| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/08/2009 - 10/09/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45411 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: BED BATH & BEYOND
Region: 4
City: OMAHA State: NE
County:
License #: SEE TEXT
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: JOE O'HARA | Notification Date: 10/05/2009
Notification Time: 10:06 [ET]
Event Date: 08/03/2009
Event Time: [CDT]
Last Update Date: 10/05/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
GLENDA VILLAMAR (FSME)
ILTAB VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT INVOLVING SEVENTEEN LOST TRITIUM EXIT SIGNS
The State of Nebraska was notified by a Bed Bath & Beyond representative that they are unable to account for a total of 17 tritium exit signs (which are general licensed materials). These 17 signs were part of an order that went to three separate Bed Bath & Beyond store locations in the Omaha, NE area. The Bed Bath & Beyond representative informed the state that Bed Bath & Beyond has performed an extensive search and considers the signs not to be present at the stores.
- Sixteen (16) signs are Safety Light Corporation Model SLX60 and contain 11.5 Ci/each H-3. The serial numbers of these 16 missing signs are as follows: 302790, 302792, 302793, 283015, 302799, 302800, 302810, 302803, 397719, 397720, 397721, 397722, 397725, 397726, 397728, and 397730.
- One (1) sign is Safety Light Corporation Model 2040 and contains 11.5 Ci H-3. The serial number for this sign is #257964.
NE Item Number NE090012 (Store #771-GL0634), NE090013 (Store #1021-GL0654) and NE090014 (Store #1184-GL0605).
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: 45414 | Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: STORK TWIN CITY TESTING
Region: 3
City: ST PAUL State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SHERRIE FLAHERTY
HQ OPS Officer: JOE O'HARA | Notification Date: 10/06/2009
Notification Time: 11:11 [ET]
Event Date: 10/05/2009
Event Time: 10:30 [CDT]
Last Update Date: 10/06/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANN MARIE STONE (R3DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - INDUSTRIAL RADIOGRAPHY SOURCE RETRACTION INCIDENT
The following event was received from the state via e-mail:
"On October 5, 2009 at approximately 1030, radiographers working for Stork Twin City Testing in a tunnel at a steam plant in St. Paul, Minnesota were unable to retract the 75 curie Iridium-192 source (serial number 56177B) of their AEA Model 660B exposure device (serial number 2657). The radiographers had the device placed on a ladder approximately six feet off the ground during this and two previous exposures. Following several attempts to retract the source the device fell from the ladder landing on the control cable. The Radiation Safety Officer was contacted at approximately 1045. The radiographers established boundaries of approximately 2 mR/h and maintained control over the area. The Radiation Safety Officer placed several layers of lead over the device and the cable to reduce the exposure levels, but he still considered the levels too high to safely work on releasing the source. Minnesota Department of Health (MDH) Radioactive Materials Unit was notified at approximately 1215. The University of Minnesota's Health Physics staff was contacted and offered to bring additional lead shielding to the area. MDH and University of Minnesota staff arrived at the location at approximately 1250. Following placing additional shielding around the device the Radiation Safety Officer made another attempt to release the source, but was unable to get the source back into the device. QSA Global was contacted for technical support at approximately 1430. At approximately 1530 the Radiation Safety Officer removed two pins from the back of the exposure device and was able to manually pull the cable and secure the source in the device. Following surveys of the device to determine the source was in the device, the control cable was examined. Damage to the cable at the point where the metal tip connects to the cable was discovered. The exposure device was transported back to Stork Twin City Testing and will be inspected and tested October 6, 2009. The Radiation Safety Officer will submit a complete report to MDH within 30 days. Personal dosimetry readings were 90 mR for the Radiation Safety Officer and approximately 80 and 30 mR for the radiographers." |
| Power Reactor | Event Number: 45420 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RON CLEVELAND
HQ OPS Officer: CHARLES TEAL | Notification Date: 10/08/2009
Notification Time: 13:39 [ET]
Event Date: 10/07/2009
Event Time: 16:41 [CDT]
Last Update Date: 10/08/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| 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 FITNESS FOR DUTY - REPORT OF FAILURE OF RANDOM DRUG TEST NON-LICENSED CONTRACTOR
A non-licensed contractor had confirmed positive for illegal drugs a random fitness for duty test. The contractors access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details. |
| Power Reactor | Event Number: 45421 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID MANKIN
HQ OPS Officer: CHARLES TEAL | Notification Date: 10/08/2009
Notification Time: 18:06 [ET]
Event Date: 10/08/2009
Event Time: 14:20 [CDT]
Last Update Date: 10/08/2009 | 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):
ANN MARIE STONE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DURING TESTING
"This report is being made under CFR 50.72(b)(2(iv)(B) for a automatic reactor scram which is preliminarily believed to have been caused while restoring reactor pressure vessel level/pressure instrumentation to service during performance of surveillance test 3.3.3.2-09 Reactor Water Level and Pressure Instruments Calibration .
"In addition, this report is being made under CRF 50.72(b)(3)(iv)(A) due to PCIS (Primary Containment Isolation System) Groups 2, 3 and 4 being received when reactor water level dropped below 170 due to the expected level shrink immediately following a reactor scram. All isolations went to completion. Reactor water level was recovered to normal vessel level as expected under post scram conditions.
"The following Technical Specification LCOs (Limiting Conditions of Operation) were in affect at the time of the reactor scram:
"TS 3.7.5, Required Action A.1, 30 day completion time for 'B' Control Building Chiller;
TS 3.7.2, Required Action A.1, 7 day completion time for 'B' River Water Supply loop;
TS 3.3.3.1, Function 6, Required Action A.1, 30 day completion time for position indication of MO-1949B, 'B' Residual Heat Removal Heat Exchanger Vent;
TS 3.7.1, Required Action A.1, 30 day completion time for 1P22D, 'D' Residual Heat Removal Service Water Pump.
"All rods fully inserted during the scram. The plant is in a normal shutdown electrical lineup with offsite sources powering the safety busses. No safety or relief valves lifted during the transient. Decay heat is being removed via the steam bypass [valves to the] condenser.
"The licensee notified the NRC Resident Inspector." | |