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Event Notification Report for October 30, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/29/2018 - 10/30/2018

** EVENT NUMBERS **


53679 53682 53683 53684 53686 53687 53702 53703

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Agreement State Event Number: 53679
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: DESERT NDT LLC
Region: 4
City: ABILENE   State: TX
County:
License #: LICEN-RAM-L06462
Agreement: Y
Docket:
NRC Notified By: ARTHUR TUCKER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/21/2018
Notification Time: 16:19 [ET]
Event Date: 10/20/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/21/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG PICK (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE FAILURE TO RETRACT

The following information was received via E-mail:

"On October 20, 2018, the agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that one of its radiography crews was unable to return an 80 curie iridium-192 source to the fully shielded position in an INC IR 100 exposure device. The RSO stated that the event occurred near Pecos, Texas. The RSO stated that the radiographers had established a 2 millirem boundary.

"An individual listed on their license responded to perform the source retrieval. The location where the event occurred was remote and the event did not present an exposure risk to any individual. The RSO stated that there are very few people at the site.

"Once the individual who was sent to retrieve the source arrived, they inspected the exposure device and guide tube. The inspection discovered the radiographers had bent the guide tube to get it through some pipes and the angle of the bend was what had prevented the source from being retracted. The guide tube was straightened and the source was retracted to the fully shielded position at 2100 hours. The guide tube was inspected and did not have any damage. The RSO stated that no overexposures had occurred."

Texas Incident Number: 9622

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Agreement State Event Number: 53682
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: TERRACON CONSULTANTS, INC.
Region: 1
City: ROCHESTER   State: NY
County:
License #: C3209
Agreement: Y
Docket:
NRC Notified By: DANIEL J. SAMSON
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/22/2018
Notification Time: 12:24 [ET]
Event Date: 09/11/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DONNA JANDA (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following was received from the State of New York by fax:

"Terracon Consultants reported that a moisture/density gauge [Troxler model 3430P, serial #70428, containing 0.30 GBq (8 mCi) Cs137 and 1.48 GBq (40 mCi) Am-Be source] was damaged at a mass fill project in Rochester, NY. The source manufacturer and serial number are not yet available.

"While at a mass fill project in Rochester, NY, a technician had completed a round of density testing and placed the gauge within a roped off area at the end of the fill area. He then walked to his truck approximately 100 feet away to get water. During that time, a 10-ton single drum roller moving in reverse headed towards the roped off area and gauge. The technician noticed the operator approaching the gauge as he walked back towards it and yelled and tried to gain the attention of the roller operator. The rear rubber tire of the roller impacted the side of the gauge and damaged the plastic covering. The technician cordoned off the area 15 feet around the gauge and surveyed the operator and roller.

"The technician called their office manager and a regional manager (who happened to be in their office) and went to the site and surveyed the gauge and all parties/equipment involved and it did not appear that the gauge was leaking. The gauge was visually inspected for damage and it appeared that only the top case was damaged, the gauge was still operational, and the source rod was fully enclosed in the gauge. The gauge was returned to its transport case and returned to its permanent storage location in Rochester, NY. The gauge will be transported for repair and leak testing.

"An internal root cause analysis and follow up training with the technician will be set in place with their corporate RSO [Radiation Safety Officer] in the next few days."

NY EVENT REPORT ID NO. NY-18-02

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Agreement State Event Number: 53683
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: ECD MID-ATLANTIC CHANTILLY
Region: 1
City: STERLING   State: VA
County: LOUDOUN
License #: 107-314-1
Agreement: Y
Docket:
NRC Notified By: ASFAW FENTA
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/22/2018
Notification Time: 12:44 [ET]
Event Date: 10/20/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DONNA JANDA (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPOT - DAMAGED MOISTURE DENSITY GAUGE

The following was received from the Commonwealth of Virginia by email:

"On October 20, 2018, the representative of the Virginia Radioactive Materials Program (VRMP) received a telephone call from the licensee that the guide tube of a portable nuclear moisture/density gauge (CPN Model MC-1DRP, Serial number MD50507856) was damaged (bent) by a truck while performing testing at a temporary jobsite in Sterling, Virginia. The gauge contained 10 milliCuries of Cesium-137 and 50 milliCuries of Americium-241/Beryllium. The sources were in the shielded position and the shielding integrity was not damaged. The licensee performed a survey of the gauge and readings observed were between 0.2 and 0.3 mR/hr at three (3) feet distance from the gauge.

