Event Notification Report for April 23, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/22/2005 - 04/23/2005
EVENT NUMBERS
41627416284162941630
Power Reactor
Event Number: 41627
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREG BAKER
HQ OPS Officer: BILL GOTT
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREG BAKER
HQ OPS Officer: BILL GOTT
Notification Date: 04/23/2005
Notification Time: 10:26 [ET]
Event Date: 04/23/2005
Event Time: 07:30 [CST]
Last Update Date: 04/23/2005
Notification Time: 10:26 [ET]
Event Date: 04/23/2005
Event Time: 07:30 [CST]
Last Update Date: 04/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (R3)
| 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 | N | 0 | Refueling | 0 | Refueling |
FITNESS FOR DUTY: ALCOHOL
A non-licensed contract employee was determined to be under the influence of alcohol during a for cause test. The employee's access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.
The licensee will notify the Resident Inspector.
A non-licensed contract employee was determined to be under the influence of alcohol during a for cause test. The employee's access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.
The licensee will notify the Resident Inspector.
Power Reactor
Event Number: 41628
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/23/2005
Notification Time: 14:58 [ET]
Event Date: 04/23/2005
Event Time: 10:45 [EST]
Last Update Date: 04/23/2005
Notification Time: 14:58 [ET]
Event Date: 04/23/2005
Event Time: 10:45 [EST]
Last Update Date: 04/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOEL MUNDAY (R2)
JOEL MUNDAY (R2)
| 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 |
PLANT LOST ERDADS (EMERGENCY RESPONSE DATA ACQUISITION DISPLAY SYSTEM) DATA LINK CAPABILITY
"On April 23, 2005, at 10:45 hours St. Lucie Plant last the ERDADS NRC Data Link capability. The System Engineer reports that the ERDADS periphery switch failed to swap to the "A" CPU from the "B" CPU on a auto failover that occurred at 10:45. The switch has been manually swapped and the Data Link has been restored. A work order has been prepared to investigate and repair the cause for this failure."
The NRC resident Inspector was notified.
"On April 23, 2005, at 10:45 hours St. Lucie Plant last the ERDADS NRC Data Link capability. The System Engineer reports that the ERDADS periphery switch failed to swap to the "A" CPU from the "B" CPU on a auto failover that occurred at 10:45. The switch has been manually swapped and the Data Link has been restored. A work order has been prepared to investigate and repair the cause for this failure."
The NRC resident Inspector was notified.
Power Reactor
Event Number: 41629
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JOHN ARONSON
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JOHN ARONSON
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/23/2005
Notification Time: 18:43 [ET]
Event Date: 04/23/2005
Event Time: 00:00 [MST]
Last Update Date: 04/23/2005
Notification Time: 18:43 [ET]
Event Date: 04/23/2005
Event Time: 00:00 [MST]
Last Update Date: 04/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MICHAEL SHANNON (R4)
MICHAEL SHANNON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
DISCOVERED TWO AXIAL INDICATIONS ON INSIDE DIAMETER OF REACTOR VESSEL HEAD PENETRATION
"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 will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On April 23, 2005, at approximately 11:35 Mountain Standard Time (MST) engineering personnel performing preplanned in-service examinations of reactor vessel head vent penetration in accordance with procedure requirements discovered two axial indications in the Palo Verde Nuclear Generating Station Unit 2 reactor vessel head vent penetration. The indications are located on the inner diameter surface of the pipe adjacent to the J-weld to the head and are part of the RCS pressure boundary. The indications are characterized as axial, estimated less than 0.080 inch deep, approximately 0.1 inch long, and oriented at approximately 90 degrees from each other. The indications are not through-wall. There is no evidence of RCS pressure boundary leakage.
"Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.14 permits no reactor coolant system (RCS) pressure boundary leakage and there is no evidence of pressure boundary leakage. Nevertheless, the indications are being conservatively identified as abnormal degradation of the reactor coolant system pressure boundary and will necessitate taking corrective action to restore the barrier's capability. Therefore, the ENS notification of this event is in accordance with 10CFR50.72(b)(3)(ii)(A). The Unit had been shutdown for its 12th refueling outage and was being maintained de-fueled for maintenance.
