| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/22/2015 - 06/23/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51155 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: SPEEDIE & ASSOCIATES
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 07-209
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 06/15/2015
Notification Time: 16:20 [ET]
Event Date: 06/12/2015
Event Time: [MST]
Last Update Date: 06/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DON ALLEN (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ROBERT BUNCH (ILTA)
CNSNS (MEXICO) (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE
The following information was received via E-mail:
"On June 12, 2015, a portable gauge was being stored in a locked box in the back of a truck which was locked in one of the user's garages. An ex-girlfriend, who had a copy of the truck keys, broke into the user's house and stole the truck with the gauge still in the back. The truck was reported stolen to the RSO on the morning of June 13, 2015. The RSO then made a police report and contacted the Agency's [Arizona Radiation Regulatory Agency] duty officer. The RSO stated that someone spotted the truck in Mesa, Arizona on the night of June 13, 2015. The gauge is a Troxler Model 3400 series, Serial Number 5310, containing 7.4 millicuries of Cesium-137 and 40 millicuries of Americium-241.
"The truck is a white, 2007 GMC Sierra crew cab with Arizona license plate number: 415ZGV.
"The investigation into this event is ongoing.
"The US NRC, Maricopa County sheriff's office, Arizona DPS [Department of Public Safety], California, New Mexico, Utah, Nevada, and Arizona governor's office are being notified of this event."
Arizona First Notice Number: 15-009
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 |
| Power Reactor | Event Number: 51170 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MCHUGH
HQ OPS Officer: DANIEL MILLS | Notification Date: 06/22/2015
Notification Time: 20:55 [ET]
Event Date: 06/22/2015
Event Time: 14:06 [EDT]
Last Update Date: 06/22/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JOHN ROGGE (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 SODIUM HYDROXIDE BELOW TECHNICAL SPECIFICATION REQUIRED CONCENTRATION
"At 1406 [EDT] on 6/22/15, the chemistry sample results for the Salem Unit 1 Containment Spray Additive tank were below the minimum Technical Specification requirement for NaOH [Sodium Hydroxide] concentration. The Containment Spray Additive tank was declared inoperable at that time in accordance with Technical Specification 3.6.2.2.a. Based on the fact that there is no redundant equipment for the Containment Spray Additive tank, this condition could have prevented this Safety System from Controlling the Release of Radioactive Material and Mitigating the consequences of an accident.
"This event is being reported under the requirements of 10 CFR 50.72(b)(3)(v)(C) and (D) as 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of systems that are needed to Control the Release of Radioactive Material and Mitigate the Consequences of an Accident.' Actions are being taken to restore the NaOH concentration to within the Technical Specification limits.
"The Licensee has notified the NRC Resident. No one was injured as a result of the event."
The licensee will notify the Lower Alloways Township. | |