Event Notification Report for June 02, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/01/2008 - 06/02/2008
EVENT NUMBERS
444614425544256442574425844347
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Hospital
Event Number: 44461
Rep Org: QUEENS MEDICAL CENTER
Licensee: QUEENS MEDICAL CENTER
Region: 4
City: HONOLULU State: HI
County:
License #: 53-16533-02
Agreement: N
Docket:
NRC Notified By: BRIAN OYTOMARI
HQ OPS Officer: JOE O'HARA
Licensee: QUEENS MEDICAL CENTER
Region: 4
City: HONOLULU State: HI
County:
License #: 53-16533-02
Agreement: N
Docket:
NRC Notified By: BRIAN OYTOMARI
HQ OPS Officer: JOE O'HARA
Notification Date: 09/03/2008
Notification Time: 14:01 [ET]
Event Date: 06/02/2008
Event Time: 00:00 [HST]
Last Update Date: 09/05/2008
Notification Time: 14:01 [ET]
Event Date: 06/02/2008
Event Time: 00:00 [HST]
Last Update Date: 09/05/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
WILLIAM JONES (R4)
RICHARD TURTIL (FSME)
WILLIAM JONES (R4)
RICHARD TURTIL (FSME)
POTENTIAL MISADMINISTRATION GREATER THAN 20% OF PRESCRIBED DOSE
The RSO performed a quarterly audit on 9/2/08 and discovered that a misadministration greater than 20% of prescribed dose and greater than 50 Rem to the lung tissue occurred on 6/2/08. The prescribed dose was 1.0 ml of P-32 chromic phosphate into two separate syringe applications.
The technician prepared the first P-32 dose into syringe "A" and recorded into the written record after calibrated assay as 1.3 ml and performed the same procedure for the second dose which was recorded into the written record as 1.0 ml into syringe "B". The first dose in syringe "A" exceeded the allowable dose. Both syringe applications were given to the patient into separate lung tube injections.
The prescribing physician and authorized user have been notified. It is not known if the patient has been notified.
* * * RETRACTION AT 1545 EDT ON 9/5/08 FROM OYTOMARI TO SANDIN * * *
Based on further review of this event by the licensee, it was determined that the total dose to the lung was less than 50 Rem. As a result, the event does not meet reportability criteria under 10CFR35.3045. The licensee has reviewed its conclusion with NRC Region 4 inspectors (Whitten and Munoz).
R4DO (Jones) and FSME (Turtil) have been notified.
The RSO performed a quarterly audit on 9/2/08 and discovered that a misadministration greater than 20% of prescribed dose and greater than 50 Rem to the lung tissue occurred on 6/2/08. The prescribed dose was 1.0 ml of P-32 chromic phosphate into two separate syringe applications.
The technician prepared the first P-32 dose into syringe "A" and recorded into the written record after calibrated assay as 1.3 ml and performed the same procedure for the second dose which was recorded into the written record as 1.0 ml into syringe "B". The first dose in syringe "A" exceeded the allowable dose. Both syringe applications were given to the patient into separate lung tube injections.
The prescribing physician and authorized user have been notified. It is not known if the patient has been notified.
* * * RETRACTION AT 1545 EDT ON 9/5/08 FROM OYTOMARI TO SANDIN * * *
Based on further review of this event by the licensee, it was determined that the total dose to the lung was less than 50 Rem. As a result, the event does not meet reportability criteria under 10CFR35.3045. The licensee has reviewed its conclusion with NRC Region 4 inspectors (Whitten and Munoz).
R4DO (Jones) and FSME (Turtil) have been notified.
General Information or Other
Event Number: 44255
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: ALPHA ANALYTICAL LABS
Region: 1
City: WESTBOROUGH State: MA
County:
License #: G0316
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: HOWIE CROUCH
Licensee: ALPHA ANALYTICAL LABS
Region: 1
City: WESTBOROUGH State: MA
County:
License #: G0316
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/02/2008
Notification Time: 15:01 [ET]
Event Date: 06/02/2008
Event Time: 00:00 [EDT]
Last Update Date: 06/02/2008
Notification Time: 15:01 [ET]
Event Date: 06/02/2008
Event Time: 00:00 [EDT]
Last Update Date: 06/02/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PAMELA HENDERSON (R1)
MICHELLE BURGESS (FSME)
PAMELA HENDERSON (R1)
MICHELLE BURGESS (FSME)
MASSACHUSETTS AGREEMENT STATE REPORT - NI-63 SOURCE LEAKAGE
The following information was obtained from the State of Massachusetts via facsimile:
The licensee reported that two Electron Capture Device (ECD) leak tests were positive for leakage. ECD serial number U0504 had a reading of 0.1 microCuries. ECD serial number U2861 had a reading of 0.06 microCuries. Both units are Agilent model G2397A and contain 15 mCi of Ni-63. The licensee has taken both units out of service and has contacted Agilent for the return of both devices.
The following information was obtained from the State of Massachusetts via facsimile:
The licensee reported that two Electron Capture Device (ECD) leak tests were positive for leakage. ECD serial number U0504 had a reading of 0.1 microCuries. ECD serial number U2861 had a reading of 0.06 microCuries. Both units are Agilent model G2397A and contain 15 mCi of Ni-63. The licensee has taken both units out of service and has contacted Agilent for the return of both devices.
General Information or Other
Event Number: 44256
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: INDIAN RIVER RADIOLOGY
Region: 1
City: VERO BEACH State: FL
County:
License #: 2308-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: HOWIE CROUCH
Licensee: INDIAN RIVER RADIOLOGY
Region: 1
City: VERO BEACH State: FL
County:
License #: 2308-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/02/2008
Notification Time: 17:18 [ET]
Event Date: 06/02/2008
Event Time: 00:00 [EDT]
Last Update Date: 06/03/2008
Notification Time: 17:18 [ET]
Event Date: 06/02/2008
Event Time: 00:00 [EDT]
Last Update Date: 06/03/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PAMELA HENDERSON (R1)
TERRANCE REIS (FSME)
PAMELA HENDERSON (R1)
TERRANCE REIS (FSME)
FLORIDA AGREEMENT STATE REPORT - LOSS OF CONTROL OF REFERENCE SOURCES
State of Florida Bureau of Radiation Control reported that the licensee, Indian River Radiology, sold two gamma cameras to another entity. By mistake, the purchaser of the cameras also took the reference sources that are used for calibrations. The sources will be returned to the licensee (seller) by Wednesday, June 4, 2008. This is considered a loss of control of radioactive material.
The sources each contained 20 mCi of Cs-137 and 250 mCi of Gd-153.
Florida Incident Number: FL08-083
* * * UPDATE FROM STEVE FURNACE TO HOWIE CROUCH @1651 HRS. ON 6/3/08 * * *
The State of Florida amended the report to state that the Cs-137 source was 30 mCi in strength as of 1 MAY 1999 and is used as a PET scan source, not a reference source. The Gd-153 source was 250 mCi on 1 DEC 2004. They are encouraging the expedited return of the sources to the licensee.
Notified R1DO (Henderson) and FSME EO (Chang).
State of Florida Bureau of Radiation Control reported that the licensee, Indian River Radiology, sold two gamma cameras to another entity. By mistake, the purchaser of the cameras also took the reference sources that are used for calibrations. The sources will be returned to the licensee (seller) by Wednesday, June 4, 2008. This is considered a loss of control of radioactive material.
The sources each contained 20 mCi of Cs-137 and 250 mCi of Gd-153.
Florida Incident Number: FL08-083
* * * UPDATE FROM STEVE FURNACE TO HOWIE CROUCH @1651 HRS. ON 6/3/08 * * *
The State of Florida amended the report to state that the Cs-137 source was 30 mCi in strength as of 1 MAY 1999 and is used as a PET scan source, not a reference source. The Gd-153 source was 250 mCi on 1 DEC 2004. They are encouraging the expedited return of the sources to the licensee.
