IR 05000259/2024403

– Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403

ML24141A217
Person / Time
Site:	Browns Ferry
Issue date:	05/22/2024
From:	Daniel Bacon NRC/RGN-II/DRS/EB2
To:	Jim Barstow Tennessee Valley Authority
Shared Package
5	List: IR 05000259/2024403
References
IR 2024403
Download: ML24141A217 (1)

Text

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 & 3 - SECURITY BASELINE INSPECTION REPORT 05000259/2024403 AND 05000260/2024403 AND 05000296/2024403

Dear James Barstow:

On May 3, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant, Units 1, 2 & 3. On April 30, 2024, the NRC inspectors discussed the results of this inspection with Quinn Leonard Assistant Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.

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

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000259, 05000260 and 05000296

License Numbers: DPR-33, DPR-52 and DPR-68

Report Numbers: 05000259/2024403, 05000260/2024403 and 05000296/2024403

Licensee: Tennessee Valley Authority

Facility: Browns Ferry Nuclear Plant, Units 1, 2 & 3

Location: Athens, Alabama

Inspection Dates: April 29, 2024 to May 03, 2024

Inspectors: L. Jones, Senior Reactor Inspector

Approved By: Daniel M. Bacon, Chief Engineering Branch 2 Division of Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a security baseline inspection at Browns Ferry Nuclear Plant, Units 1, 2 & 3, 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.

List of Findings and Violations

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

Additional Tracking Items

None.

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) 2201, Security Inspection Program for Commercial Nuclear Power Reactors. 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.

71130.14 - Review of Power Reactor Target Sets

The inspectors evaluated the Security Target Set Program. The following elements were evaluated:

Review of Power Reactor Target Sets

(1) Section 03.01 Review of Events and Logs The inspector reviewed any licensee event reports, safeguards log entries, and corrective action program entries since the last Target Set inspection that concern the target set identification, development, and maintenance program.

Section 03.02 Target Set Identification and Development Process Review The inspector assessed the licensee's documentation and maintenance of the process used to develop and identify complete and accurate target sets as required by 10 CFR Part 73 by reviewing applicable portions of procedures and samples of records and conducting interviews with responsible personnel and plant employees.

Section 03.03 Verification of Target Sets Changes The inspector reviewed changes to the licensees documented target sets since the last Target Set inspection. The inspector verified that any design modifications and procedure or configuration changes that have occurred were appropriately documented in the site's target sets.

Section 03.04 Verification of Complete and Accurate Target Sets The inspector interviewed licensee personnel and reviewed a sample of target sets for reactor operation and for modes other than operation. The inspector reviewed assumptions used in the licensees development of its target sets.

Section 03.05 Physical Protection Program Review The inspector verified that the licensee performed a review of target sets for accuracy, completeness, and applicability at least every 24 months and as otherwise required, documented the results and recommendations, and entered findings in the sites corrective action program (CAP).

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On April 30, 2024, the inspectors presented the security baseline inspection results to Quinn Leonard, Assistant Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71130.14 Corrective Action CR 1928063

Documents CR 1928065

Resulting from

Inspection

Procedures NPG-SPP-14.2 Target Set Development, Identification and Maintenance Rev. 0009

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