IR 05000263/2008404

IR 05000263-08-404, on 10/20/2008 - 10/24/2008, Monticello Nuclear Generating Plant (Mngp), Routine Security Baseline Inspection, Security Training - Cover Letter

ML083460269
Person / Time
Site:	Monticello
Issue date:	12/08/2008
From:	Eric Duncan Plant Support Branch II
To:	O'Connor T Northern States Power Co
References
IR-08-404
Download: ML083460269 (5)

Text

ber 8, 2008

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT NRC SECURITY BASELINE INSPECTION REPORT 05000263/2008404(DRS)

Dear Mr. OConnor:

On October 24, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection of your Monticello Nuclear Generating Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process.

The enclosed inspection report documents the inspection results, which were discussed on October 24, 2008, with Mr. Sawatzke and other members of your staff.

The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions 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 and three Licensee-identified violations of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process). The deficiencies were 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 NRC-identified finding had a cross-cutting aspect in the area of Human Performance (H.1(b)) because security personnel failed to conduct an effectiveness review of a decision without verifying the validity of their underlying assumption and identifying possible unintended consequences of that decision.

However, because of the very low security significance of the issues, and because the issues were entered into your corrective action program, the NRC is treating the violations as Non-Cited Violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy.

Enclosure Contains Sensitive Unclassified Non-Safeguards Information. Upon separation, this page is decontrolled. If you contest these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector at the Monticello Nuclear 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 System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site 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 letters 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 NRCs 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 inspection, we will be pleased to discuss them with you.

Sincerely,

/RA/

Eric Duncan, Chief Plant Support Branch Division of Reactor Safety Docket No. 50-263 License No. DPR-22 Nonpublic Enclosure: Inspection Report 05000263/2008404(DRS)

w/Attachment: Supplemental Information See Attached Distribution