ENS 54916: Difference between revisions
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| Line 9: | Line 9: | ||
| unit = 1 | | unit = 1 | ||
| utype = W-4-LP | | utype = W-4-LP | ||
| cfr = 10 CFR 50.72(b)(2)(iv)(B | | cfr = 10 CFR 50.72(b)(2)(iv)(B) | ||
| emergency class = | | 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 | ||
}} | }} | ||
{{ENS-Nav}}[[Category:Power Reactor]] | {{ENS-Nav}}[[Category:Power Reactor]] | ||
Latest revision as of 11:19, 15 January 2021
| Where | |
|---|---|
Callaway  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
| |
| Automatic Reactor Trip [Table view] | ||