Event Notification Report for October 16, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/15/2017 - 10/16/2017
Power Reactor
Event Number: 53018
Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: DANIEL MICKINAC
HQ OPS Officer: STEVEN VITTO
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: DANIEL MICKINAC
HQ OPS Officer: STEVEN VITTO
Notification Date: 10/16/2017
Notification Time: 17:59 [ET]
Event Date: 10/16/2017
Event Time: 08:51 [EDT]
Last Update Date: 10/16/2017
Notification Time: 17:59 [ET]
Event Date: 10/16/2017
Event Time: 08:51 [EDT]
Last Update Date: 10/16/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
STEVE ROSE (R2DO)
FFD GROUP (EMAI)
STEVE ROSE (R2DO)
FFD GROUP (EMAI)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Under Construction | 0 | Under Construction |
| 4 | N | N | 0 | Under Construction | 0 | Under Construction |
FITNESS FOR DUTY - NON LICENSED SUPERVISOR SUBVERTED TEST
"A non-licensed supervisory contractor subverted a random Fitness for Duty (FFD) test. At 0851 [EDT] on October 16, 2017, a contractor supervisor was notified to report for a random FFD test and [the individual] did not report to the testing facility and left the premises. The contractor's site access has been terminated. The NRC Resident Inspector was notified."
"A non-licensed supervisory contractor subverted a random Fitness for Duty (FFD) test. At 0851 [EDT] on October 16, 2017, a contractor supervisor was notified to report for a random FFD test and [the individual] did not report to the testing facility and left the premises. The contractor's site access has been terminated. The NRC Resident Inspector was notified."
Power Reactor
Event Number: 53019
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PHILIP SNIDER
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PHILIP SNIDER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/16/2017
Notification Time: 22:09 [ET]
Event Date: 10/16/2017
Event Time: 14:25 [CDT]
Last Update Date: 10/16/2017
Notification Time: 22:09 [ET]
Event Date: 10/16/2017
Event Time: 14:25 [CDT]
Last Update Date: 10/16/2017
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
REACTOR COOLANT SYSTEM SHUTDOWN COMMUNICATION LINE VENT THROUGH WALL DEFECT
"At 1425 CDT on 10/16/17, investigation into a boric acid indication was determined to be a through wall leak at the socket weld that joins the 3/4 inch line 2RC-92 to valve 2RC-8-37. Unit 2 is currently in Mode 5 with Reactor Coolant system (RCS) Operational Leakage limits not applicable. The leak is downstream of two first off RCS isolation valves that are normally closed. The leak is not quantifiable as it only consists of a small amount of dry boric acid at the location. This failure constitutes welding or material defects in the primary coolant system that cannot be found acceptable under ASME Section Xl.
"Therefore, this is a degraded condition reportable under 10 CFR 50.72(b)(3)(ii)(A).
"At the time of this notification, the Prairie Island Nuclear Generating Plant Unit 2 is in Mode 5 for a planned refueling outage. The identified defect will be repaired prior to entering Mode 4.
"This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."
"At 1425 CDT on 10/16/17, investigation into a boric acid indication was determined to be a through wall leak at the socket weld that joins the 3/4 inch line 2RC-92 to valve 2RC-8-37. Unit 2 is currently in Mode 5 with Reactor Coolant system (RCS) Operational Leakage limits not applicable. The leak is downstream of two first off RCS isolation valves that are normally closed. The leak is not quantifiable as it only consists of a small amount of dry boric acid at the location. This failure constitutes welding or material defects in the primary coolant system that cannot be found acceptable under ASME Section Xl.
"Therefore, this is a degraded condition reportable under 10 CFR 50.72(b)(3)(ii)(A).
"At the time of this notification, the Prairie Island Nuclear Generating Plant Unit 2 is in Mode 5 for a planned refueling outage. The identified defect will be repaired prior to entering Mode 4.
"This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."