Event Notification Report for March 25, 2020
|
U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
| 54586 | 54603 | 54605 | 54607 |
| Agreement State | Event Number: 54586 |
| Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES Licensee: XCEL NDT LLC Region: 4 City: VAN HORN State: TX County: License #: RAM - L07039 Agreement: Y Docket: NRC Notified By: KAREN BLANCHARD HQ OPS Officer: THOMAS KENDZIA |
Notification Date: 03/17/2020 Notification Time: 10:39 [ET] Event Date: 03/16/2020 Event Time: 00:00 [CDT] Last Update Date: 03/17/2020 |
| Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE |
Person (Organization): NEIL O'KEEFE (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
| AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE GUIDE TUBE DAMAGED The following was received from the State of Texas via email: "On March 17, 2020, the Texas of Department of State Health (Agency) was notified that on March 16, 2020, one of the licensee's radiography crews was performing work at a temporary job site near Van Horn, Texas, when a piece of pipe fell onto the guide tube and they were unable to retract the source. A person authorized for source retrieval was dispatched and was able to retrieve the source and secure it inside the exposure device. The source retriever's pocket dosimeter had a reading of 155 millirem at the conclusion of the retrieval. The licensee will send the retriever's and the crew's dosimetry badges for processing. There were no other exposures as a result of this event. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300. "Device Info: QSA Delta 880, SN: D5797, Source Info: 59.4 curies, Iridium-192, SN: 93949G" Texas Incident Number: 9752 |
| Power Reactor | Event Number: 54603 |
| Facility: BRUNSWICK Region: 2 State: NC Unit: [1] [] [] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: WILLIAM ROBERTS HQ OPS Officer: BETHANY CECERE |
Notification Date: 03/24/2020 Notification Time: 16:02 [ET] Event Date: 03/24/2020 Event Time: 12:05 [EDT] Last Update Date: 03/24/2020 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization): MARK MILLER (R2DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | M/R | Y | 22 | Power Operation | 0 | Hot Shutdown |
Event Text
| TECHNICAL SPECIFICATION-REQUIRED SHUTDOWN DUE TO UNIDENTIFIED LEAKAGE "At 1205 Eastern Daylight Time (EDT) on March 24, 2020, a Technical Specification-required shutdown was initiated on Unit 1 due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours. "It was expected that the leakage would not have been reduced to within limits within the required Technical Specification completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i). "Reactor water level reached low level 1 (LL1) following the reactor shutdown. The LL1 signal causes 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. The LL1 isolations occurred as designed; the Group 8 valves were closed at the time of the event. Due to the valid Primary Containment Isolation System (PCIS) actuation, this event is also being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A). "Unit 2 is not affected by this event. "There was no impact on the health and safety of the public or plant personnel. "The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 54605 |
| Facility: SOUTH TEXAS Region: 4 State: TX Unit: [1] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: MICHAEL CHANDLER HQ OPS Officer: KERBY SCALES |
Notification Date: 03/24/2020 Notification Time: 17:15 [ET] Event Date: 03/24/2020 Event Time: 10:46 [CDT] Last Update Date: 03/24/2020 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization): RAY KELLAR (R4DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | N | N | 0 | Defueled | 0 | Defueled | |||||||
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
Event Text
| SPECIFIED SYSTEM ACTUATION - AUTO START EMERGENCY DIESEL GENERATORS "At 1046 CDT on 3/24/2020, with Unit 1 defueled and Unit 2 in Mode 1 at 100 percent power, the South Texas Project (STP) South switchyard electrical bus was deenergized. This resulted in a loss of power to Standby Transformer 2 which was supplying power to the Engineered Safety Features (ESF) 4160v busses for Unit 1 A- and C-Trains, and Unit 2 B-Train. Emergency Diesel Generators (EDGs) 11, 13, and 22 automatically started in response to the undervoltage condition. "The cause for the loss of the South switchyard electrical bus was an error in relay testing in the switchyard. "This event is reportable under 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in the valid actuation of emergency AC electrical power systems (50.72(b)(3)(iv)(B)(8)) as well as the Unit 1 A- and C-Train and Unit 2 B-Train Reactor Containment Fan Coolers (50.72(b)(3)(iv)(B)(7)) and Unit 2 B-Train Auxiliary Feedwater pump (50.72(b)(3)(iv)(B)(6)). "There was no impact on the health and safety of the public or plant personnel. "The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 54607 |
| Facility: SALEM Region: 1 State: NJ Unit: [1] [] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: JASON MORGAN HQ OPS Officer: BRIAN LIN |
Notification Date: 03/25/2020 Notification Time: 03:30 [ET] Event Date: 03/25/2020 Event Time: 00:56 [EDT] Last Update Date: 03/25/2020 |
| 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): CHRISTOPHER CAHILL (R1DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | M/R | Y | 17 | Power Operation | 0 | Hot Standby |
Event Text
| MANUAL TRIP DUE TO FAILURE OF A ROD CONTROL MOTOR GENERATOR "At 0056 EDTon March 25, 2020, with Unit 1 at 17 percent power during a unit power ascension, the reactor was manually tripped due to the failure of the 11 Rod Control Motor Generator caused by a malfunction of its associated Voltage Regulator. The trip was not complex, with all systems responding normally post-trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Atmospheric Steam Dumps and Auxiliary Feedwater System. Salem Unit 2 was not affected. "Due to the actuation of the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B), This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. "There was no impact to the health and safety of the public or plant personnel. "The NRC Resident lnspector has been notified." |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021