| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/10/2010 - 12/13/2010 ** EVENT NUMBERS ** |
 | Hospital | Event Number: 46460 | Rep Org: OAKWOOD ANNAPOLIS HOSPITAL
Licensee: OAKWOOD ANNAPOLIS HOSPITAL
Region: 3
City: WAYNE State: MI
County:
License #: 21-11457-02
Agreement: N
Docket:
NRC Notified By: PIYUSH PANDYA
HQ OPS Officer: VINCE KLCO | Notification Date: 12/06/2010
Notification Time: 14:49 [ET]
Event Date: 12/04/2010
Event Time: 10:30 [EST]
Last Update Date: 12/06/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
ROBERT DALEY (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text DELIVERED DOSE GREATER THAN PRESCRIBED DOSE
"A patient was scheduled for a Tc-99m Myoview diagnostic cardiac resting perfusion study on 12/04/2010. Prescribed dosage was 10 mCi as noted on the departmental Prescribed Dosage List. These dosages are delivered as unit dose quantities along with Tc-99m in bulk quantity.
"Technetium-99m was delivered in bulk quantity in a syringe at approximately 0600 [EST] as 150 mCi calibrated for 1200 [EST]. At approximately 0900 [EST] a MAA kit was made by withdrawing 64 mCi from the bulk allotment.
"The nuclear medicine technologist inadvertently picked up the syringe at approximately 1030 [EST] containing Tc-99m as pertechnetate in bulk quantity (124.5 mCi) and without confirmatory assay in the dose calibrator injected the patient.
"As per 10 CFR 35.3045 (a)(1), the dose delivered differs from the prescribed dose by greater than 5 rem effective dose equivalent (EDE). However the upper large intestine (ULI) dose does not differ by more than 50 rads from the dose to be delivered from the prescribed dosage as follows:
Prescribed Dosage (10 mCi) EDE: 0.481 rem
Administered Dosage (31.4 mCi) EDE: 5.988 rem (Difference = 5.507 rem)
ULI Dose from Prescribed Dosage (10 mCi) 2.109 rads
ULI Dose From Administered Dosage (124.5 mCi) 26.257 rads (Difference = 24.148 rads)
"As per 10 CFR 35.3045 (a)(1)(ii), the administered dosage (124.5 mCi) differs from the prescribed dosage (10 mCi) by greater than the limit of 20%."
The physician determined there was no adverse impact on the patient.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| General Information or Other | Event Number: 46462 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: EXCELLIMS COPORATION
Region: 1
City: ACTON State: MA
County: MIDDLESEX
License #: 55-0588
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/07/2010
Notification Time: 15:01 [ET]
Event Date: 12/07/2010
Event Time: 13:30 [EST]
Last Update Date: 12/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTOPHER CAHILL (R1DO)
DIANA DIAZ-TORO (FSME)
| Event Text AGREEMENT STATE REPORT - LEAKING ECKERT & ZIEGLER MODEL NER-004 NI-63 SOURCE
"Excellims Corporation in Acton, MA. (license # 55-0588) telephoned to inform the Agency [Commonwealth of Massachusetts, Radiation Control Program] that a 6 month wipe test of a stored Ni-63 source foil yielded 0.0061 uCi. The Eckert & Ziegler model NER-004 source is stored in the container in which the manufacturer sent the source. The RSO stated that a previous wipe test of the same Ni-63 source yielded higher results and he concluded that he had wiped the 'hot' side. This wipe test (0.0061 uCi) was a wipe of the 'inactive' side, however, he thought that he may have spread contamination to the inactive side during the previous inadvertent wipe test of the 'hot' side.
"ACTION REQUESTED: The RSO will send to the Agency an initial written notification of this wipe test result and the technical data sheet of the NER-004 source that he received from the manufacturer. He stated that he could complete this request in a few days.
"ACTION TAKEN: Document this telephone notification; inform Agency supervision; submit a report to US NRC."
The source has been secured in the original container and stored in a secure location. A Eckert & Ziegler model NER-004 is used in a Gas Chromatograph and has a Ni-63 source of less that 50 millicuries. |
| Power Reactor | Event Number: 46471 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: NICHOLAS DESANTIS
HQ OPS Officer: DONG HWA PARK | Notification Date: 12/10/2010
Notification Time: 01:25 [ET]
Event Date: 12/09/2010
Event Time: 22:58 [EST]
Last Update Date: 12/10/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JAMES MOORMAN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP AFTER INDICATIONS OF A CONDENSER TUBE LEAK
"At 2200 [EST] 12/09/2010, Unit 4 had indication of a condenser tube leak. A power reduction was commenced in accordance with plant procedures to allow isolation of the leaking waterbox. Sodium levels in the Steam Generators increased and a unit shutdown was required. Power was reduced to 20% and a manual reactor trip was initiated at 2258 [EST] 12/09/10, in accordance with plant procedures. All systems operated as required and the unit is stable in mode 3."
