IR 05000458/2025090

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NRC Inspection Report 05000458/2025090 and NRC Investigation Report 4-2024-001
ML25345A164
Person / Time
Site: River Bend 
(NPF-047)
Issue date: 01/27/2026
From: Patricia Vossmar
NRC/RGN-IV/ORA/ACES
To: Hansett P
Entergy Operations
References
EAF-RIV-2025-0232 4-2024-001, IR 2025090
Download: ML25345A164 (0)


Text

January 27, 2026

SUBJECT:

RIVER BEND STATION - NRC INSPECTION REPORT 05000458/2025090 AND NRC INVESTIGATION REPORT 4-2024-001

Dear Mr. Hansett,

This letter refers to the investigation completed on September 25, 2024, by the U.S. Nuclear Regulatory Commissions (NRC) Office of Investigations at River Bend Station (RBS). The investigation was conducted, in part, to determine whether: 1) a licensed senior reactor operator (SRO) willfully stood watch as the Control Room Supervisor (CRS) while unqualified for three days, 2) a licensed SRO willfully failed to perform required procedural actions, resulting in an unqualified SRO performing licensed activities, and if 3) two SROs willfully falsified logs by logging in as the CRS while performing other duties outside the control room. A factual summary of the investigation is provided as an enclosure to this letter. The issue was discussed with Johns Giddens, and other members of your staff, during a telephone conversation on January 15, 2026.

Based on the results of this investigation, the NRC has determined that two Severity Level IV violations of NRC requirements occurred. Because you identified the violations and took prompt action to restore compliance, because the violations did not constitute deliberate misconduct based on the information developed during the NRCs investigation, and because the violations were not repetitive, the two violations are being treated as Non-Cited Violations (NCVs)

consistent with Section 2.3.2 of the Enforcement Policy. These NCVs are described in the enclosed factual summary. If you contest the violations or significance of these NCVs, you should provide a response withing 30 days of the date of this investigation report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001, with copies to: (1) the Regional Administrator, Region IV, 1600 Lamar Blvd., Arlington, TX 76001; and (2) the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter, the enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or in the NRCs ADAMS, accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy or proprietary information so that it can be made available to the public without redaction. If you have any questions concerning this matter, please contact Doug Dodson of my staff at (817) 200-1148.

Sincerely, Patricia J. Vossmar, Acting Director Division of Operating Reactor Safety Docket No. 05000458 License No. NPF-47

Enclosures:

1.

Factual Summary 2.

Inspection Report 05000458/2025090

Inspection Report

Docket Number:

05000458

License Number:

NPF-47

Report Number:

05000458/2025090

Enterprise Identifier:

I-2025-090-0010

Licensee:

Entergy Operations, Inc.

Facility:

River Bend Station

Location:

St. Francisville, LA

Inspection Dates:

September 25, 2024 to January 15, 2026

Inspectors:

R. Kumana, Senior Project Engineer

Approved By:

Patricia J. Vossmar, Acting Director

Division of Operating Reactor Safety

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SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees

performance by conducting a NRC inspection at River Bend Station, in accordance with the

Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for

overseeing the safe operation of commercial nuclear power reactors. Refer to

https://www.nrc.gov/reactors/operating/oversight.html for more information. Licensee-identified

non-cited violations are documented in report section: 71111.11Q.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

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INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in

effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with

their attached revision histories are located on the public website at http://www.nrc.gov/reading-

rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared

complete when the IP requirements most appropriate to the inspection activity were met

consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection

Program - Operations Phase. The inspectors reviewed selected procedures and records,

observed activities, and interviewed personnel to assess licensee performance and compliance

with Commission rules and regulations, license conditions, site procedures, and standards.

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation

71111.11Q

This violation of very low safety significance was identified by the licensee and has been

entered into the licensee corrective action program and is being treated as a non-cited

violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Technical Specification 5.2.2 requires, in part, that while the unit is in MODE 1, 2, or

3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.

