IR 05000271/2010403

IR 05000271/2010403; 12/05/2010 - 02/23/2011; Vermont Yankee Nuclear Power Station; Problem Identification and Resolution

ML110890093
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/29/2011
From:	Silas Kennedy NRC Region 1
To:	Michael Colomb Entergy Nuclear Operations
References
10-403, IR-10-403
Download: ML110890093 (5)

Text

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION - NRC SECURITY PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION RE PO RT 0500027 1 l 201 0403

Dear Mr. Colomb:

On February 23,2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security Problem ldentification and Resolution 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 February 23,2011, with Mr. Michael Colomb, Site Vice President, 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 inspector reviewed selected procedures and records, observed activities, and interviewed personnel.

This report documents one NRC-identified finding of very low security significance (i.e., Green as determined by the Baseline Security 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 inspector left the site.

The finding had a cross-cutting aspect in the area of Problem ldentification and Resolution (Corrective Action Program) because Entergy did not thoroughly evaluate the issue such that the resolution addressed the causes and extent of the condition P.1(c). lf you disagree with 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 RegionalAdministrator, Region l; and the NRC Resident Inspectors at the Vermont Yankee Nuclear Power Station.

When separated from its enclosure, this Document is DECONTROLLED.

SAFEUARBS INFORMATION

SAFEGUARDS I NFORMATION However, because of the very low security significance and because it is entered into your corrective action program, the NRC is treating this violation as a non-cited violation (NCV),

consistent with Section 2.3.3 of the NRC's Enforcement Policy. lf you contest this NCV, 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 l; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident lnspectors at the Vermont Yankee Nuclear Power 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:/iunrvw.nrc.oovireadinq-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.

ln accordance with 10 CFR 2.390(bX1)(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. lf Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.22. Othenvise, mark your entire response Security-Related Information - Withhold Under 10 CFR 2.390 and follow the instructions forwithholding in 10 CFR 2.390(bX1).

Sincerely,

/RN Silas R. Kennedy, Acting Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-271 License No. DPR-28 Enclosure: NRC Inspection Report No. 0500027112010403 MAttachment: Supplemental Information (coNTArNS SAFEGUARDS TNFORMATTON (SGr))