Event Notification Report for February 16, 2021

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/15/2021 - 02/16/2021

EVENT NUMBERS
55096 55097 55104
Fuel Cycle Facility
Event Number: 55096
Facility: Global Nuclear Fuel - Americas
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion (Uf6 To Uo2)
Leu Fabrication
Lwr Commerical Fuel
Region: 2
City: Wilmington   State: NC
County: New Hanover
License #: SNM-1097
Docket: 07001113
NRC Notified By: Phillip Ollis
HQ OPS Officer: Michael Bloodgood
Notification Date: 02/07/2021
Notification Time: 14:48 [ET]
Event Date: 02/06/2021
Event Time: 21:35 [EST]
Last Update Date: 02/07/2021
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
Person (Organization):
MARK MILLER (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
REPORT OF OFFSITE NOTIFICATION DUE TO IMPAIRMENT OF FIRE SUPRESSION SYSTEM

"At approximately 2135 (EST) on February 6th, 2021, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system encompassing the Fuel Manufacturing Operation (FMO) was impaired due to the failure of the diesel fire pump controller. The diesel fire pump can be activated manually but not automatically. The electric fire pump remains fully operational and available to perform its safety function. Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."

NRC Region 2 and the State of North Carolina will be notified by the licensee.


Agreement State
Event Number: 55097
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: Phillips 66 Company Alliance Refinery
Region: 4
City: Belle Chasse   State: LA
County:
License #: LA-5199-L01B, Amendment 35, AI#2418
Agreement: Y
Docket:
NRC Notified By: James Pate
HQ OPS Officer: Harry Freeman
Notification Date: 02/08/2021
Notification Time: 11:58 [ET]
Event Date: 01/12/2021
Event Time: 00:00 [CST]
Last Update Date: 02/08/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
JOHN DIXON (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
GRETCHEN RIVERA-CAPELLA (NMSS DAY)
Event Text
AGREEMENT STATE REPORT - OVEREXPOSURE TO MEMBER OF PUBLIC

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

"A written notification was received on February 8, 2021 at 09:15 am, which stated that on January 12, 2021, a contract employee was sanding and painting on the 491-V-44 ASO Washer Vessel, near two permitted nuclear level gauges. Estimated exposure time was forty minutes for the hand and forearm. The gauges were two Texas Nuclear Model 5206, 500 mCi Cs-137 (not decay corrected), gauge serial numbers B364 & source s/n GG-5325 and gauge s/n B365 & source s/n GG-5917. The exposure was calculated for extremities of hand and forearm to be 2,423 mrem. The dose to the whole body has not been calculated at this time and is in the process of being done."

Louisiana Incident Number : LA20210002


Power Reactor
Event Number: 55104
Facility: South Texas
Region: 4     State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Ron Rohan
HQ OPS Officer: Thomas Kendzia
Notification Date: 02/15/2021
Notification Time: 10:06 [ET]
Event Date: 02/15/2021
Event Time: 05:26 [CST]
Last Update Date: 02/15/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
DIXON, JOHN (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 100 Power Operation 0 Hot Standby
Event Text
EN Revision Imported Date: 2/16/2021

EN Revision Text: AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL

"At 0526 [CST] on 02/15/2021, Unit 1 automatically tripped due to low steam generator levels. The low steam generator levels were due to loss of Feedwater pumps 11 and 13 (cause unknown).

"Auxiliary Feedwater and Feedwater Isolation actuated as designed. All Control and Shutdown Rods fully inserted. No primary or secondary relief valves opened. There were no electrical problems. Normal operating temperature and pressure (NOT/NOP) is 567 degrees F and 2235 psig.

"There were no significant TS LCOs entered.

"This event was not significant to the health and safety of the public based on all safety systems performed as designed. Unit 2 was not affected. Decay heat removal is being controlled via Steam Dumps. [Auxiliary Feedwater is supplying water to the Steam Generators.] Offsite power is in the normal electrical lineup.

"The NRC Resident inspector has been notified."

Unit 2 was not affected and remains at 100% power.

Page Last Reviewed/Updated Tuesday, February 16, 2021