Event Notification Report for February 07, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/06/2001 - 02/07/2001
General Information or Other
Event Number: 37730
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: SYNCOR
Region: 4
City: AINSWORTH State: NE
County:
License #: NE-02-37-01
Agreement: Y
Docket:
NRC Notified By: BRYAN MILLER
HQ OPS Officer: DOUG WEAVER
Licensee: SYNCOR
Region: 4
City: AINSWORTH State: NE
County:
License #: NE-02-37-01
Agreement: Y
Docket:
NRC Notified By: BRYAN MILLER
HQ OPS Officer: DOUG WEAVER
Notification Date: 02/09/2001
Notification Time: 09:30 [ET]
Event Date: 02/07/2001
Event Time: 09:00 [CST]
Last Update Date: 02/09/2001
Notification Time: 09:30 [ET]
Event Date: 02/07/2001
Event Time: 09:00 [CST]
Last Update Date: 02/09/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
KEN BROCKMAN (R4)
PHILIP TING (NMSS)
KEN BROCKMAN (R4)
PHILIP TING (NMSS)
AGREEMENT STATE REPORT FROM NEBRASKA
Received report from State of Nebraska in chronological or time line format. Contents of report is summarized below:
Silverhawk Aviation Aircraft carrying 3 boxes of radiopharmaceuticals crashed approximately 1 mile away from the Ainsworth Airport located in Nebraska. The contents of the RAM packages were 18 unit doses of Technetium-99m totaling 23.4 gigabecquerels. State Highway Patrol has verified that 2 of the 3 RAM packages were unopened and that the third package was breached. One package read 1 mrem/hr on contact (normal), the other unopened package read 100 mrem/hr at 1 meter, and that the third package was broken open in the plane and no unit doses were left in the package. Contamination on scene. Bryan Enterprises Mobile Nuclear Medicine Van was available to survey the area. Nebraska State Patrol was on scene. Responders at the scene were in full HAZMAT gear and are being monitored
Received report from State of Nebraska in chronological or time line format. Contents of report is summarized below:
Silverhawk Aviation Aircraft carrying 3 boxes of radiopharmaceuticals crashed approximately 1 mile away from the Ainsworth Airport located in Nebraska. The contents of the RAM packages were 18 unit doses of Technetium-99m totaling 23.4 gigabecquerels. State Highway Patrol has verified that 2 of the 3 RAM packages were unopened and that the third package was breached. One package read 1 mrem/hr on contact (normal), the other unopened package read 100 mrem/hr at 1 meter, and that the third package was broken open in the plane and no unit doses were left in the package. Contamination on scene. Bryan Enterprises Mobile Nuclear Medicine Van was available to survey the area. Nebraska State Patrol was on scene. Responders at the scene were in full HAZMAT gear and are being monitored
General Information or Other
Event Number: 37724
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: B-D INCORPORATED
Region: 2
City: SUMTER State: SC
County:
License #: 315
Agreement: Y
Docket:
NRC Notified By: DAVID KING
HQ OPS Officer: JOHN MacKINNON
Licensee: B-D INCORPORATED
Region: 2
City: SUMTER State: SC
County:
License #: 315
Agreement: Y
Docket:
NRC Notified By: DAVID KING
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/07/2001
Notification Time: 11:14 [ET]
Event Date: 02/07/2001
Event Time: 10:00 [EST]
Last Update Date: 02/07/2001
Notification Time: 11:14 [ET]
Event Date: 02/07/2001
Event Time: 10:00 [EST]
Last Update Date: 02/07/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(a)(1) - PERS OVEREXPOSURE/TEDE >= 25 REM
10 CFR Section:
20.2202(a)(1) - PERS OVEREXPOSURE/TEDE >= 25 REM
Person (Organization):
KEN BARR (R2)
BRIAN SMITH (NMSS)
KEN BARR (R2)
BRIAN SMITH (NMSS)
POSSIBLE OVEREXPOSURE
B-D, Incorporated located in Sumter, South Carolina reported the following event to the State of South Carolina.
B-D, Incorporated has a 2.3 million curie irradiator onsite.
On 02/02/01, B-D, Incorporated received from Landauer the radiation exposure data on their film badges for the months of November through December, 2000. The Radiation Safety Officer for B-D Incorporated did not review the film badge results until 02/05/01. Upon reviewing the data, the RSO discovered that one of the film badges had been exposed beyond its limit (> 1000 Rad). The person whom the film badge had belonged to was administered a blood test today, 02/07/01.
B-D, Incorporated located in Sumter, South Carolina reported the following event to the State of South Carolina.
B-D, Incorporated has a 2.3 million curie irradiator onsite.
On 02/02/01, B-D, Incorporated received from Landauer the radiation exposure data on their film badges for the months of November through December, 2000. The Radiation Safety Officer for B-D Incorporated did not review the film badge results until 02/05/01. Upon reviewing the data, the RSO discovered that one of the film badges had been exposed beyond its limit (> 1000 Rad). The person whom the film badge had belonged to was administered a blood test today, 02/07/01.
