Event Notification Report for May 14, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/13/2003 - 05/14/2003
EVENT NUMBERS
398503985139846398473984839844
General Information or Other
Event Number: 39850
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: BLAZER INDUSTRIAL RADIOGRAPHY
Region: 4
City: PASADENA State: TX
County:
License #: LO4619
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS
HQ OPS Officer: ERIC THOMAS
Licensee: BLAZER INDUSTRIAL RADIOGRAPHY
Region: 4
City: PASADENA State: TX
County:
License #: LO4619
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS
HQ OPS Officer: ERIC THOMAS
Notification Date: 05/15/2003
Notification Time: 12:18 [ET]
Event Date: 05/14/2003
Event Time: 18:48 [CDT]
Last Update Date: 05/16/2003
Notification Time: 12:18 [ET]
Event Date: 05/14/2003
Event Time: 18:48 [CDT]
Last Update Date: 05/16/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WILLIAM JOHNSON (R4)
TOM ESSIG (NMSS)
WILLIAM JOHNSON (R4)
TOM ESSIG (NMSS)
AGREEMENT STATE REPORT
The licensee reported a potential overexposure to a radiographer who was x-raying some pipes at a worksite. After completing a section of piping, the radiographer should have cranked his source back in, but was interrupted by another technician and left his work area. When he returned, the radiographer changed out his film, and moved the guide tube to another section of piping to begin more x-rays. At this point, he realized that his survey meter had pegged high, and remembered that he had not cranked the source back in prior to moving it. He proceeded to immediately crank the source back to its fully shielded position. The exact time and distance from the source for the radiographer's exposure is unknown, and the licensee is attempting to re-create the scenario.
The source was 26 Curies of Iridium 192, model number INC-32. The serial number is unknown at this time. A preliminary investigation by the licensee estimates the radiographer's exposure to 800-900 millirem whole body. There is currently no exposure estimate for his hands/extremities.
The radiographer's badge was sent off for processing. Results will be reported on 5/16/03 to the NRC. The Texas Department of Health is sending an additional inspector to the site to investigate.
* * * UPDATE ON 5/16/03 @ 1120 BY WATKINS TO GOULD * * *
Blazer Industrial Radiography brought in a consultant to perform preliminary dose calculations for the whole body and the right hand of the radiographer. The results were 1.3R for the whole body and 37.1R for the right hand, neither of which exceeds the annual regulatory limit.
The licensee reported a potential overexposure to a radiographer who was x-raying some pipes at a worksite. After completing a section of piping, the radiographer should have cranked his source back in, but was interrupted by another technician and left his work area. When he returned, the radiographer changed out his film, and moved the guide tube to another section of piping to begin more x-rays. At this point, he realized that his survey meter had pegged high, and remembered that he had not cranked the source back in prior to moving it. He proceeded to immediately crank the source back to its fully shielded position. The exact time and distance from the source for the radiographer's exposure is unknown, and the licensee is attempting to re-create the scenario.
The source was 26 Curies of Iridium 192, model number INC-32. The serial number is unknown at this time. A preliminary investigation by the licensee estimates the radiographer's exposure to 800-900 millirem whole body. There is currently no exposure estimate for his hands/extremities.
The radiographer's badge was sent off for processing. Results will be reported on 5/16/03 to the NRC. The Texas Department of Health is sending an additional inspector to the site to investigate.
* * * UPDATE ON 5/16/03 @ 1120 BY WATKINS TO GOULD * * *
Blazer Industrial Radiography brought in a consultant to perform preliminary dose calculations for the whole body and the right hand of the radiographer. The results were 1.3R for the whole body and 37.1R for the right hand, neither of which exceeds the annual regulatory limit.
