Event Notification Report for January 09, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
01/08/2024 - 01/09/2024

EVENT NUMBERS
56849 56914
Power Reactor
Event Number: 56849
Facility: Waterford
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Ben Boone
HQ OPS Officer: Adam Koziol
Notification Date: 11/11/2023
Notification Time: 00:23 [ET]
Event Date: 11/10/2023
Event Time: 15:45 [CST]
Last Update Date: 01/08/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
Person (Organization):
Warnick, Greg (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Defueled 0 Defueled
Event Text
EN Revision Imported Date: 1/9/2024

EN Revision Text: UNANALYZED CONDITION

The following information was provided by the licensee via email:

"At 1545 CST on November 10, 2023, personnel at Waterford Steam Electric Station Unit 3 determined that 19 conduits in the engineered safety features actuation system (ESFAS) auxiliary relay cabinets A and B did not have the required fire seals for bay separation. This condition meets the criteria involving an unanalyzed condition that significantly affects plant safety.

"The plant is currently defueled. Decay heat is being removed by normal spent fuel cooling system operations. ESFAS is not required to be operable in the current plant mode.

"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety.

"There was no impact to the health and safety of the public or plant personnel.

"The NRC Region 4 Branch Chief [Dixon] has been notified."

* * * RETRACTION ON 1/8/2024 AT 1222 EST FROM PETER RAMON TO ERNEST WEST * * *

"On November 10, 2023, Waterford Steam Electric Station Unit 3 reported in EN 56849 that 19 conduits in engineered safety features actuation system (ESFAS) auxiliary relay cabinets A and B did not have the required fire seals for bay separation. This condition met the criteria involving an unanalyzed condition that significantly affects plant safety.

"Waterford 3 has determined that the ESFAS auxiliary relay cabinets A and B jumper conduits do not require fire seals based on review of an engineering specification that specifies the size and length of conduits which require fire seals to be installed. None of the nineteen affected conduits meet the size and length criteria that would necessitate installation of a fire seal. Based on this, the condition described in EN 56849 is not considered to be an unanalyzed condition that significantly affects plant safety as described in 10 CFR 50.72(b)(3)(ii)(B) and therefore is not reportable.

"The licensee notified the NRC Resident Inspector."

Notified R4DO (Gaddy)


Power Reactor
Event Number: 56914
Facility: Perry
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Luke Vriezen
HQ OPS Officer: Ernest West
Notification Date: 01/05/2024
Notification Time: 15:56 [ET]
Event Date: 01/05/2024
Event Time: 15:52 [EST]
Last Update Date: 01/08/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Stoedter, Karla (R3DO)
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
EN Revision Imported Date: 1/9/2024

EN Revision Text: OFFSITE NOTIFICATION

The following information was provided by the licensee via phone and email:

"At 1552 [EST] on 01/05/2024, Perry Nuclear Power Plant reported elevated levels of tritium in the underdrain system to the state of Ohio as a non-voluntary reporting of tritium. An investigation is currently ongoing to identify the cause of the elevated tritium levels. The tritium levels in this location do not exceed any NRC regulations or reporting criteria.

"This notification is being made solely as a four-hour, non-emergency notification for a notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."