Event Notification Report for October 21, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/20/2018 - 10/21/2018
Power Reactor
Event Number: 53680
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN ALEXANDER
HQ OPS Officer: ANDREW WAUGH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN ALEXANDER
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/21/2018
Notification Time: 19:58 [ET]
Event Date: 10/21/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/21/2018
Notification Time: 19:58 [ET]
Event Date: 10/21/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/21/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GERALD MCCOY (R2DO)
BO PHAM (IRD)
CHRIS MILLER (NRR EO)
GERALD MCCOY (R2DO)
BO PHAM (IRD)
CHRIS MILLER (NRR EO)
| 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 | 80 | Power Operation | 80 | Power Operation |
OFFSITE NOTIFICATION DUE TO DEATH OF EMPLOYEE ON SITE
"This notification is being made due to the death of an employee on-site. A Security Officer was found unresponsive on the Turbine Building Moisture Separator Re-heater deck on the Unit 1 side. Upon arrival of Fire Operations and on-site medical the individual had suffered an apparent heart attack. Hamilton County Emergency Medical Services will be transferring the individual to the medical examiner's office. The on-site NRC Senior Resident Inspector has been notified."
The licensee believes this event may receive media attention and a press release could be issued.
"This notification is being made due to the death of an employee on-site. A Security Officer was found unresponsive on the Turbine Building Moisture Separator Re-heater deck on the Unit 1 side. Upon arrival of Fire Operations and on-site medical the individual had suffered an apparent heart attack. Hamilton County Emergency Medical Services will be transferring the individual to the medical examiner's office. The on-site NRC Senior Resident Inspector has been notified."
The licensee believes this event may receive media attention and a press release could be issued.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 53678
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: JEFF HERRERA
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/21/2018
Notification Time: 06:19 [ET]
Event Date: 10/21/2018
Event Time: 00:00 [CDT]
Last Update Date: 12/13/2018
Notification Time: 06:19 [ET]
Event Date: 10/21/2018
Event Time: 00:00 [CDT]
Last Update Date: 12/13/2018
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):
GERALD MCCOY (R2DO)
GERALD MCCOY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 67 | Power Operation | 67 | Power Operation |
TECHNICAL SPECIFICATION SHUT DOWN DUE TO CHEMISTRY LIMIT EXCEEDED
"At 0200 Central Daylight Time on 10/21/2018, Browns Ferry Nuclear Plant Unit 3 commenced a reactor shutdown as required by the Technical Requirements Manual Limiting Condition for Operation 3.4.1 Coolant Chemistry Condition D due to conductivity greater than 10 micro mho/cm at 25 degrees Celsius. The required action for this condition is to immediately initiate an orderly shutdown and be in Mode 4 as rapidly as cooldown rate permits. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel. The NRC Senior Resident Inspector has been notified."
* * * RETRACTION AT 1719 EST ON 12/13/2018 FROM NEEL SHUKLA TO MARK ABRAMOVITZ * * *
"ENS Event Number 53678, made on 10/21/18, is being retracted.
"NRC notification 53678 was made to ensure that the four-hour non-emergency reporting requirements of 10 CFR 50.72 were met when the licensee discovered a condition requiring shut down of a reactor.
"10 CFR 50.72 requires a report in accordance with 50.72(b)(2)(i) for any Technical Specifications (TS) required reactor
shutdown. NUREG-1022 only specifies TS applicability and makes no mention of a Technical Requirements Manual (TRM) required shutdown. Because the shutdown comes from the TRM and not the TS as discussed in 10 CFR 50.72 and
NUREG-1022, an EN was not required.
"TVA's evaluation of this event notification is documented in the corrective action program.
"The licensee notified the NRC Resident Inspector."
Notified the R2DO (Ehrhardt).
"At 0200 Central Daylight Time on 10/21/2018, Browns Ferry Nuclear Plant Unit 3 commenced a reactor shutdown as required by the Technical Requirements Manual Limiting Condition for Operation 3.4.1 Coolant Chemistry Condition D due to conductivity greater than 10 micro mho/cm at 25 degrees Celsius. The required action for this condition is to immediately initiate an orderly shutdown and be in Mode 4 as rapidly as cooldown rate permits. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel. The NRC Senior Resident Inspector has been notified."
* * * RETRACTION AT 1719 EST ON 12/13/2018 FROM NEEL SHUKLA TO MARK ABRAMOVITZ * * *
"ENS Event Number 53678, made on 10/21/18, is being retracted.
"NRC notification 53678 was made to ensure that the four-hour non-emergency reporting requirements of 10 CFR 50.72 were met when the licensee discovered a condition requiring shut down of a reactor.
"10 CFR 50.72 requires a report in accordance with 50.72(b)(2)(i) for any Technical Specifications (TS) required reactor
shutdown. NUREG-1022 only specifies TS applicability and makes no mention of a Technical Requirements Manual (TRM) required shutdown. Because the shutdown comes from the TRM and not the TS as discussed in 10 CFR 50.72 and
NUREG-1022, an EN was not required.
"TVA's evaluation of this event notification is documented in the corrective action program.
"The licensee notified the NRC Resident Inspector."
Notified the R2DO (Ehrhardt).