General Information or Other
Event Number: 39851
Rep Org: NATIONAL RESPONSE CENTER
Licensee: NORTH ANNA
Region: 4
City: KINGMAN State: KS
County: SUMNER
License #:
Agreement: Y
Docket:
NRC Notified By: LYNN WARRICK
HQ OPS Officer: ERIC THOMAS
Licensee: NORTH ANNA
Region: 4
City: KINGMAN State: KS
County: SUMNER
License #:
Agreement: Y
Docket:
NRC Notified By: LYNN WARRICK
HQ OPS Officer: ERIC THOMAS
Notification Date: 05/15/2003
Notification Time: 13:45 [ET]
Event Date: 05/14/2003
Event Time: 18:00 [CDT]
Last Update Date: 05/16/2003
Notification Time: 13:45 [ET]
Event Date: 05/14/2003
Event Time: 18:00 [CDT]
Last Update Date: 05/16/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WILLIAM JOHNSON (R4)
DOUG BROADDUS (NMSS)
TIM MCGINTY (DIRO)
JANICE KROON (EPA)
DAVID WHITFILL (STAT)
WILLIAM JOHNSON (R4)
DOUG BROADDUS (NMSS)
TIM MCGINTY (DIRO)
JANICE KROON (EPA)
DAVID WHITFILL (STAT)
TRANSPORTATION INCIDENT
The National Response Center sent a fax to the Operations Center regarding the following transportation incident:
A tractor trailer carrying the reactor vessel head from North Anna power plant to EnviroCare in Clive, UT was sideswiped by a pickup truck being driven by a drunk driver near Kingman, KS on Route 42. The pickup truck passed the tractor trailer at approximately 80 mph, and proceeded down the road, where it was involved in a traffic accident. The incidental impact between the pickup and the tractor trailer caused a minor tear in the protective tarp and plastic container containing the vessel head, along with depositing some paint on the head itself. There was no apparent structural damage to the vessel head, and no apparent radioactive release into the atmosphere.
The truck driver stopped his vehicle in Greensburg, Kansas to assess the condition of the vessel head. The shipper is sending a representative to inspect the packing material integrity. The state of Kansas will also be sending a representative out to the scene to assist.
*****UPDATE ON 5/16/03 AT 13:50 EST FROM CONNELLY TO LAURA*****
Three independent radiological surveys conducted by the State of Kansas and North Anna determined there was no spread of contamination and only minor damage occurred to the shipping packaging for the vessel head. The minor damage was repaired and the truck was released.
Notified R4DO (W. Johnson), DIRO (McGinty) and NMSS (Essig).
The National Response Center sent a fax to the Operations Center regarding the following transportation incident:
A tractor trailer carrying the reactor vessel head from North Anna power plant to EnviroCare in Clive, UT was sideswiped by a pickup truck being driven by a drunk driver near Kingman, KS on Route 42. The pickup truck passed the tractor trailer at approximately 80 mph, and proceeded down the road, where it was involved in a traffic accident. The incidental impact between the pickup and the tractor trailer caused a minor tear in the protective tarp and plastic container containing the vessel head, along with depositing some paint on the head itself. There was no apparent structural damage to the vessel head, and no apparent radioactive release into the atmosphere.
The truck driver stopped his vehicle in Greensburg, Kansas to assess the condition of the vessel head. The shipper is sending a representative to inspect the packing material integrity. The state of Kansas will also be sending a representative out to the scene to assist.
*****UPDATE ON 5/16/03 AT 13:50 EST FROM CONNELLY TO LAURA*****
Three independent radiological surveys conducted by the State of Kansas and North Anna determined there was no spread of contamination and only minor damage occurred to the shipping packaging for the vessel head. The minor damage was repaired and the truck was released.
Notified R4DO (W. Johnson), DIRO (McGinty) and NMSS (Essig).
Power Reactor
Event Number: 39846
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN BAKER
HQ OPS Officer: ERIC THOMAS
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN BAKER
HQ OPS Officer: ERIC THOMAS
Notification Date: 05/14/2003
Notification Time: 15:46 [ET]
Event Date: 05/14/2003
Event Time: 00:00 [EDT]
Last Update Date: 05/14/2003
Notification Time: 15:46 [ET]
Event Date: 05/14/2003
Event Time: 00:00 [EDT]
Last Update Date: 05/14/2003
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):
KENNETH JENISON (R1)
MICHAEL CASE (NRR)
KENNETH JENISON (R1)
MICHAEL CASE (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 99 | Power Operation | 99 | Power Operation |
LOSS OF SIRENS
"Indian Point Energy Center (IPEC) Units 2 and 3 are making an eight-hour non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii).
"On May 14, 2003 at 1035 [EDT], Rockland County notified Emergency Planning (EP) that while attempting to perform a 'Cancel Test' of the counties sirens a communication failure was recorded on all Rockland County sirens. EP performed a review of the status of the system and determined that a communication loss was experienced that prevented transmittal of instructions to all sirens in the four counties. Communication between the Indian Point Energy Center Emergency Operations Facility (EOF) and the 154 sirens was re-established as of 1251 [EDT]. Personnel will continuously man the EOF to initiate sirens if needed, until control can be re-established from the affected counties. Route alerting was available during the loss of sirens.
"The NRC resident inspector, County and State were notified of this event."
"Indian Point Energy Center (IPEC) Units 2 and 3 are making an eight-hour non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii).
