Event Notification Report for November 21, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/20/2016 - 11/21/2016
EVENT NUMBERS
52388
Power Reactor
Event Number: 52388
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEVEN RADOMSKI
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEVEN RADOMSKI
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/21/2016
Notification Time: 21:22 [ET]
Event Date: 11/21/2016
Event Time: 17:38 [EST]
Last Update Date: 11/21/2016
Notification Time: 21:22 [ET]
Event Date: 11/21/2016
Event Time: 17:38 [EST]
Last Update Date: 11/21/2016
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):
JAMES DWYER (R1DO)
JAMES DWYER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SERVICE WATER LEAK INSIDE CONTAINMENT
"At 1738 [EST] on November 21, 2016, a leak was identified inside the Vapor Containment building on a Service Water line associated with 24 Fan Cooler Unit. The leak was isolated at 1743 by shutting the Service Water Isolation valves to 24 Fan Cooler Unit. This isolation meets the Technical Specifications of 3.6.1 Condition A Required Action. The leaking defect could have resulted in post-LOCA air leakage out of containment in excess of that allowed by Technical Specification 3.6.1 (Containment) which requires leakage rates to comply with 10 CFR 50, Appendix J. This event had no effect on the health and safety of the public.
"This event is being reported under 10 CFR 50.72(b)(3)(v) and the guidance of NUREG 1022, section 3.2.7 as a loss of safety function."
The service water was quantified at approximately 15 gpm.
The licensee notified the NRC Resident Inspector.
"At 1738 [EST] on November 21, 2016, a leak was identified inside the Vapor Containment building on a Service Water line associated with 24 Fan Cooler Unit. The leak was isolated at 1743 by shutting the Service Water Isolation valves to 24 Fan Cooler Unit. This isolation meets the Technical Specifications of 3.6.1 Condition A Required Action. The leaking defect could have resulted in post-LOCA air leakage out of containment in excess of that allowed by Technical Specification 3.6.1 (Containment) which requires leakage rates to comply with 10 CFR 50, Appendix J. This event had no effect on the health and safety of the public.
"This event is being reported under 10 CFR 50.72(b)(3)(v) and the guidance of NUREG 1022, section 3.2.7 as a loss of safety function."
The service water was quantified at approximately 15 gpm.
The licensee notified the NRC Resident Inspector.