Power Reactor
Event Number: 37726
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICK NANCE
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICK NANCE
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/07/2001
Notification Time: 23:15 [ET]
Event Date: 02/07/2001
Event Time: 18:29 [CST]
Last Update Date: 02/07/2001
Notification Time: 23:15 [ET]
Event Date: 02/07/2001
Event Time: 18:29 [CST]
Last Update Date: 02/07/2001
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):
GARY SANBORN (R4)
GARY SANBORN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 10 | Power Operation | 0 | Hot Standby |
UNIT 2 MANUAL REACTOR TRIP FOLLOWING THE LOSS OF THE "A" REACTOR COOLANT PUMP DURING ELECTRICAL BUS REALIGNMENT
"SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNIT 2, MAKES THE FOLLOWING REPORT PER 10 CFR 50.72(b)(2)(iv)(B).
"AT 1829 ON 2/7/01, OPERATORS MANUALLY TRIPPED THE REACTOR FOLLOWING LOSS OF POWER TO A REACTOR COOLANT PUMP DURING ELECTRICAL BUS REALIGNMENT. PLANT DESIGN REQUIRES FOUR REACTOR COOLANT PUMPS RUNNING WHEN THE REACTOR IS CRITICAL. THERE IS NO AUTOMATIC REACTOR TRIP FOR A LOSS OF A SINGLE REACTOR COOLANT PUMP BELOW 40% REACTOR POWER.
"WE ALSO MAKE THE FOLLOWING REPORT PER 10 CFR 50.72(b)(3)(iv)(A).
"DURING ELECTRICAL BUS REALIGNMENT, POWER WAS LOST TO TRAIN 'A' 4.16KV ENGINEERED SAFETY FEATURE BUS. DIESEL GENERATOR 21 AUTOMATICALLY STARTED AND BEGAN SUPPLYING POWER TO THE BUS. THE LOSS OF OFFSITE POWER SIGNAL RESULTED IN THE ACTUATION OF THE FOLLOWING TRAIN 'A' EQUIPMENT: ESSENTIAL COOLING WATER, COMPONENT COOLING WATER, AUXILIARY FEEDWATER, ESSENTIAL CHILLED WATER, CONTROL ROOM HVAC AND FUEL HANDLING BUILDING HVAC.
"ESSENTIAL CHILLER 22A STARTED ON THE LOSS OF POWER SIGNAL BUT WAS SUBSEQUENTLY DECLARED INOPERABLE DUE TO HIGH OIL TEMPERATURE."
OPERATORS WERE ATTEMPTING TO TRANSFER POWER ON 13.8KV BUS "2F" WHEN THE SUPPLY BREAKER OPENED DUE TO OPERATOR ERROR. ALL CONTROL RODS INSERTED FOLLOWING THE TRIP. OFFSITE POWER HAS BEEN RESTORED TO THE "2F" BUS AND THE DIESEL GENERATOR RETURNED TO STANDBY. AN EVENT RESPONSE TEAM IS EVALUATING THE TRIP. THE LICENSEE ANTICIPATES RESTORING THE "A" RCP IN APPROXIMATELY TWO HOURS.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.
"SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNIT 2, MAKES THE FOLLOWING REPORT PER 10 CFR 50.72(b)(2)(iv)(B).
"AT 1829 ON 2/7/01, OPERATORS MANUALLY TRIPPED THE REACTOR FOLLOWING LOSS OF POWER TO A REACTOR COOLANT PUMP DURING ELECTRICAL BUS REALIGNMENT. PLANT DESIGN REQUIRES FOUR REACTOR COOLANT PUMPS RUNNING WHEN THE REACTOR IS CRITICAL. THERE IS NO AUTOMATIC REACTOR TRIP FOR A LOSS OF A SINGLE REACTOR COOLANT PUMP BELOW 40% REACTOR POWER.
"WE ALSO MAKE THE FOLLOWING REPORT PER 10 CFR 50.72(b)(3)(iv)(A).
"DURING ELECTRICAL BUS REALIGNMENT, POWER WAS LOST TO TRAIN 'A' 4.16KV ENGINEERED SAFETY FEATURE BUS. DIESEL GENERATOR 21 AUTOMATICALLY STARTED AND BEGAN SUPPLYING POWER TO THE BUS. THE LOSS OF OFFSITE POWER SIGNAL RESULTED IN THE ACTUATION OF THE FOLLOWING TRAIN 'A' EQUIPMENT: ESSENTIAL COOLING WATER, COMPONENT COOLING WATER, AUXILIARY FEEDWATER, ESSENTIAL CHILLED WATER, CONTROL ROOM HVAC AND FUEL HANDLING BUILDING HVAC.
"ESSENTIAL CHILLER 22A STARTED ON THE LOSS OF POWER SIGNAL BUT WAS SUBSEQUENTLY DECLARED INOPERABLE DUE TO HIGH OIL TEMPERATURE."
OPERATORS WERE ATTEMPTING TO TRANSFER POWER ON 13.8KV BUS "2F" WHEN THE SUPPLY BREAKER OPENED DUE TO OPERATOR ERROR. ALL CONTROL RODS INSERTED FOLLOWING THE TRIP. OFFSITE POWER HAS BEEN RESTORED TO THE "2F" BUS AND THE DIESEL GENERATOR RETURNED TO STANDBY. AN EVENT RESPONSE TEAM IS EVALUATING THE TRIP. THE LICENSEE ANTICIPATES RESTORING THE "A" RCP IN APPROXIMATELY TWO HOURS.
THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.