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Entered date | Event description | |
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ENS 42746 | 1 August 2006 11:32:00 | At approximately 0335 EDT, LCO 3.4.13, RCS Operational Leakage, Action C was entered due to the identification of a pressure boundary leak. Reactor Coolant System (RCS) leak is believed to be a small pinhole on the weld on the downstream side of the check valve on Loop 1 Cold Leg Safety Injection Line. The estimated RCS leak rate is 0.1 gallons per minute. The Unit was in Mode 3 at the time of discovery. This event is being reported under 10 CFR 50.72(b)(3)(ii)(A). The plant is currently evaluating the appropriate repair method for this condition. The licensee notified the NRC Resident Inspector. |
ENS 42744 | 31 July 2006 14:13:00 | At approximately 1213 hours on July 31, 2006, with Watts Bar Nuclear Plant Unit 1 operating normally at 100% power, the main generator tripped resulting in a reactor trip per design. All control rods inserted (fully) and the auxiliary feedwater system (AFW) automatically actuated per design and the reactor was stabilized in mode 3. This event is reportable under 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip (4-hour report) and under 10 CFR 50.72(b)(3)(iv)(A ) for the RPS (reactor protection system) and AFW actuations (8-hour report). The cause of the generator trip is currently under investigation. Steam is being released via steam dump to the condenser and all systems functioned as required. The licensee notified the NRC Resident Inspector. |