Event Notification Report for April 27, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/26/2010 - 04/27/2010
Power Reactor
Event Number: 45877
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/27/2010
Notification Time: 18:44 [ET]
Event Date: 04/27/2010
Event Time: 16:37 [EDT]
Last Update Date: 04/27/2010
Notification Time: 18:44 [ET]
Event Date: 04/27/2010
Event Time: 16:37 [EDT]
Last Update Date: 04/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GERALD MCCOY (R2DO)
GERALD MCCOY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 74 | Power Operation | 0 | Hot Standby |
REACTOR TRIP FOLLOWING A GENERATOR LOCKOUT DURING AUTOMATIC VOLTAGE REGULATOR TESTING
"On 4/27/2010 at 1637 hours, during recovery from a refueling outage when the main turbines and exciter were replaced, Unit 2 experienced a generator lockout which caused a turbine trip. The turbine trip resulted in a reactor trip when the reactor was at 74% power. The generator lockout occurred while automatic voltage regulator testing was being performed. This event is reportable per 10CFR50.72(b)(2)(iv)(B) due to actuation of the Reactor Protection System.
"The Auxiliary Feedwater Pumps (AFW) received an automatic start signal due to low/low level in the steam generators following the reactor trip. Steam Generator inventory was restored to normal operating level. The Steam Driven AFW pump experienced an issue with the lube oil system which resulted in some of the oil leaking onto the floor. An investigation into the oil leakage issue will be performed. The Steam Driven AFW pump was declared inoperable until this investigation is complete. The two motor driven AFW pumps automatically started and operated as designed. This event is reportable per 10CFR50.72(b)(3)(iv)(A) due to actuation of an ESF system.
"All control rods inserted into the core following the reactor trip and decay heat is being removed using the normal steam dump system. Several secondary (feedwater) relief valves lifted and resealed during the event. Unit 2 is stable in Mode 3 at normal operating temperature and pressure."
Unit 2 is in a normal shutdown electrical lineup and there was no impact on Unit 1. The NRC Resident Inspector has been notified by the licensee.
"On 4/27/2010 at 1637 hours, during recovery from a refueling outage when the main turbines and exciter were replaced, Unit 2 experienced a generator lockout which caused a turbine trip. The turbine trip resulted in a reactor trip when the reactor was at 74% power. The generator lockout occurred while automatic voltage regulator testing was being performed. This event is reportable per 10CFR50.72(b)(2)(iv)(B) due to actuation of the Reactor Protection System.
"The Auxiliary Feedwater Pumps (AFW) received an automatic start signal due to low/low level in the steam generators following the reactor trip. Steam Generator inventory was restored to normal operating level. The Steam Driven AFW pump experienced an issue with the lube oil system which resulted in some of the oil leaking onto the floor. An investigation into the oil leakage issue will be performed. The Steam Driven AFW pump was declared inoperable until this investigation is complete. The two motor driven AFW pumps automatically started and operated as designed. This event is reportable per 10CFR50.72(b)(3)(iv)(A) due to actuation of an ESF system.
"All control rods inserted into the core following the reactor trip and decay heat is being removed using the normal steam dump system. Several secondary (feedwater) relief valves lifted and resealed during the event. Unit 2 is stable in Mode 3 at normal operating temperature and pressure."
Unit 2 is in a normal shutdown electrical lineup and there was no impact on Unit 1. The NRC Resident Inspector has been notified by the licensee.
Power Reactor
Event Number: 46046
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW RASMUSSEN
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW RASMUSSEN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/25/2010
Notification Time: 16:32 [ET]
Event Date: 04/27/2010
Event Time: 17:37 [CDT]
Last Update Date: 06/25/2010
Notification Time: 16:32 [ET]
Event Date: 04/27/2010
Event Time: 17:37 [CDT]
Last Update Date: 06/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
SCOTT SHAEFFER (R2DO)
SCOTT SHAEFFER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID GROUP 6 CONTAINMENT ISOLATION
"This notification is being made in lieu of a written report under the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of a Group 6 containment isolation signal affecting more than one system.
"On April 27, 2010, at 1737 hours Central Daylight Time, with Unit 3 operating at 100 percent thermal power, Unit 3 received a Group 6 ventilation system isolation signal during the performance of a maintenance activity on a Unit 3 Reactor/Refuel Zone Radiation Monitor, 3 RM-90-141/143. This resulted in isolation of the reactor and refuel zone ventilation systems, initiation of Standby Gas Treatment system (Trains A, B, and C) and the Control Room Emergency Ventilation system (Train A).
"All equipment responded to the Group 6 ventilation system isolation signal in accordance with the plant design. However, during the recovery effort, one of the Unit 3 Reactor Building Ventilation dampers failed to indicate fully closed. Operations personnel verified by inspection that the damper was fully closed.
"There were no safety consequences or impact on the health and safety of the public as a result of this event. The event was entered into the Corrective Action Program (CAP) as PER 227125.
"From PER 227125, trouble shooting determined a relay coil had been installed upside down when the coils were recently replaced.
"The NRC Senior Resident Inspector has been notified."
"This notification is being made in lieu of a written report under the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of a Group 6 containment isolation signal affecting more than one system.
"On April 27, 2010, at 1737 hours Central Daylight Time, with Unit 3 operating at 100 percent thermal power, Unit 3 received a Group 6 ventilation system isolation signal during the performance of a maintenance activity on a Unit 3 Reactor/Refuel Zone Radiation Monitor, 3 RM-90-141/143. This resulted in isolation of the reactor and refuel zone ventilation systems, initiation of Standby Gas Treatment system (Trains A, B, and C) and the Control Room Emergency Ventilation system (Train A).
"All equipment responded to the Group 6 ventilation system isolation signal in accordance with the plant design. However, during the recovery effort, one of the Unit 3 Reactor Building Ventilation dampers failed to indicate fully closed. Operations personnel verified by inspection that the damper was fully closed.
"There were no safety consequences or impact on the health and safety of the public as a result of this event. The event was entered into the Corrective Action Program (CAP) as PER 227125.
"From PER 227125, trouble shooting determined a relay coil had been installed upside down when the coils were recently replaced.
"The NRC Senior Resident Inspector has been notified."