Event Notification Report for July 13, 2022

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/12/2022 - 07/13/2022

EVENT NUMBERS
55977 55979 55988 55989 55992
Agreement State
Event Number: 55977
Rep Org: Louisiana DEQ
Licensee: QSA Global Inc.
Region: 4
City: Baton Rouge   State: LA
County:
License #: LA-5934-L01, Amend. 33
Agreement: Y
Docket:
NRC Notified By: James Pate
HQ OPS Officer: Kerby Scales
Notification Date: 07/05/2022
Notification Time: 15:52 [ET]
Event Date: 07/05/2022
Event Time: 00:00 [CDT]
Last Update Date: 07/05/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Proulx, David (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - MATERIAL EXCEEDING REGULATORY LIMITS DURING TRANSPORTATION

The following was received from the state of Louisiana via email and phone:

"[On] July 5, 2022, QSA Global, Inc. received a package for disposal from Costa Rica. The package read 500 mrem at the surface [exceeding the 200 mrem requirement]. The shipment contained two drums which had two sources inside each drum.

"One drum whose shielding had moved during shipment contained two Am-241 sources, serial numbers 9224 LX and 9225 LX, with an activity of one curie each. The source models are QXV 9000. The manufacturer is Valmet.

"Sources were received from DEL BCR 125 M ESTE, Cole SA, Costa Rica."


Agreement State
Event Number: 55979
Rep Org: Wisconsin Radiation Protection
Licensee: Ahlstrom-Munksjo Rhinelander
Region: 3
City: Rhinelander   State: WI
County:
License #: GL700495
Agreement: Y
Docket:
NRC Notified By: Megan Shober
HQ OPS Officer: Mike Stafford
Notification Date: 07/06/2022
Notification Time: 12:20 [ET]
Event Date: 07/06/2022
Event Time: 00:00 [CDT]
Last Update Date: 07/06/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Lafranzo, Michael (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following summary was received from the Wisconsin Department of Public Health (the Department) via email:

"During a recent routine inspection, the licensee told the Department that they disposed all their tritium exit signs in 2021; however, the licensee had no disposal records for six tritium exit signs which were distributed to the licensed location in 2012 and 2017. The licensee has thoroughly searched its facility and nearby buildings owned by the licensee but the signs could not be located. The licensee suspects the signs were discarded when the storage cabinet they were in was repurposed. Five of the signs were Isolite Model SLX60 (s/n 12-14613, 12-14615, 12-14616, 12-14617 and 12-14618, each originally containing 6.2 Ci of tritium). One sign was an Isolite Model 2000 (s/n H76360, originally containing 7.5 Ci of tritium).

"The Department considers this matter to be closed."

Wisconsin Event Report ID No.: WI220013

THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf


Power Reactor
Event Number: 55988
Facility: Dresden
Region: 3     State: IL
Unit: [2] [] []
RX Type: [2] GE-3,[3] GE-3
NRC Notified By: Alexander Rehn
HQ OPS Officer: Bill Gott
Notification Date: 07/12/2022
Notification Time: 11:47 [ET]
Event Date: 07/12/2022
Event Time: 08:03 [CDT]
Last Update Date: 07/12/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Kozak, Laura (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR SCRAM DUE TO TURBINE TRIP ON HIGH REACTOR WATER LEVEL

The following information was provided by the licensee via fax or email:

"At 0803 EDT on 7/12/2022, with the Unit 2 in Mode 1 at 100% power, an automatic scram was received on Unit 2 following a turbine trip due to high reactor water level. The trip was uncomplicated with all systems responding normally post trip. All rods inserted to their full-in positions.

"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).

"The cause of the transient is under investigation.

"Operations responded using the Emergency Operating Procedure and stabilized the plant in Mode 3. Decay heat is being removed using the steam bypass valves to the condenser and the safety relief valves did not lift as a result of the trip. Reactor vessel inventory and pressure are being maintained in normal control bands.

"Unit 3 was not affected by this transient.

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


Power Reactor
Event Number: 55989
Facility: Seabrook
Region: 1     State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Barry Bradbury
HQ OPS Officer: Thomas Herrity
Notification Date: 07/12/2022
Notification Time: 13:22 [ET]
Event Date: 07/12/2022
Event Time: 10:51 [EDT]
Last Update Date: 07/12/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Bickett, Brice (R1DO)
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
INADVERTENT SIREN ACTIVATION

The following information was provided by the licensee via fax or email:

"At 1051 EDT on July 12, 2022, Seabrook Station received report of inadvertent siren activation. Local authorities have been contacted to apprise them of inadvertent activation of sirens. No press release is planned at this time.

"This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi).

"The NRC Resident Inspector has been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The inadvertent activation involved one group of nine (9) sirens in the Seabrook Beach area. The cause of the activation is under investigation.


Power Reactor
Event Number: 55992
Facility: Browns Ferry
Region: 2     State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: LaGrant Maye
HQ OPS Officer: Bill Gott
Notification Date: 07/12/2022
Notification Time: 17:25 [ET]
Event Date: 07/12/2022
Event Time: 09:17 [CDT]
Last Update Date: 07/12/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
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 96 Power Operation 100 Power Operation
Event Text
HIGH PRESSURE COOLANT INJECTION INOPERABLE

The following information was provided by the licensee via fax or email:

"At 0917 CDT on 7/12/2022, during the performance of U1 [Unit 1] High Pressure Coolant Injection (HPCI) rated flow test, the 1-FCV-73-19 (HPCI governor valve) failed to operate as expected. This condition results in U1 HPCI being inoperable; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). The Automatic Depressurization System (ADS) and Reactor Core Isolation Cooling (RCIC) system remain operable.

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

"U1 entered TS LCO 3.5.1 Condition C, 14-day Shutdown LCO [Limiting Condition for Operation], due to the HPCI inoperability."

Page Last Reviewed/Updated Wednesday, July 13, 2022