Event Notification Report for September 23, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/22/2003 - 09/23/2003
EVENT NUMBERS
40192401934019440195
Power Reactor
Event Number: 40192
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: RICH LAURA
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: RICH LAURA
Notification Date: 09/23/2003
Notification Time: 11:15 [ET]
Event Date: 09/23/2003
Event Time: 04:00 [EDT]
Last Update Date: 09/23/2003
Notification Time: 11:15 [ET]
Event Date: 09/23/2003
Event Time: 04:00 [EDT]
Last Update Date: 09/23/2003
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):
ANNE BOLAND (R2)
ANNE BOLAND (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 |
UNANALYZED CONDITION DUE TO POTENTIAL RCS LEAKAGE AT OCONEE 1
"During a scheduled bare metal visual inspection of the Unit 1 reactor vessel head prior to RV head retirement, evidence of possible through wall leakage was observed on two control rod drive mechanism (CRDM) and one thermocouple (T/C) penetrations (nozzles 6 and 16 and T/C nozzle 7). Of these locations, only the T/C had been previously repaired (plugged) in December 2000.
"Initial Safety Significance: Any RCS leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process. Total measured RCS leakage prior to unit shutdown was varying between 0.15 gallons per minute and .24 gallons per minute.
"Corrective Action: The reactor vessel head is scheduled for replacement during the present refueling outage. Therefore, there are no plans at this time to perform additional inspections or repairs on the current head."
The NRC Resident Inspector was notified.
"During a scheduled bare metal visual inspection of the Unit 1 reactor vessel head prior to RV head retirement, evidence of possible through wall leakage was observed on two control rod drive mechanism (CRDM) and one thermocouple (T/C) penetrations (nozzles 6 and 16 and T/C nozzle 7). Of these locations, only the T/C had been previously repaired (plugged) in December 2000.
"Initial Safety Significance: Any RCS leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process. Total measured RCS leakage prior to unit shutdown was varying between 0.15 gallons per minute and .24 gallons per minute.
"Corrective Action: The reactor vessel head is scheduled for replacement during the present refueling outage. Therefore, there are no plans at this time to perform additional inspections or repairs on the current head."
The NRC Resident Inspector was notified.
General Information or Other
Event Number: 40193
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: ARVISO ENGINEERING INC
Region: 4
City: YUMA State: AZ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: RICH LAURA
Licensee: ARVISO ENGINEERING INC
Region: 4
City: YUMA State: AZ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: RICH LAURA
Notification Date: 09/23/2003
Notification Time: 13:00 [ET]
Event Date: 09/23/2003
Event Time: 10:00 [MST]
Last Update Date: 09/23/2003
Notification Time: 13:00 [ET]
Event Date: 09/23/2003
Event Time: 10:00 [MST]
Last Update Date: 09/23/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GREG PICK (R4)
JOHN HICKEY (NMSS)
GREG PICK (R4)
JOHN HICKEY (NMSS)
ARIZONA AGREEMENT STATE REPORT FOR DAMAGED GAUGE
"On 23 September 2003, the licensee notified the Agency that a Humboldt Scientific moisture/density gauge, serial number 1136, had been run over by a roller at a construction site in the vicinity of interstate 8 and Avenue 3E in Yuma. The source was in the backscatter position at the time; however, the licensee was able to retract the source into its shielded position. A leak test is being performed. The Agency will continue to investigate. The gauge contains approximately 10 millicuries of cesium 137 and 40 millicuries of americium-beryllium. The NRC and Governor's office are being notified of this event.
"On 23 September 2003, the licensee notified the Agency that a Humboldt Scientific moisture/density gauge, serial number 1136, had been run over by a roller at a construction site in the vicinity of interstate 8 and Avenue 3E in Yuma. The source was in the backscatter position at the time; however, the licensee was able to retract the source into its shielded position. A leak test is being performed. The Agency will continue to investigate. The gauge contains approximately 10 millicuries of cesium 137 and 40 millicuries of americium-beryllium. The NRC and Governor's office are being notified of this event.
Power Reactor
Event Number: 40194
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: RANDY CADE
HQ OPS Officer: ERIC THOMAS
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: RANDY CADE
HQ OPS Officer: ERIC THOMAS
Notification Date: 09/23/2003
Notification Time: 15:04 [ET]
Event Date: 09/23/2003
Event Time: 13:20 [CDT]
Last Update Date: 09/24/2003
Notification Time: 15:04 [ET]
Event Date: 09/23/2003
Event Time: 13:20 [CDT]
Last Update Date: 09/24/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GREG PICK (R4)
TERRY REIS (NRR)
RICHARD WESSMAN (IRO)
GENE CANUPP (FEMA)
ODELL BARTLETT (DOE)
GREG PICK (R4)
TERRY REIS (NRR)
RICHARD WESSMAN (IRO)
GENE CANUPP (FEMA)
ODELL BARTLETT (DOE)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
UNUSUAL EVENT
"While in Mode 5, refueling Shutdown with Core offload in progress a fuel assembly in the Spent Fuel Pool became ungrappled. The assembly is currently sitting on the top of the Spent Fuel pool racks resting against the Pool wall at approximately 15 degrees. There is no damage to the Fuel Assembly, evident by no change in area radiation dose rates. EAL 1.14, Plant Conditions Warrant Increased Awareness By Plant Staff or Government Authorities. An investigation has begun to determine the cause of the event and a team is being assembled to plan the fuel bundle recovery."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 9/23/03 AT 1857 EDT FROM RANDY CABE TO GERRY WAIG * * *
The licensee remains in a NOUE (Notice of Unusual Event) due to the ungrappled spent fuel assembly. The position of the spent fuel assembly remains the same as previously reported. No damage to the fuel assembly nor the spent fuel rack has been detected. No abnormal radiation readings have been observed. As a precaution, the licensee has suspended all fuel movement operations and evacuated the auxiliary and containment buildings. The licensee plans to stabilize the fuel assembly, attach a lifting tool, and place it into a permanent storage position in the spent fuel pool.
