ENS 54069: Difference between revisions
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| NRC officer = Joanna Bridge | | NRC officer = Joanna Bridge | ||
| event date = 05/16/2019 23:03 CDT | | event date = 05/16/2019 23:03 CDT | ||
| last update date = 05 | | last update date = 06/05/2019 | ||
| title = | | title = En Revision Imported Date 6/6/2019 | ||
| event text = This is an 8-hour, non-emergency notification for a valid reactor trip signal with the reactor not critical, and a valid auxiliary feedwater system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A) - Valid System Actuation. | | event text = EN Revision Text: REACTOR TRIP DUE TO SOURCE RANGE HI FLUX SIGNAL | ||
This is an 8-hour, non-emergency notification for a valid reactor trip signal with the reactor not critical, and a valid auxiliary feedwater system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A) - Valid System Actuation. | |||
At 2303 [CDT] on May 16, 2019, the plant was administratively in mode 2 due to withdrawing control rods for startup following refuel. The reactor had not been declared critical. The P-6 permissive at 10E-10 Amps was met for one of two Intermediate Range detectors allowing for block of the Source Range high flux trip (1E5CPS). Prior to performing the block, the Source Range high flux trip setpoint was exceeded and a reactor trip received. All systems responded as expected. A feedwater isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit. Auxiliary feedwater was started to maintain steam generator levels. The plant is being maintained stable in mode 3 with no complications. The NRC Resident Inspector was present during the startup and was notified of the reactor trip. | At 2303 [CDT] on May 16, 2019, the plant was administratively in mode 2 due to withdrawing control rods for startup following refuel. The reactor had not been declared critical. The P-6 permissive at 10E-10 Amps was met for one of two Intermediate Range detectors allowing for block of the Source Range high flux trip (1E5CPS). Prior to performing the block, the Source Range high flux trip setpoint was exceeded and a reactor trip received. All systems responded as expected. A feedwater isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit. Auxiliary feedwater was started to maintain steam generator levels. The plant is being maintained stable in mode 3 with no complications. The NRC Resident Inspector was present during the startup and was notified of the reactor trip. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2019/ | * * * UPDATE FROM JONATHAN LAUF TO HOWIE CROUCH AT 1454 EDT ON 6/5/19 * * * | ||
A correction is being made for the sixth sentence in the second paragraph above, which states, 'A Feedwater Isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit.' Within this sentence, 'feedwater temperature' is to be replaced with 'reactor coolant system temperature.' | |||
The licensee has notified the NRC Senior Resident Inspector. | |||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2019/20190606en.html#en54069 | |||
}}{{unit info | }}{{unit info | ||
| Unit = 1 | | Unit = 1 | ||
Latest revision as of 07:30, 6 June 2019
| Where | |
|---|---|
Callaway  Missouri (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.47 h-0.0196 days <br />-0.0028 weeks <br />-6.43806e-4 months <br />) | |
| Opened: | Jeff Gulick 03:35 May 17, 2019 |
| NRC Officer: | Joanna Bridge |
| Last Updated: | Jun 5, 2019 |
| 54069 - NRC Website
| |