ENS 40299: Difference between revisions
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| event date = 11/05/2003 17:34 EST | | event date = 11/05/2003 17:34 EST | ||
| last update date = 11/05/2003 | | last update date = 11/05/2003 | ||
| title = Automatic Reactor Trip Due | | title = Automatic Reactor Trip Due to High Reactor Coolant System Pressure | ||
| event text = Crystal River Unit 3 was at 37 percent power starting up from a refueling outage. During troubleshooting of control problems with the B Main Feedwater Pump, a feedwater transient occurred which underfed the steam generators. This resulted in a reactor trip on high Reactor Coolant System pressure and Emergency Feedwater Actuation on low steam generator levels. This event is reportable as a 4-Hour Non-Emergency Notification per 10CFR50.72 (b)(2)(iv)(B) for Reactor Protection System Actuation and as an 8-Hour Non Emergency Notification per 10CFR50.72 (b)(3)(iv)(A) for Emergency Feedwater Actuation. | | event text = Crystal River Unit 3 was at 37 percent power starting up from a refueling outage. During troubleshooting of control problems with the B Main Feedwater Pump, a feedwater transient occurred which underfed the steam generators. This resulted in a reactor trip on high Reactor Coolant System pressure and Emergency Feedwater Actuation on low steam generator levels. This event is reportable as a 4-Hour Non-Emergency Notification per 10CFR50.72 (b)(2)(iv)(B) for Reactor Protection System Actuation and as an 8-Hour Non Emergency Notification per 10CFR50.72 (b)(3)(iv)(A) for Emergency Feedwater Actuation. | ||
The licensee reported that all control rods fully inserted on the trip and that steam generator safety valves lifted and reseated as expected. The primary system is currently at 2155 psi, 549 degrees F with steam generator feedwater being supplied by auxiliary feedwater. The main condenser is available and is being used for primary system heat removal via steam dump. The station electrical grid is stable and in normal configuration; the emergency diesel generators are operable and in standby. | The licensee reported that all control rods fully inserted on the trip and that steam generator safety valves lifted and reseated as expected. The primary system is currently at 2155 psi, 549 degrees F with steam generator feedwater being supplied by auxiliary feedwater. The main condenser is available and is being used for primary system heat removal via steam dump. The station electrical grid is stable and in normal configuration; the emergency diesel generators are operable and in standby. | ||
Latest revision as of 22:24, 1 March 2018
| Where | |
|---|---|
Crystal River  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000302/LER-2003-005 |
| Time - Person (Reporting Time:+-3.05 h-0.127 days <br />-0.0182 weeks <br />-0.00418 months <br />) | |
| Opened: | Richard Sweeney 19:31 Nov 5, 2003 |
| NRC Officer: | Gerry Waig |
| Last Updated: | Nov 5, 2003 |
| 40299 - NRC Website
| |
Crystal River with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |