IR 05000282/2009404

IR 05000282-09-404 (Drs), 05000306-09-404 (DRS) on 10/13/2009 - 10/16/2009 (Xcel Corp.) and 10/19/2009 - 10/21/2009 (Site) for Prairie Island - Cover Letter

ML093430417
Person / Time
Site:	Prairie Island
Issue date:	12/02/2009
From:	Eric Duncan Plant Support Branch II
To:	Schimmel M Northern States Power Co
References
IR-09-404
Download: ML093430417 (5)

Text

ber 2, 2009

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 NRC SECURITY BASELINE INSPECTION REPORT 05000282/2009404(DRS);

05000306/2009404(DRS)

Dear Mr. Schimmel:

On October 21, 2009, the U. S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2. 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 21, 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 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 two findings 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 findings had cross-cutting aspects in the areas of Human Performance, Resources and Work Practices, H.2(c) and H.4(b), respectively] because the licensee failed to maintain complete and accurate procedures, and security personnel failed to follow established procedures. 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 III, and the NRC Resident Inspector at the Prairie Island Nuclear Generating Plant. The information you provide will be considered in accordance with Inspection Manual Chapter 0305.

Enclosure contains Safeguards Information.

When separated from enclosure, this transmittal document is decontrolled. If you contest these findings, 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 III; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Prairie Island Nuclear Generating Plant.

The findings were self-revealing.

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 enclosures, 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 Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Nonpublic Enclosure: Inspection Report 05000282/2009404(DRS);

05000306/2009404(DRS)

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