Event Notification Report for December 03, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/02/2022 - 12/03/2022
EVENT NUMBERS
56257
56257
Power Reactor
Event Number: 56257
Facility: Browns Ferry
Region: 2 State: AL
Unit: [3] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: Mark Moebes
HQ OPS Officer: Bill Gott
Region: 2 State: AL
Unit: [3] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: Mark Moebes
HQ OPS Officer: Bill Gott
Notification Date: 12/03/2022
Notification Time: 13:05 [ET]
Event Date: 12/03/2022
Event Time: 10:00 [CST]
Last Update Date: 12/03/2022
Notification Time: 13:05 [ET]
Event Date: 12/03/2022
Event Time: 10:00 [CST]
Last Update Date: 12/03/2022
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):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DEGRADED CONDITION DISCOVERED ON SHUTDOWN COOLING TEST LINE
The following information was provided by the licensee via email:
"On 12/2/2022 at 2330 [CST] during the planned F311 outage on Browns Ferry Nuclear Plant Unit 3, personnel entered the Unit 3 drywell for leak identification. Personnel discovered a through-wall piping leak on a 0.75 inch test line between the two test line isolation valves. This 0.75 inch test line is located on the residual heat removal (RHR) loop 1 shutdown cooling and RHR return line to the reactor vessel. On 12/3/2022 at 1000 CST, Engineering determined this location is classified as ASME Code Class 1 piping.
"This constitutes an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(ii)(A) - Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"On 12/2/2022 at 2330 [CST] during the planned F311 outage on Browns Ferry Nuclear Plant Unit 3, personnel entered the Unit 3 drywell for leak identification. Personnel discovered a through-wall piping leak on a 0.75 inch test line between the two test line isolation valves. This 0.75 inch test line is located on the residual heat removal (RHR) loop 1 shutdown cooling and RHR return line to the reactor vessel. On 12/3/2022 at 1000 CST, Engineering determined this location is classified as ASME Code Class 1 piping.
"This constitutes an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(ii)(A) - Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"The NRC Resident Inspector has been notified."