Event Notification Report for July 13, 2023

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/12/2023 - 07/13/2023

EVENT NUMBERS
56608 56618 56620
Agreement State
Event Number: 56608
Rep Org: Florida Bureau of Radiation Control
Licensee: Universal Engineering Sciences, LLC
Region: 1
City: St Petersburg   State: FL
County:
License #: 4696-11
Agreement: Y
Docket:
NRC Notified By: Reno J. Fabii
HQ OPS Officer: Karen Cotton
Notification Date: 07/05/2023
Notification Time: 16:21 [ET]
Event Date: 07/05/2023
Event Time: 00:00 [EDT]
Last Update Date: 07/05/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Lilliendahl, Jon (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT- DAMAGED TROXLER GAUGE

The following information was provided by the Florida Bureau of Radiation Control via email:

"The Radiation Safety Officer (RSO) for Universal Engineering Sciences, reported that a Troxler gauge, possibly Model 3440, was improperly secured on the back of a truck, fell off, and was damaged. The gauge was in the shielded position but not in the case. The worker was able to retrieve the gauge from the road and secure it. The Troxler sources are believed to be intact. The local office RSO is in route to the location with radiation instruments and shielding (bucket of sand) to verify the sources were not breached. If the sources are found to be breached, they will be returned to Troxler for repair/disposal. No Bureau of Radiation Control assistance was requested."

Florida Incident Number: FL23-101


Power Reactor
Event Number: 56618
Facility: North Anna
Region: 2     State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Marc Hofmann
HQ OPS Officer: Kerby Scales
Notification Date: 07/11/2023
Notification Time: 17:42 [ET]
Event Date: 07/11/2023
Event Time: 15:30 [EDT]
Last Update Date: 07/11/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Miller, Mark (R2DO)
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
2 N Y 100 Power Operation 100 Power Operation
Event Text
OFFSITE NOTIFICATION

The following information was provided by the licensee via email:

"At 1530 [EDT] on 7/11/2023, North Anna Power Station notified the Virginia Department of Environmental Quality (DEQ) that a small volume of filtered/purified water potentially discharged into Lake Anna from a leak from a reverse osmosis unit. The leak did not follow the normal release path for discharge through outfall 013. No environmental impact associated with this leak was observed or would be expected because the water in question is cleaner than the lake water, and would have met all discharge requirements for outfall 013.

"The NRC Resident Inspector was notified.

"This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi)."


Power Reactor
Event Number: 56620
Facility: Millstone
Region: 1     State: CT
Unit: [3] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Todd Stringfellow
HQ OPS Officer: Kerby Scales
Notification Date: 07/12/2023
Notification Time: 12:49 [ET]
Event Date: 07/12/2023
Event Time: 04:49 [EDT]
Last Update Date: 07/12/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(B) - Pot Rhr Inop
Person (Organization):
Henrion, Mark (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
Event Text
ECCS POTENTIALLY INOPERABLE

The following information was provided by the licensee via email:

"At 0449 [EDT] on 7/12/2023, Millstone Unit 3 declared the 'B' train of the emergency core cooling system (ECCS) inoperable due to a degraded damper associated with the ventilation support system for the 'B' charging pump. At the time of this event, the 'A' train of service water was already inoperable due to planned maintenance on a breaker that would have prevented an 'A' service water valve powered from this breaker from closing on a safety signal. This configuration resulted in the possibility that the 'A' train of ECCS would not have been available to fulfill its design function under all postulated accident conditions. This event is being reported under 10 CFR 50.72(b)(3)(v)(B), '[any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (B) remove residual heat].'

"Subsequently, the 'A' train of service water was restored to operable at 0548 on 7/12/2023. Repairs and investigation continue on the 'B' train ECCS damper. The NRC resident has been notified. This event did not impact Millstone Unit 2. There was no impact to the public."