Event Notification Report for December 21, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/20/2011 - 12/21/2011
EVENT NUMBERS
4754047541475424754347544475454756047571
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 47540
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: LANDON BRITTAIN
HQ OPS Officer: JOE O'HARA
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: LANDON BRITTAIN
HQ OPS Officer: JOE O'HARA
Notification Date: 12/21/2011
Notification Time: 06:14 [ET]
Event Date: 12/21/2011
Event Time: 00:46 [CST]
Last Update Date: 02/06/2012
Notification Time: 06:14 [ET]
Event Date: 12/21/2011
Event Time: 00:46 [CST]
Last Update Date: 02/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
PATTY PELKE (R3DO)
PATTY PELKE (R3DO)
| 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 |
BOTH UNIT TWO SECONDARY CONTAINMENT DOORS WERE INADVERTENTLY LEFT OPEN
"On 12/21/11 at 0046 Secondary Containment integrity was lost when both U2 Reactor Building interlock doors were open simultaneously. Interlock door electrical checks were in progress. TS LCORA 3.6.4.1.Condition A was entered. Reactor Building differential pressure remained within Tech Spec limits. The doors were both open for approximately 9 seconds.
"The cause of the event is being investigated."
The NRC Resident Inspector has been notified. The State of Illinois Inspector will be notified.
* * * RETRACTION FROM KATHARINE NETEMEYER TO CHARLES TEAL ON 2/6/12 AT 1243 EST * * *
"On 12/21/2011, EN 47540 was made describing a condition where secondary containment was declared inoperable due to not meeting the surveillance requirement for having one access door closed. This was reported as a loss of safety function for the secondary containment. This condition occurred during a planned maintenance activity.
"During a maintenance activity both doors unexpectedly opened. As a part of the maintenance, the inner door was opened by maintenance personnel using the normal control pushbutton. Upon personnel observing the outer door opening, the inner door button was released and the functional door automatically closed. Although both doors were briefly open, the negative pressure required to ensure secondary containment integrity was maintained at all times. Based on the door immediately closing and negative pressure being maintained, this is not considered a loss of safety function. Therefore this EN is being retracted."
The NRC Resident Inspector has been notified. Notified R3DO (Giessner).
"On 12/21/11 at 0046 Secondary Containment integrity was lost when both U2 Reactor Building interlock doors were open simultaneously. Interlock door electrical checks were in progress. TS LCORA 3.6.4.1.Condition A was entered. Reactor Building differential pressure remained within Tech Spec limits. The doors were both open for approximately 9 seconds.
"The cause of the event is being investigated."
The NRC Resident Inspector has been notified. The State of Illinois Inspector will be notified.
* * * RETRACTION FROM KATHARINE NETEMEYER TO CHARLES TEAL ON 2/6/12 AT 1243 EST * * *
"On 12/21/2011, EN 47540 was made describing a condition where secondary containment was declared inoperable due to not meeting the surveillance requirement for having one access door closed. This was reported as a loss of safety function for the secondary containment. This condition occurred during a planned maintenance activity.
"During a maintenance activity both doors unexpectedly opened. As a part of the maintenance, the inner door was opened by maintenance personnel using the normal control pushbutton. Upon personnel observing the outer door opening, the inner door button was released and the functional door automatically closed. Although both doors were briefly open, the negative pressure required to ensure secondary containment integrity was maintained at all times. Based on the door immediately closing and negative pressure being maintained, this is not considered a loss of safety function. Therefore this EN is being retracted."
The NRC Resident Inspector has been notified. Notified R3DO (Giessner).
