ENS 41414: Difference between revisions
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| event date = 02/16/2005 21:12 EST | | event date = 02/16/2005 21:12 EST | ||
| last update date = 02/17/2005 | | last update date = 02/17/2005 | ||
| title = Reactor Trip Due | | title = Reactor Trip Due to Turbine Trip as a Result of Failed Power Supply | ||
| event text = Ginna Station received a reactor trip from Turbine Trip at 2112 hrs on 02/16/05. The Turbine Trip signal was generated from the ATWS Mitigation System Actuation Circuitry (AMSAC) related to a failed power supply in the Advanced Digital Feedwater Control System. All control rods inserted on the reactor trip. The plant is currently stable in Mode 3, RCS Pressure 2235 psig, Temperature 540 deg F. AFW [Auxiliary Feed Water] did actuate as designed after the trip. | | event text = Ginna Station received a reactor trip from Turbine Trip at 2112 hrs on 02/16/05. The Turbine Trip signal was generated from the ATWS Mitigation System Actuation Circuitry (AMSAC) related to a failed power supply in the Advanced Digital Feedwater Control System. All control rods inserted on the reactor trip. The plant is currently stable in Mode 3, RCS Pressure 2235 psig, Temperature 540 deg F. AFW [Auxiliary Feed Water] did actuate as designed after the trip. | ||
For the transient, min & max Temperatures, Pressures & Levels are: | For the transient, min & max Temperatures, Pressures & Levels are: |
Latest revision as of 21:21, 1 March 2018
Where | |
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Ginna New York (NRC Region 1) | |
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:+-1.9 h-0.0792 days <br />-0.0113 weeks <br />-0.0026 months <br />) | |
Opened: | Peter Bramford 00:18 Feb 17, 2005 |
NRC Officer: | Mike Ripley |
Last Updated: | Feb 17, 2005 |
41414 - NRC Website
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