Event Notification Report for April 30, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/29/2023 - 04/30/2023
Agreement State
Event Number: 56496
Rep Org: Florida Bureau of Radiation Control
Licensee: Atkins North Americal
Region: 1
City: Tampa State: FL
County:
License #: 0689-2
Agreement: Y
Docket:
NRC Notified By: Reno Fabii
HQ OPS Officer: Kerby Scales
Licensee: Atkins North Americal
Region: 1
City: Tampa State: FL
County:
License #: 0689-2
Agreement: Y
Docket:
NRC Notified By: Reno Fabii
HQ OPS Officer: Kerby Scales
Notification Date: 04/30/2023
Notification Time: 23:14 [ET]
Event Date: 04/30/2023
Event Time: 00:00 [EDT]
Last Update Date: 04/30/2023
Notification Time: 23:14 [ET]
Event Date: 04/30/2023
Event Time: 00:00 [EDT]
Last Update Date: 04/30/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Henrion, Mark (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Henrion, Mark (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
AGREEMENT STATE REPORT - STOLEN TROXLER GAUGES
The following information was received from the Florida Bureau of Radiation Control via email:
"[The Florida Bureau of Radiation Control] received a call from the [Radiation Safety Officer] RSO at Atkins North America, reporting the theft of five Troxler gauges from their facility in Tampa, FL. Tampa Police report number 23-18111075.
"1) Model 3440, serial number 27848, source serial number Cs 750-1764, AmBe 47-24477
"2) Model 3440, serial number 23089, source serial number Cs 75-4899, AmBe 47-18903
"3) Model 3430, serial number 27128, source serial number Cs 750-846, AmBe 47-23647
"4) Model 3440, serial number 32293, source serial number Cs 750-7450, AmBe 47-10058
"5) Model 3440, serial number 29466, source serial number Cs 750-3720, AmBe 47-26413"
Activity for each gauge:
Cesium-137 8mCi
Am-Be 40mCi
Florida Incident Number: FL23-061
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 Florida Bureau of Radiation Control via email:
"[The Florida Bureau of Radiation Control] received a call from the [Radiation Safety Officer] RSO at Atkins North America, reporting the theft of five Troxler gauges from their facility in Tampa, FL. Tampa Police report number 23-18111075.
"1) Model 3440, serial number 27848, source serial number Cs 750-1764, AmBe 47-24477
"2) Model 3440, serial number 23089, source serial number Cs 75-4899, AmBe 47-18903
"3) Model 3430, serial number 27128, source serial number Cs 750-846, AmBe 47-23647
"4) Model 3440, serial number 32293, source serial number Cs 750-7450, AmBe 47-10058
"5) Model 3440, serial number 29466, source serial number Cs 750-3720, AmBe 47-26413"
Activity for each gauge:
Cesium-137 8mCi
Am-Be 40mCi
Florida Incident Number: FL23-061
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: 56494
Facility: Hope Creek
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Christopher Furst
HQ OPS Officer: Karen Cotton-Gross
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Christopher Furst
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 04/30/2023
Notification Time: 02:30 [ET]
Event Date: 04/30/2023
Event Time: 01:00 [EDT]
Last Update Date: 04/30/2023
Notification Time: 02:30 [ET]
Event Date: 04/30/2023
Event Time: 01:00 [EDT]
Last Update Date: 04/30/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation 50.72(b)(3)(ii)(A) - Degraded Condition
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation 50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Henrion, Mark (R1DO)
Henrion, Mark (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PRIMARY CONTAINMENT INTEGRITY DEGRADED
The following information was provided by the licensee via email:
"At 0100 EDT on 04/30/23, it was determined that the primary containment integrity did not meet [Technical Specification] TS 4.6.1.1.d requirement, suppression chamber in compliance with TS 3.6.2.1 due to the inability to establish test conditions for the bypass leakage test in accordance with TS 4.6.2.1.f.
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D) & 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"At 0100 EDT on 04/30/23, it was determined that the primary containment integrity did not meet [Technical Specification] TS 4.6.1.1.d requirement, suppression chamber in compliance with TS 3.6.2.1 due to the inability to establish test conditions for the bypass leakage test in accordance with TS 4.6.2.1.f.
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D) & 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 56495
Facility: Hope Creek
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Christopher Furst
HQ OPS Officer: Karen Cotton-Gross
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Christopher Furst
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 04/30/2023
Notification Time: 02:30 [ET]
Event Date: 04/30/2023
Event Time: 02:00 [EDT]
Last Update Date: 04/30/2023
Notification Time: 02:30 [ET]
Event Date: 04/30/2023
Event Time: 02:00 [EDT]
Last Update Date: 04/30/2023
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):
Henrion, Mark (R1DO)
Henrion, Mark (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via email:
"At 0200 EDT on 04/30/23, a Technical Specification required shutdown was initiated at Hope Creek Unit 1. Technical Specification Action 3.6.1.1 Primary Containment Integrity was entered on 04/30/23 at 0100 with a required action to restore primary containment integrity within 1 hour. This required action was not completed within the allowed outage time; therefore, a Technical Specification required shutdown was initiated, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"At 0200 EDT on 04/30/23, a Technical Specification required shutdown was initiated at Hope Creek Unit 1. Technical Specification Action 3.6.1.1 Primary Containment Integrity was entered on 04/30/23 at 0100 with a required action to restore primary containment integrity within 1 hour. This required action was not completed within the allowed outage time; therefore, a Technical Specification required shutdown was initiated, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."