IR 05000331/2018412

NRC Security Baseline Inspection Report 05000331/2018412 (DRS-G.Bonano)

ML18198A478
Person / Time
Site:	Duane Arnold
Issue date:	07/17/2018
From:	Steven Orth Plant Support Branch II
To:	Dean Curtland NextEra Energy Duane Arnold
References
IR 2018412
Download: ML18198A478 (6)

Text

uly 17, 2018

SUBJECT:

DUANE ARNOLD ENERGY CENTERNRC SECURITY BASELINE INSPECTION REPORT 05000331/2018412

Dear Mr. Curtland:

On June 21, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Duane Arnold Energy Center and the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of the inspection are documented in the enclosed report.

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

This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.htm and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 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 Joseph Maynen Acting for/

Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-331;72-032 License No. DPR-49 Enclosure:

Inspection Report 05000331/2018412 cc: Distribution via LISTSERV J. Schwertfeger, Security Manager A. Leek, State Liaison Officer, State of Iowa M. Davis, Licensing Manager M. Nazar, Executive Vice President, Nuclear Division and Chief Nuclear Officer

SUMMARY

The U.S. Nuclear Regulatory Commission continued monitoring licensees performance by conducting a Security Baseline Inspection at Duane Arnold Energy Center 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 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 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.

SAFEGUARDS

71130.04Equipment Performance, Testing, and Maintenance

The inspectors evaluated the Security Testing and Maintenance Program. The following elements were evaluated:

Tier I: All Tier II: (02.09a, b; 02.10a; 02.11a; 02.12.a; 02.13a)

Tier III: (02.14; 02.15a, c)

INSPECTION RESULTS

No findings or violations were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

• On June 21, 2018, the inspectors presented the baseline security inspection results to Mr. Dean Curtland, and other members of the licensee staff.

DOCUMENTS REVIEWED

71130.04 - Equipment Performance, Testing, and Maintenance

- Duane Arnold Energy Center Security Event Logs; February 2018 through June 2018

- EC 289917; Security Checkpoint Elimination; 5/24/2018

- S-11981-030-01; Calculation - Summary of DAEC Design Bases; 12/21/2017

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