Event Notification Report for June 26, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/25/2018 - 06/26/2018
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 53476
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RANDY KOUBA
HQ OPS Officer: ANDREW WAUGH
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RANDY KOUBA
HQ OPS Officer: ANDREW WAUGH
Notification Date: 06/26/2018
Notification Time: 23:29 [ET]
Event Date: 06/26/2018
Event Time: 16:30 [CDT]
Last Update Date: 08/13/2018
Notification Time: 23:29 [ET]
Event Date: 06/26/2018
Event Time: 16:30 [CDT]
Last Update Date: 08/13/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RYAN ALEXANDER (R4DO)
RYAN ALEXANDER (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 |
CONTROL ROOM EMERGENCY FILTRATION SYSTEM DECLARED INOPERABLE
"On June 26, 2018, at 1630 CDT, the Control Room Emergency Filtration System (CREFS) was declared inoperable when Main Control Room Supply Fan SF-C-1B was discovered to have elevated vibrations that brought into question the ability to meet its mission time.
"CREFS is a single train safety system. Per 10 CFR 50.72(b)(3)(v)(D), an 8 hour report is required due to the fact that at the time of discovery this condition could have prevented the fulfillment of a safety function of an SSC [System Structure or Component] that is required to mitigate the consequences of an accident.
"The licensee has notified the NRC Senior Resident Inspector."
* * * RETRACTION FROM THOMAS FORLAND TO VINCE KLCO ON 8/13/18 AT 1024 EDT * * *
The following retraction was received from Cooper Nuclear Station (CNS) via facsimile and phone call:
"CNS is retracting the 8-hour non-emergency notification made on June 26, 2018 at 1630 CDT
(EN# 53476). Subsequent evaluation concluded that overall vibration levels were not at a level that would impact the ability of the Main Control Room Supply Fan SF-C-18 to perform its safety function for its required mission time and the CREFS therefore, was operable.
"The NRC Senior Resident Inspector has been notified."
Notified the R4DO (Deese).
"On June 26, 2018, at 1630 CDT, the Control Room Emergency Filtration System (CREFS) was declared inoperable when Main Control Room Supply Fan SF-C-1B was discovered to have elevated vibrations that brought into question the ability to meet its mission time.
"CREFS is a single train safety system. Per 10 CFR 50.72(b)(3)(v)(D), an 8 hour report is required due to the fact that at the time of discovery this condition could have prevented the fulfillment of a safety function of an SSC [System Structure or Component] that is required to mitigate the consequences of an accident.
"The licensee has notified the NRC Senior Resident Inspector."
* * * RETRACTION FROM THOMAS FORLAND TO VINCE KLCO ON 8/13/18 AT 1024 EDT * * *
The following retraction was received from Cooper Nuclear Station (CNS) via facsimile and phone call:
"CNS is retracting the 8-hour non-emergency notification made on June 26, 2018 at 1630 CDT
(EN# 53476). Subsequent evaluation concluded that overall vibration levels were not at a level that would impact the ability of the Main Control Room Supply Fan SF-C-18 to perform its safety function for its required mission time and the CREFS therefore, was operable.
"The NRC Senior Resident Inspector has been notified."
Notified the R4DO (Deese).
Power Reactor
Event Number: 53472
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM BENNETT
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM BENNETT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/26/2018
Notification Time: 04:26 [ET]
Event Date: 06/26/2018
Event Time: 00:03 [CDT]
Last Update Date: 06/26/2018
Notification Time: 04:26 [ET]
Event Date: 06/26/2018
Event Time: 00:03 [CDT]
Last Update Date: 06/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RYAN ALEXANDER (R4DO)
RYAN ALEXANDER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
MAIN STEAM LINE RADIATION MONITOR DETERMINED TO BE NON-FUNCTIONAL
"At time 0003 [CDT], Main Steamline Radiation Monitor 2-RE-2326 (Main Steam line 2-02) reading spiked and [was] declared non-functional.
"With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 2-02 could neither be evaluated nor monitored. This unplanned condition is reportable as a loss of assessment capability per 10CFR50.72(b)(3)(xiii).
"Comanche Peak Nuclear Power Plant (CPNPP) has assurance of steam generator integrity and fuel cladding integrity and there is negligible safety significance to the current condition [with respect to the] public health and safety perspective.
"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding. The N16 radiation monitor serves as a backup with alarm function and Radiation Protection technicians have been briefed on taking local readings with a Geiger-Mueller tube on MSL 2-02.
"Corrective actions are being pursued to restore 2-RE-2326 to functional status.
"The NRC Resident Inspector has been notified."
"At time 0003 [CDT], Main Steamline Radiation Monitor 2-RE-2326 (Main Steam line 2-02) reading spiked and [was] declared non-functional.
"With this radiation monitor non-functional, all of the emergency action levels for a steam generator tube rupture in steam generator 2-02 could neither be evaluated nor monitored. This unplanned condition is reportable as a loss of assessment capability per 10CFR50.72(b)(3)(xiii).
"Comanche Peak Nuclear Power Plant (CPNPP) has assurance of steam generator integrity and fuel cladding integrity and there is negligible safety significance to the current condition [with respect to the] public health and safety perspective.
"Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator or fuel cladding. The N16 radiation monitor serves as a backup with alarm function and Radiation Protection technicians have been briefed on taking local readings with a Geiger-Mueller tube on MSL 2-02.
"Corrective actions are being pursued to restore 2-RE-2326 to functional status.
"The NRC Resident Inspector has been notified."