Event Notification Report for October 21, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/20/2006 - 10/21/2006
EVENT NUMBERS
42926429234292442925
Power Reactor
Event Number: 42926
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JERRY BEBB
HQ OPS Officer: MIKE RIPLEY
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JERRY BEBB
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/21/2006
Notification Time: 23:23 [ET]
Event Date: 10/21/2006
Event Time: 20:12 [CDT]
Last Update Date: 10/21/2006
Notification Time: 23:23 [ET]
Event Date: 10/21/2006
Event Time: 20:12 [CDT]
Last Update Date: 10/21/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
FITNESS FOR DUTY
A contract supervisor tested positive for alcohol during a for-cause test. The supervisor's plant access has been suspended. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified.
A contract supervisor tested positive for alcohol during a for-cause test. The supervisor's plant access has been suspended. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 42923
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: M. SECKENS
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: M. SECKENS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/21/2006
Notification Time: 10:15 [ET]
Event Date: 10/21/2006
Event Time: 07:35 [EDT]
Last Update Date: 10/21/2006
Notification Time: 10:15 [ET]
Event Date: 10/21/2006
Event Time: 07:35 [EDT]
Last Update Date: 10/21/2006
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):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
NOTIFICATION TO STATE OF CHEMICAL AND SEWAGE RELEASE
"Notification of the State [Maryland Department of the Environment] per the NPDES [National Pollution Discharge Elimination System] permit of the release of a maximum of 20 gallons of sewage and chemicals from a portable toilet to the bay through a storm drain."
A portable toilet was blown-over by high winds at the site.
The licensee notified the NRC Resident Inspector.
"Notification of the State [Maryland Department of the Environment] per the NPDES [National Pollution Discharge Elimination System] permit of the release of a maximum of 20 gallons of sewage and chemicals from a portable toilet to the bay through a storm drain."
A portable toilet was blown-over by high winds at the site.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 42924
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KLAY KLIMPLE
HQ OPS Officer: MIKE RIPLEY
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KLAY KLIMPLE
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/21/2006
Notification Time: 18:26 [ET]
Event Date: 10/21/2006
Event Time: 15:58 [CDT]
Last Update Date: 10/21/2006
Notification Time: 18:26 [ET]
Event Date: 10/21/2006
Event Time: 15:58 [CDT]
Last Update Date: 10/21/2006
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):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE MEDICAL TREATMENT OF POTENTIALLY CONTAMINATED CONTRACT EMPLOYEE
"A contract employee experienced heat exhaustion while working in the Reactor Containment Building in a contaminated area and was considered potentially contaminated because the initial survey for radioactive contamination had not been completed prior to transporting the employee offsite for medical treatment."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM LICENSEE (B. SCARBOROUGH) TO M. RIPLEY AT 1912 EDT ON 10/21/06 * * *
At 1758 CDT on 10/21/06, the licensee was notified by their Health Physics Dept. that the contract employee was transported to the Matagorda Hospital in Bay City, TX and was found not to be contaminated. Additionally, all instruments and equipment used in the incident were surveyed and no contamination was found.
The licensee notified the NRC Resident Inspector. Notified R4 DO (D. Powers).
"A contract employee experienced heat exhaustion while working in the Reactor Containment Building in a contaminated area and was considered potentially contaminated because the initial survey for radioactive contamination had not been completed prior to transporting the employee offsite for medical treatment."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM LICENSEE (B. SCARBOROUGH) TO M. RIPLEY AT 1912 EDT ON 10/21/06 * * *
At 1758 CDT on 10/21/06, the licensee was notified by their Health Physics Dept. that the contract employee was transported to the Matagorda Hospital in Bay City, TX and was found not to be contaminated. Additionally, all instruments and equipment used in the incident were surveyed and no contamination was found.
The licensee notified the NRC Resident Inspector. Notified R4 DO (D. Powers).
Power Reactor
Event Number: 42925
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRAD EKLUND
HQ OPS Officer: MIKE RIPLEY
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRAD EKLUND
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/21/2006
Notification Time: 21:37 [ET]
Event Date: 10/21/2006
Event Time: 15:48 [MST]
Last Update Date: 10/21/2006
Notification Time: 21:37 [ET]
Event Date: 10/21/2006
Event Time: 15:48 [MST]
Last Update Date: 10/21/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO CONTROL ELEMENT ASSEMBLY POSITION TRANSMITTER OUTPUT DEVIATIONS
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On October 21, 2006 at approximately 1549 MST Palo Verde Unit 1 experienced a reactor trip (RPS actuation) from 100% rated thermal power due to low departure from nucleate boiling (DNBR) trips on all four channels of the core protection calculators (CPCs). The unit was at normal temperature and pressure prior to the trip.
"Several minutes prior to the Reactor Trip, RSPT#1 (Reed Switch Position Transmitter) CEA deviation alarms were received for CEA#29 (Shutdown Group B CEA). Operators observed that the magnitude of the deviation was fluctuating erratically. While investigating the alarms CEAC #1 Sensor Fail alarms were received and at 1549 MST, the Reactor automatically tripped on a CPC generated Lo DNBR trips on all 4 channels of CPCs. The apparent cause is presently suspected to be a failure of RSPT#1. An investigation has commenced to determine the root cause of the reactor trip.
"All of the control rods fully inserted into the core. The Steam Bypass Control System operated as designed, directing steam flow to the condenser. No main steam or primary relief valves lifted and none were required. There was no loss of heat removal capability or loss of safety functions associated with the event. Electrical buses transferred to offsite power as designed. The Shift Manager determined this event was an uncomplicated reactor trip. No significant LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event nor contributed to the event.
"Unit 1 is stable at normal operating temperature and pressure in Mode 3. No ESF actuations occurred and none were required. The event did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. The event did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident was notified at 17:38 MST."
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On October 21, 2006 at approximately 1549 MST Palo Verde Unit 1 experienced a reactor trip (RPS actuation) from 100% rated thermal power due to low departure from nucleate boiling (DNBR) trips on all four channels of the core protection calculators (CPCs). The unit was at normal temperature and pressure prior to the trip.
"Several minutes prior to the Reactor Trip, RSPT#1 (Reed Switch Position Transmitter) CEA deviation alarms were received for CEA#29 (Shutdown Group B CEA). Operators observed that the magnitude of the deviation was fluctuating erratically. While investigating the alarms CEAC #1 Sensor Fail alarms were received and at 1549 MST, the Reactor automatically tripped on a CPC generated Lo DNBR trips on all 4 channels of CPCs. The apparent cause is presently suspected to be a failure of RSPT#1. An investigation has commenced to determine the root cause of the reactor trip.
"All of the control rods fully inserted into the core. The Steam Bypass Control System operated as designed, directing steam flow to the condenser. No main steam or primary relief valves lifted and none were required. There was no loss of heat removal capability or loss of safety functions associated with the event. Electrical buses transferred to offsite power as designed. The Shift Manager determined this event was an uncomplicated reactor trip. No significant LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event nor contributed to the event.
"Unit 1 is stable at normal operating temperature and pressure in Mode 3. No ESF actuations occurred and none were required. The event did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. The event did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident was notified at 17:38 MST."