ENS 49020: Difference between revisions
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| event date = 05/10/2013 06:12 EDT | | event date = 05/10/2013 06:12 EDT | ||
| last update date = 05/10/2013 | | last update date = 05/10/2013 | ||
| title = Manual Reactor Trip Due | | title = Manual Reactor Trip Due to High Turbine Bearing Vibration | ||
| event text = On May 10, 2013 at 0612 hours [EDT], Unit 2 was manually tripped from 60% power due to increased vibrations and a report of arcing on bearing #9 of the main turbine. Unit 2 was in the process of increasing power following a refueling outage when this event occurred. The Operations crew entered the reactor trip procedure and stabilized Unit 2 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10CFR50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10CFR50.72(b)(3)(iv)(A) for a valid actuation of an ESF system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 2 is in a normal shutdown electrical lineup. | | event text = On May 10, 2013 at 0612 hours [EDT], Unit 2 was manually tripped from 60% power due to increased vibrations and a report of arcing on bearing #9 of the main turbine. Unit 2 was in the process of increasing power following a refueling outage when this event occurred. The Operations crew entered the reactor trip procedure and stabilized Unit 2 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10CFR50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10CFR50.72(b)(3)(iv)(A) for a valid actuation of an ESF system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 2 is in a normal shutdown electrical lineup. | ||
The #9 bearing is on the main generator exciter. There was no effect on Unit 1. | The #9 bearing is on the main generator exciter. There was no effect on Unit 1. | ||
Latest revision as of 22:01, 1 March 2018
| Where | |
|---|---|
North Anna  Virginia (NRC Region 2) | |
| 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:+-1.87 h-0.0779 days <br />-0.0111 weeks <br />-0.00256 months <br />) | |
| Opened: | Page Kemp 08:20 May 10, 2013 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | May 10, 2013 |
| 49020 - NRC Website
| |
North Anna with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |