Event Notification Report for March 10, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/09/2023 - 03/10/2023
Agreement State
Event Number: 56406
Rep Org: Arkansas Department of Health
Licensee: Anchor Packaging Company
Region: 4
City: Paragould State: AR
County:
License #: GL-0010
Agreement: Y
Docket:
NRC Notified By: Angela Minden
HQ OPS Officer: Caty Nolan
Licensee: Anchor Packaging Company
Region: 4
City: Paragould State: AR
County:
License #: GL-0010
Agreement: Y
Docket:
NRC Notified By: Angela Minden
HQ OPS Officer: Caty Nolan
Notification Date: 03/10/2023
Notification Time: 15:52 [ET]
Event Date: 03/10/2023
Event Time: 15:52 [CST]
Last Update Date: 03/10/2023
Notification Time: 15:52 [ET]
Event Date: 03/10/2023
Event Time: 15:52 [CST]
Last Update Date: 03/10/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gepford, Heather (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
Gepford, Heather (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
AGREEMENT STATE REPORT - LOST FIXED GAUGES
The following information was received from the Arkansas Department of Health via email:
"The Arkansas Department of Health, Radiation Control Section (the Section), was notified on February 28, 2023, via a letter received from Anchor Packaging Company in Paragould, Arkansas, of two generally licensed fixed gauges that were determined to not be located on-site (GL-0010). The Section called the manufacturer on March 1, 2023, then received information on March 10, 2023, that they had no record of the gauges ever being returned to them. These gauges each contain 5.55 GBq (150 milliCuries) Am-241 -- NDC device model 102 (device SN 2844) and NDC device model 103X (device SN 13264, source SN 3576CW).
"Causes of the event are the following: the lack of effective procedures that stress the general licensee requirements, specifically those that aid accountability of sources; failure to ensure the appointing and support of the individual responsible for having knowledge of the regulations/requirements; and lack of training (though not required) needed to identify radioactive material/general license labeling and then to know what steps to take. The Section is currently working with the licensee regarding corrective actions due to a previous missing devices event, 55793."
Event Number: AR-2023-001
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
The following information was received from the Arkansas Department of Health via email:
"The Arkansas Department of Health, Radiation Control Section (the Section), was notified on February 28, 2023, via a letter received from Anchor Packaging Company in Paragould, Arkansas, of two generally licensed fixed gauges that were determined to not be located on-site (GL-0010). The Section called the manufacturer on March 1, 2023, then received information on March 10, 2023, that they had no record of the gauges ever being returned to them. These gauges each contain 5.55 GBq (150 milliCuries) Am-241 -- NDC device model 102 (device SN 2844) and NDC device model 103X (device SN 13264, source SN 3576CW).
"Causes of the event are the following: the lack of effective procedures that stress the general licensee requirements, specifically those that aid accountability of sources; failure to ensure the appointing and support of the individual responsible for having knowledge of the regulations/requirements; and lack of training (though not required) needed to identify radioactive material/general license labeling and then to know what steps to take. The Section is currently working with the licensee regarding corrective actions due to a previous missing devices event, 55793."
Event Number: AR-2023-001
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: 56403
Facility: Waterford
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Kevin Hale
HQ OPS Officer: Ernest West
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Kevin Hale
HQ OPS Officer: Ernest West
Notification Date: 03/10/2023
Notification Time: 07:25 [ET]
Event Date: 03/10/2023
Event Time: 02:37 [CST]
Last Update Date: 03/10/2023
Notification Time: 07:25 [ET]
Event Date: 03/10/2023
Event Time: 02:37 [CST]
Last Update Date: 03/10/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
Person (Organization):
Gepford, Heather (R4DO)
Gepford, Heather (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 0 | Hot Standby |
SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS
The following information was provided by the licensee via email:
"On 03/09/2023 at 2200 CST, Waterford [Unit] 3 entered OP-901-111, Reactor Coolant System Leakage, and OP-901-403, High Activity In Containment, due to elevated reactor coolant system (RCS) leakage in containment. On 03/10/2023, at 0030 Operations entered Technical Specification 3.4.5.2 action (c) due to unidentified leakage exceeding 1 gallon per minute (gpm). Technical Specification 3.4.5.2 action (c) requires reducing the leakage rate to within limits within 4 hours or be in at least hot standby within the next 6 hours and in cold shutdown within the following 30 hours.
"On 03/10/2023 at 0237 the plant discovered an unisolable RCS leak in the reactor coolant pump 1B cubicle and initiated action to complete a plant shutdown required by Technical Specifications. This event is being reported as a 4-hour report in accordance with 10 CFR 50.72(b)(2)(i) as the initiation of plant shutdown required by technical specifications. Reactor was tripped at 0521 CST on 3/10/2023."
The following information was provided by the licensee via email:
"On 03/09/2023 at 2200 CST, Waterford [Unit] 3 entered OP-901-111, Reactor Coolant System Leakage, and OP-901-403, High Activity In Containment, due to elevated reactor coolant system (RCS) leakage in containment. On 03/10/2023, at 0030 Operations entered Technical Specification 3.4.5.2 action (c) due to unidentified leakage exceeding 1 gallon per minute (gpm). Technical Specification 3.4.5.2 action (c) requires reducing the leakage rate to within limits within 4 hours or be in at least hot standby within the next 6 hours and in cold shutdown within the following 30 hours.
"On 03/10/2023 at 0237 the plant discovered an unisolable RCS leak in the reactor coolant pump 1B cubicle and initiated action to complete a plant shutdown required by Technical Specifications. This event is being reported as a 4-hour report in accordance with 10 CFR 50.72(b)(2)(i) as the initiation of plant shutdown required by technical specifications. Reactor was tripped at 0521 CST on 3/10/2023."