ENS 57107: Difference between revisions
Jump to navigation
Jump to search
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 15: | Line 15: | ||
| NRC officer = Tenisha Meadows | | NRC officer = Tenisha Meadows | ||
| event date = 05/05/2024 03:38 CDT | | event date = 05/05/2024 03:38 CDT | ||
| last update date = | | last update date = 07/05/2024 | ||
| title = Automatic Reactor Trip Due to Lowering Steam Generator Water Level | | title = Automatic Reactor Trip Due to Lowering Steam Generator Water Level | ||
| event text = The following information was provided by the licensee via email and phone: | | event text = The following information was provided by the licensee via email and phone: | ||
| Line 21: | Line 21: | ||
Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to the reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected. | Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to the reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected. | ||
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. | There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/ | * * * UPDATE ON 07/05/2024 AT 0450 EDT FROM MATTHEW WHITE TO TENISHA MEADOWS * * * | ||
The following information was provided by the licensee via email and phone: | |||
At 0338 CDT, with the unit 1 in mode 2 at 3 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-trip. Due to 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) and 10CFR50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system, eight-hour notification. | |||
Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is being removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected. | |||
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. | |||
Notified R3DO (Hartman) | |||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/20240708en.html#en57107 | |||
}}{{unit info | }}{{unit info | ||
| Unit = 1 | | Unit = 1 | ||
Latest revision as of 07:20, 8 July 2024
| Where | |
|---|---|
Braidwood  Illinois (NRC Region 3) | |
| 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:+-0.45 h-0.0188 days <br />-0.00268 weeks <br />-6.1641e-4 months <br />) | |
| Opened: | Azeam Anjum 08:11 May 5, 2024 |
| NRC Officer: | Tenisha Meadows |
| Last Updated: | Jul 5, 2024 |
| 57107 - NRC Website
| |
Braidwood with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |