Event Notification Report for March 11, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/10/2005 - 03/11/2005
General Information or Other
Event Number: 41507
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: MARIETTA MEMORIAL HOSPITAL
Region: 3
City: MARIETTA State: OH
County:
License #: 02120850007
Agreement: Y
Docket:
NRC Notified By: MARK LIGHT
HQ OPS Officer: JOHN MacKINNON
Licensee: MARIETTA MEMORIAL HOSPITAL
Region: 3
City: MARIETTA State: OH
County:
License #: 02120850007
Agreement: Y
Docket:
NRC Notified By: MARK LIGHT
HQ OPS Officer: JOHN MacKINNON
Notification Date: 03/21/2005
Notification Time: 08:50 [ET]
Event Date: 03/11/2005
Event Time: 13:00 [EST]
Last Update Date: 03/21/2005
Notification Time: 08:50 [ET]
Event Date: 03/11/2005
Event Time: 13:00 [EST]
Last Update Date: 03/21/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
LAURA KOZAK (R3)
JOHN HICKEY (NMSS)
LAURA KOZAK (R3)
JOHN HICKEY (NMSS)
POSSIBLE MEDICAL MISADMINISTRATION
A prostate implant patient at Marietta Memorial Hospital was to have received 98 Iodine-125 seeds, 0.310 millicuries per seed, but instead received 83 iodine-125 seeds and 15 palladium-103 seeds, 1.2 millicuries each (palladium-103 is accelerator produced). The patient received 98% of the planned dose. The holders for the iodine-125 seeds and the palladium-103 seeds are similar in shape and size. The State of Ohio Bureau of Radiation Protection received the above information on 03/16/05 around 1300 hours. The Ohio Bureau of Radiation Protection is investigating this event.
A prostate implant patient at Marietta Memorial Hospital was to have received 98 Iodine-125 seeds, 0.310 millicuries per seed, but instead received 83 iodine-125 seeds and 15 palladium-103 seeds, 1.2 millicuries each (palladium-103 is accelerator produced). The patient received 98% of the planned dose. The holders for the iodine-125 seeds and the palladium-103 seeds are similar in shape and size. The State of Ohio Bureau of Radiation Protection received the above information on 03/16/05 around 1300 hours. The Ohio Bureau of Radiation Protection is investigating this event.
Power Reactor
Event Number: 41482
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE MAYO
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOE MAYO
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/11/2005
Notification Time: 17:06 [ET]
Event Date: 03/11/2005
Event Time: 14:29 [EST]
Last Update Date: 03/11/2005
Notification Time: 17:06 [ET]
Event Date: 03/11/2005
Event Time: 14:29 [EST]
Last Update Date: 03/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
IT WAS DETERMINEDED THAT GREATER THAN 1% OF INSPECTED S/G TUBES MUST BE REPAIRED.
"As part of the Cycle 6 refueling outage, inspections are being performed in accordance with Technical Specification (TS) 5.7.2.12, 'Steam Generator (SG) Tube Surveillance Program.' Based on a review of the inspection results to date, it was established at approximately 14:29 EST on March 11, 2005, that greater than 1 percent of the inspected SG tubes must be repaired. In accordance with the criteria stated in TS 5.7.2.12 and the inspection findings, the four SGs must be classified as C-3. The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, 'Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73.' However, for the C-3 classification, WBN TS Table 5.7.2,12-1, 'SG Tube Inspection Supplemental Sampling Requirements,' requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of a Licensee Event Report in accordance with 10 CFR 50.73 is not planned."
The NRC Resident Inspector was notified.
"As part of the Cycle 6 refueling outage, inspections are being performed in accordance with Technical Specification (TS) 5.7.2.12, 'Steam Generator (SG) Tube Surveillance Program.' Based on a review of the inspection results to date, it was established at approximately 14:29 EST on March 11, 2005, that greater than 1 percent of the inspected SG tubes must be repaired. In accordance with the criteria stated in TS 5.7.2.12 and the inspection findings, the four SGs must be classified as C-3. The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, 'Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73.' However, for the C-3 classification, WBN TS Table 5.7.2,12-1, 'SG Tube Inspection Supplemental Sampling Requirements,' requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of a Licensee Event Report in accordance with 10 CFR 50.73 is not planned."
The NRC Resident Inspector was notified.