Event Notification Report for August 04, 2020

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
8/3/2020 - 8/4/2020

** EVENT NUMBERS **

Fuel Cycle Facility	Event Number: 54801
Facility: Westinghouse Electric Corporation RX Type: Uranium Fuel Fabrication Comments: Leu Conversion (Uf6 To Uo2) Commercial Lwr Fuel Region: 2 City: Columbia State: SC County: Richland License #: SNM-1107 Docket: 07001151 NRC Notified By: Nancy Parr HQ OPS Officer: Brian P. Smith	Notification Date: 07/26/2020 Notification Time: 08:10 [ET] Event Date: 07/25/2020 Event Time: 11:00 [EDT] Last Update Date: 07/26/2020
Emergency Class: Non Emergency 10 CFR Section: 70.50(b)(3) - Med Treat Involving Contam	Person (Organization): MARK MILLER (R2DO) NMSS_EVENTS_NOTIFICATION (EMAIL) JEFFERY GRANT (IRD) ANDREA KOCK (NMSS)

Event Text

CONTAMINATED INJURED EMPLOYEE TAKEN TO HOSPITAL

The following was received via email from Westinghouse:

"On July 25, 2020, at approximately 1100 EDT, a Westinghouse employee performing routine work in the pelleting area passed out due to a personal medical emergency. Site emergency first responders responded per plant procedures and training until Emergency Medical Services (EMS) personnel arrived. The employee was transported to an offsite medical facility accompanied by a plant health physics technician due to the potential for radioactive contamination based on the work location of the employee.

"There was no release to the environment and no process or plant equipment involved. Surveys taken at the hospital and of all emergency response equipment and response personnel revealed no contamination. [All removable contamination from the Westinghouse employee was returned to the facility.] The Columbia plant is a licensed Part 70 facility subject to 10CFR70 Subpart H."

The licensee has notified state and local county governments.

Agreement State	Event Number: 54802
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL Licensee: Unknown Region: 1 City: Jacksonville State: FL County: License #: Agreement: Y Docket: NRC Notified By: David Pieski HQ OPS Officer: Kerby Scales	Notification Date: 07/27/2020 Notification Time: 13:05 [ET] Event Date: 07/27/2020 Event Time: 00:00 [EDT] Last Update Date: 07/27/2020
Emergency Class: Non Emergency 10 CFR Section: Agreement State	Person (Organization): BRICE BICKETT (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL)

Event Text

AGREEMENT STATE REPORT - TROXLER GAUGE ON EBAY

The following was received from the Florida Bureau of Radiation Control (BRC) via email:

The RSO [Radiation Safety officer] of Laboratory Technical Services, Milton, FL (License number 3734-1) contacted this office [BRC] at 1200 [EDT] to report a model 3450 Troxler Gauge inappropriately advertised on ebay. The Troxler location is advertised in Jacksonville, FL. Acting IRC [Incident Response Coordinator] contacted ebay at 1237 to report the prohibited item.

Florida Incident Number: FL20-086

Power Reactor	Event Number: 54812
Facility: Brunswick Region: 2 State: NC Unit: [1] [] [] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: Benjamin Williams HQ OPS Officer: Bethany Cecere	Notification Date: 08/03/2020 Notification Time: 23:31 [ET] Event Date: 08/03/2020 Event Time: 23:12 [EDT] Last Update Date: 08/04/2020
Emergency Class: Unusual Event 10 CFR Section: 50.72(a) (1) (i) - Emergency Declared 50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation	Person (Organization): MARK MILLER (R2DO) LAURA DUDES (R2 RA) HO NIEH (NRR) SILAS KENNEDY (IRD) CHRIS MILLER (NRR EO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

A/R

Power Operation

Hot Shutdown

Event Text

UNUSUAL EVENT DECLARED DUE TO A LOSS OF OFFSITE POWER

At 2312 EDT, on August 3, 2020, Brunswick Unit 1 declared an Unusual Event due to a loss of offsite power. The unit was at approximately 20 percent power and was not synced to the grid when the unit automatically scrammed. All control rods fully inserted. Emergency Diesel Generators started and began powering the safety buses. Safety systems actuated as expected.

The Unit also experienced a loss of Fuel Pool Cooling and Cleanup System, but one pump was returned to service.

Unit 2 remains at 100 percent power and is unaffected.

The licensee notified State and local governments, as well as the NRC Resident Inspector.

Notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

* * * UPDATE FROM MARK TURKAL TO DONALD NORWOOD AT 0120 EDT ON 8/4/2020 * * *

"At approximately 2302 EDT, a loss of offsite power occurred on Unit 1. This resulted in a Reactor Protection System (RPS) actuation. Per design, emergency diesel generators 1 and 2 properly started and loaded to their respective emergency buses. The Reactor Core Isolation Cooling (RCIC) system was manually started and is being used to control reactor water level. The High Pressure Coolant Injection (HPCI) system was manually started and is being used for pressure control. As previously reported, an Unusual Event was declared at 2312 EDT due to the loss of offsite power. At the time of the event, Unit 1 was in the process of shutting down for maintenance associated with a ground on the main generator.

"Due to the RPS actuation while critical, this event is being reported as a four-hour, nonemergency notification per 10 CFR 50.72(b)(2)(iv)(B).

"As a result of the reactor trip, reactor water level reached low level 1 (LL1). The LL1 signal causes a Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sample isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations. The LL1 isolations occurred as designed; the Group 8 valves were closed at the time of the event. Per design, the loss of offsite power also caused a Group 1 (i.e., main steam isolation valve) isolations.

"Due to the Emergency Diesel Generator and Primary Containment Isolation System (PCIS) actuations, this event is also being reported as an eight-hour, nonemergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A).

"Unit 2 was not affected. There was no impact to the health and safety of the public or plant personnel. The safety significance of the event is minimal. All safety related systems operated as designed.

"Investigation of the cause of the loss of offsite power is in progress."

The licensee notified the NRC Resident Inspector. Notified R2DO (Inverso).

Page Last Reviewed/Updated Thursday, March 25, 2021