Event Notification Report for April 13, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/12/2024 - 04/13/2024
Agreement State
Event Number: 57078
Rep Org: California Radiation Control Prgm
Licensee: Testing Engineers, Inc.
Region: 4
City: Concord State: CA
County:
License #: 3691-07
Agreement: Y
Docket:
NRC Notified By: K. Arunika Hewadikaram
HQ OPS Officer: Ernest West
Licensee: Testing Engineers, Inc.
Region: 4
City: Concord State: CA
County:
License #: 3691-07
Agreement: Y
Docket:
NRC Notified By: K. Arunika Hewadikaram
HQ OPS Officer: Ernest West
Notification Date: 04/16/2024
Notification Time: 15:57 [ET]
Event Date: 04/13/2024
Event Time: 00:00 [PDT]
Last Update Date: 04/16/2024
Notification Time: 15:57 [ET]
Event Date: 04/13/2024
Event Time: 00:00 [PDT]
Last Update Date: 04/16/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Young, Cale (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSNS (Mexico), - (EMAIL)
Young, Cale (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSNS (Mexico), - (EMAIL)
AGREEMENT STATE - STOLEN GAUGE
The following information was provided by the California Department of Public Health, Radiologic Health Branch (RHB) via email:
"On 4/15/2024, the California Office of Emergency Services (OES) forwarded a report from Testing Engineers, Inc. The radiation safety officer (RSO) notified OES that one of their nuclear gauges (CPN MC-1, serial number MD71108870 containing 10 mCi of Cs-137 and 50 mCi of Am-241) was stolen from a storage unit that is located within a public storage facility in Concord, CA. The gauge was stolen from the storage unit at an unknown time between 04/13/2024 and 04/14/2024, but was discovered missing at 1541 [PDT] on 04/15/2024. A car was used to ram the door of the storage unit, and a pry bar was used to remove the gauge from a locked cabinet. Local law enforcement was notified, and a reward was posted on Craigslist, Facebook, and Nextdoor for the safe return of the gauge.
"RHB will investigate the incident."
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 provided by the California Department of Public Health, Radiologic Health Branch (RHB) via email:
"On 4/15/2024, the California Office of Emergency Services (OES) forwarded a report from Testing Engineers, Inc. The radiation safety officer (RSO) notified OES that one of their nuclear gauges (CPN MC-1, serial number MD71108870 containing 10 mCi of Cs-137 and 50 mCi of Am-241) was stolen from a storage unit that is located within a public storage facility in Concord, CA. The gauge was stolen from the storage unit at an unknown time between 04/13/2024 and 04/14/2024, but was discovered missing at 1541 [PDT] on 04/15/2024. A car was used to ram the door of the storage unit, and a pry bar was used to remove the gauge from a locked cabinet. Local law enforcement was notified, and a reward was posted on Craigslist, Facebook, and Nextdoor for the safe return of the gauge.
"RHB will investigate the incident."
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: 57075
Facility: Beaver Valley
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: James (Jake) Davis
HQ OPS Officer: Thomas Herrity
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: James (Jake) Davis
HQ OPS Officer: Thomas Herrity
Notification Date: 04/13/2024
Notification Time: 03:55 [ET]
Event Date: 04/13/2024
Event Time: 00:35 [EDT]
Last Update Date: 04/13/2024
Notification Time: 03:55 [ET]
Event Date: 04/13/2024
Event Time: 00:35 [EDT]
Last Update Date: 04/13/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Defrancisco, Anne (R1DO)
Defrancisco, Anne (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 97 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 4/15/2024
EN Revision Text: AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 0035 EDT on April 13, 2024, with Unit 1 at 97 percent power, the reactor automatically tripped due to 1 of 3 reactor coolant pump (RCP) low flow reactor trip [signal] associated with a loss of the 'A' and 'B' 4160 volt normal buses. Auxiliary feedwater and the 1-1 emergency diesel generator (EDG) automatically started on valid actuation signals. The 1-1 EDG sequenced on to supply all required loads per plant design. All control rods fully inserted and the trip was not complex with all systems responding normally post-trip. Operators have responded and stabilized the unit in Mode 3 [Hot Standby]. Decay heat is being removed by discharging steam to the main condenser via the condenser steam dump system with steam generators being supplied by the main feedwater system.
"Unit 2 is not affected by the event.
"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).
"Due to the valid actuations of auxiliary feedwater and the 1-1 EDG, this event is reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A).
"There was no impact to the health and safety of the public or plant personnel. The NRC senior resident inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Power for the A-E Bus is on the 1-1 EDG. The D-F Bus is on offsite power. One electrical train of offsite power is down.
EN Revision Text: AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 0035 EDT on April 13, 2024, with Unit 1 at 97 percent power, the reactor automatically tripped due to 1 of 3 reactor coolant pump (RCP) low flow reactor trip [signal] associated with a loss of the 'A' and 'B' 4160 volt normal buses. Auxiliary feedwater and the 1-1 emergency diesel generator (EDG) automatically started on valid actuation signals. The 1-1 EDG sequenced on to supply all required loads per plant design. All control rods fully inserted and the trip was not complex with all systems responding normally post-trip. Operators have responded and stabilized the unit in Mode 3 [Hot Standby]. Decay heat is being removed by discharging steam to the main condenser via the condenser steam dump system with steam generators being supplied by the main feedwater system.
"Unit 2 is not affected by the event.
"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).
"Due to the valid actuations of auxiliary feedwater and the 1-1 EDG, this event is reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A).
"There was no impact to the health and safety of the public or plant personnel. The NRC senior resident inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Power for the A-E Bus is on the 1-1 EDG. The D-F Bus is on offsite power. One electrical train of offsite power is down.