| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/09/2010 - 07/12/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 46071 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: IREDELL MEMORIAL HOSPITAL
Region: 1
City: STATESVILLE State: NC
County:
License #: 049-0412-2
Agreement: Y
Docket:
NRC Notified By: HENRY BARNES
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/06/2010
Notification Time: 11:17 [ET]
Event Date: 05/05/2010
Event Time: [EDT]
Last Update Date: 07/06/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - PATIENT RECEIVED DOSE LESS THAN PRESCRIBED
The following information was received from the State of North Carolina via email:
"On 05/05/10, a physician at Iredell Memorial Hospital (NC License 049-0412-2) performed a prostate seed implant procedure. The prescribed dose was 1440 cGray (~1440 REM). After the seeds were implanted, they did a scan and discovered a seed in the urethra. They removed the seed and it was part of a strand of four seeds.
"On 05/19/10, the patient returned for a follow-up and had an additional strand of three seeds. The patient said the seeds had come out during urination about a week before.
"The patient went through the post-implant CT scan. On 07/02/10, the post-dose calculations were performed. The D-90 actual dose (dose to 90% of the mass) was calculated as 77% of the prescribed dose.
"The hospital has made the notification [to the North Carolina Division on Radiation Protection] and is attempting to make the physician and patient notification. A report will be prepared and delivered within 15 days."
State Event No.: NC 10-32
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. |
| Fuel Cycle Facility | Event Number: 46079 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: RIK DROKE
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/08/2010
Notification Time: 16:35 [ET]
Event Date: 07/08/2010
Event Time: 14:33 [EDT]
Last Update Date: 07/08/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
74.57 - ALARM RESOLUTION
| Person (Organization):
MALCOLM WIDMANN (R2DO)
DAVID PSTRAK (NMSS)
FUELS OUO GRP EMAIL ()
| Event Text MATERIAL CONTROL AND ACCOUNTABILITY (MC&A) ALARM ACTUATION
"10 CFR 74.57 (f) (2) requires notification within 24 hours that an MC&A alarm resolution procedure has been initiated. The input minus output value exceeded the limit in the Solvent Extraction Area of Building 333. The input minus output value has been resolved. There is no indication that a material loss has occurred.
"There were no actual or potential safety consequences to workers, the public, or the environment.
"An input minus output process monitoring material balance was calculated for the Building 333 Solvent Extraction Area as specified by applicable procedures and requirements. The input minus output value exceeded the limit. An investigation was initiated."
The licensee has notified the NRC Resident Inspector. Similar EN #46064. |
| Power Reactor | Event Number: 46080 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RUSS PARKER
HQ OPS Officer: VINCE KLCO | Notification Date: 07/09/2010
Notification Time: 10:44 [ET]
Event Date: 07/09/2010
Event Time: 06:47 [CDT]
Last Update Date: 07/09/2010 | 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
| Person (Organization):
TAMARA BLOOMER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 64 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO A FEEDWATER REGULATING VALVE FAILURE
"On 07/09/10 at 0647 [CDT] hours, control room personnel initiated a manual reactor trip of Unit 2 from approximately 64% power as a result of a failure of the "A" feedwater regulating valve (FRV). All [other] systems functioned as expected. All rods fully inserted into the core. The unit is stable in MODE 3 at normal RCS [Reactor Coolant System] pressure and temperature. The cause of the FRV failure is being investigated.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The unit electrical power is lined up to offsite power in a normal configuration. Decay heat is being removed from the steam generator through the steam dumps to the main condenser. The FRV failed open and the valve controller was unable to place the FRV into the correct position. The steam generator HI-Hi level provided a feedwater isolation signal and a high level lockout of the FRV. Currently, the feedwater bypass valve is controlling steam generator level. There was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46083 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN WHALLEY
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/09/2010
Notification Time: 15:55 [ET]
Event Date: 07/09/2010
Event Time: [EDT]
Last Update Date: 07/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANTHONY DIMITRIADIS (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 OFFSITE NOTIFICATION DUE TO ELEVATED LEVELS OF TRITIUM FOUND IN A WELL SAMPLE
"Entergy Pilgrim Station has twelve groundwater monitoring wells used to sample for tritium and other radioactive nuclides in accordance with the Nuclear Energy Institute's (NEI) voluntary Groundwater Protection Initiative (GPI). One of the wells, MW-205, located in the vicinity of the Condensate Storage Tanks (CST) indicated an elevated level of tritium, however well below the limits established by the NEI Groundwater Protection Initiative, the Nuclear Regulatory Commission's (NRC) limits for liquid effluent release and the Environmental Protection Agency's (EPA) limits for tritium in drinking or non-drinking water wells. The latest sample taken on June 21, 2010, returned a test result of 11,072 picocuries per liter of tritium. To date, tritium is the only isotope detected in the samples collected at the site. This information has been communicated to federal, state and local stakeholders and a press advisory is expected to be issued by the Massachusetts Department of Public Health (MDPH). On that basis and the anticipated interest to the general public this notification is being made.
"This event has no impact on the health and/or safety of the public.
"The NRC Resident Inspector is on-site and has been notified." |
| Power Reactor | Event Number: 46084 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAUL BURWINKEL
HQ OPS Officer: PETE SNYDER | Notification Date: 07/12/2010
Notification Time: 03:37 [ET]
Event Date: 07/12/2010
Event Time: 03:40 [EDT]
Last Update Date: 07/12/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MALCOLM WIDMANN (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 PLANNED TECHNICAL SUPPORT CENTER OUTAGE
"A condition is being reported per Technical Requirements Manual 13.13.1 Emergency Response Facilities Action B.2. The Functionality of the Technical Support Center (TSC) has been lost due to planned maintenance being performed on the TSC HVAC.
"Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to FUNCTIONAL status with high priority. A 10CFR50.54 (q) Evaluation has been performed for this planned maintenance activity."
The licensee notified the NRC resident inspector. | |