Event Notification Report for August 05, 2020
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U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
| 54778 | 54802 | 54812 | 54816 |
| Agreement State | Event Number: 54778 |
| Rep Org: CALIFORNIA RADIATION CONTROL PRGM Licensee: RMA Group Region: 4 City: Rancho Cucamonga State: CA County: License #: 071420 Agreement: Y Docket: NRC Notified By: L. Robert Greger HQ OPS Officer: Ossy Font |
Notification Date: 07/14/2020 Notification Time: 23:51 [ET] Event Date: 07/13/2020 Event Time: 06:00 [PDT] Last Update Date: 07/15/2020 |
| Emergency Class: Non Emergency 10 CFR Section: Agreement State |
Person (Organization): VINCENT GADDY (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL) - CNSNS (MEXICO) (EMAIL) |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
| AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE The following was received from the California Department of Public Health via email: "A Troxler moisture density gauge (model 3430, serial # 31716) was reported stolen Monday morning at approximately 0600 PDT from the bed of an employee's vehicle while the vehicle was parked for 1-2 hours outside the employee's residence in Moreno Valley, CA. The gauge contains approximately 0.3 GBq (8 mCi) of Cs-137 and 1.50 GBq (40 mCi) of Am-241. The gauge was reportedly picked up earlier that morning at the licensee's office in Rancho Cucamonga, and left appropriately chained/locked in the back of the vehicle at the employee's residence before leaving for a work location. The theft was reported to the Moreno Valley Police Department (police report #MV201950058 taken by Officer Flores). A reward will be advertised for the return of the gauge." California 5010 NUMBER: 071420 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 |
| 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 | |||||||
| 1 | A/R | Y | 20 | Power Operation | 0 | 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). * * * UPDATE ON 8/4/2020 AT 1534 EDT FROM JOSEPH ELKINS TO ANDREW WAUGH * * * "At 1454 EDT on August 4, 2020, the Unusual Event was exited when offsite power was restored to Unit 1. "Per design, when the loss of offsite power to Unit 1 occurred, all four emergency diesel generators (EDGs) started and EDGs 1 and 2 properly suppled emergency buses 1 and 2. Since Unit 2 was not affected by the loss of power, EDGs 3 and 4 ran unloaded. "With restoration of offsite power to Unit 1, EDG 2 has been secured. EDGs 1, 3, and 4 are being secured as required by plant operating procedure." Notified R2DO (Inverso), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA OC, DHS NICC WO, CISA IOCC (email), DHS SWO (email), FEMA NWC (email), FEMA Ops Center (email), FEMA-NRCC-sasc (email), NRCC THD Desk (email), NuclearSSA (email). ******************************************************************************************************************************** |
| Power Reactor | Event Number: 54816 |
| Facility: Millstone Region: 1 State: CT Unit: [] [2] [] RX Type: [1] GE-3,[2] CE,[3] W-4-LP NRC Notified By: Michael Watson HQ OPS Officer: Andrew Waugh |
Notification Date: 08/04/2020 Notification Time: 22:43 [ET] Event Date: 08/04/2020 Event Time: 17:45 [EDT] Last Update Date: 08/04/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(3)(v)(A) - Pot Unable To Safe Sd 50.72(b)(3)(v)(B) - Pot Rhr Inop 50.72(b)(3)(v)(D) - Accident Mitigation |
Person (Organization): FRANK ARNER (R1DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 2 | N | Y | 100 | Power Operation | 75 | Power Operation |
Event Text
| BOTH SERVICE WATER HEADERS DECLARED INOPERABLE On 8/4/20, at 1745 EDT, Millstone Unit 2 entered technical specification (TS) 3.0.3 due to both service water headers being declared inoperable because strainer differential pressures (D/Ps) were greater than 9 psid. The high service water strainer D/P was the result of heavy debris impingement caused by tropical storm Isaias. To reduce heat loads and service water flow, Unit 2 reduced power to 75 percent. One service water header was restored to operable at 1816 EDT, at which time TS 3.0.3 was exited. At 1843 EDT both service water headers were declared operable. The NRC Resident Inspector has been notified. |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021