ENS 54916: Difference between revisions

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| unit = 1
| unit = 1
| utype = W-4-LP
| utype = W-4-LP
| cfr = 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.72(b)(3)(iv)(A)
| cfr = 10 CFR 50.72(b)(2)(iv)(B)
| emergency class = Non Emergency  
| emergency class = Non Emergency
| notification date = 09/27/2020 05:08
| notification date = 09/27/2020 05:08
| notification by = Tim Holland
| notification by = Tim Holland
Line 16: Line 16:
| event date = 09/27/2020 02:03 CDT
| event date = 09/27/2020 02:03 CDT
| last update date = 09/27/2020
| last update date = 09/27/2020
| title = Automatic Reactor Trip
| title = <Td Align="Left" Scope="Row">Automatic Reactor Trip
| event text = At 0203 [CDT] on September 27, 2020 the plant was in Mode 1 at 98 percent power when a turbine trip/reactor trip [from a generator trip signal] occurred. All systems responded as expected. A Feedwater Isolation signal was received due to the reactor trip with RCS average temperature less than 564 degrees Fahrenheit. The Auxiliary Feedwater system started on a valid actuation signal to restore and maintain steam generator levels. The plant is being maintained stable in Mode 3 with no complications. The NRC Resident Inspector has been notified of the reactor trip.
| event text = At 0203 [CDT] on September 27, 2020 the plant was in Mode 1 at 98 percent power when a turbine trip/reactor trip [from a generator trip signal] occurred. All systems responded as expected. A Feedwater Isolation signal was received due to the reactor trip with RCS average temperature less than 564 degrees Fahrenheit. The Auxiliary Feedwater system started on a valid actuation signal to restore and maintain steam generator levels. The plant is being maintained stable in Mode 3 with no complications. The NRC Resident Inspector has been notified of the reactor trip.
All control rods fully inserted from the reactor trip signal, and decay heat is being removed via the Auxiliary Feedwater and Steam Dump Systems.
All control rods fully inserted from the reactor trip signal, and decay heat is being removed via the Auxiliary Feedwater and Steam Dump Systems.
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200928en.html#en54916
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200928en.html#en54916
}}{{unit info
| Unit =  1
| type =
| Scram code =  A/R
| Reactor critical =  Y
| Initial power =  98
| Initial reactor mode =  Power Operation
| Current power =  0
| Current reactor mode =  Hot Standby
}}
}}


{{ENS-Nav}}[[Category:Power Reactor]]
{{ENS-Nav}}[[Category:Power Reactor]]

Latest revision as of 12:19, 15 January 2021

ENS 54916 +/-
Where
Callaway Ameren icon.png
Missouri (NRC Region 4)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation
Time - Person (Reporting Time:+-1.92 h-0.08 days <br />-0.0114 weeks <br />-0.00263 months <br />)
Opened: Tim Holland
05:08 Sep 27, 2020
NRC Officer: Thomas Kendzia
Last Updated: Sep 27, 2020
54916 - NRC Website
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