IR 05000247/2008006

Official Exhibit - NRC000107-00-BD01 - Indian Point Nuclear Generating Units 2 and 3 - NRC License Renewal Inspection Report 05000247/2008006 & 05000286/2008006

ML12339A679
Person / Time
Site:	Indian Point
Issue date:	03/31/2012
From:	Conte R Engineering Region 1 Branch 1
To:	Joseph E Pollock Entergy Nuclear Operations, Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 22176, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 IR-08-006
Download: ML12339A679 (43)

Text

United States Nuclear Regulatory Commission Official Hearing Exhibit NRC000107 In the Matter of:

Entergy Nuclear Operations, Inc. Submitted: March 31, 2012 (Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #: NRC000107-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:

Rejected: Stricken:

Other:

August 1, 2008 Mr. Joseph Pollock Site Vice President Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUBJECT: INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 - NRC LICENSE RENEWAL INSPECTION REPORT 05000247/2008006 & 05000286/2008006

Dear Mr. Pollock:

On February 14, 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 Indian Point Nuclear Generating Unit Nos. 2 and 3, with additional followup inspections through June 6, 2008. The enclosed report documents the results of the inspection, which were discussed on June 18, 2008, with you, Fred Dacimo, and members of your staff in an exit meeting open for public observation in Cortlandt Manor, NY.

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 Indian Point Nuclear Generating Unit Nos. 2 and 3. The inspection team reviewed the scoping of nonsafety-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 nonsafety-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. 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. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 Enclosure: Inspection Report 05000247/2008006 and 05000286/2008006