ENS 40370: Difference between revisions
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StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
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| event date = 12/03/2003 03:36 CST | | event date = 12/03/2003 03:36 CST | ||
| last update date = 12/03/2003 | | last update date = 12/03/2003 | ||
| title = Plant Had | | title = Plant Had an Auto Reactor Trip from 100% Power Due to Steam Generator Low Level | ||
| event text = The "2 D" steam generator Lo-2 level was caused by the loss of the "2C" feedwater pump while performing the "2 BWOS" feedwater weekly surveillance of the HP stop valve. Both trains of the aux feed actuated as expected on the "2D" Lo-2 s/g level signal. The plant is currently in mode 3 with all rods fully inserted. No ECCS or safety relief valves actuated. | | event text = The "2 D" steam generator Lo-2 level was caused by the loss of the "2C" feedwater pump while performing the "2 BWOS" feedwater weekly surveillance of the HP stop valve. Both trains of the aux feed actuated as expected on the "2D" Lo-2 s/g level signal. The plant is currently in mode 3 with all rods fully inserted. No ECCS or safety relief valves actuated. | ||
Licensee notified the NRC Resident Inspector | Licensee notified the NRC Resident Inspector | ||
Latest revision as of 22:24, 1 March 2018
| 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:+-2.52 h-0.105 days <br />-0.015 weeks <br />-0.00345 months <br />) | |
| Opened: | Kieth Zacek 07:05 Dec 3, 2003 |
| NRC Officer: | Chauncey Gould |
| Last Updated: | Dec 3, 2003 |
| 40370 - 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 | |