IR 05000373/2011404
| ML11195A175 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/11/2011 |
| From: | Richard Skokowski Plant Support Branch II |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-11-404 | |
| Download: ML11195A175 (5) | |
Text
July 11, 2011
SUBJECT:
LASALLE COUNTY STATION NRC SECURITY BASELINE INSPECTION REPORT 05000373/2011404(DRS);
Dear Mr. Pacilio:
On June 9, 2011, the U. S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your LaSalle County Station. 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 June 9, 2011, with Mr. D. Rhoades 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 NRC-identified 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, Resources H.4(c), because the licensee failed to ensure that supervisory and management oversight of work activities, including contractors, such that nuclear safety is supported. 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,
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. 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 LaSalle County Station.
In addition, if 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 Regional Administrator, Region III, and the NRC Resident Inspector at the LaSalle County 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 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. 50-373; 50-374 License Nos. NPF-11; NPF-18
Nonpublic Enclosure: Inspection Report 05000373/2011404 (DRS);
w/Attachment: Supplemental Information
DISTRIBUTION:
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