ENS 42138: Difference between revisions
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| event date = 11/11/2005 20:34 CST | | event date = 11/11/2005 20:34 CST | ||
| last update date = 11/14/2005 | | last update date = 11/14/2005 | ||
| title = Manual Reactor Trip After Loss | | title = Manual Reactor Trip After Loss of All Condenser Circulating Water Pumps | ||
| event text = Waterford 3 manually tripped the reactor at 20:34 [CST] on 11/11/05 due to lowering main condenser vacuum caused by a loss of all circ water pumps. Subsequently an Emergency Feedwater Actuation Signal (EFAS) was received due to low steam generator levels. The plant is currently being maintained in mode 3 with both Steam Generators being fed from the Auxiliary Feedwater system with Steam Generator levels in the normal operational band for mode 3. The EFAS has been reset. The plant will be maintained in Mode 3 while a Post Trip Review is performed. This report is submitted as required by 10CFR50.72. | | event text = Waterford 3 manually tripped the reactor at 20:34 [CST] on 11/11/05 due to lowering main condenser vacuum caused by a loss of all circ water pumps. Subsequently an Emergency Feedwater Actuation Signal (EFAS) was received due to low steam generator levels. The plant is currently being maintained in mode 3 with both Steam Generators being fed from the Auxiliary Feedwater system with Steam Generator levels in the normal operational band for mode 3. The EFAS has been reset. The plant will be maintained in Mode 3 while a Post Trip Review is performed. This report is submitted as required by 10CFR50.72. | ||
All control rods fully inserted on the manual trip. The main steam isolation valves are shut and the heat sink is through the atmospheric dump valves. The electrical grid is stable and plant power is from the startup transformer. No primary or secondary relief valves or safety valves lifted. The site was able to restart the B & D circ water pumps. There is no significant steam generator tube leakage. | All control rods fully inserted on the manual trip. The main steam isolation valves are shut and the heat sink is through the atmospheric dump valves. The electrical grid is stable and plant power is from the startup transformer. No primary or secondary relief valves or safety valves lifted. The site was able to restart the B & D circ water pumps. There is no significant steam generator tube leakage. | ||
Latest revision as of 21:19, 1 March 2018
| Where | |
|---|---|
Waterford  Louisiana (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+2.23 h0.0929 days <br />0.0133 weeks <br />0.00305 months <br />) | |
| Opened: | Paul Wood 04:48 Nov 12, 2005 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Nov 14, 2005 |
| 42138 - NRC Website
| |
Waterford with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |