IR 05000346/2012402

IR 05000346-12-402(DRS); 05/29/2012 - 06/01/2012; Davis-Besse Nuclear Power Station; Routine Security Baseline Inspection - Cover Letter Only

ML12193A567
Person / Time
Site:	Davis Besse
Issue date:	07/11/2012
From:	Mel Holmberg Plant Support Branch II
To:	Allen B FirstEnergy Nuclear Operating Co
References
IR-12-402
Download: ML12193A567 (4)

Text

UNITED STATES uly 11, 2012

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION NRC SECURITY BASELINE INSPECTION REPORT 05000346/2012402(DRS)

Dear Mr. Allen:

On June 1, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Davis-Besse Nuclear Power 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 1, 2012, 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 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 inspector left the site. The finding had a cross-cutting aspect in the area of Human Performance - Resources H.2(b) because the licensee failed to ensure that personnel, equipment, procedures, and other resources were available and adequate to assure nuclear safety. 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 (CAP).

Additionally, this report documents one licensee-identified violation, which was determined to be of very low security significance. The NRC is treating this violation as an NCV consistent with Section 2.3.2 of the NRC Enforcement Policy because of the very low security significance of Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. the violation and because it was entered into your CAP. If you contest the subject or severity of an 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 Davis-Besse 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 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 letter=s 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/

Mel Holmberg, Acting Chief Plant Support Branch Division of Reactor Safety Docket No. 50-346 License No. NPF-3 Nonpublic Enclosure: Inspection Report 05000346/2012402(DRS)

w/Attachment: Supplemental Information cc w/encl: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR J. Trapp, RI B. Desai, RII M. Hay, RIV M. Bear, State Liaison Officer Ohio Emergency Management Agency cc w/o encl: Distribution via ListServ'