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Design Basis Assurance Inspection Programs Inspection Report 05000400/2025010
	ML25273A185
Person / Time
Site:	Harris
Issue date:	09/30/2025
From:	Marcus Riley; NRC/RGN-II/DORS
To:	Joseph C; Duke Energy Progress
References
	IR 2025010
	Download: ML25273A185 (1)
	v • d • e

SUBJECT:

SHEARON HARRIS NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000400/2025010

Dear Carolyne Joseph:

On September 24, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Shearon Harris Nuclear Plant and 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 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, Marcus A. Riley, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket No. 05000400 License No. NPF-63

Enclosure:

As stated

Inspection Report

Docket Number:

05000400

License Number:

NPF-63

Report Number:

05000400/2025010

Enterprise Identifier:

I-2025-010-0031

Licensee:

Duke Energy Progress, LLC

Facility:

Shearon Harris Nuclear Plant

Location:

New Hill, NC

Inspection Dates:

August 25, 2025 to September 24, 2025

Inspectors:

C. Franklin, Reactor Inspector

M. Hagen, Reactor Inspector

A. Ruh, Senior Resident Inspector

Approved By:

Marcus A. Riley, Chief

Engineering Branch 1

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Shearon Harris Nuclear Plant, 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) 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.

REACTOR SAFETY

===71111.21N.03 - Commercial Grade Dedication The inspectors reviewed the implementation of the licensees processes for dedicating commercial-grade items/services as basic components and/or for procuring safety-related structures, systems, and components for the following samples:

Commercial Grade Dedication===

Main article: IP 71111.21

(1) Item 30166984, Gasket, Coupling, Viton, 8 in, Style-38 Dresser Coupling

(2) Item 74146846 Tube, Poro-Edge, 0.0625 Slot, 304SS or 316SS

(3) Item 9220201439 Lubricant, Grease, MOV Long Life, Grade 1, Tube, 14 oz

(4) Item 72458573 Bearing, Thrust, 2.5591, 5.51180, 1.2992, Angular Contact, Ball Bearing

(5) Item 72883564 Kit, Bushing, Seal, Mechanical, for 123-14 and CPL-14

(6) Item 2067 Ring, Seat, Upgraded, Valve, Globe, 8"X10", 900#

(7) Item 72419617 Capacitor, Electrolytic, Alum, 13,000uf, -10%/+50%, 150wvdc, Radial Screw Terminal, 6ma Maximum Leakage Current

(8) Item 72415144 Relay, Lockout, LOR/ER-Std Speed Trip, 125vdc, Double Sided, Double Wiping Knife Type, Electric Reset, 8 Decks

(9) Item 72432917 Relay, Rotary, 8PDT, 125vdc, Non-Latching

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On September 24, 2025, the inspectors presented the design basis assurance inspection (programs) inspection results to Carolyne Joseph and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

v t e Inspection Report - Harris - 2025010
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
2025 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 10(0) 11(0) Security 401(0) 402(0) 403(0) 404(0) Operator Exams 301(0) Emergency Planning Other

IR 05000400/2025010