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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/14/2010 - 07/15/2010
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 46081 |
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ALLIANCE ENGINEERING
Region: 4
City: FORT WORTH State: TX
County:
License #: 05889
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: CHARLES TEAL |
Notification Date: 07/09/2010
Notification Time: 12:07 [ET]
Event Date: 07/09/2010
Event Time: [CDT]
Last Update Date: 07/09/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
VINCENT GADDY (R4DO)
ANGELA MCINTOSH (FSME)
MEXICO VIA FAX ()
ILTAB VIA EMAIL () |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
AGREEMENT STATE - STOLEN MOISTURE DENSITY GAUGE
The following was received via email from the state of Texas:
"On July 9, 2010, the Agency [Texas Department of Health] was notified by the licensee that one of their technicians had reported that a moisture/density gauge had been stolen from his truck that morning. The gauge is a Humboldt model 5001 EZ (serial # 4438) containing a 40 millicurie Americium (Am) 241 source, and a 10 millicurie Cesium (Cs) 137 source. The technician had completed testing on concrete rebar and returned to his truck. He found the tailgate down and the two locked chains used to secure the gauge in the truck bed had been cut. The gauge and additional equipment were missing. The technician searched the area for the gauge and when he could not find it, contacted the company Radiation Safety Officer (RSO). The RSO stated that the truck was parked in a position where the technician could not see it while he was performing his testing. The RSO contacted Local Law Enforcement and informed them of the event. A reward will be offered for the gauges return. The RSO stated that he will have the technician provide a written report, which he will forward to this Agency [Texas Department of Health]. Additional information will be provided as it is received in accordance with Reporting Material Events - SA-300."
Texas Incident #: I-8761
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
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| General Information or Other |
Event Number: 46082 |
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: MARSHFIELD CLINIC
Region: 3
City: MARSHFIELD State: WI
County:
License #: 141-1162-01
Agreement: Y
Docket:
NRC Notified By: MEGAN SHOBER
HQ OPS Officer: CHARLES TEAL |
Notification Date: 07/09/2010
Notification Time: 12:50 [ET]
Event Date: 07/09/2010
Event Time: [CDT]
Last Update Date: 07/09/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
TAMARA BLOOMER (R3DO)
ANGELA MCINTOSH (FSME) |
Event Text
AGREEMENT STATE - BRACHYTHERAPY TREATMENT DOSE DELIVERED DIFFERS FROM PRESCRIBED
The following was received via fax from the state of Wisconsin:
"On July 8, 2010, the licensee's Radiation Safety Officer (RSO) reported the preliminary identification of six medical events involving permanent implants of I-125 for prostate brachytherapy where the total dose delivered differs from the prescribed dose by 20% or more. During recent routine inspection, DHS [Department of Health Services] inspectors determined that the licensee was not reviewing prostate brachytherapy cases against the medical event criteria. The licensee is currently evaluating all 269 prostate implants performed since August 2003. This review is ongoing and will include an assessment of whether any implants involved doses to an organ or tissue above 0.50 Sv and 50% more than the expected dose. The licensee is in the process of notifying the affected patients and referring physicians.
"The reported medical events involve two locations of use. One facility identified three under doses (74.8%, 75.2%, and 76.5%) and one overdose (121.4%). The second facility identified one under dose (78.2%) and one overdose (121.0%). DHS inspectors are investigating these medical events and will send a special inspection team following completion of the licensee's review"
Event Report No.: WI100012
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. |
| 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: 07/14/2010 |
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.
* * * UPDATE FROM RICHARD COTTY TO JOHN KNOKE AT 2100 EDT ON 07/14/10 * * *
The licensee has completed the required maintenance on the TSC HVAC. The Technical Support Center is now fully functional.
The licensee will notify the NRC Resident Inspector. |
| Fuel Cycle Facility |
Event Number: 46086 |
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: RANDY SHACKELFORD
HQ OPS Officer: JOE O'HARA |
Notification Date: 07/12/2010
Notification Time: 17:58 [ET]
Event Date: 07/12/2010
Event Time: 12:00 [EDT]
Last Update Date: 07/12/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE |
Person (Organization):
MALCOLM WIDMANN (R2DO)
DAVID PSTRAK (NMSS)
FUELS GRP via email () |
Event Text
ELECTRICAL FAULT DISABLED PUBLIC ADDRESS SYSTEM WHICH SUPPORTS VARIOUS ALARM ANNUNCIATORS
"At approximately 1200 hours (EST) on 7/12/2010, an electrical fault was identified in the fire alarm system. This fault disabled the public address portion of the system which supports annunciation of plant alarms including the following: fire alarm, criticality alarm, take-cover alarm, [carbon dioxide] discharge alarms. Trouble shooting of the problem is continuing. There is no impact to actual detection, suppression, etc. systems. Compensatory measures include the following: stop SNM handling and movement, fire patrols, restriction of hot work, notification to facility personnel, evacuation of nonessential personnel from production areas, fire brigade on standby and radios provided to fire brigade officers and some fire brigade members.
