Event Notification Report for July 30, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/29/2023 - 07/30/2023
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 56644
Facility: Waterford
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: William Crowley
HQ OPS Officer: Adam Koziol
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: William Crowley
HQ OPS Officer: Adam Koziol
Notification Date: 07/30/2023
Notification Time: 17:25 [ET]
Event Date: 07/30/2023
Event Time: 11:19 [CDT]
Last Update Date: 09/12/2023
Notification Time: 17:25 [ET]
Event Date: 07/30/2023
Event Time: 11:19 [CDT]
Last Update Date: 09/12/2023
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):
Young, Cale (R4DO)
Young, Cale (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 9/13/2023
EN Revision Text: CONTROL ROOM ENVELOPE INOPERABLE
The following information was provided by the licensee via email:
"On July 30, 2023 at 1119 CDT, Waterford Steam Electric Station Unit 3 declared the control room envelope inoperable in accordance with technical specification (TS) 3.7.6.1 due to the control room envelope doors failing a door seal smoke test creating a breach in the control room envelope.
"Operations entered TS 3.7.6.1 Action b.
"Mitigating actions were implemented and tested satisfactorily by 1215 CDT.
"There was no impact on the health and safety of the public or plant personnel.
"This event is reportable pursuant to 10 CFR 50.72(b)(3)(v)(D), as an event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident, due to the control room envelope being inoperable.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 09/12/23 AT 1357 EDT FROM MONICA PEAK TO THOMAS HERRITY * * *
"The original operability determination of inoperable was made based on a conservative evaluation that with presence of smoke in-leakage through Door 261 and 262, the CRE boundary could not perform its safety function. A more detailed engineering evaluation was subsequently performed. No maintenance or intrusive testing was performed on the doors after initial test failure. As documented in version 2 operability determination for condition report WF3-2023-14604, the CRE boundary remained intact for the condition identified and was able to fulfill its safety function."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Warnick).
EN Revision Text: CONTROL ROOM ENVELOPE INOPERABLE
The following information was provided by the licensee via email:
"On July 30, 2023 at 1119 CDT, Waterford Steam Electric Station Unit 3 declared the control room envelope inoperable in accordance with technical specification (TS) 3.7.6.1 due to the control room envelope doors failing a door seal smoke test creating a breach in the control room envelope.
"Operations entered TS 3.7.6.1 Action b.
"Mitigating actions were implemented and tested satisfactorily by 1215 CDT.
"There was no impact on the health and safety of the public or plant personnel.
"This event is reportable pursuant to 10 CFR 50.72(b)(3)(v)(D), as an event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident, due to the control room envelope being inoperable.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 09/12/23 AT 1357 EDT FROM MONICA PEAK TO THOMAS HERRITY * * *
"The original operability determination of inoperable was made based on a conservative evaluation that with presence of smoke in-leakage through Door 261 and 262, the CRE boundary could not perform its safety function. A more detailed engineering evaluation was subsequently performed. No maintenance or intrusive testing was performed on the doors after initial test failure. As documented in version 2 operability determination for condition report WF3-2023-14604, the CRE boundary remained intact for the condition identified and was able to fulfill its safety function."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Warnick).
Power Reactor
Event Number: 56645
Facility: Seabrook
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Andrew Ferraioli
HQ OPS Officer: Adam Koziol
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Andrew Ferraioli
HQ OPS Officer: Adam Koziol
Notification Date: 07/30/2023
Notification Time: 18:20 [ET]
Event Date: 07/30/2023
Event Time: 15:26 [EDT]
Last Update Date: 07/30/2023
Notification Time: 18:20 [ET]
Event Date: 07/30/2023
Event Time: 15:26 [EDT]
Last Update Date: 07/30/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Bickett, Carey (R1DO)
Bickett, Carey (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOW MAIN TURBINE ELECTRO-HYDRAULIC CONTROL (EHC) OIL LEVEL
The following information was provided by the licensee via email:
"On July 30, 2023 at 1526 EDT, with unit 1 in mode 1 at 100 percent power, the reactor was manually tripped due to low main turbine electro-hydraulic control oil level. The trip was uncomplicated with all systems responding normally post-trip. Operations stabilized the plant in mode 3. Decay heat removal is being accomplished using the steam dumps in steam pressure mode to the main condenser. Emergency Feedwater actuated due to low-low steam generator level as expected.
"This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"On July 30, 2023 at 1526 EDT, with unit 1 in mode 1 at 100 percent power, the reactor was manually tripped due to low main turbine electro-hydraulic control oil level. The trip was uncomplicated with all systems responding normally post-trip. Operations stabilized the plant in mode 3. Decay heat removal is being accomplished using the steam dumps in steam pressure mode to the main condenser. Emergency Feedwater actuated due to low-low steam generator level as expected.
"This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).
"The NRC Resident Inspector has been notified."