ENS 43435
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ENS Event | |
|---|---|
05:50 Jun 21, 2007 | |
| Title | |
| Event Description | At 2250 on 6/20/07, "Instrument Air header pressure failed at a brazed joint. The loss of Instrument Air pressure caused the Steam Generator (S/G) Feedwater Regulating Valves to stop controlling and S/G level, E-088, to rise uncontrolled. Control Room Operators tripped the reactor manually. Main Feedwater Pumps were manually tripped to stop excess feedwater to the S/Gs. Loss of Instrument Air failed the normal cooling to Containment. Containment Emergency Cooling units were manually started to provide containment cooling. The standard post trip actions were carried out with all safety functions satisfied." The site is proceeding with post trip recovery. The Instrument Air leak was isolated at 2321 PDT.
All control rods fully inserted on the manual trip. RCPs are in operation transferring decay heat to the S/Gs. Emergency feedwater is feeding the S/Gs with steam being discharged to the condenser via the steam dumps. Atmospheric relief valves were used to discharge steam to the atmosphere initially for approximately 20 minutes following the trip. There are no primary to secondary tube leaks. Containment isolation failed closed as expected following the loss of instrument air pressure to the containment. Normal offsite power is available and the emergency diesel generators are available if needed. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
San Onofre  California (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-2.43 h-0.101 days <br />-0.0145 weeks <br />-0.00333 months <br />) | |
| Opened: | Joel Barnett 03:24 Jun 21, 2007 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Jun 21, 2007 |
| 43435 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (96 %) |
| After | Hot Standby (0 %) |
San Onofre with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
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 463462010-10-19T22:15:00019 October 2010 22:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Specified System Actuation 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 439282008-01-23T22:15:00023 January 2008 22:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation One of Two Main Feedwater Pumps Trip 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 | |
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