ENS 54532: Difference between revisions
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| Line 9: | Line 9: | ||
| unit = 1 | | unit = 1 | ||
| utype = W-4-LP, W-4-LP | | utype = W-4-LP, 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 = 02/19/2020 10:20 | | notification date = 02/19/2020 10:20 | ||
| notification by = Andy Waldman | | notification by = Andy Waldman | ||
| Line 16: | Line 16: | ||
| event date = 02/19/2020 09:36 EST | | event date = 02/19/2020 09:36 EST | ||
| last update date = 02/19/2020 | | last update date = 02/19/2020 | ||
| title = Manual Reactor Trip Due to Loss of Control of Steam | | title = Manual Reactor Trip Due to Loss of Control of Steam | ||
| event text = At 0936 EST on February 19, 2020, the Watts Bar Unit 1 reactor was manually tripped while operating at 100 percent power in response to loss of control of water level for steam generator number 3. All control and shutdown bank rods inserted properly in response to the manual reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and Steam Dump Systems. There is no impact to Unit 2. | | event text = At 0936 EST on February 19, 2020, the Watts Bar Unit 1 reactor was manually tripped while operating at 100 percent power in response to loss of control of water level for steam generator number 3. All control and shutdown bank rods inserted properly in response to the manual reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and Steam Dump Systems. There is no impact to Unit 2. | ||
The manual actuation of the Reactor Protection System (RPS) is being reported as a four-hour report under 10 CFR 50. 72(b)(2)(iv)(B). | The manual actuation of the Reactor Protection System (RPS) is being reported as a four-hour report under 10 CFR 50. 72(b)(2)(iv)(B). | ||
| Line 22: | Line 22: | ||
The NRC Senior Resident Inspector has been notified for this event. | The NRC Senior Resident Inspector has been notified for this event. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200220en.html#en54532 | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200220en.html#en54532 | ||
}} | }} | ||
{{ENS-Nav}}[[Category:Power Reactor]] | {{ENS-Nav}}[[Category:Power Reactor]] | ||
Latest revision as of 11:54, 15 January 2021
| Where | |
|---|---|
Watts Bar  Tennessee (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-4.27 h-0.178 days <br />-0.0254 weeks <br />-0.00585 months <br />) | |
| Opened: | Andy Waldman 10:20 Feb 19, 2020 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Feb 19, 2020 |
| 54532 - NRC Website
| |