Event Notification Report for April 04, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/03/2023 - 04/04/2023
Agreement State
Event Number: 56436
Rep Org: Iowa Department of Public Health
Licensee: Whirlpool Corporation, AMANA Div.
Region: 3
City: Amana State: IA
County:
License #: 3367-1-48-FG
Agreement: Y
Docket:
NRC Notified By: Stuart Jordan
HQ OPS Officer: Sam Colvard
Notification Date: 03/28/2023
Notification Time: 14:59 [ET]
Event Date: 02/28/2023
Event Time: 00:00 [CDT]
Last Update Date: 03/28/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Havertape, Joshua (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST DEVICE
The following information was provided by Iowa Department of Health and Human Services via email:
"In the process of a registrant closing out their general license, the registrant identified that a generally licensed 3M model 703 handheld static eliminator (s/n: 7030250) containing hydrogen-3 with a current activity of 20 millicuries (manufactured in 1982 with 200 millicuries) had been lost. In 2015, the registrant had three (3) 703 devices, in which two (2) were disposed of through the manufacturer. No other records of sale, transfer, or disposal could be identified.
"The registrant spent 400 man-hours searching their facility, methodically sectioning off and checking all storage locations, interviewing current and former employees, contacting vendors who had conducted leak test services on other devices, and contacting radioactive waste disposal groups who have handled waste in the past. None had any records of the missing unit. It is the registrant's belief that the unit was likely removed from the site sometime before 2018. No occupational illnesses or injuries have been reported or would likely occur from the loss of this device due to its age and characteristics."
Iowa Incident Number: IA230002
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: 56451
Facility: McGuire
Region: 2 State: NC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Tim Johnson
HQ OPS Officer: Ernest West
Notification Date: 04/02/2023
Notification Time: 11:29 [ET]
Event Date: 04/02/2023
Event Time: 03:52 [EDT]
Last Update Date: 04/02/2023
Emergency Class: Non Emergency
10 CFR Section:
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 |
N |
N |
0 |
Hot Standby |
0 |
Hot Standby |
Event Text
MANUAL ACTUATION OF AUXILIARY FEEDWATER MOTOR DRIVEN PUMPS
The following information was provided by the licensee via email:
"On April 2, 2023, at 0341 EDT, with Unit 2 in Mode 3 and the 2B main feedwater pump feeding the steam generators, the 2A main feedwater pump recirculation valve, 2CF-76, failed. Further, observation of the operating 2B main feedwater pump recirculation valve, 2CF-81, called into question its functionality. At 0352 EDT, operations manually started the auxiliary feedwater motor driven pumps to feed the stream generators to allow maintenance on the main feedwater system. The auxiliary feedwater motor driven pumps started as designed. Flow to the steam generator was not adversely impacted during this sequence. This event is being reported in accordance with 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."