Event Notification Report for March 18, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/17/2016 - 03/18/2016
Power Reactor
Event Number: 51806
Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN LEWIN
HQ OPS Officer: STEVEN VITTO
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN LEWIN
HQ OPS Officer: STEVEN VITTO
Notification Date: 03/18/2016
Notification Time: 16:37 [ET]
Event Date: 03/18/2016
Event Time: 09:37 [CDT]
Last Update Date: 03/18/2016
Notification Time: 16:37 [ET]
Event Date: 03/18/2016
Event Time: 09:37 [CDT]
Last Update Date: 03/18/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)
FFD GROUP (EMAI)
ROBERT ORLIKOWSKI (R3DO)
FFD GROUP (EMAI)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - CONFIRMED POSITIVE TEST FOR ALCOHOL
"In accordance with 10 CFR 26.719(b)(2)(ii), this notification reports a non-licensed contracted employee supervisor had a confirmed positive for alcohol during a random fitness for duty test. The employee's access to the plant has been suspended.
"The licensee has notified the NRC Resident Inspector."
"In accordance with 10 CFR 26.719(b)(2)(ii), this notification reports a non-licensed contracted employee supervisor had a confirmed positive for alcohol during a random fitness for duty test. The employee's access to the plant has been suspended.
"The licensee has notified the NRC Resident Inspector."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 51807
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: JUSTIN WIEMER
HQ OPS Officer: DANIEL MILLS
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: JUSTIN WIEMER
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/18/2016
Notification Time: 18:43 [ET]
Event Date: 03/18/2016
Event Time: 11:28 [CDT]
Last Update Date: 05/16/2016
Notification Time: 18:43 [ET]
Event Date: 03/18/2016
Event Time: 11:28 [CDT]
Last Update Date: 05/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
MARK HAIRE (R4DO)
MARK HAIRE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SHUTDOWN COOLING PIPE VOID
"During a scheduled surveillance test on 3/18/2016 at 1128 [CDT], Fort Calhoun ultrasonic testing technicians discovered a void on the common shutdown cooling heat exchanger discharge piping. This piping is normally isolated during power operation, and the void does not adversely affect the Containment Spray function, Low Pressure Safety Injection function, or High Pressure Safety Injection function.
"This isolated piping with the void is placed in service only during shutdown cooling operation. The fluid height measured was 10.8 inches, compared to the required height of 11.7 inches for the surveillance test. The void could potentially complicate the initiation of shutdown cooling in the required mode of operation.
"This piping was last tested satisfactory on 12/31/2015. The source of the void is still under investigation.
"Fort Calhoun maintenance was successful in venting the void on 3/18/2016 at 1704 CDT."
The NRC Resident Inspector has been notified.
* * * RETRACTION AT 1701 EDT ON 05/16/16 FROM JAKE WALKER TO KARL DIEDERICH * * *
"Following the 8-hour 10 CFR 50.72 notification made on 3/18/16 (EN 51807), further engineering analysis has determined that the ensuing water hammer transient would not have prevented the shutdown cooling system from performing its required safety functions. Specifically, it was found that the resulting system pressure transient would not cause any relief valves to lift and that piping and supports would not be significantly challenged.
"Therefore, the common shutdown cooling heat exchanger discharge piping remained operable by the detailed analysis. As such, the safety function was not lost and the event notification is being retracted as it is not reportable pursuant to 10 CFR 50.72(b)(3)(v)(B)."
Notified the R4DO (G Miller).
"During a scheduled surveillance test on 3/18/2016 at 1128 [CDT], Fort Calhoun ultrasonic testing technicians discovered a void on the common shutdown cooling heat exchanger discharge piping. This piping is normally isolated during power operation, and the void does not adversely affect the Containment Spray function, Low Pressure Safety Injection function, or High Pressure Safety Injection function.
"This isolated piping with the void is placed in service only during shutdown cooling operation. The fluid height measured was 10.8 inches, compared to the required height of 11.7 inches for the surveillance test. The void could potentially complicate the initiation of shutdown cooling in the required mode of operation.
"This piping was last tested satisfactory on 12/31/2015. The source of the void is still under investigation.
"Fort Calhoun maintenance was successful in venting the void on 3/18/2016 at 1704 CDT."
The NRC Resident Inspector has been notified.
* * * RETRACTION AT 1701 EDT ON 05/16/16 FROM JAKE WALKER TO KARL DIEDERICH * * *
"Following the 8-hour 10 CFR 50.72 notification made on 3/18/16 (EN 51807), further engineering analysis has determined that the ensuing water hammer transient would not have prevented the shutdown cooling system from performing its required safety functions. Specifically, it was found that the resulting system pressure transient would not cause any relief valves to lift and that piping and supports would not be significantly challenged.
"Therefore, the common shutdown cooling heat exchanger discharge piping remained operable by the detailed analysis. As such, the safety function was not lost and the event notification is being retracted as it is not reportable pursuant to 10 CFR 50.72(b)(3)(v)(B)."
Notified the R4DO (G Miller).