Power Reactor
Event Number: 47541
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: JOHN KNOKE
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/21/2011
Notification Time: 11:52 [ET]
Event Date: 12/21/2011
Event Time: 09:30 [CST]
Last Update Date: 08/09/2012
Notification Time: 11:52 [ET]
Event Date: 12/21/2011
Event Time: 09:30 [CST]
Last Update Date: 08/09/2012
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):
BOB HAGAR (R4DO)
BOB HAGAR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION FOR DETECTABLE LEVELS OF TRITIUM IN GROUNDWATER WELL
"On Tuesday, December 20, 2011, technicians discovered detectable levels of tritium in an onsite groundwater well. The measured concentration of the isotope was approximately 48,000 picocuries per liter. This discovery was made during the conduct of the site's ongoing groundwater monitoring program.
"The tritium concentration in the well sample exceeds the EPA established threshold for drinking water of 20,000 picocuries per liter. However, no groundwater wells on the River Bend site are used for drinking water. There has been no tritium identified in any wells downstream of, or surrounding, the affected well.
"This test result does not indicate any threat to public health or safety, since the affected well is only used for groundwater monitoring, and not drinking water. Other onsite wells in the area were tested and will continue to be tested to ensure the tritium is not migrating offsite. The monitoring of the wells in the area immediately surrounding the affected well will be increased to a monthly frequency.
"Voluntary notification of this discovery has been made to local and state governmental agencies, with the initial notification being made at 0930 CST today. This event is being voluntarily reported in accordance with 10CFR50.72(b)(2)(xi) as a condition related to health and safety of the public and onsite personnel for which a news release is planned."
The licensee has notified the NRC Resident Inspector, state and local agencies and will be releasing information to the media.
* * * UPDATE FROM DANNY WILLIAMSON TO JOHN KNOKE AT 1518 EDT ON 08/09/12 * * *
"On August 7, 2012, one of the six new groundwater monitoring wells installed near the monitoring well which yielded the positive results on December 20, 2011, produced a groundwater sample containing 432,733 picocuries per liter of tritium. The investigation of the groundwater tritium activity is still ongoing, and the installation of these wells is part of that effort to determine the source.
"The NRC Resident Inspector has been notified and officials with the Louisiana Department of Environmental Quality will be briefed."
Notified R4DO (Michael Vasquez)
"On Tuesday, December 20, 2011, technicians discovered detectable levels of tritium in an onsite groundwater well. The measured concentration of the isotope was approximately 48,000 picocuries per liter. This discovery was made during the conduct of the site's ongoing groundwater monitoring program.
"The tritium concentration in the well sample exceeds the EPA established threshold for drinking water of 20,000 picocuries per liter. However, no groundwater wells on the River Bend site are used for drinking water. There has been no tritium identified in any wells downstream of, or surrounding, the affected well.
"This test result does not indicate any threat to public health or safety, since the affected well is only used for groundwater monitoring, and not drinking water. Other onsite wells in the area were tested and will continue to be tested to ensure the tritium is not migrating offsite. The monitoring of the wells in the area immediately surrounding the affected well will be increased to a monthly frequency.
"Voluntary notification of this discovery has been made to local and state governmental agencies, with the initial notification being made at 0930 CST today. This event is being voluntarily reported in accordance with 10CFR50.72(b)(2)(xi) as a condition related to health and safety of the public and onsite personnel for which a news release is planned."
The licensee has notified the NRC Resident Inspector, state and local agencies and will be releasing information to the media.
* * * UPDATE FROM DANNY WILLIAMSON TO JOHN KNOKE AT 1518 EDT ON 08/09/12 * * *
"On August 7, 2012, one of the six new groundwater monitoring wells installed near the monitoring well which yielded the positive results on December 20, 2011, produced a groundwater sample containing 432,733 picocuries per liter of tritium. The investigation of the groundwater tritium activity is still ongoing, and the installation of these wells is part of that effort to determine the source.
"The NRC Resident Inspector has been notified and officials with the Louisiana Department of Environmental Quality will be briefed."
