Event Notification Report for July 26, 2021

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/23/2021 - 07/26/2021

Agreement State
Event Number: 55358
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: 3M Company, Corporate Radiation Protection and Compliance
Region: 3
City: Menomonie   State: WI
County:
License #: 033-2030-01
Agreement: Y
Docket:
NRC Notified By: Kyle Walton
HQ OPS Officer: Donald Norwood
Notification Date: 07/16/2021
Notification Time: 16:26 [ET]
Event Date: 07/15/2021
Event Time: 15:30 [CDT]
Last Update Date: 07/16/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
KOZAK, LAURA (R3)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 7/26/2021

EN Revision Text: AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE STUCK SHUTTER

The following information was received via E-mail:

"At 1400 CDT on July 16, 2021, the State was contacted by a representative of the licensee to report a radiation event that had been identified at 1530 CDT on July 15. The licensee was performing routine checks on a fixed gauge device. As part of the checks, they ensure that the shutter is able to be opened and closed. The individual servicing the gauge identified that the shutter was unable to be closed. All indicators are functioning as required to alert that the gauge is open. Staff who work in the area have been instructed that the device is unable to be closed, and to avoid working around the gauge even when it is not being utilized.

"The device is a Mahlo Model 11-200933, SN: 11-011988-ah-4868. It contains an Eckert and Ziegler Pm-147 source, SN: AH-4968. It has an assay date of 4/15/16, 1000 mCi. It currently contains approximately 250 mCi.

"No exposures of any individuals are suspected. The manufacturer was notified and is currently coordinating with the licensee to get a service engineer on site. The department will continue to follow-up with the licensee as arrangements are made."

Wisconsin Event Report ID No.: WI210006


Agreement State
Event Number: 55360
Rep Org: MAINE RADIATION CONTROL PROGRAM
Licensee: MaineHealth Maine Medical Center
Region: 1
City: Scarborough   State: ME
County:
License #: ME 05611
Agreement: Y
Docket:
NRC Notified By: Catherine Perham
HQ OPS Officer: Donald Norwood
Notification Date: 07/19/2021
Notification Time: 15:38 [ET]
Event Date: 10/19/2020
Event Time: 00:00 [EDT]
Last Update Date: 07/19/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
FERDAS, MARC (R1)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 7/26/2021

EN Revision Text: AGREEMENT STATE REPORT - LEAKING SOURCE

The following information was received via E-mail:

"MaineHealth Maine Medical Center reported a leaking Cs-137 source (Eckert & Ziegler Model RV-137-200U, Serial No.: 1490-24-6) that contained an estimated activity of 5.84 MBq (157.8 microCi). The incident was discovered during a semi-annual leak test performed on 10/19/2020. Leak test results revealed 950.9 Bq (0.0257 microCi). The Cs-137 contamination was contained in the drawer the source was stored in. The assumption was made that the source was still leaking and MaineHealth sealed it in its storage lead pig. The outer surface of the lead pig was cleaned and wiped, resulting in removable contamination of less than 200 dpm. The pig was placed in a plastic bag as an extra means of containment and the bag was sealed and labeled. All other items that were contaminated or potentially contaminated in the clean-up process were also placed in a plastic bag, sealed, and labeled. The drawer was cleaned and a final wipe test confirmed that removable contamination was below 200 dpm. The staff who used the source were notified that it was considered out of service and should not be handled or used. The source remained stored in the hot laboratory pending finalization of plans for repair or disposal."

Maine Event Report ID No.: ME 20-004


Agreement State
Event Number: 55361
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: Versa Integrity Group, Inc.
Region: 4
City: Houston   State: TX
County:
License #: L 06669
Agreement: Y
Docket:
NRC Notified By: Randall Redd
HQ OPS Officer: Donald Norwood
Notification Date: 07/19/2021
Notification Time: 16:02 [ET]
Event Date: 07/16/2021
Event Time: 00:00 [CDT]
Last Update Date: 07/19/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'KEEFE, NEIL (R4)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 7/26/2021

EN Revision Text: AGREEMENT STATE REPORT - POSSIBLE OVER-EXPOSURE TO RADIOGRAPHER

The following information was received via E-mail:

"On July 19, 2021, the licensee notified the Agency [Texas Department of State Health Services] that one of its radiographer's personal dosimetry badge results for the monitoring period of June 2021 indicated a deep dose equivalent (DDE) of 5,114 millirem. The radiographer had terminated his employment with the licensee on July 6, 2021. The licensee has contacted the radiographer by phone and the radiographer stated he did not know how it could have happened. The licensee is investigating to determine if the dose was to the radiographer or to the badge only. The licensee also reported that the radiographer had more than one day of work and that the dose to this badge did not occur all within a 24 hour period. An investigation into this event is ongoing."

Texas Incident No.: 9870


Non-Agreement State
Event Number: 55362
Rep Org: Mistras Group, Inc.
Licensee: Mistras Group, Inc.
Region: 3
City: Heath   State: OH
County:
License #: 12-16559-02
Agreement: N
Docket:
NRC Notified By: Matt Kim
HQ OPS Officer: Donald Norwood
Notification Date: 07/19/2021
Notification Time: 16:10 [ET]
Event Date: 07/19/2021
Event Time: 02:00 [AST]
Last Update Date: 07/19/2021
Emergency Class: Non Emergency
10 CFR Section:
20.2202(b)(2) - Excessive Release 1xali
Person (Organization):
PELKE, PATRICIA (R3)
O'KEEFE, NEIL (R4DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 7/26/2021

EN Revision Text: TEMPORARY LOSS OF CONTROL OF RADIOGRAPHY EXPOSURE DEVICE

The following is a synopsis of information received via e-mail:

The Mistras Director of Radiation Safety was notified by a Mistras radiographer (working in Prudhoe Bay, Alaska) that an exposure device had been left unsecured in a truck in an ammo can with no lock and without the alarm set. The truck had then been turned in to the Tarmac shop for maintenance.

The Tarmac shop discovered the device in the truck around 0200 AST. Upon discovery of the device, they immediately closed the truck and notified security. They did not handle the device.

The device was retrieved by approved Mistras personnel and placed into the vault at MCC Camp. After being notified of the event, the Director personally verified that the exposure device was secured in the vault. The exposure device involved is Serial Number: D10742, containing 81 Curies of Ir-192.

The location of the event in Prudhoe Bay is a secured location with no access to or from the camp without proper security clearance. The Tarmac shop services all vehicles on the North Slope as they are owned by a Mistras customer.


Power Reactor
Event Number: 55375
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: Ossy Font
Notification Date: 07/22/2021
Notification Time: 20:28 [ET]
Event Date: 07/22/2021
Event Time: 17:51 [EDT]
Last Update Date: 07/22/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed 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
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation
Event Text
EN Revision Imported Date: 7/26/2021

EN Revision Text: UNANALYZED CONDITION OF FIRE SAFE SHUTDOWN EQUIPMENT

"On July 20, 2021, at 1707 EDT, an apparent non-compliance with 10 CFR 50, Appendix R, section III.G.2 (separation of redundant fire safe shutdown equipment) was identified. This issue was initially categorized as not affecting train separation or the ability of the equipment to perform their Design Basis functions. The original concern was entered into the licensee's Corrective Action Program as CR1177199.

"Subsequently, on July 22, 2021, at 1751 EDT, a further review of the affected control circuits for the Unit 1 and Unit 2 Emergency Diesel Generator (EDG) output breakers and emergency bus feeder breakers identified a concern that breaker position interlocks routed to or through non-safety related components or spaces may affect the ability to provide emergency power on the affected unit due to impacts on the control power circuits during an Appendix R fire associated with a loss of offsite power.

"The following are the affected fire areas:
- Unit 1 and Unit 2 Turbine Buildings
- Unit 1 and Unit 2 Cable Spreading Rooms
- Unit 1 and Unit 2 Normal (307) Switchgear Rooms

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B). This is also reportable as a 60-day written report pursuant to 10 CFR 50.73(a)(2)(ii)(B). This event was entered into the licensee's Corrective Action Program as CR 1177399.

"The NRC Resident Inspector has been notified of this event."


Power Reactor
Event Number: 55377
Facility: Prairie Island
Region: 3     State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: Bryan Truckenmiller
HQ OPS Officer: Joanna Bridge
Notification Date: 07/23/2021
Notification Time: 12:06 [ET]
Event Date: 07/23/2021
Event Time: 10:40 [CDT]
Last Update Date: 07/23/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
PELKE, PATRICIA (R3)
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 DUE TO FISH KILL

"At approximately 1040 CDT, July 23, 2021, the Minnesota State Duty Officer was notified by Xcel Energy Environmental Services of a fish kill in the Prairie Island Nuclear Generating Plant discharge canal. The fish kill resulted from a change in temperature due to the loss of power to the plant cooling tower pumps. The cause of the power loss is under investigation.

"This notification is being made as a four-hour, non-emergency notification 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."


Power Reactor
Event Number: 55379
Facility: Sequoyah
Region: 2     State: TN
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Ben Hammargren
HQ OPS Officer: Brian P. Smith
Notification Date: 07/25/2021
Notification Time: 16:00 [ET]
Event Date: 07/25/2021
Event Time: 12:38 [EDT]
Last Update Date: 07/25/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
MILLER, MARK (R2)
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
SURVEILLENCE FREQUENCY EXCEEDED FOR ICE CONDENSER TEMPERATURE

"At 1238 EDT on July 25, 2021, the Unit 2 Ice Bed became INOPERABLE due to SR [Surveillance Requirement] 3.6.12.1 exceeding its surveillance interval. LCO [Limiting Condition for Operation] 3.6.12 was declared not met as required by SR 3.0.1.

"SR 3.6.12.1 to verify maximum ice bed temperature is less than or equal to 27 degrees F could not be completed due to a failed temperature recorder. The results of the backup method of temperature verification were verified satisfactory at 1258 EDT and the LCO condition was then exited.

"The ice bed is a single train system which functions to control radiation release and mitigate the consequences of an accident by scrubbing radioactive iodine and providing a heat sink to limit containment pressure within design limits, therefore the requirements of 10 CFR 50.72 (b) (3) (v) (C) and (D) were met.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."