Notified R1DO (Henderson) and FSME EO (Chang).
Power Reactor
Event Number: 44257
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/02/2008
Notification Time: 17:17 [ET]
Event Date: 06/02/2008
Event Time: 14:40 [EDT]
Last Update Date: 06/02/2008
Notification Time: 17:17 [ET]
Event Date: 06/02/2008
Event Time: 14:40 [EDT]
Last Update Date: 06/02/2008
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):
PAMELA HENDERSON (R1)
ROBERT HAAG (R2)
PAMELA HENDERSON (R1)
ROBERT HAAG (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 94 | Power Operation | 94 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SHIPPING CASK ARRIVES WITH A LOOSE BOLT
"The following is a 4 Hr Non-Emergency notification in accordance with 10 CFR 50.72(b)(2)(xi), Offsite Notification.
"At 1440, June 2, 2008, Susquehanna LLC was notified by the Barnwell South Carolina waste disposal facility, of an issue with a shipping cask containing irradiated hardware shipped from Susquehanna LLC. The cask was received at the facility on 5/31/08 and the incoming radiological survey was completed with no out of specification values. On June 2, 2008, the cask had the impact limiter removed and was in the process of being offloaded when it was discovered that one of the twelve bolts that secure the cask base plate to the cask body was found hand tight. The remaining eleven bolts were not loose, There was no radiological safety concern associated with the bolting condition as survey results confirmed that no radioactivity leaked from the cask. The waste facility will issue a condition report for Susquehanna's response.
"The site South Carolina Department of Health and Environmental Controls (SC DHEC) Inspector was notified by Barnwell facility personnel of the issue."
The licensee's QC inspector is required to verify bolt torque before the cask leaves the site. This will be confirmed by the licensee. The licensee will be notifying PEMA (Pennsylvania Emergency Management Agency).
The licensee notified the NRC Resident Inspector.
"The following is a 4 Hr Non-Emergency notification in accordance with 10 CFR 50.72(b)(2)(xi), Offsite Notification.
"At 1440, June 2, 2008, Susquehanna LLC was notified by the Barnwell South Carolina waste disposal facility, of an issue with a shipping cask containing irradiated hardware shipped from Susquehanna LLC. The cask was received at the facility on 5/31/08 and the incoming radiological survey was completed with no out of specification values. On June 2, 2008, the cask had the impact limiter removed and was in the process of being offloaded when it was discovered that one of the twelve bolts that secure the cask base plate to the cask body was found hand tight. The remaining eleven bolts were not loose, There was no radiological safety concern associated with the bolting condition as survey results confirmed that no radioactivity leaked from the cask. The waste facility will issue a condition report for Susquehanna's response.
"The site South Carolina Department of Health and Environmental Controls (SC DHEC) Inspector was notified by Barnwell facility personnel of the issue."
The licensee's QC inspector is required to verify bolt torque before the cask leaves the site. This will be confirmed by the licensee. The licensee will be notifying PEMA (Pennsylvania Emergency Management Agency).
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 44258
Rep Org: COLORADO DEPT OF HEALTH
Licensee: KLEINFELDER
Region: 4
City: DENVER State: CO
County:
License #: 958-01
Agreement: Y
Docket:
NRC Notified By: JAMES S. JARVIS
HQ OPS Officer: STEVE SANDIN
Licensee: KLEINFELDER
Region: 4
City: DENVER State: CO
County:
License #: 958-01
Agreement: Y
Docket:
NRC Notified By: JAMES S. JARVIS
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/03/2008
Notification Time: 10:54 [ET]
Event Date: 06/02/2008
Event Time: 14:15 [MDT]
Last Update Date: 06/03/2008
Notification Time: 10:54 [ET]
Event Date: 06/02/2008
Event Time: 14:15 [MDT]
Last Update Date: 06/03/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JACK WHITTEN (R4)
MICHELE BURGESS (FSME)
JACK WHITTEN (R4)
MICHELE BURGESS (FSME)
AGREEMENT STATE REPORT INVOLVING A DAMAGED TROXLER MOISTURE DENSITY GAUGE
On June 2, 2008 at approximately 2:15 pm a Troxler Moisture Density Gauge, Model 3430, was run over by a skid steer at a construction site in the Denver Metro area . The licensee notified the Colorado Radiation Management Unit at approximately 4:00 pm that the gauge had been transported back to the main office in Golden, Colorado. Subsequent preliminary testing indicated that the sources were intact and not leaking. Results of the formal leak test are pending.
