United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2019 > January 22

Event Notification Report for January 22, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
1/18/2019 - 1/22/2019

** EVENT NUMBERS **


53752 53820 53821 53823 53837 53840 53841 53842

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53752
Facility: MILLSTONE
Region: 1     State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RYAN ROBILLARD
HQ OPS Officer: DAN LIVERMORE
Notification Date: 11/25/2018
Notification Time: 02:47 [ET]
Event Date: 11/24/2018
Event Time: 20:15 [EST]
Last Update Date: 01/18/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY POWELL (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

LOSS OF CONTROL ROOM ENVELOPE DUE TO DOOR FAILURE

"On 11/24/18 at 2015 EST, a loss of Control Room Envelope (CRE) was declared due to failure of the control room boundary door, 204-36-008. [Abnormal Operating Procedure 8588A Mitigating Actions for Control Boundary Breach was implemented]. The door was repaired at 2030 EST, restoring CRE to operable [status]."

A mechanical failure of the control room door latch prevented the door from closing.

The licensee notified the NRC Resident Inspector.



* * * RETRACTION ON 01/18/19 AT 1457 EST FROM GARY CLOSIUS TO JEFFREY WHITED * * *

"The purpose of this call is to retract a report made on November 25, 2018, NRC Event Number EN53752.

"NRC Event Report number EN53752 describes a condition at Millstone Power Station Unit 2 (MPS2) in which a control room envelope boundary door was discovered to not be able to fully close due to the latching mechanism being stuck in the extended position.

"The condition was reported to the NRC pursuant to 10 CFR 50.72(b)(3)(v)(D) via an 8-hour prompt report as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"Upon further review, MPS2 determined that there was no loss of safety function. An engineering evaluation determined that even with the control room boundary door unable to be fully closed due to the latching mechanism being stuck in the extended position, control room air in-leakage would not have been sufficient to prevent the control room emergency ventilation system from performing its safety function.

"Therefore, this condition is not reportable and NRC Event Number EN53752 is being retracted.

"The basis for this conclusion has been provided to the NRC Resident Inspector."

Notified the R1DO (Carfang).

To top of page
Agreement State Event Number: 53820
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: H & H X-RAY SERVICES, INC
Region: 4
City: WEST MONROE   State: LA
County: RED RIVER PARISH
License #: LA-2970-L01
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: ANDREW WAUGH
Notification Date: 01/10/2019
Notification Time: 13:32 [ET]
Event Date: 01/08/2019
Event Time: 00:30 [CST]
Last Update Date: 01/10/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CALE YOUNG (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - UNABLE TO RETRACT RADIOGRAPHY SOURCE

The following information was received from the State of Louisiana via email:

"On 01/08/2019, 1535 CST, [the licensee] called the Louisiana Department of Environmental Quality (LDEQ) to report a source would not retrieve back into the shielded position. The event happened at approximately 0030 CST at a temporary jobsite in Loggy Bayou, LA Red River Parish.

"The camera was being used at this temporary jobsite. The exposure was made and the source would not retract into the shielded position. The reportable event was the 'drive cable' in the crankout handle broke in the associated equipment being used with this QSA Global, Model 880 Delta gamma camera/exposure device. The SN for the 880D is #14342. The device was loaded with 72.7 Ci of Ir-192 with the SN# 73586G.

"The Industrial Radiography Crew followed the H & H Safety Procedures and contacted the radiation safety officer. A three-man crew performed the source retrieval and equipment evaluation after the repair/fix. The exposure device was put back into service after the repair. Two personnel involved in this retrieval received exposures of 40 mrem and the other individual's exposure was 50 mrem. The Industrial Radiography Crew's pocket dosimeter readings were 13 mrem and 11 mrem for the shift when the incident occurred. There were no excessive exposures associated with this event."

Event Report ID No.: LA-190001

To top of page
Agreement State Event Number: 53821
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: ARLANXEO USA LLC
Region: 4
City: ORANGE   State: TX
County:
License #: L06785
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: ANDREW WAUGH
Notification Date: 01/10/2019
Notification Time: 17:25 [ET]
Event Date: 01/10/2019
Event Time: 00:00 [CST]
Last Update Date: 01/10/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CALE YOUNG (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DAMAGED GAUGE

The following information was received from the State of Texas via email:

