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Event Notification Report for July 09, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
7/6/2018 - 7/9/2018

** EVENT NUMBERS **


53478 53480 53491 53493 53496 53497 53498 53499

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Agreement State Event Number: 53478
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: IIA FIELD SERVICES
Region: 4
City: ABILENE   State: TX
County:
License #: L06933
Agreement: Y
Docket:
NRC Notified By: ARTHUR TUCKER
HQ OPS Officer: VINCE KLCO
Notification Date: 06/28/2018
Notification Time: 10:10 [ET]
Event Date: 06/27/2018
Event Time: 00:00 [CDT]
Last Update Date: 06/28/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN ALEXANDER (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA SOURCE DISCONNECT

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

"On June 27, 2018, the Agency [Texas Department of State Health Services] was notified by the licensee's corporate radiation safety officer (CRSO) that one of his radiography crew had experienced a source disconnect. The crew was using a QSA 880D exposure device containing a 113.1 Curie iridium - 192 source. After completing the first shot on a new location on the pipeline, the crew could not get the source to return to the exposure device. The crew contacted the CRSO and set up new barriers at 2 millirem. The CRSO and a second individual qualified for source retrieval arrived at the site at 1743 hours. The retrieval team (RT) surveyed the guide tube and determined the source was in the collimator. The RT removed the guide tube from the exposure device and removed the camera from the area. Using a set of long tongs, the guide tube was removed from the pipe and the source slid down the guide tube until the connector was exposed. They could see the drive cable had broken near the connector. The source was shielded with bags of lead shot. The CRSO disconnected the broken drive cable from the source pigtail and connected the pigtail to a new drive cable that had been installed on the camera. The source was retracted to the shielded position in the camera. The camera and crank out device and drive cable will be sent to the manufacturer for inspection. No overexposures occurred as a result of this event. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident # - 9590

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Agreement State Event Number: 53480
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: WOOD MATERIAL
Region: 4
City: NEW ORLEANS   State: LA
County: JEFFERSON
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: KENNETH MOTT
Notification Date: 06/29/2018
Notification Time: 22:31 [ET]
Event Date: 06/29/2018
Event Time: 00:00 [CDT]
Last Update Date: 07/03/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN ALEXANDER (R4DO)
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 AND RECOVERED RADIATION DEVICE

The following report was received from the State of Louisiana via phone:

On June 29, 2018 the Louisiana Radiation Protection Division was notified that an employee of Wood Material (a dredging company) stole a radiation device. The radiation device was subsequently sold by the employee to the ERM Southern Recycling center. The recycling center identified and recovered the device. The recycling center then performed a leak test on the device to confirm that the device was not leaking. The device was then isolated and secured in a drum by the recycling center.

The device is manufactured by Ronan Engineering and has a serial number of 211023A, but the activity is not known at this time.

A police report was filed on the employee who stole the device.

Louisiana has notified the NRC regional office.

* * * UPDATE ON 7/3/18 AT 0923 EDT FROM JAMES PATE TO BETHANY CECERE * * *

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

"The gauge was a Ronan Engineering Flow Meter Gauge Model RLLI, Device S/N: 211023A, Source Model Number: CDC.700, Isotope: Cs-137 with Activity: 0.90 mCi.

"The gauge was stolen by an employee from Wood Materials, 6148 River Road, New Orleans 70123. A police report was made & filed. The employee confessed to scraping the gauge for scrap metal. Employee terminated.

"The gauge is secure at this time. Enforcement action will be taken on the licensee of the gauge for not securing the gauge. This matter is considered closed out."

Notified the R4DO (Miller), NMSS Events, and ILTAB.

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

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Power Reactor Event Number: 53491
Facility: BYRON
Region: 3     State: IL
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MACE DAVIS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/06/2018
Notification Time: 15:36 [ET]
Event Date: 07/06/2018
Event Time: 12:01 [CDT]
Last Update Date: 07/06/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

TRANSFORMER FAILURE CAUSES LOSS OF OFFSITE POWER TO UNIT 2

"At 1201 [CDT], Station Auxiliary Transformer 242-2 experienced a bushing failure, resulting in a loss of offsite power to Unit 2. The 2A and 2B Diesel Generators started and sequenced loads onto the Unit 2 ESF buses appropriately. All other buses normally powered from the Station Auxiliary Transformers automatically transferred to the Unit Auxiliary Transformers. ESF Bus 241 and 242 Undervoltage Relays actuated to start the Diesel Generators and the 2A Auxiliary Feedwater Pump started on the 2A Diesel Generator sequencer. ESF Battery Charger 212 tripped at the same time, which was an unexpected condition. DC Bus 212 was cross-tied with DC Bus 112.

"This notification is being made under 10 CFR 50.72(b)3(iv)(A) due to the actuation of both Unit 2 Diesel Generators and the 2A Auxiliary Feedwater Pump.

"The NRC Senior Resident Inspector has been notified."

Currently, offsite power was restored via the Unit 1 Unit Auxiliary Transformer. Both Unit 2 Emergency Diesel Generators have been secured. DC Busses are still cross-tied.

The licensee is currently in a 72-hour shutdown action statement for the loss of offsite power and a 7-day action statement for having the Unit 2 DC Bus cross-tied to Unit 1.

