Event Notification Report for March 20, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/19/2016 - 03/20/2016
EVENT NUMBERS
51809
Power Reactor
Event Number: 51809
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN HARKINS
HQ OPS Officer: VINCE KLCO
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN HARKINS
HQ OPS Officer: VINCE KLCO
Notification Date: 03/20/2016
Notification Time: 23:51 [ET]
Event Date: 03/20/2016
Event Time: 21:54 [EDT]
Last Update Date: 03/21/2016
Notification Time: 23:51 [ET]
Event Date: 03/20/2016
Event Time: 21:54 [EDT]
Last Update Date: 03/21/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JAMES NOGGLE (R1DO)
SCOTT MORRIS (NRR)
BERNARD STAPLETON (IRD)
JAMES NOGGLE (R1DO)
SCOTT MORRIS (NRR)
BERNARD STAPLETON (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 15 | Power Operation | 15 | Power Operation |
TECHNICAL SPECIFICATION (TS) REQUIRED SHUTDOWN DUE TO PRESSURE BOUNDARY LEAKAGE
"During a planned Unit 1 shutdown for a refueling outage, a 0.5 gpm 'pressure boundary leak' was identified on a 1 inch pipe connected to the '1A' RHR-Shutdown Cooling return line by the drywell leak inspection team during a drywell inspection at approximately 15% power. The leak exceeded the TS 3.4.3.2 'Operational Leakage' LCO of no pressure boundary leakage. TS action 'a' was entered which requires to be in at least Hot Shutdown within 12 hours and Cold Shutdown within the next 24 hours. Therefore, the event is reportable within 4 hours per 10CFR50.72(b)(2)(i) due to the initiation of a plant shutdown required by the plant's TS.
"The event is also reportable within 8 hours per 10CFR50.72(b)(3)(ii) due to an event that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"TS 1.28 defines Pressure Boundary Leakage as leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall; therefore, the leak is a 'pressure boundary leak' as defined in TS."
The licensee notified the NRC resident Inspector.
"During a planned Unit 1 shutdown for a refueling outage, a 0.5 gpm 'pressure boundary leak' was identified on a 1 inch pipe connected to the '1A' RHR-Shutdown Cooling return line by the drywell leak inspection team during a drywell inspection at approximately 15% power. The leak exceeded the TS 3.4.3.2 'Operational Leakage' LCO of no pressure boundary leakage. TS action 'a' was entered which requires to be in at least Hot Shutdown within 12 hours and Cold Shutdown within the next 24 hours. Therefore, the event is reportable within 4 hours per 10CFR50.72(b)(2)(i) due to the initiation of a plant shutdown required by the plant's TS.
"The event is also reportable within 8 hours per 10CFR50.72(b)(3)(ii) due to an event that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"TS 1.28 defines Pressure Boundary Leakage as leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall; therefore, the leak is a 'pressure boundary leak' as defined in TS."
The licensee notified the NRC resident Inspector.