"On May 14, 2003 at 1035 [EDT], Rockland County notified Emergency Planning (EP) that while attempting to perform a 'Cancel Test' of the counties sirens a communication failure was recorded on all Rockland County sirens. EP performed a review of the status of the system and determined that a communication loss was experienced that prevented transmittal of instructions to all sirens in the four counties. Communication between the Indian Point Energy Center Emergency Operations Facility (EOF) and the 154 sirens was re-established as of 1251 [EDT]. Personnel will continuously man the EOF to initiate sirens if needed, until control can be re-established from the affected counties. Route alerting was available during the loss of sirens.
"The NRC resident inspector, County and State were notified of this event."
Power Reactor
Event Number: 39847
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PETE GARDNER
HQ OPS Officer: ERIC THOMAS
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PETE GARDNER
HQ OPS Officer: ERIC THOMAS
Notification Date: 05/14/2003
Notification Time: 17:22 [ET]
Event Date: 05/14/2003
Event Time: 09:45 [EDT]
Last Update Date: 05/14/2003
Notification Time: 17:22 [ET]
Event Date: 05/14/2003
Event Time: 09:45 [EDT]
Last Update Date: 05/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
KENNETH JENISON (R1)
KENNETH JENISON (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY
A licensed employee was determined to be under the influence of alcohol during a random drug test. The employee's access to the plant has been removed. Contact the HOO for additional details.
The licensee informed the NRC Resident Inspector.
A licensed employee was determined to be under the influence of alcohol during a random drug test. The employee's access to the plant has been removed. Contact the HOO for additional details.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 39848
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: RICK LLEWELLYN
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: RICK LLEWELLYN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/14/2003
Notification Time: 18:44 [ET]
Event Date: 05/14/2003
Event Time: 09:45 [EDT]
Last Update Date: 05/14/2003
Notification Time: 18:44 [ET]
Event Date: 05/14/2003
Event Time: 09:45 [EDT]
Last Update Date: 05/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
KENNETH JENISON (R1)
KENNETH JENISON (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY
A licensed employee was determined to be under the influence of alcohol during a random drug test given at the Limerick Generating Station. Employee was dual-licensed at both Limerick and Peach Bottom. (Refer to Event Notification #39847). The employee's access to the plant has been removed. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified by the licensee.
A licensed employee was determined to be under the influence of alcohol during a random drug test given at the Limerick Generating Station. Employee was dual-licensed at both Limerick and Peach Bottom. (Refer to Event Notification #39847). The employee's access to the plant has been removed. Contact the Headquarters Operations Officer for additional details.
The NRC Resident Inspector has been notified by the licensee.
Power Reactor
Event Number: 39844
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JAMES VASH
HQ OPS Officer: RICH LAURA
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JAMES VASH
HQ OPS Officer: RICH LAURA
Notification Date: 05/14/2003
Notification Time: 11:43 [ET]
Event Date: 05/14/2003
Event Time: 04:10 [EDT]
Last Update Date: 05/14/2003
Notification Time: 11:43 [ET]
Event Date: 05/14/2003
Event Time: 04:10 [EDT]
Last Update Date: 05/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
KENNETH JENISON (R1)
KENNETH JENISON (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
APPENDIX "R" ISSUE AT PEACH BOTTOM 3
"On May 14, 2003, at approximately 0410, the shift supervisor determined that the Alternate Shutdown Panel on Unit 3 was not operable following discovery of a de-energized power supply. The panel provides the capability to maintain a safe shutdown path for a fire in the cable spreading room, main control room or main control room fan room. Therefore, operators would have been prevented from implementing required actions for a fire in those areas. The apparent cause of the loss of power was a broken wire, which was discovered during routine testing of the panel.
"Power was restored to the Alternate Shutdown Panel at approximately 1030 on May 14, 2003 and further investigation is in progress to determine the cause of the broken wire and full extent and effect of the de-energization of the panel."
The NRC Resident Inspector was notified.
"On May 14, 2003, at approximately 0410, the shift supervisor determined that the Alternate Shutdown Panel on Unit 3 was not operable following discovery of a de-energized power supply. The panel provides the capability to maintain a safe shutdown path for a fire in the cable spreading room, main control room or main control room fan room. Therefore, operators would have been prevented from implementing required actions for a fire in those areas. The apparent cause of the loss of power was a broken wire, which was discovered during routine testing of the panel.
"Power was restored to the Alternate Shutdown Panel at approximately 1030 on May 14, 2003 and further investigation is in progress to determine the cause of the broken wire and full extent and effect of the de-energization of the panel."
The NRC Resident Inspector was notified.