"It is believed that the condition was associated with heavy rainfall and possible water intrusion.
"There were no actual safety consequences to workers, the public, or the environment associated with the event. Potential consequences to workers, the public, or the environment are mitigated by compensatory measures."
The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 46092 |
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN BALLETTA
HQ OPS Officer: VINCE KLCO |
Notification Date: 07/14/2010
Notification Time: 10:06 [ET]
Event Date: 07/14/2010
Event Time: 07:20 [EDT]
Last Update Date: 07/14/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
JUDY JOUSTRA (R1DO) |
| 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 |
Event Text
POWER LOST TO THE EMERGENCY OPERATIONS FACILITY
"At approximately 0720 hours, an offsite 4 kv feeder to the Indian Point Energy Center Emergency Operations Facility (EOF) faulted and power was lost to the EOF. [Power was] restored at approximately 0915 hours. The Alternate Emergency Operations Facility (AEOF) was available during the time the EOF was without power, as were all sirens of the Alert Notification System (ANS). Investigation of the event is in progress."
The licensee notified the NRC Resident Inspector and the New York Public Service Commission (PSC). |
| Power Reactor |
Event Number: 46093 |
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: AL MANNING
HQ OPS Officer: JOE O'HARA |
Notification Date: 07/14/2010
Notification Time: 16:37 [ET]
Event Date: 07/14/2010
Event Time: 13:55 [EDT]
Last Update Date: 07/14/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
DEBORAH SEYMOUR (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
TSC OUT OF SERVICE FOR PLANNED MAINTENANCE
"Planned preventive maintenance activities are being performed on the Hatch Nuclear Plant's Technical Support Center (TSC) Emergency Ventilation System on July 14, 2010. These maintenance activities include the performance of preventive maintenance on the TSC air handling unit and the TSC condensing unit. These work activities are planned to be completed within the (12) hour day shift on 7/14/2010.
"During the time these activities are being performed, the TSC air handling unit, TSC condensing unit, TSC filter train and the fan unit for the TSC filter train will not be available for operation. As such, the TSC HVAC will be rendered non-functional during the performance of this work activity. If an emergency is declared requiring activation of the TSC during the time these work activities are being performed, then the contingency plans call for utilization of the TSC, as long as habitability and radiological conditions allow. Procedure 73EP-EIPÀ063-0, Technical Support Center activation, provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC so that TSC functions can be continued.
"This event is reportable per 10CFR50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution."
The NRC Resident Inspector has been notified. |
| Power Reactor |
Event Number: 46094 |
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: JOHN KNOKE |
Notification Date: 07/14/2010
Notification Time: 19:53 [ET]
Event Date: 07/14/2010
Event Time: 19:34 [EDT]
Last Update Date: 07/15/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS |
Person (Organization):
DEBORAH SEYMOUR (R2DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
100 |
Power Operation |
82 |
Power Operation |
Event Text
TECH SPEC SHUTDOWN DUE TO THROUGH WALL FLAWS IN S/G SAMPLE LINE, SECONDARY SIDE
"At 1834 hours on 7/14/10, the Unit 1 'C' Reactor Coolant Loop was declared inoperable due to small unisolable leaks on the 'C' Steam Generator secondary side surface sample line. Two small through-wall flaws were identified in the piping upstream of 1 -SS-217, 'C' Steam Generator surface sample line manual isolation valve. The piping is Class 2 and the non-conforming condition could not be evaluated with the steam generator pressurized. Based on the condition of the piping and the inability to evaluate the flaw, the 'C' Steam Generator was declared inoperable per Technical Requirements Manual 3.4.6, ASME Code Class 1, 2 and 3 Components. Subsequently, Technical Specification 3.4.4 was entered to place Unit 1 in Mode 3 within 6 hours.
"At 1934 hours on 7/14/10, North Anna Unit 1 initiated a shutdown in accordance with Technical Specification 3.4.4. The unit will be shutdown and the line will be evaluated and repaired."
The licensee is presently at 82% power and coasting down in power. All safety systems are fully operable.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM PAUL TRENT TO DONALD NORWOOD AT 0015 HRS ON 7/15/2010 * * *
North Anna Unit 1 entered mode 3 at 2353 hrs. There were no complications during shutdown. One source range monitor failed downscale low. The other source range monitor is operating correctly. The failure of this source range monitor did not affect shutdown capabilities.
Notified R2DO (Seymour). |
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