IR 05000324/2020401

Security Baseline Inspection Report 05000324/2020401 and 05000325/2020401

ML20304A465
Person / Time
Site:	Brunswick
Issue date:	10/30/2020
From:	James Shehee NRC/RGN-II
To:	Stephanie West Duke Energy Progress
References
IR 2020401
Download: ML20304A465 (8)

Text

October 30, 2020

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - SECURITY BASELINE INSPECTION REPORT 05000324/2020401 AND 05000325/2020401

Dear Mr. West:

On October 6, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant, Units 1 and 2 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,

/RA/

James C. Shehee, Chief Plant Support Branch Div of Reactor Safety Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71

Enclosure:

As stated,

Inspection Report

Docket Numbers: 05000324 and 05000325 License Numbers: DPR-62 and DPR-71 Report Numbers: 05000324/2020401 and 05000325/2020401 Enterprise Identifier: I-2020-401-0044 Licensee: Duke Energy Progress, LLC Facility: Brunswick Steam Electric Plant, Units 1 and 2 Location: Southport, NC Inspection Dates: September 30, 2020 to October 1, 2020 (Remote)

October 05, 2020 to October 06, 2020 (Onsite)

Inspectors: J. Justice, Physical Security Inspector Approved By: James C. Shehee, Chief Plant Support Branch Div of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a security baseline inspection at Brunswick Steam Electric Plant,

Units 1 and 2, 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

Unless otherwise noted, baseline security inspections were conducted in accordance with the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 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. Publicly available IPs are located at:

http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.

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), regional inspectors were directed to begin telework. The inspection documented below was completed through a combination of remote and onsite inspection.

71130.02 - Access Control

The inspectors evaluated the access control program through completion of the following

inspection elements: Access Control

(1)

• Tier I: All Requirements

• Tier II: None

• Tier III: 02.09

71130.09 - Security Plan Changes

The inspectors evaluated the security plan changes through completion of the following procedure elements: Security Plan Revision 13 and 14 were implemented based on your determination, in accordance with 10 CFR 50.54(p)(2), that the changes resulted in no decrease in safeguards effectiveness of the security plan, and that the revised security plan continues to meet the requirements of 10 CFR 73.55(b). The inspectors conducted a review of the security plan changes to evaluate for potential decreases in safeguards effectiveness of the security plan. However, this review does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

PP01: Protected Area Security Equipment Performance Index Sample (IP Section 02.17) (1 Sample)

(1) July 2019 through September

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On October 6, 2020, the inspectors presented the security baseline inspection results to Scott West and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71130.02 Corrective Action 02297862

Documents 02319830

2322325

2335626

2531804

Miscellaneous Various Key and Lock Control Records

Procedures 0AOP-40.0 Security Events 34

0PEP-03.8.2 Personnel Accountability and Evacuation 25

AD-SY-ALL-0110 Protection of Information Related to Nuclear Security 6

AD-SY-ALL-0210 Site Access Controls 6

AD-SY-ALL-0215 Security Search and Entry Processing 5

AD-SY-ALL-0240 Security Key and Lock Controls 1

Self-Assessments Access Control and PI Data Self-Assessment Report 08/25/2020

71130.09 Procedures Brunswick Nuclear Plant Security Plan 13 and 14

71151 Procedures AD-PI-ALL-0700 Performance Indicators 4

AD-SY-ALL-0150 Reporting of Safeguards, Security, and Fitness for Duty 4

Events

5