Notified R4DO (Greg Pick)
* * * UPDATE ON 09/24/03 @ 1414 BY CADE TO GOULD * * *
At 12:42 CDT the fabricated stabilization device installation was completed and it is currently secured to two walls of the spent fuel pool. The plant will remain in a NOUE until the fuel assembly is lowered into a safe location in the spent fuel pool. A tool has been fabricated to grapple the fuel assembly and it will be moved with the Spent Fuel Pool Refueling Machine. The tool is currently being tested and weighed. All unnecessary personnel were moved from the Protected Area to the Administration and Training Buildings during the placement of the stabilization device.
The NRC Resident Inspector was notified.
Reg 4 RDO (Greg Pick) was notified
* * * UPDATE ON 09/24/03 @ 1800 EDT BY RANDY CADE TO GERRY WAIG * * *
The licensee reported that the ungrappled spent fuel assembly was placed in a permanent storage position in the spent fuel pool at 1654 CDT. As a result of this action, the licensee terminated the Notice of Unusual Event (NOUE) condition at this time. Normal access to the facility protected area and radiation control area has been restored. Fuel movement operations remain suspended and a root cause investigation of this event is being conducted.
The licensee notified the NRC Resident Inspector.
NRC R4DO (Greg Pick), DIRO (Richard Wessman), NRR EO (Gene Imbro), FEMA (Ken Sweetser), DOE (Joe Stanbaugh), DHS (Sam Neglia) were notified by the Headquarters Operations Officer.
"While in Mode 5, refueling Shutdown with Core offload in progress a fuel assembly in the Spent Fuel Pool became ungrappled. The assembly is currently sitting on the top of the Spent Fuel pool racks resting against the Pool wall at approximately 15 degrees. There is no damage to the Fuel Assembly, evident by no change in area radiation dose rates. EAL 1.14, Plant Conditions Warrant Increased Awareness By Plant Staff or Government Authorities. An investigation has begun to determine the cause of the event and a team is being assembled to plan the fuel bundle recovery."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 9/23/03 AT 1857 EDT FROM RANDY CABE TO GERRY WAIG * * *
The licensee remains in a NOUE (Notice of Unusual Event) due to the ungrappled spent fuel assembly. The position of the spent fuel assembly remains the same as previously reported. No damage to the fuel assembly nor the spent fuel rack has been detected. No abnormal radiation readings have been observed. As a precaution, the licensee has suspended all fuel movement operations and evacuated the auxiliary and containment buildings. The licensee plans to stabilize the fuel assembly, attach a lifting tool, and place it into a permanent storage position in the spent fuel pool.
Notified R4DO (Greg Pick)
* * * UPDATE ON 09/24/03 @ 1414 BY CADE TO GOULD * * *
At 12:42 CDT the fabricated stabilization device installation was completed and it is currently secured to two walls of the spent fuel pool. The plant will remain in a NOUE until the fuel assembly is lowered into a safe location in the spent fuel pool. A tool has been fabricated to grapple the fuel assembly and it will be moved with the Spent Fuel Pool Refueling Machine. The tool is currently being tested and weighed. All unnecessary personnel were moved from the Protected Area to the Administration and Training Buildings during the placement of the stabilization device.
The NRC Resident Inspector was notified.
Reg 4 RDO (Greg Pick) was notified
* * * UPDATE ON 09/24/03 @ 1800 EDT BY RANDY CADE TO GERRY WAIG * * *
The licensee reported that the ungrappled spent fuel assembly was placed in a permanent storage position in the spent fuel pool at 1654 CDT. As a result of this action, the licensee terminated the Notice of Unusual Event (NOUE) condition at this time. Normal access to the facility protected area and radiation control area has been restored. Fuel movement operations remain suspended and a root cause investigation of this event is being conducted.
The licensee notified the NRC Resident Inspector.
NRC R4DO (Greg Pick), DIRO (Richard Wessman), NRR EO (Gene Imbro), FEMA (Ken Sweetser), DOE (Joe Stanbaugh), DHS (Sam Neglia) were notified by the Headquarters Operations Officer.
Power Reactor
Event Number: 40195
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: AL CLARK
HQ OPS Officer: GERRY WAIG
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: AL CLARK
HQ OPS Officer: GERRY WAIG
Notification Date: 09/23/2003
Notification Time: 15:15 [ET]
Event Date: 09/23/2003
Event Time: 12:27 [CDT]
Last Update Date: 09/23/2003
Notification Time: 15:15 [ET]
Event Date: 09/23/2003
Event Time: 12:27 [CDT]
Last Update Date: 09/23/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
GREG PICK (R4)
GREG PICK (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 |
SAFEGUARD SYSTEM VULNERABILITY DISCOVERED BY FT CALHOUN
The licensee discovered a vulnerability in a safeguard system that could have allowed access to a controlled area for which compensatory measures had not been employed. The licensee has notified the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details.
The licensee discovered a vulnerability in a safeguard system that could have allowed access to a controlled area for which compensatory measures had not been employed. The licensee has notified the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details.