Event Notification Report for December 22, 2022

EN Revision Imported Date: 12/22/2022

EN Revision Text: OFFSITE AGENCY NOTIFICATION DUE TO CHEMICAL LEAK

The following information was provided by the licensee via email:

"On 12/8/2022, Prairie Island Nuclear Generating Plant initiated a notification to the State of Minnesota due to a HVAC coolant leak reaching waters of the state. The estimated quantity is 5 gallons of NALCO LCS-60. The leak was due to a failed heat exchanger coil and has been isolated. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable 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."

* * * RETRACTION ON 12/21/2022 AT 1115 EST FROM RAYMOND YORK TO JEFF WHITED * * *
The following information was provided by the licensee via email:
"At 0019 EST on 12/9/2022, the Prairie Island Nuclear Generating Plant (PINGP) made Event Notification 56266 notifying the NRC of an environmental report to the State of Minnesota due to an estimated 5 gallons of NALCO LCS-60 that leaked from a failed heat exchanger coil and reached the waters of the state. This event notification was made in accordance with 10 CFR 50.72(b)(2)(xi). During further review of NRC reporting guidance, PINGP has concluded that the reported quantity of NALCO LCS-60 that leaked during this event was below the reporting threshold outlined in NUREG 1022, Revision 3. The NRC Resident Inspector has been notified."
Notified R3DO (Kozak)

AGREEMENT STATE REPORT - OVEREXPOSURE EVENT
The following information was provided by the Texas Department of Health Services (the Agency) via email:
"On December 14, 2022, the Agency was notified by the licensee's radiation safety officer (RSO) of a potential overexposure event. The RSO reported three of their radiographers were working at a remote site using a 30.4 curie cobalt 60 source. The exposure time for each exposure was two minutes. The distance from the source to the pipe was two feet. During the first exposure, one of the radiographers was between the source and the pipe being tested. The RSO stated the individual stayed in the area for about one minute. The radiographer operating the source was standing behind a brick wall and was unaware of the individual being in the area. The operator thought the others had cleared the area, and it was safe to perform the exposure. The individual who received the exposures stated the noise in the area was too loud to hear their alarming rate meter. The exposed individual's self-reading dosimeter was off scale. All radiographers' dosimeters have been sent to the licensee's dosimetry processor for reading. The RSO stated their calculations indicated the individual could have received 7 rem from this event. The RSO stated the individual exposed had received 12 millirem prior to this event. All three individuals have been removed from any duties that would require any additional exposure. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident no.: 9973
Texas NMED no.: TX220041

* * * UPDATE ON 12/16/22 AT 1522 CST FROM ARTHUR L TUCKER TO LAUREN BRYSON * * *
"On December 16, 2022, the licensee reported they had received the badge reading for the individual involved in this event. The Deep Dose Equivalent (DDE) on the badge was 5,450 millirem bringing the individuals DDE total for the year to 5,662 millirem. The Agency has requested the licensee determine if the badge was worn in the highest dose field during the event. Additional information will be provided as it is received in accordance with SA-300."

Notified R4DO (Drake) and NMSS Events Notification via email.

AGREEMENT STATE REPORT - PATIENT UNDERDOSE

The following information was provided by the Illinois Emergency Management Agency (The Agency) via email:

"The Agency was contacted on 12/14/22 by the medical physicist for Alexian Brothers Medical Center to advise that a Y-90 microsphere administration conducted that morning resulted in a reportable under dose. The administered amount was 20.4 percent lower than that specified in the written directive. This was not a stasis case. The licensee has tried multiple times, but has so far been unable to reach the patient for notification. The referring physician has been notified. Agency inspectors have gathered preliminary information but will conduct a reactionary site visit on Tuesday, December 20, 2022. More information will be provided once it becomes available."

Illinois Event Number: IL220043


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 - FOUND GAUGE

The following information was provided by the Pennsylvania Bureau of Radiation Protection (the Department) via email:

"On December 14, 2022, a consultant health physicist informed the Department that a Troxler Model 104-117 nuclear density gauge, serial number 433, containing 3 millicuries of radium-226 beryllium (Ra:Be) had been found. The gauge was found in a trash transfer trailer entering Waste Management, Mountain View Reclamation Landfill on December 2, 2202. This load originated from West Virginia. The load was isolated until consultant health physicist was able to respond on December 13, 2022, to resurvey the trailer. A gamma radiation measurement made at contact with the source housing was 18 milliroentgens/hour. At 1 foot from the approximate location of the source, the gamma dose rate was 5 mrem/hour. No evaluation was made of the neutron dose rate. The device was placed in a locked storage shed posted with a Caution - Radioactive Material sign. The Department was onsite during the recovery of the gauge and continues to investigate its origin.

"The Department will update this event as soon as more information is provided."

Event Report ID No.: PA220030

AGREEMENT STATE REPORT - LEAKING SOURCE

The following information was provided by the the Arizona Department of Health Services (the Department) via email:

"The Department received notification from the licensee of a leak test that exceeded the regulatory limit of 0.005 microcuries. The licensee is going to return the vial to the manufacturer and exchange it for a new vial source. The Department has requested additional information and continues to investigate the event."

[Source information:]
"Cs-137 Vial
"Serial number: 788-3-11
"Assay date: 11/1/2001

"Additional information will be provided as it is received in accordance with SA-300."

Arizona Incident Number: 22-015

MANUAL SCRAM DUE TO LOSS OF FEEDWATER PUMP

The following information was provided by the licensee via email:

"At 2101 [CST] on December 19, 2022, a manual reactor scram was initiated at Grand Gulf Nuclear Station (GGNS). Following the reactor scram, the high pressure core spray (HPCS) system was used to maintain reactor water level. The manual [reactor protection system] RPS actuation is being reported in accordance with 10 CFR 50.72(b)(2) and the HPCS actuation is being reported in accordance with 10 CFR 50.72(b)(3).

"At 2058, GGNS experienced a loss of a condensate booster pump. At 2101, the `A' reactor feedwater pump tripped and the reactor was manually scrammed. All control rods were fully inserted into the core.

"At 2104, the `B' reactor feedwater pump tripped and HPCS was manually started. HPCS was manually injected to maintain reactor water level at 2121. The `A' reactor feedwater pump was successfully restarted at 2126.

"GGNS is currently in Mode 3. Reactor level is being maintained with the `A' reactor feedwater pump and pressure is being maintained with the turbine bypass valves.

"The NRC Resident Inspector was notified."

60-DAY TELEPHONIC NOTIFICATION - INVALID SPECIFIC SYSTEM ACTUATION
The following information was provided by the licensee via email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid specific system actuation of the Emergency Service Water System (ESW).

"On 11/2/2022, during normal reactor operations, multiple main control room alarms were received for D12 Emergency Diesel Generator (EDG) running and Unit 1 Division 2 Safeguard Battery Ground. The D12 EDG did not start; however, the 'B' ESW Pump auto started. Subsequent troubleshooting determined that the cause of the D12 EDG running alarms and the inadvertent auto start of the 'B' ESW Pump was a malfunction on the D12 EDG speed switch. This event is considered an invalid system actuation because the 'B' ESW Pump started in response to a false signal that the D12 EDG was running when D12 EDG did not start. This was a complete actuation of the ESW System and the system functioned as expected in response to the actuation. The affected ESW Pump was shut down in accordance with plant procedures and the degraded D12 EDG speed switch was replaced. There was no impact on the health and safety of the public or plant personnel. The licensee notified the NRC Resident Inspector."