IR 05000271/2009402

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IR 05000271-09-402, on 06/01/2009 - 06/05/2009, for Vermont Yankee
ML091880020
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 07/06/2009
From: James Trapp
Plant Support Branch 1
To: Michael Colomb
Entergy Nuclear Operations
References
IR-09-402
Download: ML091880020 (5)


Text

July 6, 2009 Mr. Michael Colomb Site Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station 185 Old Ferry Road P.O. Box 500 Brattleboro, VT 05302-0500 SUBJECT VERMONT YANKEE NUCLEAR POWER STATION - NRC SECURITY INSPECTION REPORT NO. 05000271/2009402

Dear Mr. Colomb:

On June 5, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Vermont Yankee 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 June 5, 2009, with you 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). This was determined to be a violation of NRC requirements. 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. Additionally, two 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 in your corrective action program, the NRC is treating these violations as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy.

When separated from its Enclosure, this document is DECONTROLLED. 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 Vermont Yankee Nuclear Power Plant.

In accordance with 10 CFR 2.390 of the NRC=s ARules 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 information 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 ASecurity-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. 50-271 License No. DPR-28 Enclosure: NRC Inspection Report No. 05000271/2009402 w/Attachment: Supplemental Information (CONTAINS (OUO-SRI)