"On January 10, 2019, during a routine gauge inspection/shutter check, the handle broke off the rod that turns the shutter on an Ohmart Model HM-10 source holder which contained 5,000 milliCuries of cesium-137 (original activity) (SN: 6967). The shutter is in the closed position and there is no risk of exposure. External corrosion was observed. The licensee plans, at this time, to replace the gauge and further evaluation will be performed at the time of replacement. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident #: I-9649

To top of page
Agreement State Event Number: 53823
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: FOAM INDUSTRIES, INC
Region: 3
City: ROGERS   State: MN
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: BRANDON JURAN
HQ OPS Officer: BETHANY CECERE
Notification Date: 01/11/2019
Notification Time: 10:08 [ET]
Event Date: 12/24/2018
Event Time: 00:00 [CST]
Last Update Date: 01/11/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID HILLS (R3DO)
ILTAB (EMAIL)
NMSS_EVENTS_NOTIFICATION (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST THEN FOUND STATIC ELIMINATOR

The following report was received from the State of Minnesota by email:

"The licensee uses a static eliminator on the end of an air line. Typically the static eliminator is kept on the line and not removed. The licensee recently moved locations and not all of their stations were set up, so they were moving the static eliminator around. The static eliminator was removed from a line and placed on top of a box. It slid off the box and ended up under a nearby pallet. They noticed the static eliminator was missing on 12/24/2018. The pallet was moved and the static eliminator was found on 1/11/2019. All of the stations are now set up and the static eliminator will stay connected to a dedicated line.

"Material: Po-210, NRD model P-2021, 1.9 mCi on 1/10/19

"State event report: MN190001"

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

To top of page
Power Reactor Event Number: 53837
Facility: WATERFORD
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: JERRY BROWN
HQ OPS Officer: JEFFREY WHITED
Notification Date: 01/18/2019
Notification Time: 17:03 [ET]
Event Date: 01/18/2019
Event Time: 13:33 [CST]
Last Update Date: 01/18/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JAMES DRAKE (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Refueling 0 Refueling

Event Text

REACTOR COOLANT SYSTEM WELD DOES NOT MEET ACCEPTANCE CRITERIA

"This is a non-emergency notification from Waterford 3.

"On January 18, 2019, a relevant indication was detected in the performance of Phased Array Ultrasonic Examinations of A600 Dissimilar Metal Piping Welds during planned inspections. The indication was observed during the analysis of data recorded of the Reactor Coolant System (RCS) Loop 2A Reactor Coolant Pump Suction Drain Nozzle to Safe-End Butt Weld (11-007). This indication does not meet applicable acceptance criteria under American Society of Mechanical Engineers (ASME) Section XI. The plant was in Mode 6 (Refueling) at 0 percent power for a planned refueling outage at the time of discovery. The condition will be resolved prior to plant startup. This condition has no impact to the health and safety of the public. This report is being made in accordance with 10 CFR 50 .72(b)(3)(ii)(A), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded,' because an indication was found that did not meet acceptance criteria referenced in ASME Section XI , IWB-3514-2 and Code Case N-770-2, 3132.

"The NRC Resident Inspector has been notified.

"Reference: CR-WF3-2019-01041"

To top of page
Power Reactor Event Number: 53840
Facility: WATTS BAR
Region: 2     State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID ALLEN
HQ OPS Officer: OSSY FONT
Notification Date: 01/22/2019
Notification Time: 09:41 [ET]
Event Date: 12/02/2018
Event Time: 00:28 [EST]
Last Update Date: 01/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
NICOLE COOVERT (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

Event Text

INVALID CONTAINMENT VENTILATION ISOLATION ACTUATION

"This 60-day telephone notification is being submitted in accordance with paragraphs 10 CFR 50.73(a)(1) and 50.73(a)(2)(iv)(A) to report an invalid Containment Ventilation Isolation (CVI) actuation at Watts Bar Nuclear Plant (WBN) Unit 1.

"On December 2, 2018 at 0028 Eastern Standard Time (EST), the Train A CVI actuated due to an invalid High Radiation signal from 1-RM-90-130, Containment Purge Exhaust Radiation Monitor. In addition to the Train A CVI, instrument malfunction alarms were received for 1-RM-90-106, Lower Containment Radiation Monitor and 1-RM-90-112, Upper Containment Radiation Monitor as the associated valves isolated for the CVI. A common instrument malfunction alarm was also received for 1-RM-90-130 and 1-RM-90-131, Containment Purge Exhaust Radiation Monitors. Prior to and following the invalid High Radiation alarm, all radiation monitors except 1-RM-90-130 were stable at their normal values. All required automatic actuations occurred as designed. Upon investigation, the cause of the invalid High Radiation alarm was due to a failed ratemeter for 1-RM-90-130.

