IR 07200004/2021001

Operation of an Independent Spent Fuel Storage Installation Report 07200004/2021001

ML21238A096
Person / Time
Site:	Oconee
Issue date:	08/26/2021
From:	Binoy Desai NRC/RGN-II
To:	Snider S Duke Energy Carolinas
References
IR 2021001
Download: ML21238A096 (5)

Text

August 26, 2021

SUBJECT:

OCONEE NUCLEAR STATION-- OPERATION OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200004/2021001

Dear Mr. Snider:

On July 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Oconee Nuclear Station and discussed the results of this inspection with 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,

/RA/

Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 07200004

Enclosure:

As stated

Inspection Report

Docket Number: 07200004 License Number: DPR-38, DPR-47, and DPR-55 Report Number: 07200004/2021001 Enterprise Identifier: I-2021-001-0151 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station Location: Seneca, SC Inspection Dates: July 26, 2021 to July 29, 2021 Inspectors: P. Cooper, Senior Reactor Inspector J. Tapp, Transportation and Storage Inspector M. Haywood, General Engineer Approved By: Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting inspections of activities related to Oconee Nuclear Station operational activities of dry cask storage of spent fuel from July 26, 2021 to July 29, 2021. The NRCs program for overseeing the safe operation of dry storage of spent fuel at an Independent Spent Fuel Storage Installations (ISFSI) is described in Inspection Manual Chapter 2690, Inspection Program for Dry Storage of Spent Reactor Fuel at Independent Spent Fuel Storage Installations and for 10 CFR Part 71 Transportation Packagings.

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) 2690, Inspection Program for Storage of Spent Reactor Fuel and Reactor-Related Greater-than-Class C Waste at Independent Spent Fuel Storage Installations (ISFSI) and for 10 CFR Part 71 Transportation Packagings."

60855 - OPERATION OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION Operation of an Independent Spent Fuel Storage Installation (1 Sample)

From July 26 through 29, 2021, the inspectors performed a review of the licensees ISFSI activities to verify compliance with regulatory requirements. During the on-site inspection, the inspectors observed and reviewed licensee activities in each of the five safety focus areas including occupational exposure, public exposure, fuel damage, confinement, and impact to plant operations.

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. Additionally, the inspectors performed independent walkdowns of the heavy load lifting equipment and the ISFSI haul path.

The inspector also performed an independent radiation survey of the ISFSI pad.

INSPECTION RESULTS No findings were identified.

EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.

On July 29, the inspectors presented the results to Steve Snider, Site Vice President, and other members of the licensee staff.

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