Event Notification Report for February 05, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/04/2022 - 02/05/2022
Power Reactor
Event Number: 55733
Facility: Oconee
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: Christopher Tam
HQ OPS Officer: Lloyd Desotell
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: Christopher Tam
HQ OPS Officer: Lloyd Desotell
Notification Date: 02/05/2022
Notification Time: 04:32 [ET]
Event Date: 02/05/2022
Event Time: 03:57 [EST]
Last Update Date: 02/08/2022
Notification Time: 04:32 [ET]
Event Date: 02/05/2022
Event Time: 03:57 [EST]
Last Update Date: 02/08/2022
Emergency Class: Unusual Event
10 CFR Section:
50.72(a) (1) (i) - Emergency Declared 50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(a) (1) (i) - Emergency Declared 50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Miller, Mark (R2)
Veil, Andrea (NRR)
Dudes, Laura (R2 RA)
Gott, William (IR)
Miller, Mark (R2)
Veil, Andrea (NRR)
Dudes, Laura (R2 RA)
Gott, William (IR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 3/7/2022
EN Revision Text: UNUSUAL EVENT DECLARED DUE TO VISUAL OBSERVATION OF SMOKE AND MULTIPLE FIRE ALARMS IN THE WEST PENETRATION ROOM
The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
At 0357 EST on 2/5/22, Oconee Unit 2 declared an Unusual Event due to a multiple fire alarms and visual observance of a smoke filled room in the West Penetration Room (EAL HU 4.1). Unit 2 automatically tripped and entered Mode 3. There was an indication that a release to the environment potentially occurred. Units 1 and 3 remained at 100% power.
The Licensee notified the NRC Resident Inspector, the State, and local authorities.
Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), and DHS Nuclear SSA (email).
* * * UPDATE ON 2/5/22 AT 0748 EST FROM CHUCK CLEMONS TO LLOYD DESOTELL * * *
The following information was provided by the licensee via email:
"At 0343 EST on February 5th, 2022, with Unit 2 in Mode 1 at 100% power, the reactor automatically tripped due to Reactor Coolant Pump (RCP) Flux/Flow Imbalance caused by the simultaneous trip of all 4 RCPs. The cause of the loss of all RCPs is under investigation. The trip was not complex. There was no inoperable equipment prior to the event that contributed to it.
"Operations responded and stabilized the plant. Decay heat is being removed by the Reactor Coolant System (RCS) in natural circulation with normal feedwater flow.
"Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a four hour, nonemergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The Licensee notified the State and local authorities.
Notified R2DO (Miller)
* * * UPDATE ON 2/5/22 AT 0815 EST FROM CHUCK CLEMONS TO LLOYD DESOTELL * * *
The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
At 0811 EST on 2/5/22, Oconee Unit 2 terminated the notification of unusual event because EAL HU 4.1 criteria were no longer met. Unit 2 remains shutdown in Mode 3.
The licensee has notified the State and local authorities and will notify the NRC Resident Inspector.
Notified R2DO (Miller), IRD MOC (Gott), NRR EO (Regan), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE ON 2/7/22 AT 2342 EST FROM PATRICK GADSBY TO OSSY FONT * * *
The following information was provided by the licensee via email:
"The follow-up investigation determine that the cause of the trip was determined to be a failed fuse in an undervoltage monitoring circuit for the electrical bus powering the reactor coolant pumps. The trip of the reactor coolant pumps resulted in an automatic reactor trip as designed. The plant responded as expected. There was no fire. The response of the main feedwater system caused an expected increase in temperature in a standby portion of the system which caused the breakdown of the pipe coating producing smoke. There was no release to the environment. The reading of a single instrument was determined to be invalid and other indications supported the conclusion that no release occurred."
The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The Licensee notified the NRC Resident Inspector, State and local authorities. A media release was issued on 2/5/22.
Notified R2DO (Miller), IRD MOC (Gott), NRR EO (Regan).
EN Revision Text: UNUSUAL EVENT DECLARED DUE TO VISUAL OBSERVATION OF SMOKE AND MULTIPLE FIRE ALARMS IN THE WEST PENETRATION ROOM
The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
At 0357 EST on 2/5/22, Oconee Unit 2 declared an Unusual Event due to a multiple fire alarms and visual observance of a smoke filled room in the West Penetration Room (EAL HU 4.1). Unit 2 automatically tripped and entered Mode 3. There was an indication that a release to the environment potentially occurred. Units 1 and 3 remained at 100% power.
The Licensee notified the NRC Resident Inspector, the State, and local authorities.
Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), and DHS Nuclear SSA (email).
* * * UPDATE ON 2/5/22 AT 0748 EST FROM CHUCK CLEMONS TO LLOYD DESOTELL * * *
The following information was provided by the licensee via email:
"At 0343 EST on February 5th, 2022, with Unit 2 in Mode 1 at 100% power, the reactor automatically tripped due to Reactor Coolant Pump (RCP) Flux/Flow Imbalance caused by the simultaneous trip of all 4 RCPs. The cause of the loss of all RCPs is under investigation. The trip was not complex. There was no inoperable equipment prior to the event that contributed to it.
