Event Notification Report for October 05, 2021

EN Revision Imported Date: 10/5/2021

EN Revision Text: AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The following was received via email:

"On Monday, September 27, 2021, Twining, Inc. reported the theft of a CPN MC-1DR #MD01005907 containing sealed sources of Cs-137 (10 mCi) and Am-241 (50 mCi). The theft of a vehicle containing the gauge was reported to the San Bernardino Police Dept. on Sunday, September 26, 2021, when the theft was discovered. Additional information has been requested by CDPH."

California 5010 No.: 092721

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

EN Revision Imported Date: 10/5/2021

EN Revision Text: AGREEMENT STATE REPORT - UNRETRACTABLE SOURCE

The following was received from the state of Texas (the Agency) via email:

"On September 27, 2021, the licensee notified the Agency that one of its industrial radiography crews working at a temporary job site had been unable to retract the source. The crew was using a QSA 880D exposure device, containing a 35 curie iridium-192 source, and they had placed it on pipe approximately two feet off the ground so the guide tube/collimator would reach where the shot was to be taken. After cranking out the source, they recognized the drive cable was not straight and when they pulled back to straighten it, the device fell and bent the guide tube and the source could not be retracted. The source was cranked into the collimator and the radiographers stayed outside their barricade until an authorized person arrived to retrieve the source. The authorized person pulled back on the camera and the guide tube straightened enough so they could retract the source into the fully shielded/locked position. No one received an overexposure as a result of this event. The camera was taken to the manufacturer and the inspection found no issues. The guide tube was removed from service and will be disposed. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident Number: 9887

EN Revision Imported Date: 10/5/2021

EN Revision Text: AGREEMENT STATE REPORT - LOST SOURCE

The following is summary of an event received from the state of Florida via email:

A Cs-137 source (184.3 microcuries) was discovered missing at the Reception and Medical Center (RMC) of the Lake Butler Nuclear Medicine Department, at the Lake Butler Department of Corrections (DOC). The medical center is contracted to operate under Jacksonville Cardiovascular Center. The building is a modular trailer. The missing source was noted during a scheduled inventory. The source is believed to have been moved or relocated by the DOC during construction to repair a collapsed floor. The source is believed to be somewhere in the trailer.

Florida Incident Number: FL21-122

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

EN Revision Imported Date: 10/5/2021

EN Revision Text: SPECIFIED SYSTEM ACTUATION

"At 1525 CDT, 10/3/2021, with Unit 2 in Mode 5 at 0 percent power for a refueling outage, the 22 Turbine-Driven Auxiliary Feedwater (AFW) pump received an actuation signal during preparations for an Integrated Safety Injection test. The reason for the actuation signal is under investigation. The AFW steam admission valve opened and then, due to plant conditions, received a trip signal due to low discharge pressure. The steam supplies to the TD AFW pump were isolated.

"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 AFW system. Unit 1 was not affected by this issue.

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

VALID SYSTEM ACTUATION

"The 'A' Steam Generator Narrow Range Water Level went less than 17 percent causing an Auxiliary Feed Water System valid actuation signal.

"The Auxiliary Feed Water System was in service at the time of the event providing decay heat removal. There was no adverse effect on plant systems. The Steam Generator Narrow Range Water Level was restored to normal operating band.

"This is being reported per 10 CFR 50.72(b)(3)(iv)(A), which states, 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'

"[Reactor Coolant System] RCS Pressure 340 pounds and RCS Temperature 340 Degrees F."

The NRC Resident Inspector was notified.

PART 21 - ACTUATOR FAILURE

The following is a summary of the report provided by Flowserve:

Flowserve - Limitorque was notified by Framatome Nuclear Parts Center that TVA Browns Ferry Nuclear (BFN) plant reported that a Limitorque SMB actuator had failed to operate electrically. It was noted by TVA that the actuator failure was discovered following a recent steam leak in the vicinity of the actuator. Investigation at BFN identified the failed component as the DC electric motor. The motor was removed from the actuator and disassembled by BFN personnel. Subsequently the motor was returned to Flowserve - Limitorque for evaluation. The subject motor is designated as a safety related basic component. Flowserve' s investigation, in conjunction with the motor original equipment manufacturer (OEM), has concluded that during manufacture, the subject motor sustained mechanical damage to the stator assembly field coil which led to the failure. As the dedicating entity, Flowserve is reporting this deviation in the assembly of the motor as a defect per the requirements of 10 CFR 21. Flowserve's investigation has concluded that this manufacturing defect is an isolated occurrence. No other instances of similar mechanical damage to the stator field coil insulation of Peerless DC motors have been observed or reported. The defect is specific to a quantity of one motor originally supplied to Framatome NPC on Limitorque Order Number 164879.001. This motor was subsequently supplied to the TVA Browns Ferry Nuclear Plant.

Identification of Component: Limitorque part # P-140-851-18F0
Description: Peerless 7.5 ft-lb, 250 volt DC motor
Serial Number: E18-99091-2 manufactured in August 2018

Corrective Actions to Date: The motor OEM is implementing additional assembly controls and quality control verification concerning the installation and final appearance of the coil support rod that damaged the stator field coil. This action, to be completed by October 15, 2021 will supplement the existing inspection checks on fully assembled motors, which includes insulation resistance tests and high potential tests which verify the integrity of the motor insulation system.

Technical questions concerning this notification can be directed to Kyle Ramsey, Engineering Specialist, Flowserve - Limitorque Actuation Systems: kramsey@flowserve.com

DEGRADED CONDITION DISCOVERED ON REACTOR VESSEL HEAD PENETRATION

"At 1433 CDT, on October 4, 2021, Arkansas Nuclear One, Unit 2 (ANO-2) completed the analysis related to an indication revealed on head penetration 46 during Reactor Vessel Closure Head inspections. It was determined the indication is not acceptable under ASME code requirements. The indication displays characteristics consistent with primary water stress corrosion cracking. No leak path signal was identified during ultrasonic testing.

"The plant was in cold shutdown at 0 percent power and in Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. This condition has no impact to the health and safety of the public.

"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier. This is the only indication that is currently present, however, if additional indications are found, they will also be repaired prior to the plant startup.

"The NRC Senior Resident Inspector has been notified."