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Alert

The NRC is shutdown due to the lapse in appropriations. Exempted activities to maintain critical health and safety activities and progress on critical activities, including activities outlined in Executive Order 14300, as described in the OMB Approved NRC Lapse Plan will continue.

Event Notification Report for September 13, 2021

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
09/12/2021 - 09/13/2021

Power Reactor
Event Number: 55451
Facility: Grand Gulf
Region: 4     State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Gabe Hargrove
HQ OPS Officer: Kerby Scales
Notification Date: 09/09/2021
Notification Time: 04:19 [ET]
Event Date: 09/09/2021
Event Time: 00:33 [CDT]
Last Update Date: 09/09/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
TAYLOR, NICK (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 70 Power Operation 80 Power Operation
Event Text
EN Revision Imported Date: 9/13/2021

EN Revision Text: HIGH PRESSURE CORE SPRAY INOPERABLE

At 0033 CDT on September 9, 2021, Grand Gulf Nuclear Station (GGNS) was operating at 70 percent power when the High Pressure Core Spray (HPCS) was declared inoperable. The inoperability determination was made due to control room annunciations. In accordance with GGNS Technical Specification 3.5.1.B.1, the Reactor Core Isolation Cooling system was verified to be operable. Troubleshooting is in progress.

This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as an event or condition which could have prevented the fulfillment of a safety function.

The NRC Resident Inspector has been notified.


Part 21
Event Number: 55453
Rep Org: AMETEK SOLIDSTATE CONTROLS
Licensee: AMETEK SOLIDSTATE CONTROLS
Region: 3
City: Columbus   State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Ethan Salsbury
HQ OPS Officer: Donald Norwood
Notification Date: 09/09/2021
Notification Time: 13:53 [ET]
Event Date: 09/09/2021
Event Time: 00:00 [EDT]
Last Update Date: 09/09/2021
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
DENTEL, GLENN (R1DO)
MILLER, MARK (R2DO)
RIEMER, KENNETH (R3DO)
TAYLOR, NICK (R4DO)
PART 21/50.55 REACTORS, - (EMAIL)
Event Text
EN Revision Imported Date: 9/13/2021

EN Revision Text: PART 21 REPORT - NONCONFORMING RELAY LED TO FAILURES OF BATTERY CHARGERS

The following is a synopsis of information received via E-mail:

Component Description:
AMETEK Part Number 07-740108-00, K306 relay, used in the float/equalize circuit of AMETEK Battery Chargers. The relay is a solid-state timer manufactured by Omron with manufacturer part number H3CR-A-AC100-240/DC100125.

Problem You Could See:
AMETEK was notified of a condition of a nonconforming K306 relay that led to failures of battery chargers. AEP DC Cook reported a single failure of a K306 Float/Equalize timer relay in a controlled environment where the relay failed to transfer from float to equalize and caused the DC output to fail. Transferring the battery charger to equalize mode is always a manual operation and the float/equalize function is typically used after an outage or a discharge test in order to bring the batteries back to full charge. Before performing a discharge test, the charger should be put in equalize mode. AMETEK was not able to evaluate this specific instance of failure, but it was determined the circuit does not meet the minimum contact current rating. As a result, the operation of the relay may be unreliable and the charger may experience a loss of output when equalize is initiated, failing to charge the batteries. The failed relay was installed in 2017 and was original to the equipment.

Effect on System Performance:
If the charger fails to transfer between float and equalize, the equalize light may turn on, the charger output will fail, voltage will drop below float voltage or to 0, and there will be no charging capabilities. An alarm will indicate Low DC voltage in the event the charger does not transfer between float and equalize. The charger will restart after the AC input breaker is cycled Off and On. The relay should be replaced if the charger output is lost. Other alarm(s) may be included with the design:
- Battery Discharge Alarm
- Low Current Alarm
The battery will charge with float voltage, but will take longer than with equalize voltage (~8-24 hours after charging current stabilizes).

The safety impact is a loss of battery charger output after an event where the float/equalize button is utilized and does not retransfer to equalize for charging. If the charger fails to transfer and the output is lost prior to a safety event, the battery may not be at full capacity for a shutdown. Each utility will need to evaluate the application of the battery charger and the battery it is charging.

Affected Entities:
Alabama Power Company; Arkansas Nuclear One; Atomic Energy of Canada; Constellation Energy; Consumer's Power, Palisades; Dominion - Kewaunee; Dominion Energy; Dominion Inc.; Duke Energy; Duke Power Co.; EM Test (Switzerland) GMBH; Engine Systems; Ergytech Inc.; Exelon; Exelon Generation Co.; First Energy; Formosa Nextech Co.; Framatome Technologies; Georgia Power; Indiana Michigan Power Co.; Millstone Nuclear Power Station; Niagara Mohawk; NPP Krsko; Progress Energy; TVA; TVA Watts Bar; Ulysses - Taiwan Power; and Ulysses System Development.

Ametek Contact: Ametek Solidstate Controls Client Services group, 1-800-222-9079 or 614-846-7500, extension 1.


