Event Notification Report for June 07, 2024

EN Revision Imported Date: 6/6/2024

EN Revision Text: AUTOMATIC START OF 'B' EMERGENCY DIESEL GENERATOR

The following information was provided by the licensee via phone and email:

"On February 19, 2024, at 0236 EST, with VC Summer Unit 1 in Mode 1 at 100 percent power, an actuation of the `B' emergency diesel generator (EDG) occurred. The reason for the `B' EDG auto-start was the trip of 1 `DB' normal incoming breaker. The `B' EDG automatically started as designed when the undervoltage signal was received. The `B' emergency feedwater pump started due to the undervoltage signal and ran for approximately 1 minute and was secured by operations per procedure. Other plant equipment and systems also responded as expected. 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 `B' EDG and a valid actuation of the `B' emergency feedwater pump. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

"The `A' Emergency Diesel Generator was tagged out for maintenance earlier in the shift, but maintenance has not started. The plan is to restore the `A' emergency diesel generator to an operable status and investigate the cause of the 1 `DB' normal incoming breaker trip."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

This event resulted in the plant entering a 12 hour limiting condition for operation (LCO) in accordance with technical specification (TS) 3.8.1.1.C. due to having one operable EDG and a loss of offsite power.

*** RETRACTION ON 06/06/2024 AT 1356 EDT FROM JUSTIN BOUKNIGHT TO NATALIE STARFISH ***

"VC Summer is retracting event notification (EN) 56978 regarding the unexpected actuations of the 'B' emergency diesel generator and 'B' emergency feedwater pump on 02/19/2024. Both were previously reported as valid actuations under 10 CFR 50.72(b)(3)(iv)(A). Subsequent evaluation has determined that the actuations were the result of an invalid signal caused by equipment failure on the 1 DB bus undervoltage control circuit.

"The event, its cause, and corrective actions were reported in VC Summer licensee event report 2024-001-00 (ML24108A143) on 04/17/2024, pursuant to the requirements of 10 CFR 50.73(a)(2)(iv)(A). There was no impact on the health and safety of the public or plant personnel as a result of the actuations.

"The NRC Senior Resident Inspector has been notified."

Notified R2DO (Franke)

AGREEMENT STATE REPORT - STUCK SHUTTER

The following information was provided by the New Jersey Department of Environmental Protection via email:

"While performing routine 6-month fixed gauge shutter checks, the licensee became aware of a shutter that was stuck partially open. The fixed gauge is located 20 feet above a platform and only accessible to licensee staff via scaffolding. No member of the public has access to this location.

"The shutter is currently in its normal open position. No maintenance activities are scheduled which would require closure of the shutter.

"The licensee has a contract with the manufacturer. They have scheduled them to assess this situation and make any necessary repairs."

Gauge information: Cs-137 sealed source in Ohmart/Vega holder SH-F2 (s/n 0361CG), max activity 300 mCi. Leak test conducted October 2023. No detectable leakage.

NJ Event ID Number: To Be Determined

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE.

The following information was provided by the Texas Department of State Health Services (the Department) via email:

"On May 30, 2024, the Department was notified by the licensee's radiation safety officer (RSO) that a Humboldt 5001 moisture density gauge was damaged at a temporary job site. The gauge contains a 40 millicurie americium-241 source and a 10 millicurie cesium-137 source. The RSO stated the technicians were standing next to the gauge waiting to perform a test when a drum compactor ran next to them and ran over the gauge. The gauge case was damaged. The cesium source operating rod was broken, but the cesium source remained fully shielded. The americium-241 source was still in its housing. Dose rates at the gauge were normal. No overexposures occurred due to the event. The gauge was returned to its storage location. The technicians contacted a service company to inspect and repair the gauge. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident Number: I-10108
Texas NMED Number: TX240016

AGREEMENT STATE REPORT - POTENTIAL UNPLANNED CONTAMINATION EVENT

The following information was provided by the Florida Bureau of Radiation Control (BRC) via email and phone:

