IR 05000334/2008007

IR 05000334-08-007 & 05000412-08-007; Firstenergy Nuclear; 06/23/2008 - 07/18/208; Beaver Valley Power Station Units 1 & 2; Scoping of Non-Safety Systems and the Proposed Aging Management Programs for the Beaver Valley Application for Renew

ML083590068
Person / Time
Site:	Beaver Valley
Issue date:	12/23/2008
From:	Conte R Engineering Region 1 Branch 1
To:	Sena P FirstEnergy Nuclear Operating Co
References
IR-08-007
Download: ML083590068 (37)

Text

ber 23, 2008

SUBJECT:

BEAVER VALLEY POWER STATION - NRC LICENSE RENEWAL INSPECTION REPORT 05000334/2008007 & 05000412/2008007

Dear Mr. Sena:

On July 18, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed the major onsite portion of the Region I team inspection of your application for license renewal of your Beaver Valley Power Station Units 1 and 2. The enclosed report documents the results of the inspection, which were discussed on November 12, 2008, with you and members of your staff in an exit meeting open for public observation in Pittsburgh, PA.

The purpose of this inspection was to examine, on a sampling basis, the plant activities and documents that support the application for a renewed license of the Beaver Valley Power Station Units 1 and 2. The inspection team reviewed the scoping of non-safety-related systems, structures, and components, as required in 10 CFR 54.4(a)(2). Further, the team determined whether the proposed aging management programs are capable of reasonably managing the effects of aging. These NRC inspection activities constitute one of several inputs into the NRC review process for license renewal applications.

The team concluded that the scoping of non-safety-related systems, structures, and components was implemented as required in 10 CFR 54.4(a)(2). Further, the team concluded that the aging management portion of the license renewal activities was conducted as described in the License Renewal Application. The team concluded that the documentation supporting the application was in an auditable and retrievable form. The team identified a number of areas that resulted in changes to the application.

Overall, the inspection results support a conclusion of reasonable assurance that actions have been identified and have been taken or will be taken to manage the effects of aging in the systems, structures, and components identified in your application and that the intended functions of these systems, structures, and components will be maintained in the period of extended operation. III 2 In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its 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). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Richard J. Conte, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-334 and 50-412 License Nos. DPR-66, NPF-73 Enclosure: Inspection Report 05000334/2008007 and 05000412/2008007