IR 05000333/2007007

IR 05000333-07-007, on 04/09/2007 - 04/26/2007; James A. FitzPatrick Nuclear Power Plant; Scoping of Non-Safety Systems and the Proposed Aging Management Procedures for the James A. FitzPatrick Nuclear Power Plant Application for Renewed Li

ML072140637
Person / Time
Site:	FitzPatrick
Issue date:	08/02/2007
From:	Conte R Engineering Region 1 Branch 1
To:	Peter Dietrich Entergy Nuclear Northeast
Shared Package
ML072140656	List: IR 05000333/2007007
References
IR-07-007
Download: ML072140637 (37)

Text

ust 2, 2007

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC LICENSE RENEWAL INSPECTION REPORT 05000333/2007007

Dear Mr. Dietrich:

On April 26, 2007, an NRC team completed the onsite portion of its inspection of your application for license renewal of your James A. FitzPatrick Nuclear Power Plant. The enclosed report documents the results of the inspection, which were discussed on June 21, 2007, with you and members of your staff in an exit meeting open for public observation in Fulton, New York.

The purpose of this inspection was to examine the plant activities and documents that support the application for a renewed license of the James A. FitzPatrick Nuclear Power Plant. The inspection reviewed the screening and scoping of non-safety related systems, structures, and components, as required in 10 CFR 54.4(a)(2), and 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 inspection team concluded screening and scoping of non-safety related systems, structures, and components were implemented as required in 10 CFR 54.4(a)(2), and the aging management portion of the license renewal activities was conducted as described in the License Renewal Application. The inspection 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, programs, and procedures.

Overall, the inspection results support a conclusion that the proposed activities will reasonably 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. 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 NRCs 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 No. 50-333 License No. DPR-59 Enclosure: Inspection Report 05000333/2007007