ENS 54560: Difference between revisions
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| unit = 2 | | unit = 2 | ||
| utype = CE, CE, CE | | utype = CE, CE, CE | ||
| 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 = 03/04/2020 02:07 | | notification date = 03/04/2020 02:07 | ||
| notification by = Anton Pestka | | notification by = Anton Pestka | ||
| Line 16: | Line 16: | ||
| event date = 03/03/2020 20:50 MST | | event date = 03/03/2020 20:50 MST | ||
| last update date = 05/04/2020 | | last update date = 05/04/2020 | ||
| title = | | title = Reactor Trip Due to Low Steam Generator Level | ||
| event text = | | event text = At 2050 MST on March 3, 2020, Unit 2 reactor automatically tripped on Low Steam Generator (SG) Number 1 level signal from the Reactor Protection System. The low SG level occurred as the result of a trip of both Main Feedwater Pumps, which tripped during restoration of power to the Main Feedwater Pump Lube oil control panel. Auxiliary Feedwater (AFAS-1 and AFAS-2) actuated due to low SG levels in both SG post reactor trip as designed. This event is being reported as a reactor protection system and a specified system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). | ||
At 2050 MST on March 3, 2020, Unit 2 reactor automatically tripped on Low Steam Generator (SG) Number 1 level signal from the Reactor Protection System. The low SG level occurred as the result of a trip of both Main Feedwater Pumps, which tripped during restoration of power to the Main Feedwater Pump Lube oil control panel. Auxiliary Feedwater (AFAS-1 and AFAS-2) actuated due to low SG levels in both SG post reactor trip as designed. This event is being reported as a reactor protection system and a specified system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). | |||
Following the reactor trip, all [control element assemblies] CEAs inserted fully into the core. All systems operated as expected. No emergency plan classification was required per the Emergency Plan. Safety related busses remained powered during the event from offsite power and the offsite power grid is stable. Unit 2 is stable and in Mode 3. Steam Generators are being fed via the class 1E powered motor driven auxiliary feedwater pump. | Following the reactor trip, all [control element assemblies] CEAs inserted fully into the core. All systems operated as expected. No emergency plan classification was required per the Emergency Plan. Safety related busses remained powered during the event from offsite power and the offsite power grid is stable. Unit 2 is stable and in Mode 3. Steam Generators are being fed via the class 1E powered motor driven auxiliary feedwater pump. | ||
The NRC Senior Resident Inspector has been informed. | The NRC Senior Resident Inspector has been informed. | ||
| Line 27: | Line 26: | ||
Notified R4DO (Drake). | Notified R4DO (Drake). | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200505en.html#en54560 | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200505en.html#en54560 | ||
}} | }} | ||
{{ENS-Nav}}[[Category:Power Reactor]] | {{ENS-Nav}}[[Category:Power Reactor]] | ||
Latest revision as of 11:40, 15 January 2021
| Where | |
|---|---|
Palo Verde  Arizona (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.72 h-0.0717 days <br />-0.0102 weeks <br />-0.00236 months <br />) | |
| Opened: | Anton Pestka 02:07 Mar 4, 2020 |
| NRC Officer: | Jeffrey Whited |
| Last Updated: | May 4, 2020 |
| 54560 - NRC Website
| |