"The gauge was put in its transport box and returned to the office. Wipe test samples were taken. Samples were sent to the North East Technical Services for analysis. Results are pending. The VRMP is currently working with the licensee to obtain additional information. This report will be updated when VRMP receives more information."

VA Event Report ID No.: VA-18-006

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Agreement State Event Number: 53684
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: APPLUS RTD USA, INC.
Region: 1
City: CHARLOTTE   State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TRAVIS CARTOSKI
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/22/2018
Notification Time: 14:22 [ET]
Event Date: 10/20/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DONNA JANDA (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE FAILED TO RETRACT

The following was received from the State of North Carolina by email:

"On 10/20/18, at 1757 EDT, the office RSO [Radiation Safety Officer] received a call from a crew working a project at Kings Mountain Compressor Station in Kings Mt., NC. The qualified radiographer assigned is Technician 1, with assistant Technician 2. Upon exposure of a 3 inch weld, the source did not retract when attempting to secure the RAM to end exposure. The crew immediately verified and re-verified and secured boundaries and called the RSO as required by operating and emergency procedures.

"The local RSO notified the CRSO [corporate RSO] of the event at 1803 EDT and proceeded to the site. [While] in route to the project site, Technician 4 was notified to go to the Charlotte office to get spare control cables for possible use in recovery operations. Upon arrival at approximately 1830 EDT, the RSO evaluated the site and boundaries and took action to move the source and collimator assembly to a better position to allow stacking of available sand bags in order to minimize boundary area for a more condensed and controllable area. During the movement of the exposure device, positive pressure was applied to the control to prevent the source from moving out of the collimator. Once the exposure device was positioned correctly, sand bags were placed over the source assembly to reduce exposure limits. During this operation, survey meters were used to verify radiation exposures. The radiation area was reduced to 30-35 feet.

"A conversation with the CRSO and calls with additional Applus groups were made in order to identify the closest source recovery tools and equipment in order to attempt recovery of the source.

"[Personnel] added another layer of area markings for control purposes. Contractor site personnel stayed clear of the area without issue during event. No exposure to the general public occurred.

"The recovery kit arrived on site at approximately 1030 EDT, 10/21/18. After review of available equipment, a recovery plan was discussed. Dosimetry, equipment operation, and proper calibrations were verified. All dosimeter pencils were verified at zero at the beginning of the event and monitored at stages during recovery. Actions were broken down in order to balance and reduce exposure to each individual and modified as necessary during event.

"The plan of action was to create a shielded dam with available lead shot and sand bags at the open end of the guide tube, with one bag directly in front of the tube to stop the source assembly at the most shielded position, with the others providing a shielded position for the capsule of the source assembly. The last sand bag on the collimator was left in position up until the last step. Two individuals were directed to quickly remove the last shielding bag while the other utilized an extended tong device to lift the collimator assembly directly upward to propel the source to the established dam of shielding. Survey meters were used to monitor this action to verify the source moved from the previous position to the created shielding dam. All dosimeter pencils were reviewed in order to determine who would be chosen to disconnect damaged connector and then another to make the connection to the functioning control cable. The first person pulled the connection out only far enough to disconnect the damaged connector. The second person performed the re-connection. The survey meter reading at the connection area was approximately 200 mR/hr during these steps. The time of exposure to perform these two events was estimated to be less than 30 seconds, which would have equaled approximately 1.6 mR of exposure to the hands of each individual. From the safe distance of the control cable, the source was retracted to the shielded position of the device and surveyed and secured. At this time, the exposure device and control cable have been returned to the office and tagged with damage tags so no one will use it."

