Event Notification Report for February 15, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/14/2004 - 02/15/2004
Power Reactor
Event Number: 40521
Facility: HATCH
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GREG JOHNSON
HQ OPS Officer: BILL GOTT
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GREG JOHNSON
HQ OPS Officer: BILL GOTT
Notification Date: 02/15/2004
Notification Time: 11:16 [ET]
Event Date: 02/15/2004
Event Time: 08:22 [EST]
Last Update Date: 02/15/2004
Notification Time: 11:16 [ET]
Event Date: 02/15/2004
Event Time: 08:22 [EST]
Last Update Date: 02/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
MARK LESSER (R2)
MARK LESSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
CONTAMINATED AND INJURED EMPLOYEE TRANSPORTED TO OFFSITE MEDICAL FACILITY
No System or Plant affect.
At 08:22 AM EST, an injured Contractor worke[r] who was potentially contaminated was transported by ambulance to an offsite medical facility. The Contract employee fell approximately 15 to 20 feet in the Unit 1 Circulation Water box which is located in the Condenser Bay area. Unit 1 is presently in Cold Shutdown and in Mode 4 for a scheduled Refueling Outage. The employee received cuts to the forehead and nose and an injury to the arm and also some back pain. In an effort to provide medical treatment as the first priority, decontamination efforts were not completed on site and the individual was transported as potentially contaminated. The injured cont[r]act employee was also accompanied by a Health Physics Technician. Upon arrival at the hospital and while receiving medial care, the Health Physics technicians did discover a 500 dpm/cm2 spot of contamination on the back of the head of the injured person. Decontamination efforts are underway while medical treatment is rendered.
The licensee notified the NRC Resident Inspector.
No System or Plant affect.
At 08:22 AM EST, an injured Contractor worke[r] who was potentially contaminated was transported by ambulance to an offsite medical facility. The Contract employee fell approximately 15 to 20 feet in the Unit 1 Circulation Water box which is located in the Condenser Bay area. Unit 1 is presently in Cold Shutdown and in Mode 4 for a scheduled Refueling Outage. The employee received cuts to the forehead and nose and an injury to the arm and also some back pain. In an effort to provide medical treatment as the first priority, decontamination efforts were not completed on site and the individual was transported as potentially contaminated. The injured cont[r]act employee was also accompanied by a Health Physics Technician. Upon arrival at the hospital and while receiving medial care, the Health Physics technicians did discover a 500 dpm/cm2 spot of contamination on the back of the head of the injured person. Decontamination efforts are underway while medical treatment is rendered.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 40522
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: HOPE BRADLEY
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: HOPE BRADLEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/15/2004
Notification Time: 20:18 [ET]
Event Date: 02/15/2004
Event Time: 15:19 [CST]
Last Update Date: 02/16/2004
Notification Time: 20:18 [ET]
Event Date: 02/15/2004
Event Time: 15:19 [CST]
Last Update Date: 02/16/2004
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):
CHUCK CAIN (R4)
CHUCK CAIN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 20 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP WITH AUXILIARY FEEDWATER ACTUATION
The following information was received from the licensee via facsimile:
"At 1519 [CDT] on 2-15-04, the plant was at 20 power, increasing load. During the transfer from the bypass feedwater regulating valves to the main feedwater regulating valves, the main turbine tripped due to a P-14 S/G Hi-Hi level signal. The P-14 signal also caused a Feedwater Isolation Signal (FWIS), which resulted in a Motor Driven Aux Feedwater Actuation (MDAFAS), and Steam Generator Blowdown Isolation Signal.
"Steam Generator levels subsequently shrunk to low levels causing a Steam Generator low level reactor trip at 1524 [hrs]. Sometime after the turbine trip, the turbine driven aux feed pump [(TDAFP)] was manually started to help restore S/G levels. The pump was later manually secured, but then received a subsequent auto-start signal and tripped on overspeed. The TDAFP was declared inoperable at 1535 [hrs]. With the exception of the TDAFP, all safety systems operated properly.
"The plant is currently stable in Mode 3, with the primary plant at 557 deg F and 2235 psig, and pressurizer level at 25%."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0031 EST ON 2/16/04 HOPE BRADLEY TO GOTT * * *
The following information was received from the licensee via facsimile as a "rewrite of above paragraph 2."
"Sometime after the turbine trip, the Turbine Driven Aux Feedwater Pump (TDAFP) was manually started to help restore S/G levels. Due to decreasing reactor coolant system (RCS) temperature, it was decided to stop the TDAFP since it is a steam load. The steam supply valves were remote manually closed from the control room. At the same time the steam supply valves were closing, the steam generator levels shrunk to low levels causing a Steam Generator low level reactor trip and Turbine Driven Aux Feedwater Actuation (TDAFAS) at 1524. The steam supply valves immediately reopened due to the TDAFAS. It is postulated that this transient in the steam supply caused the pump to overspeed trip. The TDAFP was declared inoperable at 1535. With the exception of the TDAFP, all safety systems operated properly."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Cain).
The following information was received from the licensee via facsimile:
"At 1519 [CDT] on 2-15-04, the plant was at 20 power, increasing load. During the transfer from the bypass feedwater regulating valves to the main feedwater regulating valves, the main turbine tripped due to a P-14 S/G Hi-Hi level signal. The P-14 signal also caused a Feedwater Isolation Signal (FWIS), which resulted in a Motor Driven Aux Feedwater Actuation (MDAFAS), and Steam Generator Blowdown Isolation Signal.
"Steam Generator levels subsequently shrunk to low levels causing a Steam Generator low level reactor trip at 1524 [hrs]. Sometime after the turbine trip, the turbine driven aux feed pump [(TDAFP)] was manually started to help restore S/G levels. The pump was later manually secured, but then received a subsequent auto-start signal and tripped on overspeed. The TDAFP was declared inoperable at 1535 [hrs]. With the exception of the TDAFP, all safety systems operated properly.
"The plant is currently stable in Mode 3, with the primary plant at 557 deg F and 2235 psig, and pressurizer level at 25%."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0031 EST ON 2/16/04 HOPE BRADLEY TO GOTT * * *
The following information was received from the licensee via facsimile as a "rewrite of above paragraph 2."
"Sometime after the turbine trip, the Turbine Driven Aux Feedwater Pump (TDAFP) was manually started to help restore S/G levels. Due to decreasing reactor coolant system (RCS) temperature, it was decided to stop the TDAFP since it is a steam load. The steam supply valves were remote manually closed from the control room. At the same time the steam supply valves were closing, the steam generator levels shrunk to low levels causing a Steam Generator low level reactor trip and Turbine Driven Aux Feedwater Actuation (TDAFAS) at 1524. The steam supply valves immediately reopened due to the TDAFAS. It is postulated that this transient in the steam supply caused the pump to overspeed trip. The TDAFP was declared inoperable at 1535. With the exception of the TDAFP, all safety systems operated properly."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Cain).