IR 05000282/2011403
| ML11179A118 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/24/2011 |
| From: | Richard Skokowski Plant Support Branch II |
| To: | Schimmel M Northern States Power Co |
| References | |
| IR-11-403 | |
| Download: ML11179A118 (4) | |
Text
June 24, 2011
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2
NRC SECURITY BASELINE INSPECTION REPORT 05000282/2011403(DRS);
Dear Mr. Schimmel:
On May 27, 2011, the U. S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Prairie Island 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 May 27, 2011, with Mr. K. Davison 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 inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
This report documents one self-revealing finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) and associated 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 this inspection before the inspectors left the site. The finding had a cross-cutting aspect in the area of Human Performance, Work Practices (H.4(b)), because the security supervisor failed to comply with established procedures.
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the NRC Enforcement Policy because of the very low security significance of the violation and because it was entered into your corrective action program.
If you contest the subject or severity of a NCV, 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 20555-0001, with a copy 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 Office at the Prairie Island Nuclear Generating Plant.
In addition, if you disagree with the cross-cutting aspect assigned to the findings 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.
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 document system, ADAMS.
ADAMS is 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/
Richard A. Skokowski, Chief Plant Support Branch Division of Reactor Safety
Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60
Nonpublic Enclosure: Inspection Report 05000282/2011403(DRS);
50000306/2011403(DRS)
w/Attachment: Supplemental Information
cc w/encl:
S. Coker, NSIR/DSO/DDSO/ST C. Johnson, NSIR J. Trapp, Region I M. Ernstes, RII M. Hay, RIV
cc w/o encl:
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