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Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for February 5, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/02/2018 - 02/05/2018

** EVENT NUMBERS **


53182 53186 53196

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Agreement State Event Number: 53182
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: EXXON MOBIL OIL CORPORATION
Region: 4
City: BEAUMONT State: TX
County:
License #: 00603
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JEFF HERRERA 		Notification Date: 01/25/2018
Notification Time: 17:16 [ET]
Event Date: 01/25/2018
Event Time: [CST]
Last Update Date: 01/25/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
 Person (Organization):
GREG PICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - TWO NUCLEAR GAUGES FOUND WITH SHUTTERS STUCK OPEN

The following report was received from the Texas Department of State Health Services via email:

"On January 25, 2018, the Agency [Texas Department of State Health Services] was notified that two of the licensee's Ohmart-Vega Model SHLG fixed nuclear gauges were found to have shutters stuck in the open position during preventative maintenance. These gauges normally operate with the shutter in the open position. There is no increased risk of exposure to any member of the public or licensee employees. Coordination is underway between the licensee, the service company, and the manufacturer for the gauges to be removed and returned to the manufacturer for repair or disposal.

"Source Information:
SN: 3253CM 2,000 milliCuries cesium-137
SN: 4021CM 2,000 milliCuries cesium-137"

Texas Incident #: I-9533

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Agreement State Event Number: 53186
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: PACIFIC AURORA, LLC
Region: 4
City: Aurora State: NE
County:
License #: GL0704
Agreement: Y
Docket:
NRC Notified By: MALISA MCCOWN
HQ OPS Officer: BETHANY CECERE 		Notification Date: 01/26/2018
Notification Time: 15:11 [ET]
Event Date: 01/10/2018
Event Time: [CST]
Last Update Date: 01/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
 Person (Organization):
GREG PICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGN

The following information was received via email:

"On January 12, 2018, GL0704 Pacific Aurora, LLC (formerly Aurora Coop West) contacted [the Nebraska Department of Health and Human Services (NEDHHS)] regarding their overdue Annual Invoice and Current Inventory. The Environmental Manager [EM] noted that Aurora Coop West was bought by Pacific Ethanol on December 16, 2017 and has combined into one entity: Pacific Aurora, LLC. The EM indicated he was unable to locate several of the tritium exit signs on the inventory but would attempt location for one additional week. NEDHHS Office of Radiological Health received written notification on January 25, 2018 of one lost/missing tritium exit sign. The EM assumes the sign may have been moved during a renovation. Should the sign be located, the EM has indicated they will contact [NEDHHS].

"Device Name: Radioluminescent Sign
Manufacturer: Safety Light Corp.
Model Number: SLX60
Serial Number: 418040
Radionuclide: H-3
Activity: 11.5 Ci."

NEDHHS Item Number: NE180002

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

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Power Reactor Event Number: 53196
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN McILNAY
HQ OPS Officer: MARK ABRAMOVITZ 		Notification Date: 02/04/2018
Notification Time: 12:00 [ET]
Event Date: 02/04/2018
Event Time: 04:45 [EST]
Last Update Date: 02/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
 Person (Organization):
JAMIE HEISSERER (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

FAILURE OF CONTAINMENT PENETRATION THERMAL RELIEF CHECK VALVES TO MEET SURVEILLANCE ACCEPTANCE CRITERIA

"At 0445 [EST] on February 4, 2018, Watts Bar Unit 1 entered Technical Specification 3.6.1 condition A and 3.6.3 condition A.1 and A.2 due to inoperable containment penetration thermal relief check valves 1-CKV-31-3407 and 1-CKV-31-3421 associated with one train of the Containment Incore Instrument Room Chiller system. During surveillance testing, the thermal relief check valves failed to open and pass flow as required by acceptance criteria. The two penetrations were subsequently drained and isolated in accordance with the surveillance procedure to remove any thermal expansion concerns. Technical Specification 3.6.1 was exited February 4, 2018 at 0512 once the two penetrations were drained and isolated.

"The purpose of the thermal relief check valves is to allow flow from an isolated penetration back into the upstream containment piping to prevent over-pressurization due to thermal expansion. Over-pressurization of an isolated containment penetration could potentially cause the penetration or both of the isolation valves to fail and provide a direct flow path to the environment from the potentially contaminated containment atmosphere under certain Design Basis Accidents. Therefore, failure of the thermal relief check valves to open could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(C).

"NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Thursday, March 25, 2021

Page Last Reviewed/Updated Thursday, March 25, 2021