| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/21/2018 - 02/22/2018 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 53206 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: E. I. DUPONT
Region: 4
City: ORANGE State: TX
County:
License #: 01819
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2018
Notification Time: 12:57 [ET]
Event Date: 02/09/2018
Event Time: [CST]
Last Update Date: 02/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE STUCK SHUTTER
The following report was received via e-mail:
"On February 12, 2018, the licensee notified the Agency [Texas Department of State Health Services] that one of its fixed nuclear gauges had a shutter stuck in the closed position. The gauge is an Ohmart-Vega model SH-F1B containing 40 milliCuries of cesium-137. Arrangements have been made with a service company to make repairs. There is no risk of exposure to employees or members of the public. More information will be provided as it is obtained in accordance with SA-300."
Texas Event: I-9540 |
| Agreement State | Event Number: 53207 | Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: INTERNATIONAL PAPER - GEORGETOWN MILL
Region: 1
City: GEORGETOWN State: SC
County:
License #: 060
Agreement: Y
Docket:
NRC Notified By: ANDREW ROXBURGH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2018
Notification Time: 13:28 [ET]
Event Date: 02/12/2018
Event Time: 13:00 [EST]
Last Update Date: 02/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE BROKEN SHUTTER
The following report was received via e-mail:
"The licensee notified the Department [South Carolina Department of Health and Environmental Control] at 1115 [EST] on February 13, 2018, that it had discovered a broken shutter on one of its gauges during the six-month shutter checks on February 12th. The gauge is a Berthold Model LB7440D containing 100 mCi of Cs-137. Source serial number is N-A04538DZ242A and source holder serial number is 2179. The gauge is still in service and a radiation reading of 2 mR/hr was observed on the surface of the gauge. There is no radiation exposure risk to personnel." |
| Agreement State | Event Number: 53208 | Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: JOHNS HOPKINS MEDICAL INSTITUTION
Region: 1
City: BALTIMORE State: MD
County:
License #: MD-07-005-03
Agreement: Y
Docket:
NRC Notified By: ALAN GOLDEY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2018
Notification Time: 16:00 [ET]
Event Date: 02/08/2018
Event Time: [EST]
Last Update Date: 02/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
GRETCHEN RIVERA-CAPE (NMSS)
PATRICIA MILLIGAN (INES)
| Event Text AGREEMENT STATE REPORT - PERSONNEL OVEREXPOSURE
The following report was received from the Maryland Department of the Environment Radiological Health Program via email:
"On February 8, 2018, the Maryland Department of the Environment - Radiological Health Program was contacted by Johns Hopkins Medical Institution (MD-07-005-03) of an incident in which one researcher had received a total effective dose equivalent exceeding 5 Rem and likely an extremity dose exceeding 50 Rem. The licensee received results of a researcher's 4th quarter 2017 radiation badge readings. The researcher was conducting tracer studies using PET isotopes C-11 and F-18 in animals. The researcher has been monitored since February 2012 and has frequently used F-18 in similar studies with no problems. Use of PET isotopes in the lab has been halted pending an investigation by the licensee. The Maryland Radiological Health Program will schedule a reactive investigation.
"The result of the whole-body radiation badge readings (monitoring period Oct 1 - Dec 31, 2017) was:
Deep Dose: 12,818 milliRem
Lens of the Eye: 28,280 milliRem
Shallow Dose: 46,206 milliRem
Beta Dose: 33,388 milliRem
"The researcher's assigned extremity ring badge was not worn during the 4th quarter of 2017.
"The licensee will submit a written report as required within 30 days." |
| Agreement State | Event Number: 53209 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: RADIOCAT
Region: 1
City: PITTSBURGH State: PA
County:
License #: PA-1060
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/14/2018
Notification Time: 14:56 [ET]
Event Date: 01/09/2017
Event Time: [EST]
Last Update Date: 02/14/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - IODINE-131 SPILL
The following report was received via fax:
"On February 13, 2018, during a routine inspection, the licensee informed the Department [Pennsylvania Department of Environmental Protection] of a contamination event that occurred on January 9, 2017 (over a year earlier). The event is reportable under 10 CFR 30.50 (b)(1)(i).