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Power Reactor Event Number: 53493
Facility: CALVERT CLIFFS
Region: 1     State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DANIEL GENEVA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/07/2018
Notification Time: 08:29 [ET]
Event Date: 07/07/2018
Event Time: 02:42 [EDT]
Last Update Date: 07/07/2018
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
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

CONTROL ROOM VENTILATION INOPERABLE

"At 0242 EDT, the CCNPP (dual unit, single control room) control room supply damper failed shut. This rendered the Unit 1 and Unit 2 control room ventilation inoperable and the appropriate LCOs were entered.

"At 0249, control room ventilation was restored to service and the appropriate LCOs were exited. This is being reported under 10 CFR 50.72(b)(3)(v)(D)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 53496
Facility: DUANE ARNOLD
Region: 3     State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: SCHUYLER VREEMAN
HQ OPS Officer: STEVEN VITTO
Notification Date: 07/09/2018
Notification Time: 16:25 [ET]
Event Date: 07/09/2018
Event Time: 13:34 [CDT]
Last Update Date: 07/09/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
MARK JEFFERS (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 97 Power Operation 97 Power Operation

Event Text

SECONDARY CONTAINMENT INOPERABLE

"At approximately 1334 CDT on 7/9/18, both doors of a Secondary Containment Airlock were reported to be open simultaneously for a period of less than 3 seconds. The brief time that the doors were simultaneously open constituted an inoperable condition of Secondary Containment. Secondary Containment was immediately restored to operable by closing the airlock doors. Subsequently, the airlock interlock was verified to operate correctly.

"This event is being reported pursuant of 10 CFR 50.72(b)(3)(v)(C). The Senior NRC Resident Inspector has been notified."

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Power Reactor Event Number: 53497
Facility: BROWNS FERRY
Region: 2     State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANTHONY ALSUP
HQ OPS Officer: STEVEN VITTO
Notification Date: 07/09/2018
Notification Time: 17:01 [ET]
Event Date: 07/09/2018
Event Time: 09:58 [CDT]
Last Update Date: 07/09/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RANDY MUSSER (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

HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE

"On 07/09/2018 at 1111 CDT, Browns Ferry Unit 1 Operators identified U1 High Pressure Cooling Injection system steam supply valves were isolated. After reviewing ICS [Integrated Computer System], Operations determined isolation occurred at 0958 CDT during performance of surveillance testing. The Browns Ferry Nuclear Plant Unit 1 High Pressure Coolant Injection (HPCI) system was declared inoperable at 0958 CDT due to an inadvertent isolation that occurred during testing. During performance of surveillance procedure 1-SR-3.3.6.1.2(3B) HPCI System Steam Supply Low Pressure Functional test, an erroneous signal was induced causing actuation of primary containment isolation system group IV (i.e., HPCI Isolation). Technical Specification 3.5.1, ECCS-Operating, Condition C was entered as a result of the inoperable HPCI system. This constitutes an unplanned HPCI system inoperability and requires an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(v)(D). The erroneous signal was cleared and the HPCI isolation was reset. Upon reset of the isolation signal, the HPCI system was returned to available status. The HPCI system was unavailable for 2 hours and 55 minutes, however the HPCI system remains inoperable.

"There was no impact to the health and safety of the public or plant personnel as a result of this condition.

"The NRC Resident Inspector has been notified.

"A condition report has been entered into the Licensee's Corrective Action Program to capture this event."

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Power Reactor Event Number: 53498
Facility: MCGUIRE
Region: 2     State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC WILKINSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/09/2018
Notification Time: 18:23 [ET]
Event Date: 07/09/2018
Event Time: 11:55 [EDT]
Last Update Date: 07/09/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RANDY MUSSER (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

UNPLANNED LOSS OF TECHNICAL SUPPORT CENTER (TSC) VENTILATION

"On July 9, 2018, at 1155 hours [EDT], while testing the TSC Ventilation System, an equipment malfunction occurred that resulted in an unplanned loss of TSC ventilation functionality/habitability for greater than seventy-five minutes.

"If an emergency had been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures. If relocation of the TSC had been necessary, the Emergency Coordinator would have relocated the TSC staff to an alternate location in accordance with applicable site procedures. The TSC ventilation system has been placed in an interim configuration that restored functionality and habitability. Additional maintenance is planned to promptly resolve the malfunctioning equipment.

"This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the equipment malfunction affected the functionality of an emergency response facility.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."

The equipment malfunction (a failed solenoid valve) resulted in the loss of the ability to pressurize and filter the air in the TSC.

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Power Reactor Event Number: 53499
Facility: VOGTLE
Region: 2     State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: DANIEL MICKINAC
HQ OPS Officer: STEVEN VITTO
Notification Date: 07/09/2018
Notification Time: 20:05 [ET]
Event Date: 07/09/2018
Event Time: 15:15 [EDT]
Last Update Date: 07/09/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RANDY MUSSER (R2DO)
FFD GROUP (EMAIL)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Under Construction 0 Under Construction
4 N N 0 Under Construction 0 Under Construction

Event Text

CONTRACTOR SUPERVISOR TESTS POSITIVE ON FITNESS FOR DUTY TEST

"At 1515 [EDT] on July 9, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for a controlled substance during a for cause Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified."


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