ENS 54607: Difference between revisions
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| 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 = 03/25/2020 03:30 | | notification date = 03/25/2020 03:30 | ||
| notification by = Jason Morgan | | notification by = Jason Morgan | ||
| Line 19: | Line 19: | ||
| event text = At 0056 EDTon March 25, 2020, with Unit 1 at 17 percent power during a unit power ascension, the reactor was manually tripped due to the failure of the 11 Rod Control Motor Generator caused by a malfunction of its associated Voltage Regulator. The trip was not complex, with all systems responding normally post-trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Atmospheric Steam Dumps and Auxiliary Feedwater System. Salem Unit 2 was not affected. | | event text = At 0056 EDTon March 25, 2020, with Unit 1 at 17 percent power during a unit power ascension, the reactor was manually tripped due to the failure of the 11 Rod Control Motor Generator caused by a malfunction of its associated Voltage Regulator. The trip was not complex, with all systems responding normally post-trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Atmospheric Steam Dumps and Auxiliary Feedwater System. Salem Unit 2 was not affected. | ||
Due to the actuation of the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B), This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. | Due to the actuation of the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B), This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. | ||
There was no impact to the health and safety of the public or plant personnel. | There was no impact to the health and safety of the public or plant personnel. | ||
The NRC Resident lnspector has been notified. | The NRC Resident lnspector has been notified. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200326en.html#en54607 | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2020/20200326en.html#en54607 | ||
}} | }} | ||
{{ENS-Nav}}[[Category:Power Reactor]] | {{ENS-Nav}}[[Category:Power Reactor]] | ||
Latest revision as of 11:48, 15 January 2021
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.43 h-0.0596 days <br />-0.00851 weeks <br />-0.00196 months <br />) | |
| Opened: | Jason Morgan 03:30 Mar 25, 2020 |
| NRC Officer: | Brian Lin |
| Last Updated: | Mar 25, 2020 |
| 54607 - NRC Website
| |