Event Notification Report for August 04, 2023

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
08/03/2023 - 08/04/2023

EVENT NUMBERS
56570 56652 56653
Power Reactor
Event Number: 56570
Facility: Fermi
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: Jonathan Holdwick
HQ OPS Officer: Sam Colvard
Notification Date: 06/13/2023
Notification Time: 06:02 [ET]
Event Date: 06/12/2023
Event Time: 23:33 [EDT]
Last Update Date: 08/03/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Peterson, Hironori (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 0 Power Operation 0 Power Operation
Event Text
EN Revision Imported Date: 8/4/2023

EN Revision Text: ACCIDENT MITIGATION - HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE

The following information was provided by the licensee via email:

"At 2333 EDT on June 12, 2023, the division 2 Mechanical Draft Cooling Tower (MDCT) Fan `D' was declared inoperable due to a trip of the fan while running in high speed. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the division 2 Emergency Equipment Cooling Water (EECW) system. The EECW system cools various safety related components, including the High-Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI room cooler. The cause of MDCT Fan `D' trip is currently unknown with trouble shooting being developed for remediation of the condition. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability.

"The NRC Senior Resident Inspector has been notified."

* * * RETRACTION AT 1540 EDT ON 8/8/2023 FROM WHITNEY HEMINGWAY TO BILL GOTT * * *

"The purpose of this notification is to retract a previous event notification (EN) 56570 reported on June 13, 2023, at 0602 EDT.

"The cause of the fan trip was a failed vibration switch. At 0429 EDT on June 14, 2023, the vibration switch was replaced, the MDCT fan "D" was tested satisfactory for operability, and the UHS, emergency diesel generator 13/14, and MDCT were declared operable.

"Following the initial EN, further analysis of the condition was performed utilizing a previously performed gothic analysis model (to perform HPCI room heat-up calculations) which bounded this condition. Based on the initial conditions at the time of the indication loss, specifically HPCI room and suppression pool temperature, it was determined that the resulting worst case post-accident room temperature was sufficiently low enough to provide margin to HPCI operability without the room cooler in service for the required mission time.

"No other concerns were noted during the event. HPCI remained operable and there was no loss of safety function. The fan trip did not involve a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D).

"Therefore, the NRC non-emergency 10CFR50.72(b)(3)(v)(D) report was not required and the NRC report 56570 can be retracted, and no licensee event report under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted."

The licensee notified the NRC Resident Inspector.

Notified R3DO (Nguyen)


Power Reactor
Event Number: 56652
Facility: Nine Mile Point
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: Ryan Bracht
HQ OPS Officer: Bill Gott
Notification Date: 08/03/2023
Notification Time: 16:58 [ET]
Event Date: 08/03/2023
Event Time: 10:03 [EDT]
Last Update Date: 08/03/2023
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Bickett, Brice (R1DO)
FFD Group, (EMAIL)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
FAILED FITNESS FOR DUTY TEST

The following information was provided by the licensee via email:

A licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.

The NRC Senior Resident Inspector was notified.


Part 21
Event Number: 56653
Rep Org: Paragon Energy Solutions
Licensee:
Region: 2
City:   State:
County:
License #:
Agreement: N
Docket:
NRC Notified By: Richard Knott
HQ OPS Officer: Bill Gott
Notification Date: 08/03/2023
Notification Time: 17:05 [ET]
Event Date: 08/03/2023
Event Time: 00:00 []
Last Update Date: 08/03/2023
Emergency Class: Non Emergency
10 CFR Section:
21.21(a)(2) - Interim Eval Of Deviation
Person (Organization):
Miller, Mark (R2DO)
Nguyen, April (R3DO)
Part 21/50.55 Reactors, - (EMAIL)
Event Text
INITIAL PART 21 REPORT - DEFECT WITH EATON/CUTLER HAMMER SIZE 4 AND 5 FREEDOM SERIES CONTACTORS

The following information was provided by Paragon Energy Solutions, LLC via email:

"Pursuant to 10CFR 21.21(d)(3)(i), Paragon Energy Solutions, LLC is providing this initial notification of a potential defect with Eaton/Cutler Hammer size 4 and 5 freedom series contactors that have been modified to include either a special coil and/or to improve the securing of shading coils. These contactors may have been supplied integral to a motor control center (MCC) cubicle or as spare parts. This condition, if left uncorrected, could potentially cause a substantial safety hazard.

"Paragon completed an initial evaluation of a failure of a size 4 freedom series contactor (PN: NLI-CN15NN3A-T16-MOD-M) supplied to Perry Nuclear Power Plant. The reported failure occurred 26 days following installation into its associated MCC Cubicle. Perry identified the screws holding the contact bar to the push bars had fallen out and were laying in the bottom of the molded base. This allowed the movable contact bar to sit on the stationary contacts and significantly degrade due to arcing and then fail in the energized position. This condition could prevent the contactor from performing its safety function to either energize or de-energize the attached load.

"The loose hardware is most likely a workmanship error since the contactor must be disassembled to complete the special coil and RTV modifications to the shading coils. In the fully re-assembled condition, inspection of this hardware for tightness is not possible."

Affected plants: North Anna, Turkey Point, Harris, and Perry.