Notified R4DO (Michael Vasquez)
Power Reactor
Event Number: 47542
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: JOHN KNOKE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/21/2011
Notification Time: 15:38 [ET]
Event Date: 12/21/2011
Event Time: 15:15 [EST]
Last Update Date: 12/21/2011
Notification Time: 15:38 [ET]
Event Date: 12/21/2011
Event Time: 15:15 [EST]
Last Update Date: 12/21/2011
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):
NEIL PERRY (R1DO)
NEIL PERRY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO WATER SAMPLE TESTING POSITIVE FOR LOW LEVEL OF TRITIUM
"On December 20, 2011, Vermont Yankee (VY) was notified by its vendor laboratory that a water sample, taken from the Connecticut River on November 3, 2011, tested positive for a low level of tritium [1120 pCi/L]. This report is being made in accordance with 10 CFR50.72(b)(2)(xi) since VY is notifying government agencies and issuing a press release. The VY Off-Site Dose Calculation Manual contains effluent dose calculations that account for groundwater releases of this type. There is no impact on public health and safety as a result of this event."
The licensee has notified the NRC Resident Inspector and the state of Vermont.
"On December 20, 2011, Vermont Yankee (VY) was notified by its vendor laboratory that a water sample, taken from the Connecticut River on November 3, 2011, tested positive for a low level of tritium [1120 pCi/L]. This report is being made in accordance with 10 CFR50.72(b)(2)(xi) since VY is notifying government agencies and issuing a press release. The VY Off-Site Dose Calculation Manual contains effluent dose calculations that account for groundwater releases of this type. There is no impact on public health and safety as a result of this event."
The licensee has notified the NRC Resident Inspector and the state of Vermont.
Power Reactor
Event Number: 47543
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: PETE SNYDER
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: PETE SNYDER
Notification Date: 12/21/2011
Notification Time: 15:38 [ET]
Event Date: 12/21/2011
Event Time: 12:00 [CST]
Last Update Date: 12/21/2011
Notification Time: 15:38 [ET]
Event Date: 12/21/2011
Event Time: 12:00 [CST]
Last Update Date: 12/21/2011
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):
PATTY PELKE (R3DO)
PATTY PELKE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PLANT COMPUTER CALCULATION INCORRECT FOR BACK-UP METEOROLOGICAL DATA
"During specification review of the computer points for the Monticello Nuclear Generating Plant backup meteorological tower (MET), it was identified by the station that the computer program software for the backup MET had not calculated the correct 15 minute average wind direction in all instances, A review and analysis of the historical data revealed that there were times that this condition existed when the site's primary MET had been out-of-service for maintenance or equipment issues. During those times the backup MET was relied on for determination of wind direction. Analysis determined that during those times the potential existed to incorrectly report affected sectors for Protective Action Recommendations.
"Currently the station's primary MET has been verified to be in service and functioning properly.
"The licensee has notified the NRC Resident Inspector."
"During specification review of the computer points for the Monticello Nuclear Generating Plant backup meteorological tower (MET), it was identified by the station that the computer program software for the backup MET had not calculated the correct 15 minute average wind direction in all instances, A review and analysis of the historical data revealed that there were times that this condition existed when the site's primary MET had been out-of-service for maintenance or equipment issues. During those times the backup MET was relied on for determination of wind direction. Analysis determined that during those times the potential existed to incorrectly report affected sectors for Protective Action Recommendations.
