operation Instruction S023-12-4 'Steam Generator Tube Rupture'. At 1800 PST the affected steam generator was isolated. All control rods fully inserted on the trip. Decay heat is being removed thru the main steam bypass valves into the main condenser. Main feedwater is maintaining steam generator level. No relief valves lifted during the manual trip. The plant is in normal shutdown electrical lineup. Unit 2 is presently in a refueling outage and was not affected by this event. The licensee has notified the NRC Resident Inspector. The licensee has issued a press release. |
Where | |
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San Onofre California (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
Time - Person (Reporting Time:+-2.53 h-0.105 days <br />-0.0151 weeks <br />-0.00347 months <br />) | |
Opened: | Doug Foote 22:58 Jan 31, 2012 |
NRC Officer: | John Knoke |
Last Updated: | Jan 31, 2012 |
47628 - NRC Website
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Unit 3 | |
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Reactor critical | Critical |
Scram | Yes, Manual Scram |
Before | Power Operation (100 %) |
After | Hot Standby (0 %) |
WEEKMONTHYEARENS 476282012-02-01T01:30:0001 February 2012 01:30:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to a Primary to Secondary Leak Greater than 30 Gal/Hr ENS 472522011-09-08T22:38:0008 September 2011 22:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Grid Disturbance ENS 453472009-09-13T19:43:00013 September 2009 19:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Following Turbine Trip for Loss of Condenser Vacuum ENS 442732008-06-06T05:56:0006 June 2008 05:56:00 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 Low Cooling Flow to Main Generator Rectifier ENS 434352007-06-21T05:50:00021 June 2007 05:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Failed Instrument Air Header Leads to Manual Reactor Trip ENS 413682005-02-03T20:27:0003 February 2005 20:27:00 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 Unit Auxiliary Transformer Trip ENS 412092004-11-19T16:07:00019 November 2004 16:07:00 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 Turbine Trip on Main Generator Trip ENS 407912004-06-04T11:45:0004 June 2004 11:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Intake Structure Seaweed Fouling ENS 406642004-04-10T18:50:00010 April 2004 18:50:00 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 Loss of Both Main Feedwater Pumps 2012-02-01T01:30:00 | |