ENS 46584
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ENS Event | |
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10:33 Feb 2, 2011 | |
Title | Automatic Reactor Trip Due to Loss of Rcs Coolant Flow in One Loop |
Event Description | Unit 2 Reactor automatically tripped at 0533 EST. This was due to loss of coolant flow in the 'C' RCS Loop. The first indication of the reactor trip was the annunciator for 'Loss of Coolant Flow > P8.' The 'C' RCP is running with motor current indicating normal. 'C' LOOP RCS flow is approximately 25% on all three channels with 'A' & 'B' RCS LOOP FLOW approximately 104%. All three auxiliary feedwater [AFW] pumps automatically initiated as designed on low-low steam generator level following the trip. Currently, RCS temperature is being maintained stable at no load temperature. All systems responded as expected with the exception of the Intermediate Range Neutron Indication. N36 indication was undercompensated and Source Range indication did not automatically energize, but was subsequently manually energized.
This notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) for 4-hour notification of RPS Activation and 10 CFR 50.72(b)(3)(iv)(A) for 8-hour notification of actuation of AFW. Plant responded as expected. The NRC Resident Inspector has been notified of this event and is on site. There were no radiation releases due this event, nor were there any personnel injuries or contamination events. This was an uncomplicated reactor trip and all control rods fully inserted. The plant is in a normal electrical alignment. AFW has been secured and the steam generators are being feed from main feedwater. Decay heat is being released through the main condenser steam dumps. Estimated time for repair and re-start is not known. |
Where | |
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Surry Virginia (NRC Region 2) | |
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:+-1.68 h-0.07 days <br />-0.01 weeks <br />-0.0023 months <br />) | |
Opened: | Curtis Lycke 08:52 Feb 2, 2011 |
NRC Officer: | John Shoemaker |
Last Updated: | Feb 2, 2011 |
46584 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
After | Hot Standby (0 %) |
Surry with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 571582024-06-02T21:08:0002 June 2024 21:08:00
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