Event Notification Report for March 06, 2019
U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
53898 | 53911 |
Agreement State | Event Number: 53898 |
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES Licensee: BRASKEM AMERICA, INC Region: 4 City: FREEPORT State: TX County: License #: Licen-RAM-L06443 Agreement: Y Docket: NRC Notified By: CHRIS MOORE HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/25/2019 Notification Time: 15:43 [ET] Event Date: 02/25/2019 Event Time: 00:00 [CST] Last Update Date: 02/25/2019 |
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE | Person (Organization): RICK DEESE (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
AGREEMENT STATE REPORT - GAUGE SHUTTER FAILURE The following information was received via e-mail: "On February 25, 2019, the Agency [Texas Department of State Health Services] received a report from the licensee's technical representative stating that the shutter on an Ohmart Vega model SH-F1 gauge, containing a 50 millicurie cesium-137 source, failed to shut during maintenance when the handle broke off. Open is the normal operation position of the gauge shutter. No licensee employee received any exposure as a result of this event. The gauge will be repaired in September 2019 during an outage. Additional information will be sent in accordance with SA-300." Texas Incident #: 9659 |
Power Reactor | Event Number: 53911 |
Facility: BRUNSWICK Region: 2 State: NC Unit: [] [2] [] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: RICHARD BARRETT HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/05/2019 Notification Time: 12:46 [ET] Event Date: 03/05/2019 Event Time: 05:35 [EST] Last Update Date: 03/05/2019 |
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION | Person (Organization): STEVE ROSE (R2DO) |
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
2 | N | N | 0 | Refueling | 0 | Refueling |
Event Text
AUTOMATIC ACTUATION OF THE PRIMARY CONTAINMENT ISOLATION SYSTEM "At 05:35 Eastern Standard Time (EST) on March 5, 2019, with Unit 2 in Mode 5 at 0% power, an actuation of the Primary Containment Isolation System occurred during hydrolazing of the reactor water level variable leg instrumentation line nozzle N011B in the reactor cavity. The hydrolazing activity caused low reactor water level to be sensed on Division II of the shutdown range level instrumentation. Per design, the low level 1 signal resulted in Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations. "This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Primary Containment Isolation System. "There was no impact on the health and safety of the public or plant personnel. The Group 8 was reset and shutdown cooling was restored at approximately 05:45 EST. "The safety significance of this event was minimal. Although there was a brief interruption of the shutdown cooling, the Residual Heat Removal (RHR) shutdown cooling system operation was restored in approximately 10 minutes without extensive troubleshooting or maintenance, and remained operable. The RHR shutdown cooling system is not credited in any Updated Final Safety Analysis Report Chapter 6 or 15 accidents or transients. "The NRC Resident Inspector has been notified." |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021