Report a Safety Concern
Search

The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home NRC Library Document Collections Events, Reports Associated with Event Notification Reports 2019

Event Notification Report for March 29, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
3/28/2019 - 3/29/2019

** EVENT NUMBERS **


539485394953950539515396153962


Agreement State Event Number: 53948
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: OKLAHOMA STATE UNIVERSITY
Region: 4
City: STILLWATER   State: OK
County:
License #: OK-00237-03
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: OSSY FONT 		Notification Date: 03/20/2019
Notification Time: 14:14 [ET]
Event Date: 03/20/2019
Event Time: 00:00 [CDT]
Last Update Date: 03/20/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
NEIL O'KEEFE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - CONTAMINATED RADIATION WORKER

The following was received from the Oklahoma Department of Environmental Quality via email:

"A person administering a dose of I-131 to a cat at Oklahoma State University (OK-00237-03) was found to have contamination on the palm of one hand after the injection. According to the licensee, the contaminated individual is a radiation worker. The amount of material on the individual is estimated at 0.17 microCuries and it is believed to have been on the person for 15 to 30 minutes. After the discovery, the person was decontaminated, which reduced the radiation level to background. The [contaminated individual] will be bio-assayed tomorrow."

Inspection number 19-01


Agreement State Event Number: 53949
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: COVESTRO LLC
Region: 4
City: BAYTOWN   State: TX
County:
License #: L01577
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: MARK ABRAMOVITZ 		Notification Date: 03/21/2019
Notification Time: 11:14 [ET]
Event Date: 03/20/2019
Event Time: 00:00 [CDT]
Last Update Date: 03/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
NEIL O'KEEFE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE STUCK SHUTTER

The following report was received from the state of Texas via e-mail:

"On March 21, 2019, the licensee notified the Agency [Texas Department of State Health Services] that during routine shutter checks on March 20, 2019, it had discovered that the shutter on one of the Ronan Model SA-1 gauges (SN: M-3824) was stuck in the open position. Open is the normal operating position for this gauge. The gauge contains a cesium-137 source with a calculated current activity of 10 milliCuries. Due to the location of the gauge, there is no increased risk of exposure. The licensee plans to replace the gauge."

Texas Incident #9667


Agreement State Event Number: 53950
Rep Org: ALABAMA RADIATION CONTROL
Licensee: TTL, INC
Region: 1
City: MONTGOMERY   State: AL
County:
License #: 512
Agreement: Y
Docket:
NRC Notified By: CASON COAN
HQ OPS Officer: JEFFREY WHITED 		Notification Date: 03/21/2019
Notification Time: 16:04 [ET]
Event Date: 03/19/2019
Event Time: 20:00 [CDT]
Last Update Date: 03/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The following was received from the state of Alabama via fax:

"On March 20, 2019 at approximately 0800 [CDT], [an individual] of Alabama licensee TTL, lnc. notified the Alabama Office of Radiation Control [Agency] that gauge make and model Troxler 3440P was stolen from a technician's vehicle between approximately 2000 [CDT] March 19, and 0500 [CDT] March 20, 2019. The technician was working at a temporary job site in Auburn, AL, and the truck parked in the hotel parking lot. [The individual] reported that the technician stored the gauge in a gauge box; the gauge box was appropriately secured to the truck bed. The technician reported the theft to the local police department before contacting the Agency. The Agency has no further information regarding the whereabouts of this gauge as of today, March 21, 2019.

"TTL, Inc. is authorized to possess gauges under Alabama license 512. The stolen gauge is identified as Troxler model 3440P [serial number] 72314, with maximum source activities of 10 mCi Cs-137 and 50 mCi Am/Be-241."

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


Agreement State Event Number: 53951
Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: GE HEALTHCARE
Region: 1
City: ATLANTA   State: GA
County:
License #: GA 1166-1
Agreement: Y
Docket:
NRC Notified By: IRENE BENNETT
HQ OPS Officer: JEFFREY WHITED 		Notification Date: 03/21/2019
Notification Time: 15:44 [ET]
Event Date: 03/18/2019
Event Time: 00:00 [EDT]
Last Update Date: 03/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
- CNSC (CANADA) (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - GENERATOR LOST IN TRANSIT

The following was received from the state of George via e-mail:

"On January 17, 2019, GE Healthcare in Atlanta (GA 1166-1) consigned a Mo-99/Tc-99m generator (5.14 mCi at the time of shipment) to [common carrier] for delivery to Medi-Ray in Tuckahoe, NY for recycling (the trip included a transit stop in Charlotte, NC). As of March 20, 2019, the device has not arrived at its final destination. On March 18, 2019, [the common carrier] formally notified GE Healthcare that the device was lost in transit.

