Event Notification Report for October 14, 2015
| U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/13/2015 - 10/14/2015 ** EVENT NUMBERS ** | | Power Reactor | Event Number: 51467 | Facility: SURRY Region: 2 State: VA Unit: [1] [ ] [ ] RX Type: [1] W-3-LP,[2] W-3-LP NRC Notified By: THOMAS OLIVER HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/13/2015 Notification Time: 21:20 [ET] Event Date: 10/13/2015 Event Time: 18:15 [EDT] Last Update Date: 10/13/2015 | Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL | Person (Organization): SHAKUR WALKER (R2DO) | | Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP AFTER A TURBINE TRIP "Surry Unit 1 Reactor automatically tripped at 1815 hours [EDT] on 10/13/2015 due to a Generator Differential Lockout Turbine trip. The cause of the Generator Differential Lockout is under investigation at this time. Reactor Coolant System is currently being maintained at 548 degrees F on the Steam Generator PORVs due to closing Main Steam Trip Valves manually. All three Auxiliary Feedwater Pumps started automatically as designed on Low-Low Steam Generator Water Level following the trip. Auxiliary Feedwater Pumps have since been secured and Main Feedwater is in use. All systems operated as required. Off-site power remains available. There is no impact on Surry Unit 2. "This notification is being made pursuant to 10CFR50.72(b)(2)(iv)(B) for 4 hour notification of Reactor Protection System activation and 10CFR50.72(b)(3)(iv)(A) for 8 hour notification of automatic actuation of Auxiliary Feedwater. The NRC Resident Inspector has been notified and is on site. "There were no radiation releases, personnel injuries, or contamination events due to this event." All control rods fully inserted during the reactor trip. The Main Steam Trip Valves were shut due to excessive cooldown. The plant is in its normal shutdown electrical lineup. There is no steam generator tube leakage. | |
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