NC tracking number: 180043

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Agreement State Event Number: 53686
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CAPITOL ULTRASONICS, LLC
Region: 4
City: BATON ROUGE   State: LA
County:
License #: LA-5838-L01
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/22/2018
Notification Time: 15:27 [ET]
Event Date: 10/22/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DRAKE (R4DO)
GRETCHEN RIVERA-CAPELLA (NMSS DAY)
PATRICIA MILLIGAN (INES)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - OVEREXPOSURE EVENT

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

"On October 22, 2018 around 1000 CDT, Capitol Ultrasonics, L.L.C. was working at Exxon Refinery. Two industrial radiographers' pocket ion chambers went off scale while moving the source guide tube. Dose reconstruction indicated 743 mR whole body to one radiographer. The second radiographer received 294 mR whole body and 51 Rem extremity dose to the hands.

"The industrial radiography camera being used was an 880D Amersham, serial number: D15404, with a source strength of 34.3 Ci of Ir-192, serial number: 66839G.

"Body badges are being sent in for immediate processing at this time."

Louisiana Event Report ID No.: LA20180017

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Agreement State Event Number: 53687
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: TRIAD ENGINEERING, INC.
Region: 1
City: STERLING   State: VA
County:
License #: 840-240-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/22/2018
Notification Time: 16:24 [ET]
Event Date: 10/22/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DONNA JANDA (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following was received from the Commonwealth of Virginia by email:

"On October 22, 2018, the RSO [Radiation Safety Officer] for the licensee reported an accident that morning at a construction site near Sterling, Virginia. A roller hit a portable moisture/density gauge with its rear wheels while backing up. The gauge user established an exclusionary area until the RSO arrived to perform an onsite investigation and radiation survey. The RSO reported the plastic housing of the gauge was cracked but the source rod and shielding were intact. Surveys indicated no unusual radiation levels. The licensee contacted a vendor to analyze leak test samples and to determine potential repairs to the gauge.

"The gauge was a Troxler 3430, serial [number] 30198, with an 8 milliCurie Cs-137 source, serial [number] 750-2497, and a 40 milliCurie Am-241:Be source, serial [number] 47-27175."

VA Event Report ID No.: VA-18-007

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Power Reactor Event Number: 53702
Facility: PALO VERDE
Region: 4     State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JORDAN ANDAZOLA
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/29/2018
Notification Time: 12:56 [ET]
Event Date: 10/29/2018
Event Time: 00:00 [MST]
Last Update Date: 10/29/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CALE YOUNG (R4DO)
CHRIS MILLER (NRR EO)
WILLIAM GOTT (IRD)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N N 0 Defueled 0 Defueled
3 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION OF NON- WORK RELATED FATALITY

"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"At approximately 03:30 MST on October 29, 2018, an Arizona Public Service Company (APS) employee developed a personal medical condition in the Owner Controlled Area outside of the Secured Owner Controlled Area at Palo Verde Generation Station (PVGS). PVGS Emergency Medical Technicians responded and transported the individual to an offsite emergency trauma center. Upon arrival at the trauma center, medical personnel declared the individual deceased at approximately 05:35 MST.

"The fatality was not work related and the individual was outside of the Radiological Controlled Area and no radioactive material or contamination was involved.

"No news release by APS is planned. Notifications were made to the Arizona Division of Occupational Safety and Health at 08:15 MST.

"The NRC Resident Inspectors have been notified."

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Power Reactor Event Number: 53703
Facility: SAINT LUCIE
Region: 2     State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: REESE KILIAN
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/29/2018
Notification Time: 16:47 [ET]
Event Date: 10/29/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/29/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ERIC MICHEL (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO INADEQUATE FEEDWATER FLOW

"On October 29, 2018 at 1317 EDT, with St. Lucie Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to inadequate feedwater flow to both 1A and 1B Steam Generators (S/Gs). The trip was uncomplicated with all systems responding normally post-trip. [All control rods fully inserted and there were no specified system actuations.] Operators responded and stabilized the plant in Mode 3. The cause of the inadequate feed flow to the 1A and 1B Steam Generators is currently under investigation.

"Decay Heat removal is being accomplished through forced circulation with stable conditions from Main Feedwater and the Steam Bypass Control System to the Main Condenser. Currently maintaining Pressurizer pressure at 2250 psia and Reactor Coolant System temperature at 532 degrees F.

"St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100% power.

"This report is submitted in accordance with 10CFR50.72(b)(2)(iv)(B) for the reactor trip.

"The NRC Senior Resident Inspector has been notified."


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