IR 07200006/2021001

Operation of an Independent Spent Fuel Storage Installation Report 07200006/2021001

ML21238A033
Person / Time
Site:	07200006
Issue date:	08/26/2021
From:	Binoy Desai NRC/RGN-II
To:	Krakuszeski J Duke Energy Progress
References
IR 2021001
Download: ML21238A033 (5)

Text

August 26, 2021

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT -- OPERATION OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200006/2021001

Dear Mr. Krakuszeski:

On July 20, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Brunswick Steam Electric Plant and discussed the results of this inspection with you and members of your staff. The results of this inspect ion 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. 07200006

Enclosure:

As stated

Inspection Report

Docket Number: 07200006

License Number: DPR-62 and DPR-71

Report Number: 07200006/2021001

Licensee: Duke Energy Progress, LLC

Facility: Brunswick Steam Electric Plant

Location: Southport, NC

Inspection Dates: July 12, 2021 to July 20, 2021

Inspectors: P. Cooper, Senior Reactor Inspector J. Tapp, Transportation and Storage Inspector

Approved By: Binoy B. Desai, Chief Engineering Branch 3 Division of Reactor Safety

Enclosure SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitori ng the licensees performance by conducting inspections of activities related to Brunswick Steam Electric Plant operational activities of dry cask storage of spent fuel from J uly 12, 2021 to July 20, 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 Inspec tion Manual Chapter 2690, Inspection Program for Dry Storage of Spent Reactor Fuel at In dependent 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 th e inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise note d. Currently approved IPs with their attached revision histories are located on the public web site 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 inspe ction activity were met consistent with Inspection Manual Chapter (IMC) 2690, Inspecti on Program for Storage of Spent Reactor Fuel and Reactor-Related Greater-than-Class C Was te at Independent Spent Fuel Storage Installations (ISFSI) and for 10 CFR Part 71 Trans portation Packagings."

60855 - OPERATION OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLA TION

Operation of an Independent Spent Fuel Storage Installation

From July 12 through 20, 2021, the inspectors performed a revie w of the licensees ISFSI activities to verify compliance with regulatory requirements. D uring 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, observ ed activities, and interviewed personnel to assess licensee performance and compliance with Co mmission rules and regulations, license conditions, site procedures, and standards. Additionally, the inspectors performed independent walkdowns of the heavy load lifting equip ment 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 20, 2021, the inspectors presented the results to John A. Krakuszeski, Site Vice President and other members of the licensee staff.

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