IR 05000424/2016404

Vogtle Electric Generating Plant, Units 1 and 2, U.S. Nuclear Regulatory Commission Special Security Inspection Report 05000424/2016404 and 05000425/2016404

ML16043A270
Person / Time
Site:	Vogtle
Issue date:	02/12/2016
From:	Gody A T Division of Reactor Safety II
To:	McGavin S P Southern Nuclear Operating Co
Linda Gruhler 404-997-4633
References
EA-16-017 IR 2016404
Download: ML16043A270 (5)

Text

February 12, 2016

EA-16-017

Mr. StephenFleet Security Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway (Bin 042) Birmingham, AL 35242

SUBJECT: VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - U.S. NUCLEAR REGULATORY COMMISSION SPECIAL SECURITY INSPECTION REPORT 05000424/2016404 AND 05000425/2016404

Dear Mr. McGavin:

On January 29, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a special inspection (SI) at your Vogtle Electric Generating Plant, Units 1 and 2. The enclosed inspection report (IR) documents the inspection results that were discussed with Mr. Brian K. Taber, and other members of your staff on January 11, 2016. A final exit meeting was conducted on February 8, 2016. The inspection commenced on January 8, 2016, in accordance with NRC Management Directive 8.3, "NRC Incident Investigation Program," and Inspection Manual Chapter 0309,

"Reactive Inspection Decision Basis for Reactors," based on the initial risk and deterministic criteria evaluation made by the NRC on January 7, 2016.

The SI reviewed the circumstances surrounding an event that occurred on January 7, 2016, and examined activities conducted under your license as they relate to safety, security, and compliance with the Commission's rules and regulations, and with the conditions of your license.

The attached report documents one or more findings that have preliminarily been determined to have greater than very low security significance that may require additional inspections, regulatory actions, and oversight. These finding(s) were assessed based on the best available information, using the Physical Protection Significance Determination Process (SDP). The deficiencies were promptly corrected or compensated for, and the plant was in compliance withapplicable physical protection and security requirements within the scope of this inspection before the team arrived onsite. The NRC will inform you in writing when the final significance has been determined. The finding(s) were determined to be apparent violation(s) (AV) of NRC requirements, and are being considered for escalated enforcement action in accordance with the Enforcement Policy, which appears on the NRC's Web site at http://www.nrc.gov/about-nrc/regulatory/enforcement/enforce-pol.html. We intend to complete and issue our final safety significance determination within 90 days from the date of this letter. The NRC's SDP is designed to encourage an open dialogue between your staff and the NRC; however, the dialogue should not affect the timeliness of our final determination.

Before the NRC makes a final decision on this matter, you may choose to (1) attend a regulatory conference where you can present to the NRC your point of view on the facts and assumptions used to arrive at the finding(s), and assess its significance, or (2) submit your position on the finding to the NRC in writing. If you request a regulatory conference, it should be held within 30 days of your receipt of this letter. We encourage you to submit supporting documentation at least 1 week prior to the conference, in an effort to make the conference more efficient and effective. If you decide to submit only a written response, it should be sent to the NRC within 30 days of your receipt of this letter. If you choose not to request a regulatory conference or to submit a written response, you will not be allowed to appeal the NRC's final significance determination.

Please contact Binoy Desai at 404-997-4519, and in writing, within 10 days from the issue date of this letter to notify the NRC of your intentions. If we have not heard from you within 10 days, we will continue with our significance determination and enforcement decision. Because the NRC has not made a final determination in this matter, no notice of violation is being issued for these inspection finding(s) at this time. In addition, please be advised that the number and characterization of the AVs may change based on further NRC review.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public inspections, exemptions, requests for withholding," of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room, or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS); accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1), and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the Enclosure will not be made available electronically for public inspection in the NRC Public Document Room, or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information-Withhold from public disclosure under 10 CFR 2.390" in accordance withCFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.

Sincerely,/RA/

Anthony T. Gody, Director Division of Reactor Safety Docket Nos. 50-424 and 50-425 License Nos. NPF-68 and NPF-81

Enclosure:

NRC IR 05000424/2016404 and 05000425/2016404,

w/Attachment:

Supplementary Information (OUO)

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