IR 05000458/2010201

Download: ML102030471

Text

August 6, 2010

Mr. Michael Perito Vice President River Bend Station Nuclear Power Station 5485 US Highway 61N St. Francisville, LA 70775

SUBJECT: RIVER BEND STATION NUCLEAR POWER STATION - U.S. NUCLEAR REGULATORY COMMISSION SECURITY BASELINE INSPECTION REPORT 05000458/2010201

Dear Mr. Perito:

On May 28, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your River Bend Station Nuclear Power Station. 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 discussed on July 1, 2010, with Jerry Roberts 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 one finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiency was promptly 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 finding had a cross-cutting aspect in the area of Human Performance because the licensee failed to ensure that personnel, equipment, procedures, and other resources are available and adequate to assure nuclear safety. Specifically, those necessary for complete, accurate and up-to-date design documentation, procedures, and work packages, and correct labeling of components. H.2(c) If you disagree with the characterization of the finding or the cross-cutting aspect assigned to the finding in this report you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Director, Nuclear Security Incident Response, and to the Branch Chief, Security Performance Evaluation Branch. The finding was NRC identified. However, because of the very low security significance and because it is entered into your corrective action program, the NRC is treating the violation as a non-cited violation (NCV) consistent with Section VI.A1 of the NRC Enforcement Policy. If you contest this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for Enclosure contains Safeguards Information. Upon removal, this letter is decontrolled.your denial, to the U.S. Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Director, Office of Nuclear Security and Incident Response (NSIR); the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; the Branch Chief, Security Performance Evaluation Branch; the Regional Administrator Region IV; and the NRC Resident Inspector at the River Bend Station Nuclear Power Station. In accordance with the Title 10 Code of Federal Regulations (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 System component of the NRC's Agency-wide Documents Access and Management System (ADAMS), 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 document system, 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 "Security-Related Information-Withhold Under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).Should you have any questions concerning this letter, please contact us. Your cooperation is appreciated.

Sincerely,/RA/

Robert C. Johnson, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos.: 50-458 License Nos.: NPF-47

Enclosure:

Inspection Report No. 05000458/2010201 cc w/encl: D. Brady, NSIR J. Curry, NSIR R. Albert, NSIR S. Coker, NSIR G. Larkin, IV J. Trapp, RI M. Ernstes, RII E. Duncan, RIII M. Shannon, RIV cc w/o encl: F. Lyon, NRR T. Howard, NSIR Senior Vice President and COO, Entergy Operations, Inc. Vice President Oversight, Entergy Operations, Inc. Senior Manager Nuclear Safety and Licensing, Entergy Operations, Inc. Manager Licensing, Entergy Operations, Inc. Associates General Counsel Nuclear, Entergy Services In