"Currently the station's primary MET has been verified to be in service and functioning properly.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 47544
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DALE SHELTON
HQ OPS Officer: JOHN KNOKE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DALE SHELTON
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/21/2011
Notification Time: 19:56 [ET]
Event Date: 12/21/2011
Event Time: 17:57 [CST]
Last Update Date: 12/21/2011
Notification Time: 19:56 [ET]
Event Date: 12/21/2011
Event Time: 17:57 [CST]
Last Update Date: 12/21/2011
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):
PATTY PELKE (R3DO)
C. PEDERSON (RA)
B. BOGER (ET)
W. GOTT (IRDM)
M. ARNOLD (DHS)
PATTY PELKE (R3DO)
C. PEDERSON (RA)
B. BOGER (ET)
W. GOTT (IRDM)
M. ARNOLD (DHS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 18 | Power Operation | 18 | Power Operation |
UNUSUAL EVENT - HYDROGEN LEAK IN TURBINE BUILDING
"At 1641 CST, during preparations to synchronize the generator, hydrogen pressure began to lower. Personnel were dispatched to identify the source of the leak. At 1752 CST reports from personnel in the turbine building identified high hydrogen levels and the turbine building was evacuated. An Unusual Event [HU7] was declared at 1757 CST and state notification was completed at 1809 CST. Turbine building roof vents were opened to ventilate the turbine building and all elevations were verified to be clear of hydrogen. Access to the turbine building was restored.
"The Unusual Event was terminated at 1838 CST."
The licensee has notified the NRC Resident Inspector.
"At 1641 CST, during preparations to synchronize the generator, hydrogen pressure began to lower. Personnel were dispatched to identify the source of the leak. At 1752 CST reports from personnel in the turbine building identified high hydrogen levels and the turbine building was evacuated. An Unusual Event [HU7] was declared at 1757 CST and state notification was completed at 1809 CST. Turbine building roof vents were opened to ventilate the turbine building and all elevations were verified to be clear of hydrogen. Access to the turbine building was restored.
"The Unusual Event was terminated at 1838 CST."
The licensee has notified the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 47545
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JAMES PRY
HQ OPS Officer: JOHN KNOKE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JAMES PRY
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/21/2011
Notification Time: 21:37 [ET]
Event Date: 12/21/2011
Event Time: 13:59 [EST]
Last Update Date: 02/15/2012
Notification Time: 21:37 [ET]
Event Date: 12/21/2011
Event Time: 13:59 [EST]
Last Update Date: 02/15/2012
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):
PATTY PELKE (R3DO)
PATTY PELKE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
GROUNDWATER LEVEL MAY EXCEED DESIGN ASSUMPTIONS
"On December 21, 2011, at 1359 hours EST, it was determined that the test instruction for the weekly groundwater level readings contained non-conservative acceptance criteria. The test instruction acceptance criteria for groundwater level exceeds the initial assumptions used in the Updated Safety Analysis Report (USAR) Chapter 15 accident analysis for 'Postulated Radioactive Releases due to Liquid Containing Tank Failures.' The issue was identified during the conduct of a prompt functionality assessment evaluating the plant underdrain system performance and to ensure all USAR described functions were being met.
"The test instruction acceptance criteria is less than 575 feet. The calculation supporting the Chapter 15 accident analysis assumes an initial groundwater elevation of 568 feet in order to accumulate a sufficient volume of groundwater to dilute the tank inventory prior to exiting the underdrain system. The accumulation volume results in hold up time allowing for mixing and radioactive decay. With the degraded performance of the underdrain system pumps and high precipitation, the groundwater level had risen above 568 feet but was still less than 575 feet. A preliminary engineering evaluation has determined that significant margin exists in the calculation. A calculation revision is being pursued in parallel with this notification.
"Compensatory actions involving the repair of 1 permanent non-safety pump and installation of temporary pumps were previously initiated and the groundwater levels are decreasing. Restoration of the remaining permanent plant pumps continues.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 2/15/12 AT 1315 EST FROM LLOYD ZERR TO ERIC SIMPSON * * *
"The calculation supporting the USAR Chapter 15 accident analysis was reviewed and subsequently revised. The revised calculation verifies an initial groundwater elevation of 575 feet is consistent with the preliminary assessment that substantial margin existed in the calculation for the underdrain system. Because the condition reported in Event Number 47545 was not an event or condition that results in the nuclear power plant being in an unanalyzed condition that degrades safety, the condition is not reportable, and this notification is retracted. The evaluation for this condition is documented in condition report 2011-07169."