"On May 30, 2024, at 1710 [EDT], BRC received a notification from Cape Coral Fire [department] concerning a deceased individual's body 'exploding' while being cremated. The BRC received this notification because the deceased individual was known to have been receiving pancreatic cancer treatment. A notification was also received from the State watch office. The son of the deceased stated that he did not believe that the deceased had received treatment within the last two months, but he was unsure. Crematory staff stated that a large flame exited the bottom of the oven and they began to feel sick. A crematory employee stated that the body completed the cremation process in half the time expected. The Cape Coral Fire [department] responded. Background readings were observed at 3 micro R/hr and readings within the incident room registered at 10 micro R/hr. An inspector has been assigned by regional manager for immediate response."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The contaminated areas have been isolated and locked until the inspector arrives.

Florida Incident Number: FL24-041

* * * UPDATE ON 5/31/2024 AT 1215 EDT FROM MONROE COOPER TO ERNEST WEST * * *

"The elevated [background] readings were identified as thorium in the bricks."

Notified R1DO (DeFrancisco) and NMSS Events via email.

AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

The following information was provided by the New York State Department of Health (NYSDOH) via email and phone:

"The NYSDOH received a phone call from the Radiation Safety Officer (RSO) at 0953 EDT on May 31, 2024, reporting a stolen portable moisture/density gauge.

"At approximately 0700 [on May 31, 2024,] an authorized user (AU) went to their vehicle and noticed that the back window was open and the vehicle was unlocked. The AU inspected the internal cab of the vehicle and did not notice anything missing and then drove to a job site. Upon arrival at the job site, the AU realized the gauge was stolen and called the RSO. The RSO instructed the AU to return to the the original location and called the police. The lock on the storage case was found broken, and the gauge was removed from the storage case."

Device information:
Device Make: Troxler
Device Model: 3430
Device Serial Number: 21150
Isotope: Am-241/Be (44 mCi) and Cs-137 (9 mCi)

NY Incident Number: 1488

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

NON-AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE

The following information was provided by the licensee via phone:

On May 31, 2024, a moisture density gauge (InstroTek Xplorer, model: 3500, serial number: 5130, 10 mCi Cs-137, 40 mCi Am-241:Be) could not be found when an authorized user went to retrieve it from storage for calibration at their Dexter, MI office. The gauge was last inventoried on November 16, 2023, at the licensee's Ann Arbor office location and then relocated in January, 2024, to their Dexter location. The licensee inspected their former Ann Arbor location and verified that the space was empty. The licensee's Radiation Safety Officer is currently directing ongoing search efforts.

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

PRIMARY CONTAINMENT ISOLATION DUE TO LOSS OF RPS POWER SUPPLY

The following information was provided by the licensee via fax or email:

"On June 4, 2024, at 2141 PDT, with the unit in Mode 1 at 100 percent power, the reactor protection system (RPS) 'B' power supply unexpectedly de-energized which caused containment isolations to occur in reactor water clean up, equipment drains radioactive, floor drains radioactive, reactor recirculation, and traversing in-core probe systems. All actuations occurred as designed upon the partial loss of RPS power.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(xiii) as a major loss of emergency assessment capability due to the inability to assess primary containment identified and unidentified leakage rates. Emergency assessment capability was restored at 2204."

The NRC Senior Resident has been notified.

MANUAL REACTOR TRIP

The following information was provided by the licensee via email:

"At 1648 EDT on 06/05/2024, with Unit 4 in Mode 1 at approximately 35 percent power, the reactor was manually tripped due to unexpected response of the turbine run back circuitry following a trip of main feedwater pump `C'. The trip was not complex, with all safety systems responding normally post-trip.

"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam through the steam dumps to the main condenser and main feedwater is supplying the steam generators. Units 1, 2 and 3 are not affected.

"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).

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