Event Notification Report for June 02, 2023

AUTOMATIC REACTOR TRIP

The following information was provided by the licensee via email:

"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS [Emergency Notification System] or under the reporting requirements of 10 CFR 50.73.

"At 0405 MDT on June 2, 2023, the Unit 2 reactor automatically tripped on low steam generator water levels due to degraded flow from the A main feedwater pump. Steam generator water levels reached the automatic Auxiliary Feedwater Actuation System (AFAS) setpoint resulting in automatic AFAS-1 and AFAS-2 actuations and subsequent start of both class auxiliary feedwater pumps.

"Steam Generator water levels are being restored to normal band with the class 1E powered motor driven auxiliary feedwater pump.

"Following the reactor trip, all control element assemblies inserted fully into the core. No emergency plan classification was required per the Emergency Plan. Safety related buses remained powered from offsite power during the event and the offsite power grid is stable. Both emergency diesel generators automatically started on the AFAS-1 and AFAS-2 actuations as designed and are currently running unloaded. This event is being reported as a reactor protection system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and a specified system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A).

"The NRC Senior Resident Inspector has been informed. Unit 1 and 3 are in Mode 1 at 100 percent power."

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

Decay heat is being removed to main condenser via automatic steam bypass and B auxiliary feedwater pump.

UNSCHEDULED SHUTDOWN

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

"An unscheduled shutdown of the reactor occurred on 6/2/23 at 0818 EDT due to an abnormal response of the Safety Power Level channel during the approach to power of 1 MW at 150 kW. The Reactor Operator observed a discrepancy in power indications by the Linear Power Level and Safety Power Level channels and took immediate actions required by procedure NRP-OP-105, Response to SCRAMS, Alarms, and Abnormal Conditions. The reactor was shut down and secured immediately. The Designated Senior Reactor Operator was immediately notified.

"The Safety Power Level channel is required to be operable per Technical Specification 3.3.b Table 3.3-1 while the reactor is being operated. During the startup checklist, the channel performed satisfactorily. The Safety Power Level channel is part of the reactor safety system and has two automatic shutdowns (SCRAMs) associated with it. Reactor power was correctly monitored by all other operable power monitoring channels which have redundant SCRAM capabilities. No SCRAM occurred or was needed due to the power level of the reactor. Following the reactor shutdown, the reactor staff investigated and determined that the high voltage power supply in the Safety Power channel was faulty. The power supply was replaced and a channel calibration of the Safety Power channel will be performed using procedure PS 1-05-03A:S1 to verify the channel is operable. Maintenance Log #0888 has been opened. There was no safety issue with this event. Procedures were followed during reactor operation, shutdown, and the investigation.

"This unscheduled shutdown is a reportable event per TS 6.7.1 based on the circumstances and as defined in the facility Technical Specification (TS 1.2.24.d) for reportable events from operation in violation of Limiting Conditions for Operation (LCO) established in TS. TS 1.2.24.d, does not allow for an exception for taking prompt remedial action.

"A report to the NRC is required within one working day and will be made by 1700 EDT by phone on 6/2/23, as required by TS 6.7.1. Also as required by TS 6.7.1, a written report to the NRC is due in 14 days (6/16/23)."

EN Revision Imported Date: 6/23/2023

EN Revision Text: FITNESS-FOR-DUTY REPORT

The following information was provided by the licensee via email:

"On June 2, 2023, a blind specimen provided to a laboratory did not analyze as expected. The specimen reported a false negative for amphetamines and a false positive for opiates.

"This event is being reported pursuant to 10 CFR 26.719(c)(2) and 10 CFR 26.719(c)(3).

"The NRC Resident Inspector has been notified."

* * * RETRACTION AT 0909 EDT ON JUNE 22, 2023 FROM ANDREW CORRETTE TO BRIAN P. SMITH * * *

"Follow-up investigation by an independent Health and Human Services laboratory confirmed that the blind specimen in question was analyzed correctly. The error is thought to have occurred during the preparation of the blind specimen, prior to delivery to the site.

"The NRC Resident Inspector has been notified."

Notified R1DO (Eve) and FFD Group (email)

AGREEMENT STATE REPORT - MISSING SOURCES

The following report was received via email from the Georgia Radioactive Material Program [the Department]:

"On Thursday, August 31, 2023, the radiation safety officer (RSO) reported two missing solution standard sources of Am-241, 1.0 microcurie each (37 kBq each) to the Department. These two sources were lost during transportation to Nuclear Fuel Services located in Erwin, Tennessee on June 2, 2023. The customer, Nuclear Fuel Services, notified the licensee that they did not receive the shipment package. The RSO contacted the common carrier to trace its whereabouts. On June 26, 2023, the common carrier's records show that the shipment was signed for by an individual at Nuclear Fuel Services. However, Nuclear Fuel Services confirmed that they did not receive this shipment. There is a communication discrepancy between the common carrier and Nuclear Fuel Services. Currently, the licensee is waiting for a detailed response from the customer regarding this shipment."

Georgia Incident Report Number: 69

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