ENS 43141
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ENS Event | |
|---|---|
08:07 Feb 5, 2007 | |
| Title | Manual Reactor Trip Due to Steam Leak During Main Feed Booster Pump Startup |
| Event Description | While starting D Feedwater Booster pump, a steam leak developed in the Turbine building. The Reactor was manually tripped at 0307 on 02/05/07. Investigation revealed that an orifice (XPS0006D) in the D Feedwater Booster pump recirculation header was the source of the leak. The steam/water leak was isolated at 0500 on 02/05/07. All systems responded normally on the Reactor trip. Emergency Feedwater (AFW) system started on LoLo Steam Generator level. Steam Generator level recovered quickly.
All control rods fully inserted on the manual Reactor trip signal. No relief valves or PORVs lifted as a result of the transient. Decay heat is being removed by the main condenser via the steam dump valves. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Summer  South Carolina (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:+-1.48 h-0.0617 days <br />-0.00881 weeks <br />-0.00203 months <br />) | |
| Opened: | Jerry Shepp 06:38 Feb 5, 2007 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Feb 5, 2007 |
| 43141 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (95 %) |
| After | Hot Standby (0 %) |
Summer with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 569782024-02-19T07:36:00019 February 2024 07:36:00
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