"This information was received on March 20, 2019."

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: 53961
Facility: BRUNSWICK
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DEREK WATSON
HQ OPS Officer: JEFF HERRERA 		Notification Date: 03/28/2019
Notification Time: 15:07 [ET]
Event Date: 03/28/2019
Event Time: 14:50 [EDT]
Last Update Date: 03/29/2019
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
JOEL MUNDAY (R2)
HO NIEH (NRR)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 58 Power Operation

Event Text

UNUSUAL EVENT DECLARED DUE TO RCS UNIDENTIFIED LEAKAGE

At 1450 EDT on March 28, 2019, the licensee observed that the Unit 1 unidentified Reactor Coolant System (RCS) leakage was greater than 10 gallons per minute (gpm) for greater than or equal to 15 minutes. The licensee declared an Unusual Event in accordance with their EAL SU 5.1. The licensee initiated a unit shutdown in accordance with their procedures and the unit was approximately 58 percent reactor power at 1507 EDT, with unit shutdown in progress. The licensee also received an alarm due to increasing Drywell Pressure at 1.7 pounds drywell pressure.

At 1600 EDT the licensee called with an update. Unit 1 was still in an Unusual Event with the unit at 37 percent power with the shutdown continuing. Drywell Pressure had decreased to 0.8 pounds. At 1603 the licensee scrammed Unit 1.

Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

* * * UPDATE ON 3/28/2019 AT 1808 EDT FROM MARK TURKAL TO THOMAS KENDZIA * * *

"At 1437 EDT on March 28, 2019, with Unit 1 in Mode 1 at approximately 100 percent power, a Technical Specification-required shutdown was initiated due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours.

"It is expected that the leakage would not have been reduced to within limits within the required Technical Specification completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

* * * UPDATE ON 03/29/19 AT 0302 EDT FROM TOM FIENO TO BETHANY CECERE * * *

At 0259 EDT on March 29, 2019, the Unusual Event was terminated because RCS leakage was reduced to less than 10 gallons per minute. The most recent leakage rate measured at 0225 EDT was 3.9 gpm. The source of the leak will be identified when plant conditions allow containment entry. No elevated radiation levels were observed during this event. Drywell pressure is currently 0.0 psig. Unit 1 is in Mode 4.

The licensee notified the NRC Resident Inspector.

Notified R2DO (Bonser), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).


Power Reactor Event Number: 53962
Facility: BRUNSWICK
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: THOMAS FIENO
HQ OPS Officer: ANDREW WAUGH 		Notification Date: 03/28/2019
Notification Time: 20:55 [ET]
Event Date: 03/28/2019
Event Time: 16:54 [EDT]
Last Update Date: 03/28/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN BONSER (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

AUTOMATIC ACTUATION OF THE PRIMARY CONTAINMENT ISOLATION SYSTEM AND THE REACTOR PROTECTON SYSTEM

"At 1654 EDT on March 28, 2019, with Unit 1 in Mode 3 at 0 percent power, an actuation of the Primary Containment Isolation System occurred, closing the outboard Main Steam Isolation Valves (MSIVs) due to a low condenser vacuum signal. The MSIVs had been manually closed, per procedure, during the shutdown evolution to address drywell leakage. The inboard MSIVs had not been reopened when the isolation occurred.

"Subsequently, at 1658 EDT a Reactor Protection System (RPS) actuation occurred due to reactor water level dropping below the actuation setpoint. All control rods were inserted at the time of the actuation.

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System and the Reactor Protection System.

"There was no impact on the health and safety of the public or plant personnel. The safety function of both the MSIVs and the RPS had already been completed at the time of the event.

"The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Wednesday, March 24, 2021