ENS 55028: Difference between revisions
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{{ENS notification | {{ENS notification | ||
| event number = 55028 | | event number = 55028 | ||
| facility = | | facility = Arkansas Nuclear | ||
| Organization = | | Organization = | ||
| license number = | | license number = | ||
| region = | | region = 4 | ||
| state = | | state = Arkansas | ||
| city = | | city = | ||
| unit = | | unit = 2 | ||
| utype = | | utype = B, CE | ||
| cfr = | | cfr = 10 CFR 50.72(b)(2)(iv)(B) | ||
50.72( | <br>50.72(b)(3)(iv)(A) | ||
< | | emergency class = Non Emergency | ||
| emergency class = | | notification date = 12/10/2020 20:43 | ||
| notification date = | | notification by = Danny Watts | ||
| notification by = | | NRC officer = Kerby Scales | ||
| NRC officer = | | event date = 12/10/2020 16:08 CST | ||
| event date = | | last update date = 12/11/2020 | ||
| last update date = | | title = Automatic Reactor Scram Due to Low Steam Generator Water Level | ||
| title = | | event text = On December 10, 2020 at 1608 CST, Arkansas Nuclear One, Unit 2 (ANO-2) experienced an automatic reactor scram from 100 percent power due to Low Steam Generator Water Level in 2E-24A Steam Generator. Emergency Feedwater actuated automatically due to low water level in the A Steam Generator. Due to inadequate control of the B Main Feedwater Control System, water level in the B Steam generator rose to a level requiring manual trip of the B Main Feedwater pump. Emergency Feedwater responded as designed to feed both steam generators automatically. | ||
| event text = | All other systems responded as designed. All electrical power is being supplied from offsite power and maintaining unit electrical loads as designed. | ||
Unit 2 is currently stable in Mode 3 (Hot Standby) maintaining pressure and temperature via Emergency Feedwater and secondary system steaming. | |||
There are no indications of a radiological release on either unit as a result of this event. | |||
This report satisfies the reporting criteria of both 10 CFR 50.72(b)(2)(iv)(6) for the Reactor Protection System actuation and 10 CFR 50.72(b)(3)(iv)(A) for the actuation of the Emergency Feedwater System. | |||
The Arkansas Nuclear One NRC Senior Resident Inspector has been notified. | |||
* * * UPDATE FROM JOHN LINDSEY TO DONALD NORWOOD AT 1605 EST ON 12/11/2020 * * * | |||
The purpose of this [report] is to provide an update to NRC Event Number 55028. | |||
The cause of the inadequate control of the B Main Feedwater Control System to control B Steam Generator Level was verified to be associated with the failure that led to the A Steam Generator low level condition. | |||
After taking action to trip the B Main Feedwater Pump, Emergency Feedwater was manually actuated for the B Steam Generator and the Emergency Feedwater System was verified to maintain proper automatic control of both Steam Generator levels. | |||
At the time of the initial event notification, plant temperature and pressure control had been transferred from Emergency Feedwater to Auxiliary Feedwater along with secondary system steaming. | |||
The licensee notified the NRC Resident Inspector. | |||
Notified R4DO (Kellar). | |||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20201214en.html#en55028 | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20201214en.html#en55028 | ||
}} | }} | ||
{{ENS-Nav}}[[Category:Power Reactor]] | {{ENS-Nav}}[[Category:Power Reactor]] | ||
Revision as of 01:33, 15 January 2021
| Where | |
|---|---|
Arkansas Nuclear  Arkansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B)
50.72(b)(3)(iv)(A) | |
| Time - Person (Reporting Time:+-1.42 h-0.0592 days <br />-0.00845 weeks <br />-0.00195 months <br />) | |
| Opened: | Danny Watts 20:43 Dec 10, 2020 |
| NRC Officer: | Kerby Scales |
| Last Updated: | Dec 11, 2020 |
| 55028 - NRC Website
| |