Event Notification Report for September 28, 2020
|
U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
| 54913 | 54914 | 54916 |
| Power Reactor | Event Number: 54913 |
| Facility: FitzPatrick Region: 1 State: NY Unit: [1] [] [] RX Type: [1] GE-4 NRC Notified By: Robert Graham III HQ OPS Officer: Jeffrey Whited |
Notification Date: 09/25/2020 Notification Time: 15:28 [ET] Event Date: 09/25/2020 Event Time: 12:38 [EDT] Last Update Date: 09/25/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 26.719 - Fitness For Duty |
Person (Organization): DONNA JANDA (R1DO) FFD GROUP (EMAIL) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | N | N | 0 | Refueling | 0 | Refueling |
Event Text
| FITNESS FOR DUTY REPORT A non-licensed contract supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector. |
| Part 21 | Event Number: 54914 |
| Rep Org: NUTHERM INTERNATIONAL, INC Licensee: Nutherm International, Inc. Region: 3 City: Mount Vernon State: IL County: License #: Agreement: Y Docket: NRC Notified By: Thomas Sterbis HQ OPS Officer: Jeffrey Whited |
Notification Date: 09/25/2020 Notification Time: 19:59 [ET] Event Date: 09/25/2020 Event Time: 00:00 [CDT] Last Update Date: 09/25/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 21.21(d)(3)(i) - Defects And Noncompliance |
Person (Organization): MARK MILLER (R2DO) JAMNES CAMERON (R3DO) - PART 21/50.55 REACTORS (EMAIL) |
Event Text
| PART 21 REPORT - CONTINUOUSLY ENERGIZED EATON D26 RELAYS The following is a summary of the report provided by the notifier: "Pursuant to 10 CFR 21.21(d)(3)(ii), Nutherm International, Inc. is providing written notification of the identification of a potential defect found in Eaton D26 relays. "On July 23, 2019, Eaton Corporation released a letter, 'Update on Reports of Size 1 & 2 AC Contactors that Failed to Open When Deenergized'. This letter described a condition observed on AC contactors after being energized for a long period of time without being 'cycled'. Eaton also stated that this would occur in only a few isolated cases in continuously energized applications. "The cause of the problem is the coating on each of the steel laminations in the cores of these devices. This steel is coated with an organic insulating varnish classified as C3. This coating, when heated for a long time period, can migrate from the lamination surfaces to the edges at the area between the separate core pieces (referred to as armatures and magnets). This substance is sticky and can potentially hold the core pieces together with enough strength to overcome the forces of the device's return springs." Potentially impacted components may include: Freedom contactors NEMA Size 00 through 5 A200 contactors NEMA Size 00 through 4 D15 Relays D26Relays AR Relays (AC Only) BF Relays (AC Only and including NBF relays) Vacuum contactors NEMA Size 4 Nutherm identified that they had supplied the Eaton relays to the following facilities: Dresden Nuclear Station Quad Cities Nuclear Station Palisades Nuclear Power Plant HB Robinson Steam Electric Plant Point Beach Nuclear Plant If you have any questions please contact Adrienne Smith at 618-244-6000, extension 3034, email adrienne.smith@nutherm.com or Kyle Mitchell at 618-244-6000, extension 3097 email kyle.mitchell@nutherm.com. |
| Power Reactor | Event Number: 54916 |
| Facility: Callaway Region: 4 State: MO Unit: [1] [] [] RX Type: [1] W-4-LP NRC Notified By: Tim Holland HQ OPS Officer: Thomas Kendzia |
Notification Date: 09/27/2020 Notification Time: 05:08 [ET] Event Date: 09/27/2020 Event Time: 02:03 [CDT] Last Update Date: 09/27/2020 |
| 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): RICK DEESE (R4DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | A/R | Y | 98 | Power Operation | 0 | Hot Standby |
Event Text
| AUTOMATIC REACTOR TRIP "At 0203 [CDT] on September 27, 2020 the plant was in Mode 1 at 98 percent power when a turbine trip/reactor trip [from a generator trip signal] occurred. All systems responded as expected. A Feedwater Isolation signal was received due to the reactor trip with RCS average temperature less than 564 degrees Fahrenheit. The Auxiliary Feedwater system started on a valid actuation signal to restore and maintain steam generator levels. The plant is being maintained stable in Mode 3 with no complications. The NRC Resident Inspector has been notified of the reactor trip." All control rods fully inserted from the reactor trip signal, and decay heat is being removed via the Auxiliary Feedwater and Steam Dump Systems. |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021