Power Reactor
Event Number: 55455
Facility: Three Mile Island
Region: 1     State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: Brian Miscavage
HQ OPS Officer: Thomas Kendzia
Notification Date: 09/10/2021
Notification Time: 14:45 [ET]
Event Date: 09/10/2021
Event Time: 10:55 [EDT]
Last Update Date: 09/10/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification 72.75(b)(2) - Press Release/Offsite Notification
Person (Organization):
DENTEL, GLENN (R1)
MILLER, CHRIS (NRR EO)
RIVERA-CAPELLA, GRETCHEN (NMSS DAY)
GOTT, WILLIAM (IR)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Defueled 0 Power Operation
Event Text
OFFSITE NOTIFICATION DUE TO CONTRACTOR FATALITY

"This is a four-hour notification, non-emergency for a notification of another government agency. This event is being reported under 10 CFR 50.72(b)(2)(xi) and 10 CFR 72.75(b)(2).

"At 1055 EDT on 9/10/21, an employee of a site contractor that was performing work under a contract and in possession of the immediate area where the work was being performed, was involved in a material handling accident in the owner controlled area at Three Mile Island. Londonderry Township EMS and Fire responded to render assistance to the individual. Upon arrival to the site, medical personnel declared the individual deceased.

"The fatality was work related and the individual was outside of the Radiological Controlled Area."


Power Reactor
Event Number: 55457
Facility: North Anna
Region: 2     State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: David McGowan
HQ OPS Officer: Thomas Kendzia
Notification Date: 09/12/2021
Notification Time: 22:41 [ET]
Event Date: 09/12/2021
Event Time: 17:28 [EDT]
Last Update Date: 09/12/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
MILLER, MARK (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
EN Revision Imported Date: 9/14/2021

EN Revision Text: DEGRADED CONDITION IDENTIFIED WHILE UNIT SHUTDOWN

"On September 12, 2021, at 1728 EDT, with Unit 1 in Mode 5 (Cold Shutdown) while performing inspections of the North Anna Power Station Unit 1 reactor vessel head flange area, a weld leak was identified on the reactor vessel flange leak-off line that connects to the flange between the inner and outer head o-rings. Entered TRM 3.4.6 Condition B for ASME Code Class 1,2, and 3 components. With known leakage past the inner head o-ring, this condition is reported since the fault in the tubing is considered pressure boundary [Reactor Coolant System] leakage.

"This event is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(A) for any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded."

The NRC Resident has been notified.


Non-Agreement State
Event Number: 55405
Rep Org: U. S. CUSTOMS SERVICE
Licensee: U. S. Customs and Border Patrol
Region: 1
City: Miami   State: FL
County:
License #: 08-17447-01
Agreement: Y
Docket:
NRC Notified By: David Park
HQ OPS Officer: Jeffrey Whited
Notification Date: 08/13/2021
Notification Time: 13:22 [ET]
Event Date: 08/12/2021
Event Time: 09:00 [EDT]
Last Update Date: 09/13/2021
Emergency Class: Non Emergency
10 CFR Section:
20.2201(a)(1)(i) - Lost/Stolen LNM>1000x
Person (Organization):
WERKHEISER, DAVE (R1)
ILTAB, (EMAIL)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 9/14/2021

EN Revision Text: STOLEN SOURCE REPORT

The following is a summary of a report by Customs and Border Patrol received via telephone:

Five sources were stolen from the back of a truck while it was parked in a hotel lot in the Miami area, after the lock on the truck was broken. The sources were being transported to calibrate Radiation Portal Monitors at Customs and Border Patrol offices in the Miami area.

The theft was reported to the US NRC Region 1 Office and the Miami-Dade Police Department (report number: PD210812-254442).

Source details: Cf-252, 5.16 microCuries (S/N: N7- 402); Co-57, 75.44 microCuries (S/N: 2187-53-6); Co-60, 9.3 microCuries (S/N: 2185-40-6); Ba-133, 6.7 microCuries (S/N: 1794-56-5); and Cs-137, 6.79 microCuries (S/N: 1288-76-5).

* * * UPDATE ON 9/13/2021 AT 1201 EDT FROM SHINKYU PARK TO BRIAN LIN * * *
The following is a summary of a report by Customs and Border Patrol received via email:
At approximately 0900 EDT on August 12, 2021, the licensee discovered that five sources were stolen out of their truck that was parked at the Element Miami International Airport Hotel. The sources were stored in a shielded pelican case and are low activity sealed sources. There is no significant external radiation exposure risk and the sources are extremely robust reducing the potential for any internal exposure if the capsule were breached. A report was filed with local law enforcement.

