Event Notification Report for March 28, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
03/27/2024 - 03/28/2024

EVENT NUMBERS
57039 57040 57042 57053
Agreement State
Event Number: 57039
Rep Org: Georgia Radioactive Material Pgm
Licensee: ATLANTIC COAST CONSULTING, INC
Region: 1
City: Kathleen   State: GA
County:
License #: GA 1541-1
Agreement: Y
Docket:
NRC Notified By: Kaamilya Najeeullah
HQ OPS Officer: Ian Howard
Notification Date: 03/21/2024
Notification Time: 12:16 [ET]
Event Date: 03/20/2024
Event Time: 00:00 [EDT]
Last Update Date: 03/22/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Ford, Monica (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST GAUGE

The following information was provided by the Georgia Radioactive Material Program (the Department) via email:

"A call was made to the Department on March 20, 2024, to report a missing nuclear gauge from the radiation safety officer (RSO) with Atlantic Coast Consulting. Per the conversation, the RSO stated that the gauge was placed on the tailgate of the truck by the technician at the landfill work site. It was out of its storage case and not secured in the truck. The technician went on a lunch break, and, when he returned, the gauge was missing. The RSO stated that criminal activity is not suspected at this time. The licensee will be contacted for more detailed information. The Department will update this report as more information comes in."

Nuclear Gauge Information
Isotope: Cs-137/Am-241
Activity: 10mCi/50mCi
Manufacturer: CPN
Model: MC1DRP
Serial #: MD90805260

Georgia Incident No.: 80

* * * UPDATE ON 03/22/2024 AT 1209 EDT FROM KAAMILYA NAJEEULLAH TO IAN HOWARD * * *

The following update was provided by the Georgia Radioactive Material Program (the Department) via email:

"The official written report from Atlantic Coast Consulting, Inc. was received on March 22, 2024. [The] RSO informed the local police authority of the lost gauge and [told] them to be on the lookout. Upon receipt we will update this report as more information comes in."

Notified R1DO (Ford), NMSS Events (email), and ILTAB (email).

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


Agreement State
Event Number: 57040
Rep Org: California Radiation Control Prgm
Licensee: CTE CAL, INC
Region: 4
City: Pittsburg   State: CA
County:
License #: 8327-01
Agreement: Y
Docket:
NRC Notified By: Robert Greger
HQ OPS Officer: Ian Howard
Notification Date: 03/21/2024
Notification Time: 16:13 [ET]
Event Date: 03/20/2024
Event Time: 00:00 [PDT]
Last Update Date: 03/21/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Gepford, Heather (R4DO)
NMSS_Events_Notification, (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following report was received by the California Department of Public Health , Radiation Health Branch (RHB) via email:

"CTE CAL, Inc. radiation safety officer (RSO) contacted RHB by email at 1634 [PDT] on March 20, 2024. A portable moisture density gauge containing radioactive material (Troxler Model 3430, Serial #T343 23828, Cs-137/Am-241:Be, 8mCi/40mCi) was run over by a smooth drum roller, on a construction site. The source rod and handle were damaged, and the source end of the rod broke off and was still on the ground. The accident site was cordoned off with barrier tape and the broken source rod and Cs-137 source were recovered by Pacific Nuclear Technology (PNT) and placed into a shielded recovery drum. The accident site was surveyed and no radiation above background was found. The damaged gauge and recovery drum were transported to PNT to be surveyed for radiation leakage. PNT surveyed the gauge, leak tested the sources, and determined that the sources were still intact and there was no leakage of radioactive material.

"RHB will continue to investigate the circumstances surrounding the accident."

