ENS 57175: Difference between revisions

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| title = Automatic Reactor Trip
| title = Automatic Reactor Trip
| event text = The following information was provided by the licensee via email:
| event text = The following information was provided by the licensee via email:
On June 16, 2024, at 1233 CDT, Waterford Steam Electric Station Unit 3 was operating at 93 percent power when an automatic reactor trip occurred. Immediately following the reactor trip, emergency feedwater (EFW) actuated automatically. The unit is currently in Mode 3. All control rods fully inserted. Decay heat removal is via the main condenser. Preliminary evaluation indicates that all plant systems functioned normally after the reactor trip, except steam generator (SG) feedwater pump ''A'' tripped and SG ''1'' main feed regulatory controller went to manual. Steam generator water levels are being controlled with the SG feedwater pump ''B''. The cause of the trip is currently being investigated.
On June 16, 2024, at 1233 CDT, Waterford Steam Electric Station Unit 3 was operating at 93 percent power when an automatic reactor trip occurred. Immediately following the reactor trip, emergency feedwater (EFW) actuated automatically. The unit is currently in Mode 3. All control rods fully inserted. Decay heat removal is via the main condenser. Preliminary evaluation indicates that all plant systems functioned normally after the reactor trip, except steam generator (SG) feedwater pump 'A' tripped and SG '1' main feed regulatory controller went to manual. Steam generator water levels are being controlled with the SG feedwater pump 'B'. The cause of the trip is currently being investigated.
This event is being reported as a 4-hour non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an actuation of the reactor protection system when the reactor is critical and as an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as a valid actuation of the EFW system.
This event is being reported as a 4-hour non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an actuation of the reactor protection system when the reactor is critical and as an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as a valid actuation of the EFW system.
The NRC Resident Inspector has been notified.
The NRC Resident Inspector has been notified.
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/20240617en.html#en57175
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/20240618en.html#en57175
}}{{unit info
}}{{unit info
| Unit = 3
| Unit = 3

Latest revision as of 23:38, 18 June 2024

ENS 57175 +/-
Where
Waterford Entergy icon.png
Louisiana (NRC Region 4)
Reporting
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation

10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-0.87 h-0.0363 days <br />-0.00518 weeks <br />-0.00119 months <br />)
Opened: Kylie Granier
16:41 Jun 16, 2024
NRC Officer: Kerby Scales
Last Updated: Jun 16, 2024
57175 - NRC Website
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