10 CFR 55.53(e) requires, in part, that if a licensee has not been actively performing the

functions of an operator or senior operator, the licensee may not resume activities authorized

by a license issued under Part 55 except as permitted by 10 CFR 55.53(f). To maintain active

status, the licensee shall actively perform the functions of an operator or senior operator on a

minimum of seven 8-hour or five 12-hour shifts per calendar quarter.

Contrary to the above, from July 9 to July 11, 2023, the licensee resumed activities

authorized by a license issued under Part 55 and did not maintain active status by actively

performing the functions of an operator or senior operator on a minimum of five 12-hour shifts

per calendar quarter, and one licensed SRO was not always present in the control room while

the unit was in MODE 1, 2, or 3. Specifically, the facility licensee scheduled a senior operator

to stand watch as Control Room Supervisor when not in an active status, and the individual

licensee had failed to maintain an active status by actively performing the functions of a

senior operator on a minimum of five 12-hour shifts during the calendar quarter.

Subsequently, the individual licensee inappropriately assumed the duties of the CRS on July

9, 10, and 11, 2023, while not maintaining an active license, and the individual with the

inactive license was the only senior operator in the control room at various points on July 9,

10, and 11, 2023, while the unit was in MODE 1.

Significance/Severity: Severity Level IV. The ROPs significance determination process does

not specifically consider the regulatory process impact in its assessment of licensee

performance. Therefore, it is necessary to address this violation which impedes the NRCs

ability to regulate using traditional enforcement to adequately deter non-compliance.

The violation was evaluated under the NRCs traditional enforcement process as set forth in

the NRC Enforcement Policy (the Policy). This violation meets the definition of a Severity

Level IV violation in the Policyless serious, but of more than minor concern, which resulted

in no or relatively inappreciable potential safety or security consequences (e.g., violations that

created the potential of more than minor safety or security consequences). Additionally, after

considering the factors set forth in Section 2.3.2.a of the Policy, this violation is being treated

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as a non-cited violation (NCV), because the issue is non-repetitive and non-willful, has been

entered in your corrective action program, and compliance was restored within a reasonable

period of time

Corrective Action References: CR-RBS-2026-00183

Licensee-Identified Non-Cited Violation

71111.11Q

This violation of very low safety significance was identified by the licensee and has been

entered into the licensee corrective action program and is being treated as a non-cited

violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10 CFR 50.9(a) requires, in part, that information required by the Commissions

regulations, orders, or license conditions to be maintained by the licensee shall be complete

and accurate in all material respects.

10 CFR Part 50, Appendix B, Criterion V, requires, in part, that activities affecting quality shall

be prescribed by documented instructions, procedures, or drawings, of a type appropriate to

the circumstances and shall be accomplished in accordance with these instructions,

procedures, or drawings.

Procedure EN-OP-115-09, Maintaining the Station Narrative Log, a quality-related

procedure, requires, in part, that shift management review the logs to ensure logs are

accurate and appropriate and condition reports have been initiated for log entries as

warranted.

Contrary to the above, from July 9 to July 11, 2023, shift management review of the logs did

not ensure logs were accurate and appropriate and condition reports initiated for log entries

as warranted. Specifically, the narrative logs were inaccurate and inappropriate because two

individuals signed in as the Control Room Supervisor while not present in the control room

and while another individual actively performed the functions of the Control Room Supervisor

(CRS) without an active license.

Significance/Severity: Severity Level IV. The ROPs significance determination process does

not specifically consider the regulatory process impact in its assessment of licensee

performance. Therefore, it is necessary to address this violation which impedes the NRCs

ability to regulate using traditional enforcement to adequately deter non-compliance.

This violation meets the definition of a Severity Level IV violation in the Policyless serious,

but of more than minor concern, which resulted in no or relatively inappreciable potential

safety or security consequences (e.g., violations that created the potential of more than minor

safety or security consequences). Additionally, after considering the factors set forth in

Section 2.3.2.a of the Policy, this violation is being treated as a non-cited violation (NCV)

because the issue is non-repetitive and non-willful, has been entered in your corrective action

program, and compliance was restored within a reasonable period of time.

Corrective Action References: CR-RBS-2026-00184

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EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On January 15, 2026, the inspectors presented the NRC inspection results to John

Giddens, Senior Manager Regulatory Compliance.