The NRC Resident Inspector and R3DO (Passehl) were notified.
"On December 21, 2011, at 1359 hours EST, it was determined that the test instruction for the weekly groundwater level readings contained non-conservative acceptance criteria. The test instruction acceptance criteria for groundwater level exceeds the initial assumptions used in the Updated Safety Analysis Report (USAR) Chapter 15 accident analysis for 'Postulated Radioactive Releases due to Liquid Containing Tank Failures.' The issue was identified during the conduct of a prompt functionality assessment evaluating the plant underdrain system performance and to ensure all USAR described functions were being met.
"The test instruction acceptance criteria is less than 575 feet. The calculation supporting the Chapter 15 accident analysis assumes an initial groundwater elevation of 568 feet in order to accumulate a sufficient volume of groundwater to dilute the tank inventory prior to exiting the underdrain system. The accumulation volume results in hold up time allowing for mixing and radioactive decay. With the degraded performance of the underdrain system pumps and high precipitation, the groundwater level had risen above 568 feet but was still less than 575 feet. A preliminary engineering evaluation has determined that significant margin exists in the calculation. A calculation revision is being pursued in parallel with this notification.
"Compensatory actions involving the repair of 1 permanent non-safety pump and installation of temporary pumps were previously initiated and the groundwater levels are decreasing. Restoration of the remaining permanent plant pumps continues.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 2/15/12 AT 1315 EST FROM LLOYD ZERR TO ERIC SIMPSON * * *
"The calculation supporting the USAR Chapter 15 accident analysis was reviewed and subsequently revised. The revised calculation verifies an initial groundwater elevation of 575 feet is consistent with the preliminary assessment that substantial margin existed in the calculation for the underdrain system. Because the condition reported in Event Number 47545 was not an event or condition that results in the nuclear power plant being in an unanalyzed condition that degrades safety, the condition is not reportable, and this notification is retracted. The evaluation for this condition is documented in condition report 2011-07169."
The NRC Resident Inspector and R3DO (Passehl) were notified.
Agreement State
Event Number: 47560
Rep Org: NV DIV OF RAD HEALTH
Licensee: CARDINAL HEALTH
Region: 4
City: Las Vegas State: NV
County:
License #: 03-11-0332-01
Agreement: Y
Docket:
NRC Notified By: ADRIAN HOWE
HQ OPS Officer: BILL HUFFMAN
Licensee: CARDINAL HEALTH
Region: 4
City: Las Vegas State: NV
County:
License #: 03-11-0332-01
Agreement: Y
Docket:
NRC Notified By: ADRIAN HOWE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/29/2011
Notification Time: 17:41 [ET]
Event Date: 12/21/2011
Event Time: 00:00 [PST]
Last Update Date: 12/29/2011
Notification Time: 17:41 [ET]
Event Date: 12/21/2011
Event Time: 00:00 [PST]
Last Update Date: 12/29/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
VINCENT GADDY (R4DO)
JACK FOSTER (FSME)
VINCENT GADDY (R4DO)
JACK FOSTER (FSME)
AGREEMENT STATE REPORT - IODINE-125 BRACHYTHERAPY SEED MISSING FROM TRANSPORTATION PACKAGE
The following report was received by telephone from the State of Nevada.
A representative of the State of Nevada Radiation Control Program was notified by a call from Cardinal Health and Summerlin Hospital in Las Vegas NV concerning a missing I-125 brachytherapy seed. Summerlin Hospital on or about 12/21/11 transferred 33 Iodine-125 brachytherapy seeds to Cardinal Health for shipment back to Bard Brachytherapy in Illinois. The 33 Iodine-125 seed shipment was packaged and sent by Cardinal Health to Bard via commercial carrier on or about 12/21/11. Upon receipt of the seeds by Bard, the top of the shipping pig was discovered to not be completely sealed. Some of the seeds were outside the pig but within the shipping package. After all the seeds were inventoried, a total of 32 seeds were received by Bard. At this time, one of the seeds appears to be unaccounted for. The missing I-125 seed had an activity of 0.23 milliCuries at the time of shipment. The half-life of Iodine-125 is approximately 60 days.