"Operations responded and stabilized the plant. Decay heat is being removed by the Reactor Coolant System (RCS) in natural circulation with normal feedwater flow.
"Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a four hour, nonemergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The Licensee notified the State and local authorities.
Notified R2DO (Miller)
* * * UPDATE ON 2/5/22 AT 0815 EST FROM CHUCK CLEMONS TO LLOYD DESOTELL * * *
The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
At 0811 EST on 2/5/22, Oconee Unit 2 terminated the notification of unusual event because EAL HU 4.1 criteria were no longer met. Unit 2 remains shutdown in Mode 3.
The licensee has notified the State and local authorities and will notify the NRC Resident Inspector.
Notified R2DO (Miller), IRD MOC (Gott), NRR EO (Regan), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE ON 2/7/22 AT 2342 EST FROM PATRICK GADSBY TO OSSY FONT * * *
The following information was provided by the licensee via email:
"The follow-up investigation determine that the cause of the trip was determined to be a failed fuse in an undervoltage monitoring circuit for the electrical bus powering the reactor coolant pumps. The trip of the reactor coolant pumps resulted in an automatic reactor trip as designed. The plant responded as expected. There was no fire. The response of the main feedwater system caused an expected increase in temperature in a standby portion of the system which caused the breakdown of the pipe coating producing smoke. There was no release to the environment. The reading of a single instrument was determined to be invalid and other indications supported the conclusion that no release occurred."
The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The Licensee notified the NRC Resident Inspector, State and local authorities. A media release was issued on 2/5/22.
Notified R2DO (Miller), IRD MOC (Gott), NRR EO (Regan).
Power Reactor
Event Number: 55734
Facility: Davis Besse
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: Nicholas Buehler
HQ OPS Officer: Brian Lin
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: Nicholas Buehler
HQ OPS Officer: Brian Lin
Notification Date: 02/05/2022
Notification Time: 18:54 [ET]
Event Date: 02/05/2022
Event Time: 15:14 [EST]
Last Update Date: 02/05/2022
Notification Time: 18:54 [ET]
Event Date: 02/05/2022
Event Time: 15:14 [EST]
Last Update Date: 02/05/2022
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):
Orth, Steve (R3)
Regan, Chris (NRR EO)
Gott, William (IR)
Dickson, Billy (R3)
Orth, Steve (R3)
Regan, Chris (NRR EO)
Gott, William (IR)
Dickson, Billy (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 15 | Power Operation |
EN Revision Imported Date: 3/4/2022
EN Revision Text: TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via email:
"At approximately 1402 EST on 2/5/2022, with the Unit in Mode 1 at approximately 98 percent power, Operations was performing a valve lineup and inadvertently isolated a portion of the Reactor Coolant System (RCS) Letdown System, resulting in the system relief valve lifting and entry into the Makeup and Purification System Malfunction Abnormal Procedure due to loss of letdown. Pressurizer level increased and Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.9 CONDITION A was entered at 1414 EST due to Pressurizer level not below the limit of 228 inches, which has a REQUIRED ACTION to restore Pressurizer level within one hour. A rapid plant down power was initiated at approximately 1430 EST to reduce Pressurizer level.
"At 1514 EST on 2/5/2022, TS LCO 3.4.9 CONDITION B was entered, which has a REQUIRED ACTION to place the Unit in MODE 3 in 6 hours and in MODE 4 in 12 hours. As the Unit was continuing to down power, this represents initiation of a Technical Specification required shutdown, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"At approximately 1542 EST the down power was stopped at 15 percent power. Pressurizer level was restored to less than 228 inches at approximately 1603 EST, and TS LCO 3.4.9 was exited.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
EN Revision Text: TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via email:
"At approximately 1402 EST on 2/5/2022, with the Unit in Mode 1 at approximately 98 percent power, Operations was performing a valve lineup and inadvertently isolated a portion of the Reactor Coolant System (RCS) Letdown System, resulting in the system relief valve lifting and entry into the Makeup and Purification System Malfunction Abnormal Procedure due to loss of letdown. Pressurizer level increased and Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.9 CONDITION A was entered at 1414 EST due to Pressurizer level not below the limit of 228 inches, which has a REQUIRED ACTION to restore Pressurizer level within one hour. A rapid plant down power was initiated at approximately 1430 EST to reduce Pressurizer level.
"At 1514 EST on 2/5/2022, TS LCO 3.4.9 CONDITION B was entered, which has a REQUIRED ACTION to place the Unit in MODE 3 in 6 hours and in MODE 4 in 12 hours. As the Unit was continuing to down power, this represents initiation of a Technical Specification required shutdown, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"At approximately 1542 EST the down power was stopped at 15 percent power. Pressurizer level was restored to less than 228 inches at approximately 1603 EST, and TS LCO 3.4.9 was exited.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."