"On January 9, 2017, during a routine injection of 5 milliCuries of iodine-I31 (l-131) into a feline, the needle was removed before the injection was complete, resulting in a spill of I-131 onto the fur of the animal. The spill was not noticed until the animal was being relocated from the injection table to the isolation cage. This resulted in contamination of the technician's skin, clothing, and shoes, and the floor of the injection room. The technician immediately decontaminated her skin, and placed the contaminated clothing into a plastic bag for decay. It was estimated by the licensee she received a skin dose of 1 millirem. The floor of the room was decontaminated and access to the room was restricted over the period of a week until decontamination was complete. All surrounding areas and personnel were monitored and no other contamination was discovered.
"The Department [Pennsylvania Department of Environmental Protection] plans to have a 'call for conference' with the licensee and issue violations regarding this event. More information will be provided as received."
Pennsylvania report: PA180004 |
| Agreement State | Event Number: 53211 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: DELANE GEORGE AUTO PARTS
Region: 4
City: DE KALB State: MS
County:
License #: GL-426
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/14/2018
Notification Time: 17:52 [ET]
Event Date: 01/01/2015
Event Time: [CST]
Last Update Date: 02/14/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST PO-210 SOURCE
The following report was received via e-mail:
"The general licensee's president said he lost the static eliminator sometime in 2015. The general licensee's president said he used the device once and it did not work well. The general licensee also said the static eliminator must be lost and is probably in the dump somewhere."
Make/Model: NRD / P-2021
Serial: A2KD940
Source: Po-210, 10 mCi in April 1995
Mississippi Report: MS-180002
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 |
| Non-Power Reactor | Event Number: 53222 | Facility: UNIV OF FLORIDA
RX Type: 100 KW ARGONAUT
Comments:
Region: 0
City: GAINESVILLE State: FL
County: ALACHUA
License #: R-56
Agreement: Y
Docket: 05000083
NRC Notified By: DAN CRONIN
HQ OPS Officer: DAVID AIRD | Notification Date: 02/20/2018
Notification Time: 16:45 [ET]
Event Date: 02/16/2018
Event Time: 08:55 [EST]
Last Update Date: 02/21/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
DUANE HARDESTY (NRR)
ELIZABETH REED (NRR)
| Event Text TECHNICAL SPECIFICATIONS VIOLATION DUE TO INCORRECTLY CALIBRATED REACTOR TRIP INSTRUMENTATION
"On 2/16/18, the calorimetric portion of Surveillance Requirement (SR) 3.2.3.3 for Limiting Condition for Operations (LCO) 3.2.3.1 was performed in accordance with University of Florida Test Reactor (UFTR) procedures. Reactor power was stabilized at an indicated power of approximately 94 percent with actual thermal power (calculated by heat balance) at approximately 98kW (98 percent RTP) [rated thermal power]. Indicated power was then adjusted to approximately 99 percent to ensure adequate margin to the license limit of 100kW thermal steady-state (100 percent RTP). At no time was actual reactor power allowed to exceed the license limit. The reactor was then shutdown and secured to perform post-calorimetric verifications. SR 3.2.2.1 and 3.2.3.1 were performed satisfactorily just prior to operation to verify the High Reactor Power trip function and setpoint. Reactor Power Channel 1 was set to actuate at 110 percent and Reactor Power Channel 2 was set to actuate at 108 percent.
"At about 1400 on 2/19/18, during review of surveillance parameters and discussion with the operators, UFTR management determined that Limited Safety System Setting 2.2.1 and LCO 3.2.2.1 had been violated. The Technical Specifications allowable value for the automatic High Reactor Power trip function is less than or equal to 110 percent RTP. There was a period of approximately 5 hours of operation prior to adjustment of the power channels, however, during which actual thermal power was greater than indicated power (but less than 100kW thermal). During this period, if a power excursion had occurred, the High Reactor Power trip would have actuated at approximately 114 percent RTP. This condition is reportable in accordance with Sections 6.7.2.a.3 and 6.7.2.a.4 of the UFTR Technical Specifications. As described above, this condition was corrected by adjusting indicated power on both reactor power channels to greater than actual thermal power.
"The NRC Project Manager, assigned inspector, and Non-Power Reactor Licensing Branch Chief (acting) have been notified."
* * * UPDATE AT 0854 EST ON 02/21/2018 FROM DAN CRONIN TO DAN LIVERMORE * * *
"If a power excursion during the period of operation prior to adjustment of the power channels, Reactor Power Channel 2 would have provided a High Reactor Power trip at approximately 112% RTP."
Notified NRR PM (Hardesty) and NRR ENC (Reed). | |