Event Notification Report for February 01, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/31/2020 - 02/01/2020
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 54507
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: CLIFFORD JONES
HQ OPS Officer: KERBY SCALES
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: CLIFFORD JONES
HQ OPS Officer: KERBY SCALES
Notification Date: 02/01/2020
Notification Time: 16:29 [ET]
Event Date: 02/01/2020
Event Time: 11:50 [EST]
Last Update Date: 03/16/2020
Notification Time: 16:29 [ET]
Event Date: 02/01/2020
Event Time: 11:50 [EST]
Last Update Date: 03/16/2020
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):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOW PRESSURE CORE SPRAY INOPERABLE
"At 1150 EST on 2/1/2020, it was discovered that the Low Pressure Core Spray System was inoperable due to a divisional battery voltage being out-of-specification. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). The Low Pressure Core Spray is a single train safety system in Modes 1, 2, and 3. Low Pressure Core Spray was restored to operable, restoring function at 1230 on 2/1/2020.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 03/16/2020 AT 1156 EDT FROM JOHN NAKEL TO BETHANY CECERE * * *
"On February 01, 2020, event notification (EN-54507) was made to the NRC for Low Pressure Core Spray (LPCS) inoperability. This notification was made due to high DC bus voltages resulting in LPCS being declared inoperable which resulted in a loss of safety function.
"An Engineering Evaluation Request (EER) was performed to determine an upper limit for DC bus voltage. This EER determined that LPCS could perform its required functions with a voltage increase of up to 150V DC if the duration was not greater than two hours.
"The elevated voltage was experienced for approximately 59 minutes. The maximum voltage experienced was 147.07V DC. Therefore, LPCS remained operable and no loss of safety function existed.
"The NRC Resident Inspector has been briefed on the evaluation results and informed of this retraction."
Notified R3DO (Hanna).
"At 1150 EST on 2/1/2020, it was discovered that the Low Pressure Core Spray System was inoperable due to a divisional battery voltage being out-of-specification. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). The Low Pressure Core Spray is a single train safety system in Modes 1, 2, and 3. Low Pressure Core Spray was restored to operable, restoring function at 1230 on 2/1/2020.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 03/16/2020 AT 1156 EDT FROM JOHN NAKEL TO BETHANY CECERE * * *
"On February 01, 2020, event notification (EN-54507) was made to the NRC for Low Pressure Core Spray (LPCS) inoperability. This notification was made due to high DC bus voltages resulting in LPCS being declared inoperable which resulted in a loss of safety function.
"An Engineering Evaluation Request (EER) was performed to determine an upper limit for DC bus voltage. This EER determined that LPCS could perform its required functions with a voltage increase of up to 150V DC if the duration was not greater than two hours.
"The elevated voltage was experienced for approximately 59 minutes. The maximum voltage experienced was 147.07V DC. Therefore, LPCS remained operable and no loss of safety function existed.
"The NRC Resident Inspector has been briefed on the evaluation results and informed of this retraction."
Notified R3DO (Hanna).
Power Reactor
Event Number: 54508
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: ERIC CARLSON
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: ERIC CARLSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/01/2020
Notification Time: 23:06 [ET]
Event Date: 02/01/2020
Event Time: 18:45 [CST]
Last Update Date: 02/01/2020
Notification Time: 23:06 [ET]
Event Date: 02/01/2020
Event Time: 18:45 [CST]
Last Update Date: 02/01/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 0 | Hot Standby |
TECHNICAL SPECIFICATION SHUTDOWN DUE TO CONTAINMENT PURGE VALVE EXCESSIVE LEAKAGE
At 1845 CST on 2/1/2020, during surveillance testing (STS PE-015, Containment Purge Valve Leakage Test) containment leakage in excess of Technical Specification requirements was observed. A Technical Specification required shutdown was initiated at 2030 CST and Mode 3 was achieved at 2154 CST. All systems functioned as required during and following shutdown. The unit is proceeding to Mode 5.
The licensee notified the NRC Resident Inspector.
At 1845 CST on 2/1/2020, during surveillance testing (STS PE-015, Containment Purge Valve Leakage Test) containment leakage in excess of Technical Specification requirements was observed. A Technical Specification required shutdown was initiated at 2030 CST and Mode 3 was achieved at 2154 CST. All systems functioned as required during and following shutdown. The unit is proceeding to Mode 5.
The licensee notified the NRC Resident Inspector.