"No ESF actuations occurred and none were required. There were no structures, systems, or components that were inoperable at the time of discovery that contributed to this condition. There were no failures that rendered a train of a safety system inoperable and no failures of components with multiple functions were involved. The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public.
" An investigation of this event will be conducted in accordance with PVNGS corrective action program."
The NRC Resident Inspector was notified of this event by the licensee.
"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 will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On April 23, 2005, at approximately 11:35 Mountain Standard Time (MST) engineering personnel performing preplanned in-service examinations of reactor vessel head vent penetration in accordance with procedure requirements discovered two axial indications in the Palo Verde Nuclear Generating Station Unit 2 reactor vessel head vent penetration. The indications are located on the inner diameter surface of the pipe adjacent to the J-weld to the head and are part of the RCS pressure boundary. The indications are characterized as axial, estimated less than 0.080 inch deep, approximately 0.1 inch long, and oriented at approximately 90 degrees from each other. The indications are not through-wall. There is no evidence of RCS pressure boundary leakage.
"Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.14 permits no reactor coolant system (RCS) pressure boundary leakage and there is no evidence of pressure boundary leakage. Nevertheless, the indications are being conservatively identified as abnormal degradation of the reactor coolant system pressure boundary and will necessitate taking corrective action to restore the barrier's capability. Therefore, the ENS notification of this event is in accordance with 10CFR50.72(b)(3)(ii)(A). The Unit had been shutdown for its 12th refueling outage and was being maintained de-fueled for maintenance.
"No ESF actuations occurred and none were required. There were no structures, systems, or components that were inoperable at the time of discovery that contributed to this condition. There were no failures that rendered a train of a safety system inoperable and no failures of components with multiple functions were involved. The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public.
" An investigation of this event will be conducted in accordance with PVNGS corrective action program."
The NRC Resident Inspector was notified of this event by the licensee.
General Information or Other
Event Number: 41630
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: QORE INC.
Region: 1
City: WEST PALM BEACH State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: JOHN MacKINNON
Licensee: QORE INC.
Region: 1
City: WEST PALM BEACH State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/24/2005
Notification Time: 12:25 [ET]
Event Date: 04/23/2005
Event Time: 23:00 [EST]
Last Update Date: 04/24/2005
Notification Time: 12:25 [ET]
Event Date: 04/23/2005
Event Time: 23:00 [EST]
Last Update Date: 04/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAVID SILK (R1)
JOSEPH GIITTER (NMSS)
DAVID SILK (R1)
JOSEPH GIITTER (NMSS)
FLORIDA AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
State of Florida Bureau of Radiation Control received the following information from the Radiation Safety Officer for Qore Inc., located in West Palm Beach, FL.
On 04/23/05 at 2300 EDT a Qore Inc. employee discovered that the Troxler Moisture Density gauge that had been cabled and locked to the bed of his truck was missing, cable had been cut Model number of the Troxler gauge is unknown at this time but usually a Troxler Moisture Density gauge contains 10 milliCuries of cesium-137 and 40 milliCuries of Am-241/Be. The gauge serial number is 22430, cesium-137 source serial number is 75-4160 and the americium-241 source serial number is 47-18251. The gauge was in its locked position and locked inside its case at the time it was stolen. The employee's truck was parked in front of a private residence at the time of the incident. West Palm Beach police were notified by the licensee of the stolen Troxler Moisture Density gauge and the report case number is 0S-9770.
State of Florida Bureau of Radiation Control received the following information from the Radiation Safety Officer for Qore Inc., located in West Palm Beach, FL.
On 04/23/05 at 2300 EDT a Qore Inc. employee discovered that the Troxler Moisture Density gauge that had been cabled and locked to the bed of his truck was missing, cable had been cut Model number of the Troxler gauge is unknown at this time but usually a Troxler Moisture Density gauge contains 10 milliCuries of cesium-137 and 40 milliCuries of Am-241/Be. The gauge serial number is 22430, cesium-137 source serial number is 75-4160 and the americium-241 source serial number is 47-18251. The gauge was in its locked position and locked inside its case at the time it was stolen. The employee's truck was parked in front of a private residence at the time of the incident. West Palm Beach police were notified by the licensee of the stolen Troxler Moisture Density gauge and the report case number is 0S-9770.