The reactor trip was not complicated. All control rods inserted fully and decay heat is being removed by the atmospheric steam dumps. There is no indications of primary to secondary leakage. Normal offsite power is available and Unit 3 is unaffected. 3 of 3 steam generators are affected by the increase in sodium levels. The licensee is in progress of conducting steam generator blowdowns.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46473 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GRZECK
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/10/2010
Notification Time: 15:54 [ET]
Event Date: 12/09/2010
Event Time: 23:04 [EST]
Last Update Date: 12/12/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMES MOORMAN (R2DO)
|
| 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 | Event Text OFFSITE NOTIFICATION - AGENCIES NOTIFIED OF ONSITE TRITIUM LEAK
"On December 9, 2010, elevated levels of tritium were identified in water samples taken from in-leakage into the below ground elevation of the diesel generator building (i.e., through underground conduit penetrations). The tritium levels were determined to be in excess of the Nuclear Energy Institute (NEI) voluntary reporting criteria (i.e., 30,000 pCi/L for onsite groundwater, as specified in the Offsite Dose Calculation Manual). Further investigation determined that the likely source of the tritiated water is buried piping located west of the diesel generator building. The area of the leak is inside the plant protected area, well inside the site's property boundary. There is no indication that tritium has migrated into drinking water sources or has migrated off plant property. The leakage has not impacted plant reliability or the operability of any safety-related equipment.
"Corrective actions taken were to capture the in-leakage of water into the diesel generator building and route it through our normal permitted discharge paths. Additional water samples will continue to be obtained from site monitoring wells until the source of the leak is isolated. Efforts to identify and isolate the source of the leakage, and plans for excavation of the suspected area, are in-progress.
"The Brunswick plant has had an extensive groundwater protection monitoring program in place since 2007. This environmental sampling program consists of more than 100 monitoring wells which are routinely sampled.
"The following agencies will be updated on the status of the onsite tritium samples: City of Southport, Brunswick County, State Officials, NEI, INPO, and ANI.
"The Licensee has notified the NRC Resident Inspector."
* * * UPDATE ON 6/12/10 AT 1610 EST FROM GRZECK TO HUFFMAN * * *
"On December 10, 2010, at 2124 hours (EST), the buried piping leak was stopped after isolating the Unit 1 Condensate Make-up line to the Main Condenser (i.e., from the Condensate Storage Tank (CST)). The elevated levels of tritium are confined to the area in close proximity to the identified buried pipe location, west of the diesel generator building, well within the site's property boundary. The perimeter monitoring wells to the plant's protected area and site boundary continue to be analyzed with no increase in tritium levels identified. Preparations for the excavation and repair of the Condensate Make-up line are in-progress.
"The following agencies will be provided an update of this event: City of Southport, Brunswick County, State Officials, NEI, INPO, and ANI.
"The initial safety significance of this event is minimal. The Brunswick Steam Electric Plant has not identified any health or safety risk to the public or onsite personnel. There is no impact to plant reliability or safety.
"The Licensee has notified the NRC Resident Inspector." R2DO (Moorman) notified. |
| Power Reactor | Event Number: 46474 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRANDON SHULTZ
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/12/2010
Notification Time: 16:44 [ET]
Event Date: 12/12/2010
Event Time: 11:28 [EST]
Last Update Date: 12/12/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
CHRISTOPHER CAHILL (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 | Event Text HIGH PRESSURE COOLANT INJECTION SYSTEM UNAVAILABLE
"During quarterly operability verification of the HPCI Turbine Overspeed Trip Assembly, the Trip/Reset knob was manually lifted and released to time the automatic reset function. Upon release of the knob, the Trip Assembly failed to automatically reset (the HPCI Turbine Stop and Control Valves remained closed). Adjustment of the Trip/Reset needle valve was unsuccessful. The HPCI Turbine Stop and Control Valves remain in the tripped condition, rendering HPCI unavailable.
"Engineering and Maintenance have been dispatched to troubleshoot and repair the Overspeed Trip Assembly and restore HPCI to operable status.
"All other required systems are available, operable, and protected."
The licensee is in the 14 day LCO 3.5.1. The licensee has notified the NRC Resident Inspector. | |