IR 05000456/2018412

NRC Security Baseline Inspection Report 05000456/2018412; 05000457/2018412 (DRS-M.Ziolkowski)

ML18347A463
Person / Time
Site:	Braidwood
Issue date:	12/13/2018
From:	Steven Orth Plant Support Branch II
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2018412
Download: ML18347A463 (6)

Text

ber 13, 2018

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2NRC SECURITY BASELINE INSPECTION REPORT 05000456/2018412; 05000457/2018412

Dear Mr. Hanson:

On November 16, 2018, U.S. Nuclear Regulatory Commission (NRC) completed a Security Inspection at your Braidwood Station, Units 1 and 2, and the NRC inspector discussed the results of this inspection with Mr. Lizalek and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspector did not identify any finding or violation of more-than-minor significance.

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 (CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii). Should you have any questions concerning this inspection, we will be pleased to discuss them with you.

Sincerely,

/RA/

Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure:

IR 05000456/2018412; 05000457/2018412 cc: Distribution via LISTSERV

SUMMARY

The U.S. Nuclear Regulatory Commission continued monitoring licensees performance by conducting a Security Baseline Inspection at Braidwood Station, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the U.S. Nuclear Regulatory Commissions 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 were identified.

Additional Tracking Items None

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures in effect at the beginning of the inspection unless otherwise noted. Samples were declared complete when the inspection procedure requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspector 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.

SAFEGUARDS

71130.14Review of Power Reactor Target Sets

The inspector evaluated the Security Target Set Program. The following elements were evaluated:

Requirements: 02.02 (a-f), 02.03, 02.04 (a-b)

OTHER ACTIVITIES

BASELINE None

INSPECTION RESULTS

No findings or violations were identified.

EXIT MEETINGS AND DEBRIEFS

The inspector confirmed that proprietary information was controlled to protect from public disclosure. No proprietary information was documented in this report.

• On November 16, 2018, the inspector presented the security baseline inspection results to Mr. Lizalek, and other members of the licensee staff.

DOCUMENTS REVIEWED

71130.14Review of Power Reactor Target Sets

- Braidwood Nuclear Power Station Physical Security Plan; Revision 16

- SY-BR-101-116; Target Set Self Assessment; 11/14/18

- SY-BR-101-502; Braidwood Nuclear Generating Station Target Sets; Revision 6

- BB PRA-013a; Braidwood Nuclear Power Station Probabilistic Risk Assessment;

Revision BB016a

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