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


Agreement State
Event Number: 55446
Rep Org: NEW MEXICO RAD CONTROL PROGRAM
Licensee: CHRISTUS St. Vincent Regional Medical Center
Region: 4
City: Santa Fe   State: NM
County:
License #: General License
Agreement: Y
Docket:
NRC Notified By: Carl Sullivan
HQ OPS Officer: Donald Norwood
Notification Date: 09/07/2021
Notification Time: 12:30 [ET]
Event Date: 08/06/2021
Event Time: 00:00 [MDT]
Last Update Date: 09/07/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
TAYLOR, NICK (R4)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
ILTAB, (EMAIL)
CNSNS (MEXICO) (EMAIL)
Event Text
EN Revision Imported Date: 9/14/2021

EN Revision Text: AGREEMENT STATE REPORT - LOST AMPULES FROM A TRITIUM EXIT SIGN

The following is a synopsis of information received via E-mail:

This event was originally reported via phone to the New Mexico Radiation Control Bureau on August 6, 2021.

This incident involved a double sided (2 sign faces) tritium exit sign. Specific details of the sign are: Radioactive Material: Tritium (H-3), Quantity: 7.5 Ci per sign face, Chemical and Physical form: Gas, Manufacturer: Sign Tex Inc.

This sign was located outside of the hospital building. The sign was damaged, and was then cleaned up by facilities and placed in a trash receptacle. The staff member who cleaned up the sign was confident that none of the glass ampules were broken and that all pieces were collected. The incident was then reported to the Safety Officer and the sign was removed from the waste bin. The Safety Officer then reported the sign to the RSO [Radiation Safety Officer] for guidance on how to properly dispose of the sign. Upon evaluation of the sign it was discovered that a part of one of the sign faces was missing. This piece includes the ampules which make up the letter "T" and an arrow (3 tubes total) of the sign. In addition, the sign casing was reported as missing. The activity information noted above was received from the sign manufacturer based off of the part number listed on the Order Acknowledgement document. The order date was reported as August 23, 2017. As there is no observable original date for the H-3, no decay correction was made in order to be conservative. It is currently assumed that the casing and the missing piece were disposed of, and due to the radiological properties, the piece was not detected by any waste radiation monitors. All remaining pieces of the sign are intact and were observed to glow, confirming that the ampules are not leaking.





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


Agreement State
Event Number: 55447
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: St. Elizabeth Healthcare, Edgewood
Region: 1
City: Edgewood   State: KY
County:
License #: 202-152-27
Agreement: Y
Docket:
NRC Notified By: Anjan Bhattacharyya
HQ OPS Officer: Donald Norwood
Notification Date: 09/07/2021
Notification Time: 15:09 [ET]
Event Date: 08/24/2021
Event Time: 11:00 [CDT]
Last Update Date: 09/07/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
DENTEL, GLENN (R1)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 9/14/2021

EN Revision Text: AGREEMENT STATE REPORT - UNDER-DOSING EVENT WITH Y-90 THERASPHERES

The following information was received via E-mail:

"On 8/24/21, a Y-90 TheraSphere treatment was to deliver a planned 13.65 GBq to the patient's anterior right hepatic lobe. The written instructions were followed in the usual fashion and the dose was administered to the patient. The catheter and administration set tubing were placed into the waste container. The patient, personnel, and room were surveyed. No spill was detected. Upon post-calculation measurements, it was found that the patient only received approximately 77 percent of the expected dose of 200 Gray. While the received 154 Gray was medically appropriate given the patient's condition, tumor type and tumor location, this treatment still fell below that intended on the written directive. Further investigation found that this patient was rescheduled multiple times and the dose had decayed further than it was planned to, the patient really should have been treated the day before on a Monday instead of the Tuesday to get the full dose as planned or a new Treatment Window Illustrator to secure a more appropriate Y-90 dose should have been completed. Patient and referring provider were notified. There were no contaminations verified by survey meter measurements. The licensee is currently implementing an Excel spreadsheet program to review accuracy prior to patient scheduling and dose ordered. Reporting Criteria under 10 CFR 35.3045."

Kentucky Event Report ID No.: KY210002

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.


Power Reactor
Event Number: 55458
Facility: McGuire
Region: 2     State: NC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Travis Rollins
HQ OPS Officer: Bethany Cecere
Notification Date: 09/13/2021
Notification Time: 05:53 [ET]
Event Date: 09/13/2021
Event Time: 00:11 [EDT]
Last Update Date: 09/13/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
MILLER, MARK (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
SPECIFIED SYSTEM ACTUATION

"At 0011 EDT, with Unit 2 in Mode 5 (Cold Shutdown), actuations of the 2B Diesel Generator (DG) and the 2B Motor Driven Auxiliary Feedwater (AFW) Pump occurred during Engineered Safety Features Actuation Periodic Testing while resetting the 2B DG Load Sequencer. The 2B DG was running unloaded following test actuation, and during realignment from the test, a blackout condition was experienced when the breaker opened supplying the 4160 Volt Essential Power System 2ETB from the Standby Auxiliary Power Transformer SATB. Sequencer actuation closed the emergency breaker to 2ETB and loaded the 2B Motor Driven AFW Pump onto the bus. Steam supply valves to the Turbine Driven AFW Pump were open from the previous test configuration.

"This event is being reported in accordance with 10CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the 2B DG and the 2B Motor Driven AFW Pump.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."