Event Notification Report for April 20, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/19/2014 - 04/20/2014
Power Reactor
Event Number: 50046
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MITCH STACY
HQ OPS Officer: JEFF ROTTON
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MITCH STACY
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/20/2014
Notification Time: 08:08 [ET]
Event Date: 04/20/2014
Event Time: 02:15 [EDT]
Last Update Date: 04/20/2014
Notification Time: 08:08 [ET]
Event Date: 04/20/2014
Event Time: 02:15 [EDT]
Last Update Date: 04/20/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ALAN BLAMEY (R2DO)
ALAN BLAMEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF SECONDARY CONTAINMENT DUE TO OPENING IN REACTOR BUILDING ROOF DRAIN PIPING
"Due to openings found in degraded roof drain piping, Brunswick Nuclear Power Plant Unit 2 secondary containment was declared inoperable at 0215 [EDT] on 04/20/2014. During operator rounds the Reactor Building Aux Operator noted rainwater coming out of a roof drain line into the Reactor building. Upon further investigation a rusted area 2 foot by 2 inches was found on the pipe. Several through wall holes were found in this rusted area and the remainder of the rusted area was allowing water to weep through. The openings resulting from the through wall holes and rusted area exceeded the allowable openings in secondary containment, and this would have challenged secondary containment from performing its safety function. This event did not result in any adverse impact to the health and safety of the public. This is a non-emergency notification.
"INITIAL SAFETY SIGNIFICANCE EVALUATION: At the time that is was discovered that Unit 2 Secondary Containment was inoperable. Unit 2 was at 100% steady state conditions. Reactor building ventilation was in service in a normal alignment. The Unit 2 reactor building differential pressure was normal during the entire time secondary containment was inoperable. At no time was there a release of radioactive material from Unit 2 secondary containment.
"CORRECTIVE ACTIONS: The Unit 2 reactor building roof drain line has had a temporary repair applied. This repair has been evaluated by the Engineering department with site procedures and meets the requirements to maintain Secondary Containment operable. Unit 2 Secondary Containment operability was restored at 04/20/2014 0600 [EDT]."
The licensee notified the NRC Resident Inspector.
"Due to openings found in degraded roof drain piping, Brunswick Nuclear Power Plant Unit 2 secondary containment was declared inoperable at 0215 [EDT] on 04/20/2014. During operator rounds the Reactor Building Aux Operator noted rainwater coming out of a roof drain line into the Reactor building. Upon further investigation a rusted area 2 foot by 2 inches was found on the pipe. Several through wall holes were found in this rusted area and the remainder of the rusted area was allowing water to weep through. The openings resulting from the through wall holes and rusted area exceeded the allowable openings in secondary containment, and this would have challenged secondary containment from performing its safety function. This event did not result in any adverse impact to the health and safety of the public. This is a non-emergency notification.
"INITIAL SAFETY SIGNIFICANCE EVALUATION: At the time that is was discovered that Unit 2 Secondary Containment was inoperable. Unit 2 was at 100% steady state conditions. Reactor building ventilation was in service in a normal alignment. The Unit 2 reactor building differential pressure was normal during the entire time secondary containment was inoperable. At no time was there a release of radioactive material from Unit 2 secondary containment.
"CORRECTIVE ACTIONS: The Unit 2 reactor building roof drain line has had a temporary repair applied. This repair has been evaluated by the Engineering department with site procedures and meets the requirements to maintain Secondary Containment operable. Unit 2 Secondary Containment operability was restored at 04/20/2014 0600 [EDT]."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 50047
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: P.C. MOORE
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: P.C. MOORE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/20/2014
Notification Time: 19:58 [ET]
Event Date: 04/20/2014
Event Time: 14:42 [CDT]
Last Update Date: 04/20/2014
Notification Time: 19:58 [ET]
Event Date: 04/20/2014
Event Time: 14:42 [CDT]
Last Update Date: 04/20/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
VINCENT GADDY (R4DO)
VINCENT GADDY (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
EMERGENCY CORE COOLING SYSTEM PIPING LEAK WHILE SHUTDOWN
"A leak was discovered in the area of EPV0109, COMBINED SI/RHR [Safety Injection/Residual Heat Removal] TO ACCUMULATOR D OUTLET LINE VENT. The leak rate was estimated at 2.5 gallons per hour. The plant is in Mode 5, RCS [Reactor Coolant System] depressurized.
"This leak is considered a material problem that causes abnormal degradation of or stress upon the reactor coolant system pressure boundary, reportable in accordance with 10CFR 50.72(b)(3)(ii)(A).
"Efforts are underway to characterize the leak and plan for repairs. The leak has been secured after realigning RHR cooling from the B to the A train.
"The Resident Inspector has been notified."
The cause of the leak is being investigated.
"A leak was discovered in the area of EPV0109, COMBINED SI/RHR [Safety Injection/Residual Heat Removal] TO ACCUMULATOR D OUTLET LINE VENT. The leak rate was estimated at 2.5 gallons per hour. The plant is in Mode 5, RCS [Reactor Coolant System] depressurized.
"This leak is considered a material problem that causes abnormal degradation of or stress upon the reactor coolant system pressure boundary, reportable in accordance with 10CFR 50.72(b)(3)(ii)(A).
"Efforts are underway to characterize the leak and plan for repairs. The leak has been secured after realigning RHR cooling from the B to the A train.
"The Resident Inspector has been notified."
The cause of the leak is being investigated.