Bard has surveyed the local carrier that transported the shipment to its facility. It has also surveyed the regional facility of the shipping carrier. Cardinal Health and Summerlin are still attempting to confirm the original inventory of seeds was 33.
The State of Nevada is continuing its investigation of the missing seed.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following report was received by telephone from the State of Nevada.
A representative of the State of Nevada Radiation Control Program was notified by a call from Cardinal Health and Summerlin Hospital in Las Vegas NV concerning a missing I-125 brachytherapy seed. Summerlin Hospital on or about 12/21/11 transferred 33 Iodine-125 brachytherapy seeds to Cardinal Health for shipment back to Bard Brachytherapy in Illinois. The 33 Iodine-125 seed shipment was packaged and sent by Cardinal Health to Bard via commercial carrier on or about 12/21/11. Upon receipt of the seeds by Bard, the top of the shipping pig was discovered to not be completely sealed. Some of the seeds were outside the pig but within the shipping package. After all the seeds were inventoried, a total of 32 seeds were received by Bard. At this time, one of the seeds appears to be unaccounted for. The missing I-125 seed had an activity of 0.23 milliCuries at the time of shipment. The half-life of Iodine-125 is approximately 60 days.
Bard has surveyed the local carrier that transported the shipment to its facility. It has also surveyed the regional facility of the shipping carrier. Cardinal Health and Summerlin are still attempting to confirm the original inventory of seeds was 33.
The State of Nevada is continuing its investigation of the missing seed.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Agreement State
Event Number: 47571
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: CANBERRA
Region: 1
City: DOVER State: NJ
County:
License #: 110002-440566
Agreement: Y
Docket:
NRC Notified By: JENNY GOODMAN
HQ OPS Officer: STEVE SANDIN
Licensee: CANBERRA
Region: 1
City: DOVER State: NJ
County:
License #: 110002-440566
Agreement: Y
Docket:
NRC Notified By: JENNY GOODMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/05/2012
Notification Time: 14:26 [ET]
Event Date: 12/21/2011
Event Time: 00:00 [EST]
Last Update Date: 01/05/2012
Notification Time: 14:26 [ET]
Event Date: 12/21/2011
Event Time: 00:00 [EST]
Last Update Date: 01/05/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DANIEL HOLODY (R1DO)
CHRISTEPHER MCKENNEY (FSME)
ILTAB via email
DANIEL HOLODY (R1DO)
CHRISTEPHER MCKENNEY (FSME)
ILTAB via email
AGREEMENT STATE REPORT INVOLVING A MISSING AMERICIUM-241 CHECK SOURCE
The following report was received from the State of New Jersey via email:
"Canberra is terminating their license and in reconciling their inventory, and on 12/21/11 they discovered that a 8uCi Am-241 source [used as a check source] was missing. The source was last used by an employee in June or August. That employee had a stroke and did not return to work. Other employees cleaned out his cube area, mailed his personal belongings to his house, and threw everything else in the garbage. NJDEP instructed Canberra to go to the former employee's home. They will send a technician to do a search/survey."
This incident was reported by Canberra to the State of New Jersey on 1/4/12.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following report was received from the State of New Jersey via email:
"Canberra is terminating their license and in reconciling their inventory, and on 12/21/11 they discovered that a 8uCi Am-241 source [used as a check source] was missing. The source was last used by an employee in June or August. That employee had a stroke and did not return to work. Other employees cleaned out his cube area, mailed his personal belongings to his house, and threw everything else in the garbage. NJDEP instructed Canberra to go to the former employee's home. They will send a technician to do a search/survey."
This incident was reported by Canberra to the State of New Jersey on 1/4/12.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf