IR 05000346/2007007

Davis-Besse - Information Request for NRC Biennial Baseline Component Design Bases Inspection 05000346-07-007 (DRS)

ML070851413
Person / Time
Site:	Davis Besse
Issue date:	03/26/2007
From:	Stone A M NRC/RGN-III/DRS/EB2
To:	Bezilla M B FirstEnergy Nuclear Operating Co
References
IR-07-007
Download: ML070851413 (10)

Text

March 26, 2007

Mr. Mark B. BezillaSite Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760

SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION - INFORMATION REQUESTFOR AN NRC BIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION 05000346/2007007(DRS)

Dear Mr. Bezilla:

On October 22, 2007, the NRC will begin a biennial baseline Component Design BasesInspection (CDBI) at the Davis-Besse Nuclear Power Station. This inspection will be performed in accordance with revised NRC Baseline Inspection Procedure (IP) 71111.21 and replaces the biennial Safety System Design and Performance Capability Inspection. The CDBI inspection focuses on components which have high risk and low design margins. The components to be reviewed during this baseline inspection will be identified during an in-office preparation week prior to the first week of the on-site inspection. In addition, a number of risk significant operator actions and operating experience issues, associated with the component samples, will also be selected for review. The inspection will include three weeks on-site, including the information gathering during thefirst on-site week. The inspection team will consist of six NRC inspectors, of whom five will focus on engineering and one on operations. The current inspection schedule is as follows: *October 22 through October 26, 2007;*November 5 through November 9, 2007; and

• November 26 through November 30, 2007.The team will be preparing for the inspection, mainly during the week of October 15, 2007, asdiscussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany theinspection team during the week of October 22, 2007, to review probabilistic risk assessment data and assist in identifying risk significant components, which will be reviewed during the inspection.Experience with previous baseline design inspections of similar depth and length has shownthat these type of inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection.

M. Bezilla-2-It is important that all of these documents are up to date and complete in order to minimize thenumber of additional documents requested during the preparation and/or the on-site portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector. The information request has been divided into three groups:*The first group lists information necessary for our initial inspection scoping activities. This information should be available to the lead inspector no later than September 24, 2007. By October 3, 2007, the lead inspector will communicate the initial selected set of approximately 30 high risk components. *The second group of documents requested are those items needed to support ourin-office preparation activities. This set of documents, including the calculations associated with the initial selected components, should be available at the Regional Office no later than October 10, 2007. During the in-office preparation activities, the team may identify additional information needed to support the inspection. *The last group includes the additional information above as well as plant specificreference material. This information should be available to the team on the first day of the inspection. It is also requested that corrective action documents and questions developed during the inspection be provided to the inspectors throughout the inspection.The lead inspector for this inspection is Mr. Andrew Dunlop. We understand that our licensingcontact for this inspection is Mr. G. Wolfe of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9726 or via e-mail at AXD7@nrc.gov.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter andits enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (thePublic Electronic Reading Room).

Sincerely,/RA/Ann Marie Stone, ChiefEngineering Branch 2 Division of Reactor Safety Docket No. 50-346License No. NPF-3

Enclosure:

Component Design Bases Inspection Document RequestSee Attached Distribution