Event Notification Report for November 15, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/14/2023 - 11/15/2023
Agreement State
Event Number: 56836
Rep Org: Colorado Dept of Health
Licensee: Fairfield Inn by Marriott
Region: 4
City: Lakewood State: CO
County:
License #: GL0000212
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Ernest West
Notification Date: 11/07/2023
Notification Time: 10:16 [ET]
Event Date: 10/30/2023
Event Time: 00:00 [MST]
Last Update Date: 11/07/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Warnick, Greg (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST EXIT SIGNS
The following is a synopsis of information provided by the Colorado Department of Public Health and Environment via email:
On 10/30/23, the licensee discovered that 11 tritium exit signs were not able to be located. The exit signs were SRB Technologies (model number BX-10-BK) signs each containing 10 Ci of tritium (H-3). This is being reported under Colorado Regulations Section 4.51.1.1 (10 CFR 20.2202(a)(1)(i)).
Event Report ID No.: CO230040
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: 56837
Rep Org: Florida Bureau of Radiation Control
Licensee: Environmental Safety Consultant Florida, LLC
Region: 1
City: Fort Myers State: FL
County:
License #: 3440-6
Agreement: Y
Docket:
NRC Notified By: Mark Seidensticker
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/07/2023
Notification Time: 12:46 [ET]
Event Date: 11/07/2023
Event Time: 11:30 [EST]
Last Update Date: 11/07/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:
A Radiation Safety Officer (RSO) with Environmental Safety Consultant (ESC) Florida, LLC called BRC in Orlando on November 7, 2023, at 1150 EST to report a soil moisture density gauge (Model: Instro Tek Xplorer 3500, 8 mCi Cs-137, 40 mCi Am-241:Be) was run over on a job site around 1130 this morning. The RSO indicated that the source rod was retracted when the incident occurred. An inspector was sent to investigate.
Florida Event Number: FL23-161
Agreement State
Event Number: 56842
Rep Org: Colorado Dept of Health
Licensee: Five Rivers Cattle Feeding
Region: 4
City: Lamar State: CO
County:
License #: GL002209
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/08/2023
Notification Time: 16:01 [ET]
Event Date: 11/08/2023
Event Time: 00:00 [MST]
Last Update Date: 11/08/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Warnick, Greg (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST EXIT SIGN
The following information was obtained and summarized from the Colorado Department of Public Health and Environment in accordance with Headquarters Operations Officers Report Guidance:
On November 8, 2023, Five Rivers Cattle Feeding (Lamar) reported to the Colorado Department of Public Health and Environment one lost exit sign (Manufacturer: Isolite Corporation; Model #: SLX60; Isotope & activity: H-3, 6.2 Ci).
Event Report ID No.: CO230041
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: 56852
Facility: Farley
Region: 2 State: AL
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Roosevelt Scott
HQ OPS Officer: Ernest West
Notification Date: 11/14/2023
Notification Time: 14:36 [ET]
Event Date: 11/14/2023
Event Time: 10:41 [CST]
Last Update Date: 11/14/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Miller, Mark (R2DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
2 |
M/R |
Y |
10 |
Power Operation |
0 |
Hot Standby |
Event Text
MANUAL REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 1041 CST on 11/14/23 with Farley Unit 2 in Mode 1 at 10 percent power, the reactor was manually tripped due to rising steam generator levels. The trip was not complex, with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Auxiliary feedwater (AFW) was manually initiated in accordance with plant procedures and is feeding the steam generators. Heat removal is being provided via the atmospheric relief valves. Unit 1 is not affected.
"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). This event is also being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feedwater system.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
All rods fully inserted. The licensee attempted to take manual control of the feedwater control valves to lower steam generator level but, due to reaching a steam generator level that requires a manual trip, the licensee manually tripped the reactor.