2023 Reactor Actions

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Virgil C. Summer Nuclear Station (EA-23-093)

On December 21, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Dominion Energy (licensee) at the Virgil C. Summer Nuclear Station. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to identify and correct the failure mechanism resulting in cracked piping/fittings in the emergency diesel generator (EDG) fuel oil lines, a condition adverse to quality, and a violation of Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix B, Criterion XVI, “Corrective Action.” This eventually led to the failure of the ‘A’ EDG fuel oil piping during testing on November 2, 2022.

Columbia Generating Station (EA-23-054)

On November 1, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Energy Northwest (licensee) at the Columbia Generating Station. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to take suitable and timely measurements to adequately assess the internal dose of two pipefitters after a reactor water cleanup contamination event. This failure resulted in a violation of Title 10 of the Code of Federal Regulations 20.1204 "Determination of internal exposure."

Calvert Cliffs Nuclear Power Plant (EA-23-097)

On October 26, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Constellation Energy Generation, LLC at Calvert Cliffs Nuclear Power Plant. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to establish and implement appropriate procedures and instructions for performing maintenance on the safety-related 1A emergency diesel generator as required by Technical Specification 5.4.1.a and Regulatory Guide 1.33.

Joseph M. Farley Nuclear Plant (EA-23-080)

On October 19, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Southern Nuclear Operating Company, Inc. (licensee) at the Joseph M. Farley Nuclear Plant, Unit 1. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to identify and correct a condition adverse to quality associated with the inadequate installation of a lube oil coupling assembly that resulted in the inoperability of the Unit 1 ‘B’ train (1B) emergency diesel generator (EDG). This failure resulted in a violation of Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix B, Criterion XVI, “Corrective Action.” With the 1B EDG inoperable, the licensee also failed to meet the Technical Specification Limiting Condition for Operations 3.0.1 and 3.8.1 between December 7, 2022 and March 3, 2023.

Oyster Creek Nuclear Generating Station (EA-23-076)

On November 9, 2023, the NRC issued a notice of violation and proposed imposition of civil penalty in the amount of $43,750 to Holtec Decommissioning International, LLC (licensee) for a Severity Level III violation. The violation involved the failure by the licensee’s staff at Oyster Creek to design and prepare radioactive materials for shipment so that, under conditions normally incident to transportation, the radiation level did not exceed 200 mrem/hour at any point on the external surface of the package. Specifically, on May 3, 2023, the licensee’s staff at Oyster Creek shipped reactor segmentation tooling that had a maximum contact dose rate of 450 mrem/hour, contrary to Title 10 of the Code of Federal Regulations (10 CFR) Part 71.5.

River Bend Station (EA-23-071)

On August 15, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Entergy Operations, Inc. (licensee) at the River Bend Station. The white finding, an issue of low-to-moderate safety significance, involved the failure to properly calibrate radiation monitors and the associated impacts on emergency action level classification and dose assessment to meet the requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b), as required by 10 CFR 50.54(q)(2).

River Bend Station (EA-23-055)

On July 20, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Entergy Operations, Inc. at River Bend Station. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to adequately inspect the high-pressure core spray transformer wiring in accordance with site maintenance procedures as required by Technical Specification 5.4.1.a and Regulatory Guide 1.33.

Columbia Generating Station (EA-21-170)

On June 1, 2023, the NRC issued a notice of violation to Energy Northwest, Inc. (licensee) for three violations grouped as a problem associated with a white significance determination process finding at Columbia Generating Station (Columbia). The white finding, an issue of low‑to‑moderate safety significance, involved the licensee’s failure to: 1) control work activities in a high radiation area with dose rates greater than 1.0 rem/hour at 30 centimeters; 2) develop surveys of areas that were reasonable under the circumstances to evaluate the magnitude and extent of radiation levels; and 3) use processes or other engineering controls to limit the concentration of radiation material in the air surrounding a work area. These failures are in violation of 10 CFR 20.1701, Columbia Technical Specifications, and 10 CFR 20.1501(a)(2), respectively, which resulted in an airborne radioactivity event and multiple confirmed uptakes of radioactive materials to workers.

University of Texas at Austin (EA-22-134)

On May 10, 2023, the NRC issued a notice of violation to the University of Texas at Austin (licensee) for one Severity Level (SL) III violation. The SL III violation involved the licensee’s operation of the research reactor with fuel elements that did not comply with Technical Specifications. Specifically, the reactor was operated with two non-conforming aluminum cladded fuel elements installed in the reactor core.

Browns Ferry Nuclear Plant, Unit 1 (EA-22-122)

On May 8, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to the Tennessee Valley Authority (licensee) at Browns Ferry Nuclear Plant, Unit 1 (BFN1). The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to promptly identify and correct a condition adverse to quality as required by Title 10 of the Code of Federal Regulations Part 50, Appendix B, Criterion XVI. This failure resulted in the inoperability of the BFN1 high‑pressure coolant injection system.

Waterford Steam Electric Station, Unit 3 (EA-22-119)

On February 1, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Entergy Operations, Inc. (licensee) at the Waterford Steam Electric Station, Unit 3. The white finding, an issue of low-to-moderate safety significance, involved licensee errors associated with the engineering conversion factors used with the plant stack wide range gas monitor (WRGM) which made the results of radiological dose projection modeling inaccurate in cases using the plant stack WRGM. Accordingly, the licensee failed to maintain the effectiveness of an emergency plan that met the requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix E, and the planning standards of 10 CFR 50.47(b), as required by 10 CFR 50.54(q)(2).

Southern Nuclear Operating Company, Inc. (EA-22-108)

On September 5, 2023, the NRC issued a notice of violation (Notice) to Southern Nuclear Operating Company, Inc (licensee) for a Severity Level (SL) III violation at Vogtle Electric Generating Plant Units 1 and 2. The SL III violation involved the licensee’s failure to follow a radiological work permit (RWP) as required by licensee technical specifications. Specifically, three contract employees entered the containment building on an improper RWP.

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