Event Notification Report for November 15, 2021

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/12/2021 - 11/15/2021

EVENT NUMBERS
55562 55570 55572 55574 55575 55576
Agreement State
Event Number: 55562
Rep Org: Louisiana DEQ
Licensee: Source Production & Equipment Co.
Region: 4
City: St. Rose   State: LA
County:
License #: LA-2966-L01
Agreement: Y
Docket:
NRC Notified By: Richard S Blackwell
HQ OPS Officer: Mike Stafford
Notification Date: 11/05/2021
Notification Time: 12:24 [ET]
Event Date: 11/05/2021
Event Time: 10:45 [CDT]
Last Update Date: 11/05/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Kozal, Jason (R4)
NMSS_Events_Notification, (EMAIL)
Event Text
EN Revision Imported Date: 11/15/2021

EN Revision Text: AGREEMENT STATE REPORT - IMPROPER SOURCE SHIPMENT

The following was received from the Louisiana Department of Environmental Quality (DEQ) via email:

"Louisiana DEQ was notified by Source Production & Equipment (SPEC) Radiation Safety Officer, via the DEQ Radiation Hotline at approximately 1045 CDT on November 5, 2021, concerning an industrial radiography camera shipment from Nigeria. According to the RSO, Dynaquest Energy Limited in Nigeria wanted to exchange three Industrial Radiography Ir-192 sources. When the package was received, two of the drums had the Industrial Radiography cameras (SPEC 150) and the other drum did not have a camera just the unshielded source. The unshielded source was in the type B container without a camera. The source is an Ir-192 with 0.06987 Ci. The reading on the side of the drum was 300 mR/hr and the reading from the top of the drum with the lid off was 40 - 50 mR/hr. SPEC retrieved the source and put it in a shield. The individual that was handling the package and retrieval received 5 mR exposure. The two cameras were a SPEC 150 (s/n 2619) with Ir-192 source s/n AF2815 and SPEC 150 (s/n 2618) with Ir-192 source s/n AF2814 and were locked. SPEC 150 (s/n 2618) did not have a locking cap on it even though the camera was locked. SPEC stated that they will hold on to the devices and terminate their relationship with Dynaquest Energy Limited."

Louisiana Event Report ID Number: LA 202100010


Power Reactor
Event Number: 55570
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: Howie Crouch
Notification Date: 11/10/2021
Notification Time: 18:38 [ET]
Event Date: 11/10/2021
Event Time: 15:15 [EST]
Last Update Date: 11/12/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Miller, Mark (R2)
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
EN Revision Imported Date: 11/15/2021

EN Revision Text: OFFSITE NOTIFICATION DUE TO PCB OIL SPILL

"At 1515 EST on 11/10/21, approximately 89 gallons of PCB oil is unaccounted for from the Substation 'N' Transformer, located in the Owner Controlled Area. Transformer nameplate oil capacity is 569 gallons. Prior to removal of the original Substation 'N' Transformer, approximately 475 gallons of 10-CA-OIL (PCB Oil) was evacuated and stored by HEPACO (a licensee vendor). Approximately 5 gallons of oil is inaccessible to evacuate and remains in the original transformer. Below the transformer was evidence of oil leakage to the ground. The leakage appears to have been occurring over time, not as a result of a catastrophic failure. This condition is reportable to the Virginia Department of Environmental Quality (VA DEQ). The VA DEQ was notified of this condition at 1815 on 11/10/21. Cleanup activities are on-going.

"This event is reportable in accordance with 10CFR50.72(b)(2)(xi) for 'Any event or situation, related to the health and safety of the public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'"

The licensee will be notifying the Louisa County administrator and has notified the NRC Resident Inspector.

* * * UPDATE FROM MARC HOFMANN TO DONALD NORWOOD AT 1309 EST ON 11/12/2021 * * *

"Initial, unofficial, field testing performed by HEPACO indicated the oil released to the ground was PCB-Contaminated Oil. The official test results from the lab indicated that the oil is in fact not classified as PCB-Contaminated Oil. Therefore, this update is being made to EN55570 to clarify that the oil released to the environment was not PCB-Contaminated Oil."

The licensee notified the NRC Resident Inspector and the VA DEQ of this update.

Notified R2DO (Miller).


Power Reactor
Event Number: 55572
Facility: Beaver Valley
Region: 1     State: PA
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Sean McGee
HQ OPS Officer: Donald Norwood
Notification Date: 11/12/2021
Notification Time: 13:52 [ET]
Event Date: 11/12/2021
Event Time: 10:07 [EST]
Last Update Date: 11/12/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Henrion, Mark (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 17 Power Operation 0 Power Operation
Event Text
MANUAL REACTOR TRIP DUE TO INCREASING STEAM GENERATOR WATER LEVELS

"At 1007 EST on November 12, 2021, with Unit 2 in Mode 1 at approximately 17 percent power following a refueling outage, the reactor was manually tripped due to increasing steam generator water levels due to an oscillating Main Feedwater Pump Recirculation Valve. Additionally, the Main Steam Isolation Valves were manually closed to prevent excessive reactor coolant system cooldown. Decay heat is being removed by discharging steam to the atmosphere using the Atmospheric Dump Valves.

"The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response. Operations responded and stabilized the plant.

"Beaver Valley Power Station Unit 1 is unaffected and remains at 100 percent power in Mode 1.

"Due to 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).

"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: 55574
Facility: Turkey Point
Region: 2     State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Humberto Benitez
HQ OPS Officer: Donald Norwood
Notification Date: 11/12/2021
Notification Time: 20:47 [ET]
Event Date: 11/12/2021
Event Time: 16:05 [EST]
Last Update Date: 11/12/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Miller, Mark (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Hot Standby 0 Hot Standby
Event Text
REACTOR COOLANT SYSTEM PRESSURE BOUNDARY DEGRADED

"At 1605 EST on 11/12/21, it was determined that the RCS Pressure Boundary does not meet ASME Section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak of the Core Exit Thermocouple Nozzle Assembly.

"Measures have been taken to establish Mode 5 for corrective actions.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A).

"The NRC Resident Inspector has been notified.


Power Reactor
Event Number: 55575
Facility: Peach Bottom
Region: 1     State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Chris Wainaina
HQ OPS Officer: Karen Cotton
Notification Date: 11/14/2021
Notification Time: 08:50 [ET]
Event Date: 11/14/2021
Event Time: 05:25 [EST]
Last Update Date: 11/14/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Henrion, Mark (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 100 Power Operation 0 Hot Standby
Event Text
MANUAL TRIP DUE TO LOWERING MAIN CONDENSER VACUUM
At 0525 EST, November 14, 2021, "Unit 2 was manually scammed by operations due to lowering main condenser vacuum. This resulted in PCIS (process control and instrumentation system) Group II/III isolation signals. All control rods inserted, and all systems operated as designed."

Unit 3 is unaffected and remains at 100 percent power in Mode 1.

The Resident Inspector was notified.


Power Reactor
Event Number: 55576
Facility: Millstone
Region: 1     State: CT
Unit: [2] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Sunyoung Kwon
HQ OPS Officer: Donald Norwood
Notification Date: 11/14/2021
Notification Time: 17:06 [ET]
Event Date: 11/14/2021
Event Time: 11:50 [EST]
Last Update Date: 11/14/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
Person (Organization):
Henrion, Mark (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
NON-FUNCTIONAL STEAM SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP

"On November 14, 2021, at 1150 EST, while operating in Mode 1 at 100 percent power, the supply check valve from the Number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the Number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure.

"There has been no radioactive release to the environment. The steam lines from the steam generators to the turbine driven auxiliary feedwater pump have been isolated by use of a motor operated valve in the discharge line of the Number 2 steam generator. There has been no impact to Unit 3 which remains at 100 percent power.

"The NRC Senior Resident has been notified.

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."