California incident number: 032024


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 57042
Facility: Waterford
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Nathan Marsh
HQ OPS Officer: Bill Gott
Notification Date: 03/22/2024
Notification Time: 01:17 [ET]
Event Date: 03/21/2024
Event Time: 23:37 [CDT]
Last Update Date: 03/27/2024
Emergency Class: Unusual Event
10 CFR Section:
50.72(a) (1) (i) - Emergency Declared
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Heather Gepford (R4DO)
John Monninger (R4)
Andrea Veil (NRR)
Grant, Jeffery (IR)
Victor Dricks (R4 PAO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 98 Power Operation 0 Hot Standby
Event Text
EN Revision Imported Date: 3/28/2024

EN Revision Text: NOTIFICATION OF UNUSUAL EVENT DUE TO FIRE IN THE PROTECTED AREA

The following information was provided by the licensee:

A Notification of Unusual Event, HU4.4 (see note below) was declared based a fire in the protected area requiring off site assistance to extinguish. The fire was in the main transformer yard. The fire was detected at 2328 CDT on March 21, 2024, and the fire was declared out at 0009 CDT on at March 22, 2024. An automatic reactor trip was initiated due to a loss of offsite power to the "B" train and a failure to automatically transfer from unit auxiliary transformer "B" to startup transformer "B."

The licensee notified State and local authorities and the NRC Resident Inspector.

The NRC remained in Normal.

Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email).

NOTE: Due to a typographical error initiating condition HU4.1 was initially recorded for the event. The correct initiating condition is HU4.4 as now shown.

* * * UPDATE AT 0345 EDT ON 03/22/24 FROM LARRY GONSALES TO BILL GOTT * * *

The licensee terminated the Notification of Unusual Event at 0221 CDT on 3/22/24.

The licensee notified the NRC Resident Inspector.

Notified R4DO (Gepford), IR-MOC (Grant), NRR-EO (Felts), DHS-SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email).

* * * UPDATE AT 0420EDT ON 03/22/24 FROM JOHN LEWIS TO BILL GOTT * * *

RPS ACTUATION

The following information was provided by the licensee via email:

"On March 21, 2024, at 2328 CDT, Waterford 3 Steam Electric Station, Unit 3 was operating at 98 percent power when an automatic reactor trip was initiated due to a loss of offsite power to the 'B' train and a failure to automatically transfer from unit auxiliary transformer 'B' to startup transformer 'B.'

"Emergency feedwater actuation signal 2 (EFAS), safety injection actuation signal (ECCS), containment isolation actuation signal and emergency diesel generators automatically actuated. The unit is currently stable in Mode 3. All control rods fully inserted and all other plant equipment functioned as expected. Forced circulation remains with one reactor coolant pump per loop running. Decay heat removal is via the main condenser. 'A' train safety bus is being supplied by off-site power, and 'B' train safety bus is being supplied by emergency diesel generator 'B.'

"Following the loss of offsite power to the 'B' train, it was reported that main transformer 'B' and startup transformer 'B' were both on fire. The Emergency Director declared an Unusual Event at time 2337 CDT. The fire was reported extinguished at 0009 CDT on March 22, 2024, and the Unusual Event was terminated at 0221 CDT on March 22, 2024. Offsite assistance was requested. The local fire department responded to the site but the fire was extinguished by the on-shift fire brigade. NRC Region IV management was contacted regarding the emergency plan entry at 0030 CDT on March 22, 2024.

"This event is being reported as a 4-hour non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an actuation of the reactor protection system (RPS) when the reactor is critical and as an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as valid actuation of the EFW system, ECCS, Containment Isolation and Emergency Diesel Generators.

"The NRC Resident Inspector has been notified."

Notified R4DO (Gepford)

* * * RETRACTION OF NOTICE OF UNUSUAL EVENT FROM ON 03/26/24 AT 1721 FROM L. BROWN TO K. COTTON * * *

"The initial notification in event notice #57042 by Waterford Steam Electric Station, Unit 3, reported a Notice Of Unusual Event (NOUE) emergency declaration due to a fire in the protected area requiring off site support to extinguish. The basis for retraction of the initial emergency notification is that this event did not meet the definition of a fire in the protected area that requires off site support to extinguish. Guidance provided in Nuclear Energy Institute (NEI) 99-01, Rev. 6 and implemented in Waterford's Emergency Plan procedure, initiating Condition HU4.4 states, 'The dispatch of an offsite firefighting agency to the site requires an emergency declaration only if it is needed to actively support firefighting efforts because the fire is beyond the capability of the Fire Brigade to extinguish.' (NOTE: The Initial Notification Form sent from the Control Room at 2341 CDT on March 21, 2024, requested by and provided to the NRC Headquarter Operations Center via e-mail at 0302 CDT on March 22, 2024, stated that the Emergency Classification had been made on Initiating Condition HU4.4 rather than HU4.1)"

