Skip to main content

Morning Overview

A Louisiana reactor tripped offline from 75% power and a backup diesel took over when a bus transfer failed

Waterford Steam Electric Station Unit 3 in Louisiana shut down automatically at 10:45 p.m. Central Time on October 16, 2026, when a turbine trip knocked the reactor offline from 75% power. In the same sequence a transfer of the plant’s 2B electrical bus failed, and Emergency Diesel Generator B started and took over the load, according to the licensee’s report to the Nuclear Regulatory Commission, filed as Event Number 58501.

Save more, waste less: The Cool Down’s newsletter sends smart, simple changes that help you and the planet in your everyday life.

Subscribe to The Cool Down →

We may earn a commission if you sign up.

The unit was being reduced in power for a refueling outage when it tripped, so the shutdown arrived partway through a planned power coast-down rather than from full output. The company told the NRC that the reactor was stable afterward, with all control rods inserted, and the report lists the event class as non-emergency. The cause of the turbine trip that started it all remained under investigation when the report was posted.

The 2B bus transfer and Emergency Diesel Generator B

The sequence in the NRC’s daily event notification report is short but specific. The plant’s own wording is that the “Fast dead bus transfer of the ‘2B’ bus failed.” A fast dead bus transfer is the automatic move of a safety-related electrical bus from one power source to another; when it does not complete, the bus loses its supply, and the backup has to carry it.

In this event, Emergency Diesel Generator B started and loaded onto the 3B bus, which is the job emergency diesels exist to do. An emergency feedwater actuation signal was also received, a signal that calls on the plant’s emergency feedwater system to keep water flowing to the steam generators so heat can still be carried away. The report describes the diesel as starting and loading, and it names no component failure beyond the failed transfer itself, so the question of why the bus did not shift cleanly is left to the licensee’s follow-up.

A turbine trip during routine testing

The first event in the chain was the turbine. The report says an automatic reactor trip was initiated due to an automatic turbine trip, and that routine testing of the turbine electrohydraulic system was in progress when it happened. Entergy has not stated a cause: the cause of the turbine trip is being investigated, in the licensee’s words.

A reactor trip is the term pressurized water reactors use for a reactor scram, and the NRC’s own glossary entry for a reactor trip says exactly that. Control rods drop into the core and the chain reaction stops. Here, the report says all control rods fully inserted, and that the reactor protection system was among the systems involved alongside the turbine controls, the two buses, the diesel and the emergency feedwater signal.

Power had been falling on purpose for the outage, and the report gives the level before the trip as 75% and after it as zero. Routine testing of the turbine electrohydraulic system was under way at the moment of the trip, which is why the investigation starts there. Whether the test caused the turbine trip is not stated, and the report treats the cause as unknown.

Entergy’s Waterford 3 and the reporting rules behind Event 58501

The unit is a pressurized water reactor from Combustion Engineering at Killona, Louisiana, about 25 miles west of New Orleans, and the NRC’s page for the plant lists Entergy Operations, Inc. as operator, a licensed thermal power of 3,716 megawatts and a license that runs to December 18, 2044. The operating license was first issued on March 16, 1985 and renewed on December 27, 2018, and the site falls under the NRC’s Region IV, the same region office that received the notification. The event report itself carries no licensee field, so the operator name here comes from that facility page.

The licensee reported under two provisions of federal regulation, 10 CFR 50.72(b)(2)(iv)(B), for a reactor protection system actuation while critical, and 10 CFR 50.72(b)(3)(iv)(A), for a valid specified system actuation. The rule text sits in the eCFR section for 50.72 event notifications. The report cites a section number that looks like a typo for the first item, an inconsistency that does not change what was reported.

The notification went to the NRC on October 17 at 3:00 a.m. Eastern Time, about three hours after the trip, which was logged at 10:45 p.m. Central on October 16. Remy Devoe was the licensee’s notifying contact, and the NRC informed its Region 4 Reactor Events group, Region 4 branch chief John Dixon, and the resident inspector.

After the trip, the unit was stable in Mode 3, hot standby, with decay heat removed through the main condenser. What remains open is the cause of the turbine trip, the question the investigation is meant to answer, and the report does not say when the unit will resume the refueling outage preparations it was in the middle of.

This article was produced with the assistance of AI and reviewed by Morning Overview editors prior to publication.

Save more, waste less: Subscribe to The Cool Down →

We may earn a commission if you sign up.


More from Morning Overview

Morning Overview is reader-supported. Some links in our articles are affiliate links, and we may earn a commission at no extra cost to you. As an Amazon Associate I earn from qualifying purchases. Full disclosure.