Event Notification Report for August 17, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/16/2017 - 08/17/2017
Power Reactor
Event Number: 52911
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DREW RICHARDS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DREW RICHARDS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/17/2017
Notification Time: 16:48 [ET]
Event Date: 08/17/2017
Event Time: 14:42 [CDT]
Last Update Date: 08/17/2017
Notification Time: 16:48 [ET]
Event Date: 08/17/2017
Event Time: 14:42 [CDT]
Last Update Date: 08/17/2017
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):
THOMAS FARNHOLTZ (R4DO)
WILLIAM GOTT (IRD)
CHRIS MILLER (NRR)
THOMAS FARNHOLTZ (R4DO)
WILLIAM GOTT (IRD)
CHRIS MILLER (NRR)
| 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 | 100 | Power Operation | 100 | Power Operation |
NON WORK RELATED ONSITE FATALITY
"At 1315 Central Daylight Time (CDT) on 8/17/2017, the South Texas Project Unit 1 Control Room was notified that a contract employee had experienced a non-work-related medical emergency within the Protected Area. The individual was transported to Matagorda Regional Medical Center in Bay City, TX. At 1442 CDT, the Unit 1 Control Room was notified that the patient was declared deceased.
"The Occupational Safety and Health Administration (OSHA) will be notified. This notification is being made under 10CFR50.72(b)(2)(xi) as an event for which another government agency is being notified. The deceased individual was not radioactively contaminated.
"The NRC Senior Resident Inspector has been notified."
"At 1315 Central Daylight Time (CDT) on 8/17/2017, the South Texas Project Unit 1 Control Room was notified that a contract employee had experienced a non-work-related medical emergency within the Protected Area. The individual was transported to Matagorda Regional Medical Center in Bay City, TX. At 1442 CDT, the Unit 1 Control Room was notified that the patient was declared deceased.
"The Occupational Safety and Health Administration (OSHA) will be notified. This notification is being made under 10CFR50.72(b)(2)(xi) as an event for which another government agency is being notified. The deceased individual was not radioactively contaminated.
"The NRC Senior Resident Inspector has been notified."
Power Reactor
Event Number: 52912
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN McILNAY
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN McILNAY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/17/2017
Notification Time: 17:24 [ET]
Event Date: 08/17/2017
Event Time: 12:05 [EDT]
Last Update Date: 08/17/2017
Notification Time: 17:24 [ET]
Event Date: 08/17/2017
Event Time: 12:05 [EDT]
Last Update Date: 08/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARVIN SYKES (R2DO)
MARVIN SYKES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
ACTUATION OF TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DUE TO LOSS OF 6.9KV SHUTDOWN BOARD
"On August 17, 2017, at 1205 Eastern Daylight Time (EDT), the Watts Bar Nuclear Plant (WBN) lost power to the 1B-B 6.9kV Shutdown Board. The loss of power to this safety related bus resulted in an automatic start of the Unit 1 Turbine Driven Auxiliary Feedwater Pump (TDAFWP). The motor driven AFW pumps did not start and were not expected to start for this event. No other system actuations occurred as a result of loss of power to the 1B-B 6.9kV Shutdown Board. Power to the 1B-B Shutdown Board was restored at 1505 EDT on August 17, 2017.
"During the loss of power to the 1B-B Shutdown Board, a reduction in containment and control rod drive mechanism cooling occurred. At 1233 EDT, lower containment average temperature exceeded the procedural limitations specified, and Technical Specification 3.6.5 Condition A was entered for containment average air temperature not within limits. Lower containment average temperature was restored to within limits at 1525 EDT on August 17, 2017. This is reportable as a potential loss of safety function.
"Other than several common Unit Technical Specifications having not been met, Unit 2 was not operationally impacted by the loss of power to the 1B-B Shutdown Board and remains in Mode 1 at 100% power.
"The NRC Resident Inspector has been notified."
The loss of power occurred during restoration from Emergency Diesel Generator maintenance.
"On August 17, 2017, at 1205 Eastern Daylight Time (EDT), the Watts Bar Nuclear Plant (WBN) lost power to the 1B-B 6.9kV Shutdown Board. The loss of power to this safety related bus resulted in an automatic start of the Unit 1 Turbine Driven Auxiliary Feedwater Pump (TDAFWP). The motor driven AFW pumps did not start and were not expected to start for this event. No other system actuations occurred as a result of loss of power to the 1B-B 6.9kV Shutdown Board. Power to the 1B-B Shutdown Board was restored at 1505 EDT on August 17, 2017.
"During the loss of power to the 1B-B Shutdown Board, a reduction in containment and control rod drive mechanism cooling occurred. At 1233 EDT, lower containment average temperature exceeded the procedural limitations specified, and Technical Specification 3.6.5 Condition A was entered for containment average air temperature not within limits. Lower containment average temperature was restored to within limits at 1525 EDT on August 17, 2017. This is reportable as a potential loss of safety function.
"Other than several common Unit Technical Specifications having not been met, Unit 2 was not operationally impacted by the loss of power to the 1B-B Shutdown Board and remains in Mode 1 at 100% power.
"The NRC Resident Inspector has been notified."
The loss of power occurred during restoration from Emergency Diesel Generator maintenance.