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Design Basis Assurance Inspection (Teams) Inspection Report 05000313/2021011 and 05000368/2021011
	ML21263A012
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/23/2021
From:	Vincent Gaddy; Region 4 Engineering Branch 1
To:	Dinelli J; Entergy Operations
References
	IR 2021011
	Download: ML21263A012 (17)
	v • d • e

September 23, 2021

SUBJECT:

ARKANSAS NUCLEAR ONE - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000313/2021011 AND 05000368/2021011

Dear Mr. Dinelli:

On August 4, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One. On September 13, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

No NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Arkansas Nuclear One. 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, Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000313 and 05000368 License Nos. DPR-51 and NPF-6

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000313 and 05000368

License Numbers:

DPR-51 and NPF-6

Report Numbers:

05000313/2021011 and 05000368/2021011

Enterprise Identifier:

I-2021-011-0003

Licensee:

Entergy Operations, Inc.

Facility:

Arkansas Nuclear One

Location:

Russellville, AR

Inspection Dates:

June 14, 2021 to July 2, 2021

Inspectors:

R. Deese, Senior Reactor Analyst

J. Drake, Senior Reactor Inspector

N. Okonkwo, Reactor Inspector

D. Reinert, Reactor Inspector

W. Sifre, Senior Reactor Inspector

T. Steadham, Senior Resident Inspector

Approved By:

Vincent G. Gaddy

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Arkansas Nuclear One, 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.

A licensee-identified non-cited violation is documented in report section: 71111.21M.

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) 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)

=

Main article: IP 71111.21

(1) Service Water Motor Operated Valve MOV CV-3823 (Unit 1)

Valve testing procedures and performance history were reviewed to assure consistency with vendor and industry standards

Monitoring programs, health reports, and corrective action program reports to verify the monitoring of potential degradation

Design basis calculations including system hydraulic analysis

Valve and actuator design drawings and vendor specifications