"When the event occurred on March 21, 2024, the Emergency Director declared an Unusual Event at 2337 CDT and requested offsite support based on the information available at that time including the initial assessment by the fire brigade leader and expected need for offsite support to extinguish the fire. As reported in the 0420 EDT update on March 22, 2024, the fire was reported extinguished at 0009 CDT on March 22, 2024, by the Waterford Fire Brigade without the need of offsite support."

Notified R4DO (Kellar).

* * * UPDATE AT 1209 EDT ON 03/27/24 FROM JOHN LEWIS TO KAREN COTTON * * *

"The initial notification in EN 57042 by Waterford Steam Electric Station, Unit 3, reported an emergency declaration of an Unusual Event due to a fire in the protected area requiring off site support to extinguish. The basis for the update to the initial notification is that this event did not meet the definition of a Fire in the Protected Area that requires offsite support to extinguish. As provided in NEI 99-01, Rev. 6 and implemented in Waterford's emergency plan procedure, initiating condition HU4.4 states, 'The dispatch of an offsite firefighting agency to the site requires an emergency declaration only if it is needed to actively support firefighting efforts because the fire is beyond the capability of the Fire Brigade to extinguish.' Additionally, EAL 4.1 for a fire not extinguished within 15 minutes of detection in any Table H-1 fire area was not applicable because the fire did not occur in a Table H-1 fire area.

"When the event occurred on March 21, 2024, the Emergency Director declared an Unusual Event at 2337 CDT and requested offsite support based on the information available at that time including the initial assessment by the fire brigade leader and expected need for offsite support to extinguish the fire. As reported in the 0420 EDT update on March 22, 2024, the fire was reported extinguished at 0009 CDT on March 22, 2024, by the Waterford Fire Brigade without the need of offsite support.

"(NOTE: The Initial Notification Form sent from the Control Room at 2341 CDT on March 21, 2024, requested by and provided to the Headquarters Operation Center via e-mail at 0302 CDT on March 22, 2024, stated that the emergency classification had been made on initiating condition HU4.4 rather than HU4.1)

"In accordance with NRC Approved guidance in FAQ 21-02 (ML21117A104), Waterford 3 is retracting the initial event notification made at 0117 EDT on March 22, 2024. The remaining events that were reported in EN 57042 as a 4-hour non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an actuation of the reactor protection system (RPS) when the reactor is critical and as an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as valid actuation of the EFW (emergency feedwater) system, ECCS (emergency core cooling system), containment isolation and emergency diesel generators are still applicable and require no additional update at this time."

The licensee also provided a site map.

Notified R4DO (Kellar)


Power Reactor
Event Number: 57053
Facility: Grand Gulf
Region: 4     State: MS
Unit: [] [] []
RX Type: [1] GE-6
NRC Notified By: Gabe Hargrove
HQ OPS Officer: Natalie Starfish
Notification Date: 03/26/2024
Notification Time: 16:21 [ET]
Event Date: 03/26/2024
Event Time: 11:15 [CDT]
Last Update Date: 03/26/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Kellar, Ray (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
Event Text
EN Revision Imported Date: 3/28/2024

EN Revision Text: ACTUATION OF REACTOR PROTECTION SYSTEM

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

"On March 26, 2024 at 1115 CDT, Grand Gulf Nuclear Station experienced an actuation of the reactor protection system (RPS) due to high reactor coolant system pressure. The plant was in Mode 4 at zero percent power and performing scram time testing. All rods were fully inserted at the time of the RPS actuation, and all required equipment responded as designed.

"This actuation is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A).

"The cause of the event is under investigation.

"The NRC resident inspector has been notified."