ENS 47781
ENS Event | |
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19:03 Mar 28, 2012 | |
Title | Automatic Reactor Trip Due to Steam Generator High Water Level Condition |
Event Description | At 1503 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.718915e-4 months <br /> EDT on March 28, 2012, with the unit in Mode 1 at 55% power, an automatic reactor trip occurred. The reactor trip was the result of a turbine trip from a 'B' Steam Generator Hi Level. All Reactor Coolant Pumps (RCP) remained running.
The Auxiliary Feeedwater (AFW) System automatically actuated due to both main feedwater pump breakers opening from a valid feedwater isolation signal. Steam Generator Levels were then controlled by Auxiliary Feedwater pumps. Steam Generator Blowdown was automatically isolated with the AFW actuation. The RCS Code Safety valves, Pressurizer Power Operated Relief Valves (PORVs), Steam Generator PORVs or the Main Steam Safety valves (MSSVs) did not open during the event. All control rods fully inserted following the reactor trip. The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable. Decay heat is being removed via the condenser. The reactor is currently in Mode 3 and stable. There were no radiological consequences or releases as a result of this event. The cause of the Steam Generator Hi Level is under investigation. The Resident NRC Inspector has been informed. |
Where | |
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Robinson ![]() South Carolina (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:+-1.82 h-0.0758 days <br />-0.0108 weeks <br />-0.00249 months <br />) | |
Opened: | Martin Arnold 17:14 Mar 28, 2012 |
NRC Officer: | Bill Huffman |
Last Updated: | Mar 28, 2012 |
47781 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (55 %) |
After | Hot Standby (0 %) |
Robinson ![]() | |
WEEKMONTHYEARENS 565852023-06-22T14:35:00022 June 2023 14:35:00
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