IR 05000443/2009402

Download: ML091760992

Text

June 25, 2009

Mr. Gene St. Pierre Vice President, North Region Seabrook Nuclear Power Plant FPL Energy Seabrook, LLC c/o Mr. Michael O'Keefe P.O. Box 300 Seabrook, NH 03874

SUBJECT: SEABROOK STATION, UNIT 1 - NRC SECURITY INSPECTION REPORT NO. 05000443/2009402

Dear Mr. St. Pierre:

On May 22, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Seabrook Station, Unit 1. 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 May 22, 2009, with Mr. Paul Freeman, Plant General Manager, 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 the inspection before the inspectors left the site.

The finding had a cross-cutting aspect in the area of Human Performance, because a station employee failed to perform a self-check while performing a task. If you disagree with the characterization of any 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 Regional Administrator, Region I, and the NRC Resident Inspector at Seabrook Station. The information you provide will be considered in accordance with Inspection Manual Chapter 0305. When separated from its Enclosure, this document is DECONTROLLED.Additionally, licensee identified violations which were determined to be of very low security significance are listed in this report. However, because of the very low security significance and because they are entered into your corrective action program, the NRC is treating these violations as non-cited violations (NCVs) consistent with Section VI.A. of the NRC Enforcement Policy. 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 for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator Region I, the Director, Office of Enforcement, United States Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Seabrook Station. 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 document system, ADAMS. ADAMS 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 document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.22. 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).

Sincerely,/RA/ James M. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-443 License No. NPF-86

Enclosure:

NRC Inspection Report No. 05000443/2009402

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Supplemental Information (CONTAINS (OUO-SRI)