On June 2, 2008 at approximately 2:15 pm a Troxler Moisture Density Gauge, Model 3430, was run over by a skid steer at a construction site in the Denver Metro area . The licensee notified the Colorado Radiation Management Unit at approximately 4:00 pm that the gauge had been transported back to the main office in Golden, Colorado. Subsequent preliminary testing indicated that the sources were intact and not leaking. Results of the formal leak test are pending.
Power Reactor
Event Number: 44347
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: STEVE CARTER
HQ OPS Officer: JOE O'HARA
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: STEVE CARTER
HQ OPS Officer: JOE O'HARA
Notification Date: 07/16/2008
Notification Time: 09:49 [ET]
Event Date: 06/02/2008
Event Time: 06:24 [CDT]
Last Update Date: 07/16/2008
Notification Time: 09:49 [ET]
Event Date: 06/02/2008
Event Time: 06:24 [CDT]
Last Update Date: 07/16/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
CLAUDE JOHNSON (R4)
CLAUDE JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID SYSTEM ACTUATION OF DIVISION 1 CONTAINMENT ISOLATION VALVES
"On June 2, 2008 at 6:24 a.m. CDT power was lost on the reactor protection system (RPS) bus 'A'. The plant was operating at 100 percent power at the time. The loss of RPS bus 'A' interrupted power to containment isolation actuation circuitry. This caused the Division 1 containment isolation valves in various balance of plant systems to automatically close, as designed. Plant operators implemented recovery procedures to shift RPS 'A' to its alternate power supply, and restore the systems affected by the isolation. The containment isolation valves were confirmed to have actuated as required. Plant capacity was not interrupted by the containment isolation signal.
"As their primary power source, each RPS bus is supplied by its own motor generator set. The investigation of this event found that two resistors on a circuit card in the voltage regulator on the 'A' RPS motor-generator set failed. This had the effect of causing the generator voltage to fluctuate significantly, resulting in a automatic trip of the generator output breaker and a loss of power on the bus.
"This event is being reported in accordance with 10CFR50.73(a)(2)(iv)(A) as an invalid actuation of the Division I containment isolation actuation system."
The licensee informed the NRC Resident Inspector.
"On June 2, 2008 at 6:24 a.m. CDT power was lost on the reactor protection system (RPS) bus 'A'. The plant was operating at 100 percent power at the time. The loss of RPS bus 'A' interrupted power to containment isolation actuation circuitry. This caused the Division 1 containment isolation valves in various balance of plant systems to automatically close, as designed. Plant operators implemented recovery procedures to shift RPS 'A' to its alternate power supply, and restore the systems affected by the isolation. The containment isolation valves were confirmed to have actuated as required. Plant capacity was not interrupted by the containment isolation signal.
"As their primary power source, each RPS bus is supplied by its own motor generator set. The investigation of this event found that two resistors on a circuit card in the voltage regulator on the 'A' RPS motor-generator set failed. This had the effect of causing the generator voltage to fluctuate significantly, resulting in a automatic trip of the generator output breaker and a loss of power on the bus.
"This event is being reported in accordance with 10CFR50.73(a)(2)(iv)(A) as an invalid actuation of the Division I containment isolation actuation system."
The licensee informed the NRC Resident Inspector.