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Event Notification Report for September 13, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
9/12/2019 - 9/13/2019

** EVENT NUMBERS **

Fuel Cycle Facility	Event Number: 54255
Facility: NUCLEAR FUEL SERVICES INC. RX Type: URANIUM FUEL FABRICATION Comments: HEU CONVERSION & SCRAP RECOVERY NAVAL REACTOR FUEL CYCLE LEU SCRAP RECOVERY Region: 2 City: ERWIN State: TN County: UNICOI License #: SNM-124 Docket: 07000143 NRC Notified By: RON RICE HQ OPS Officer: JEFFREY WHITED	Notification Date: 09/04/2019 Notification Time: 16:55 [ET] Event Date: 09/04/2019 Event Time: 03:46 [EDT] Last Update Date: 09/04/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 70.50(b)(1) - UNPLANNED CONTAMINATION	Person (Organization): SCOTT SHAEFFER (R2DO) NMSS_EVENTS_NOTIFICATION (EMAIL) - FUELS GROUP (EMAIL)

Event Text

UNPLANNED CONTAMINATION EVENT

The following was received via e-mail:

"On September 4, 2019, at approximately 0346 EDT, a glass component failed, resulting in an unplanned contamination event. The release was limited to an area inside of the Radiologically Controlled Area. This area is designed for radiological work. There has been no personnel contamination. Airborne radioactivity samples are below action levels. Cleanup and Decontamination activities were safely and promptly initiated, but due to the complexity and space constraints of the system components, normal access to the area is not likely be restored within 24 hours. There has been no exposures or releases to the environment or public.

"The licensee has notified the NRC Resident Inspector."

Power Reactor	Event Number: 54271
Facility: GRAND GULF Region: 4 State: MS Unit: [1] [] [] RX Type: [1] GE-6 NRC Notified By: GERRY ELLIS HQ OPS Officer: JEFF HERRERA	Notification Date: 09/12/2019 Notification Time: 00:49 [ET] Event Date: 09/11/2019 Event Time: 17:19 [CDT] Last Update Date: 09/12/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL	Person (Organization): RYAN ALEXANDER (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

Power Operation

Event Text

PRIMARY CONTAINMENT AIRLOCK DOOR NOT IN FULLY SEATED POSITION

"On September 11, 2019 at 1719 CDT, plant personnel identified a condition in which the 208 foot elevation inner primary containment airlock door was not in its fully seated and latched position while the 208 foot elevation outer primary containment airlock door was opened. The 208 foot elevation outer containment airlock door was subsequently closed by the individual exiting the area. The time that both 208 foot elevation containment airlock doors were not in their fully seated and latched positions was less than 1 minute. Following this occurrence, maintenance personnel inspected the 208 foot elevation inner containment airlock door and re-positioned this door to its fully seated and latched position. There was no radioactive release as a result of this event.

"This condition requires an 8-hour non-emergency notification in accordance with 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material.

"The NRC Resident Inspector has been notified."

Power Reactor	Event Number: 54272
Facility: PALO VERDE Region: 4 State: AZ Unit: [] [] [3] RX Type: [1] CE,[2] CE,[3] CE NRC Notified By: JASON HILL HQ OPS Officer: JEFF HERRERA	Notification Date: 09/12/2019 Notification Time: 03:25 [ET] Event Date: 09/11/2019 Event Time: 18:24 [MST] Last Update Date: 09/12/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): RYAN ALEXANDER (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

100

Power Operation

100

Power Operation

Event Text

MAIN STEAM LINE RADIATION MONITOR COMMUNICATION FAILURE

"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.

"Radiation monitor RU-140 (#2 Steam Generator Main Steam Line radiation monitor) experienced a communication failure on both ports A and B. The RU-140 monitor is off line and non-functional at this time.

"At least one channel of RU-140 is required to perform a Steam Generator Tube Rupture (SGTR) dose assessment. This represents an unplanned loss of radiological assessment capability for the inability to perform dose assessments that require the radiation monitor. The ability to make emergency classifications from other radiological data collection methods such as field sampling remains available. Actions have been initiated to restore the radiation monitor.

"The NRC Resident Inspector has been informed."

Fuel Cycle Facility	Event Number: 54273
Facility: FRAMATOME ANP RICHLAND RX Type: URANIUM FUEL FABRICATION Comments: LEU CONVERSION FABRICATION & SCRAP RECOVERY COMMERCIAL LWR FUEL Region: 2 City: RICHLAND State: WA County: BENTON License #: SNM-1227 Docket: 07001227 NRC Notified By: CALVIN MANNING HQ OPS Officer: OSSY FONT	Notification Date: 09/12/2019 Notification Time: 20:08 [ET] Event Date: 09/12/2019 Event Time: 13:35 [PDT] Last Update Date: 09/12/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS	Person (Organization): FRANK EHRHARDT (R2DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

UNPLANNED SURFACE CONTAMINATION

"Heeled 30B UF6 Cylinders arrived at Framatome at approximately 1235 (PDT) on September 12, 2019. The cylinders were inspected/surveyed for loose surface contamination at approximately 1335 (PDT). Two cylinders were identified to have greater than 24 dpm/cm2 alpha contamination limit and the 240 dpm/cm2 beta/gamma contamination limit set by DOT [Department of Transportation] and NRC. Each cylinder contained contamination on and around the valve cover. One cylinder contained 250 dpm/cm2 alpha and 2,500 dpm/cm2 beta/gamma, and another 35-40 dpm/cm2 alpha and 2,000 dpm/cm2 beta/gamma.

"The top of the cylinders have been decontaminated and the valve covers have been removed and bagged.

"[Title] 10 CFR 20.1906 requires immediate notification of the operations center and carrier in the event of contamination in excess of the limits specified in 49 CFR 173.443 during inspections required by 10 CFR 71.87."

There were no exposures to personnel and no contamination was found on the transport vehicle. The licensee is attempting to contact Westinghouse from where the cylinders originated.

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