"Control room operators performed appropriate checks and confirmed that the subject indication was an invalid high radiation signal. The ratemeter for 1-RM-90-130 was replaced and the monitor returned to service. At the time of the event, plant conditions for a High Radiation alarm did not exist; therefore, the CVI was invalid.

"The NRC Resident Inspector was notified."

To top of page
Non-Power Reactor Event Number: 53841
Facility: UNIV OF MISSOURI-COLUMBIA
RX Type: 10000 KW TANK
Comments:
Region: 0
City: COLUMBIA   State: MO
County: BOONE
License #: R-103
Agreement: N
Docket: 05000186
NRC Notified By: BRUCE MEFFERT
HQ OPS Officer: BRIAN P. SMITH
Notification Date: 01/22/2019
Notification Time: 12:15 [ET]
Event Date: 01/21/2019
Event Time: 12:35 [CST]
Last Update Date: 01/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
Person (Organization):
GEOFFREY WERTZ (NRR)
ELIZABETH REED (NRR)

Event Text

DEVIATION OF TS 3.3.a(1) for ANTI-SIPHON DEVICE FOUND INOPERABLE

"On January 21, 2019 at approximately 1235 CST, with all four (4) shim control rods fully inserted into the reactor core during performance of a pre-startup checklist, the University of Missouri-Columbia Research Reactor (MURR) deviated from Technical Specification (TS) 3.3.a(1) due to test jumpers being installed while electrical power was available to the shim rod drive mechanism electromagnets. Prior to this event, the reactor was shut down for a regularly-scheduled maintenance period. A required notification per TS 6.6.c(1) to report to the NRC Operations Center that an Abnormal Occurrence, as defined by MURR TS 1.1, had occurred. Specifically, MURR was not in compliance with all TS Limiting Conditions for Operations, specifically TS 3.3.a(1).

"For about ten (10) seconds at approximately 1235 CST, power was available to the shim rod drive mechanism electromagnets while electrical test jumpers, which hold anti-siphon system isolation valves V543A and V543B closed, were inserted. In effect, the anti-siphon system was not operable while the reactor was technically operating for ten (10) seconds per the following definitions:

1. TS 1.23 Reactor in Operation - The reactor shall be considered in operation unless it is either shutdown or secured.
2. TS 1.27 Reactor Shutdown - The reactor is shutdown when: All four (4) of the shim blades (rods) are fully inserted and power is unavailable to the shim rod drive mechanism electromagnets.
3. TS 1.26 Reactor Secured - MURR did not meet the definition of Reactor Secured during the event.

"Though all four shim rods were fully inserted and a reactor startup had not commenced, electrical power being available to the shim rod drive mechanism electromagnets caused the reactor to technically be in Operation for a very brief period. Though this event happened at approximately 1235 CST, it was not fully identified as an abnormal occurrence per TS 1.1.b until approximately 1625 CST, after a reactor startup was performed to 10 MW operation. Once the abnormal occurrence was realized, the Reactor Facility Director was immediately notified at 1715 CST, and he gave permission to continue reactor operation. A detailed event report will follow within 14 days as required by MURR TS 6.6.c(3)."

To top of page
Power Reactor Event Number: 53842
Facility: WOLF CREEK
Region: 4     State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JON WEBER
HQ OPS Officer: JEFFREY WHITED
Notification Date: 01/22/2019
Notification Time: 14:40 [ET]
Event Date: 01/22/2019
Event Time: 07:23 [CST]
Last Update Date: 01/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MICHAEL VASQUEZ (R4DO)
FFD GROUP (EMAIL)
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 POLICY VIOLATIONS - PRESENCE OF ALCOHOL IN THE PROTECTED AREA

"On January 22, 2019, 0723 CST, the Contracts group called and reported to FFD [fitness for duty], that a box of candy was received from a supplier vendor that may contain alcohol. Upon investigation of the candy with the manufacturer, pieces of the candy contain 20-30mg of Alcohol after the chocolate is cooked. The Contract offices are located in the Protected Area and this incident is being reported under 10 CFR 26.719."

No for-cause testing was performed based on the consumption of the candy.

No safety related work was performed by the individuals who may have consumed the candy.

The box of candy was removed from the site.

The licensee notified the NRC Resident Inspector.


Page Last Reviewed/Updated Friday, May 03, 2019
Friday, May 03, 2019