Event Notification Report for July 08, 2024

EN Revision Imported Date: 7/8/2024

EN Revision Text: AUTOMATIC REACTOR TRIP DUE TO LOWERING STEAM GENERATOR WATER LEVEL

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

"At 0338 CDT, with the unit 1 in mode 1 at 6 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-trip. 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) and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system.

"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to the reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.

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

* * * UPDATE ON 07/05/2024 AT 0450 EDT FROM MATTHEW WHITE TO TENISHA MEADOWS * * *

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

"At 0338 CDT, with the unit 1 in mode 2 at 3 percent power, the reactor automatically tripped due to lowering steam generator water level. The trip was uncomplicated with all systems responding normally post-trip. 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) and 10CFR50.72(b)(3)(iv)(A) for an actuation of the auxiliary feedwater system, eight-hour notification.

"Operations responded using procedure 1BwEP-0 and stabilized the plant in mode 3. Decay heat is being removed by steam dumps via the main condenser. 1A and 1B auxiliary feedwater pumps were actuated manually prior to reactor trip in an attempt to restore steam generator water level. Unit 2 is not affected.

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

Notified R3DO (Hartman)

AGREEMENT STATE REPORT - Y-90 UNDERDOSE

The following information was received from the Massachusetts Radiation Control Program (the Agency) via email:

"On 06/28/24 at 1430 EDT, the licensee reported a medical event under license 60-0096 for BWXT Medical Ltd. TheraSpheres Model TheraSphere Y-90 Glass Microsphere System (Sealed Source and Device Registry: NR-0220-D-131-S) for total administered activity that differed from prescribed treatment activity as documented in the written directive by 20 percent or more.

"The medical event was reported to the radiation safety officer (RSO) at 1430 EDT on 6/27/2024. The prescribed dose to the patient was 106.4 mCi over two fractions. The dose received by the patient was 68.5 mCi (60.4 mCi on the first fraction, and 8.1 mCi on the second fraction). This resulted in an under dose of 35.6 percent. The authorized user and prescribing physician have been notified. The licensee has not reported whether the patient has been notified.

"The Agency will follow up with licensee RSO to determine the event cause and corrective actions.

"The Agency considers this event open. The Agency will follow up with a special inspection of the licensee."


A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

AGREEMENT STATE REPORT - LOST EXIT SIGNS

The following information was provided by the Colorado Department of Public Health and Environment (the Department) via email:

"Five Rivers Cattle Feeding, LLC reported eight missing tritium (H-3) exit signs. The initial registration received on June 26, 2012, indicated that each tritium exit sign contained 6.2 Ci (49.6 Ci total)."

Colorado State Event Report Number: CO240016

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

BOTH TRAINS OF CONTROL ROOM VENTILATION TEMPERATURE CONTROL SYSTEM INOPERABLE

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

"At 1440 CDT on 7/7/2024, it was discovered that both trains of the control room ventilation temperature control system were simultaneously inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).

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

"One train of control room ventilation temperature control was restored to operable status at 1634 CDT on 7/7/2024."