IR 05000424/2013403
| ML13266A298 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, 07201039  |
| Issue date: | 09/23/2013 |
| From: | Desai B B NRC/RGN-II/DRS/PSB2 |
| To: | Tynan T E Southern Nuclear Operating Co |
| Linda K. Gruhler 404-997-4633 | |
| References | |
| IR-13-401, IR-13-403 | |
| Download: ML13266A298 (4) | |
Text
September 23, 2013
Mr. TomVice President Southern Nuclear Operating Company, Inc. Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
SUBJECT: VOGTLE ELECTRIC GENERATING PLANT - NRC SECURITY INSPECTION REPORT 05000424/2013403, 05000425/2013403, AND 07201039/2013401
Dear Mr. Tynan:
On August 15, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Vogtle Electric Generating Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were initially discussed onsite on August 15, 2013, with Mr. J. Thomas and other members of your staff. A final exit was conducted by telephone on September 11, 2013 with Ms. R. Barringer and other members of your staff.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
This report documents two findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) that were identified during this inspection. The deficiencies were corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the site. The findings had crosscutting aspects in the area of Problem Identification & Resolution, P.1 (a), which states that the licensee implement a corrective action program with a low threshold for identifying issues and identify such issues completely, accurately, and in a timely manner commensurate with their safety significance and P.1 (d), which states that the licensee takes appropriate corrective actions to address safety issues and adverse trends in a timely manner commensurate with their safety significance and complexity.The NRC is treating these violations as non-cited violations (NCV) consistent with Section 2.3.2, of the NRC Enforcement Policy because of the very low safety significance of the violations, and because they were entered into your corrective actions program. If you contest these non-cited violations, you should provide a response within 30 days of the date of this inspection report, with the basis of your denial, to the Nuclear Regulatory Commission, Administrator, Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Vogtle Electric Generating Plant. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), which is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the Enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's Enclosure will not be available for public inspection. In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room, or from the NRC's ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response as Security Related Information-Withhold Under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390 (b)(1).
Sincerely,/RA/ Binoy Desai, Chief Plant Support Branch 2 Division of Reactor Safety Docket Nos. 50-424, 50-425, and 72-1039 License Nos. NPF-68 and NPF-81
Enclosure:
Inspection Report 05000424/2013403, 05000425/2013403 and 07201039/2013401
w/Attachment:
Supplementary Information (OUO) cc: (See page 3)