ML083220249

Acceptance Review of Relief Request CR-26, Inservice Inspection Program Relief Regarding Examination Coverage for Second 10-Year Inservice Inspection Interval

ML083220249
Person / Time
Site:	LaSalle
Issue date:	11/20/2008
From:	Sands S P Plant Licensing Branch III
To:	Pardee C G Exelon Nuclear
Sands S P
References
TAC MD9817, TAC MD9818
Download: ML083220249 (3)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 20, 2008 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNITS 1 AND 2 -REQUEST FOR SUPPLEMENTAL INFORMATION REGARDING RELIEF REQUEST CR-26, INSERVICE INSPECTION PROGRAM RELIEF REGARDING EXAMINATION COVERAGE FOR SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NOS. MD9817 AND MD9818)

Dear Mr. Pardee:

By letter to the Nuclear Regulatory Commission (NRC), dated October 1, 2008, Exelon Generation Company, LLC (the licensee), submitted a relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The proposed relief requested NRC approval to use a proposed alternative to the existing American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements is impractical due to plant design. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this RR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Section 50.55a(g)(5)(iii) of Title 10 of the Code of Federal Regulations (10 CFR), if the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in

§ 50.4, information to support the determination. Based on the review conducted by the NRC staff, it has been determined that there is insufficient technical information in scope and depth to allow NRC to complete its technical review. Therefore, the NRC staff has requested additional information be provided in order to make an independent assessment regarding the acceptability of the RR in terms of regulatory requirements and the protection of public health and safety. In order to make the request complete, the NRC staff requests that you supplement your October 1,2008, submittal to address the information requested below, by November 21,2008. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by this date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the request. If the request is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review C. Pardee -2 by separate correspondence. The information requested and associated time-frame in this letter was discussed with members of your staff on November 6, 2008. INFORMATION NEEDED Provide further detailed information to support the basis for each limited examination in RR CR-26, and therefore, demonstrate impracticality. This information should include detailed descriptions (with sufficient explanation, and lay-out or cross-sectional drawings/sketches) to enable the NRC staff to fully understand the causes of the inspection coverage limitations and their impact on examination volume coverage. If you have any questions, please contact Stephen P. Sands, at (301) 415-3154. Stephen P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: Distribution via Listserv C. Pardee -2 by separate correspondence.

The information requested and associated time-frame in this letter was discussed with members of your staff on November 6, 2008. INFORMATION NEEDED Provide further detailed information to support the basis for each limited examination in RR CR-26, and therefore, demonstrate impracticality.

This information should include detailed descriptions (with sufficient explanation, and lay-out or cross-sectional drawings/sketches) to enable the NRC staff to fully understand the causes of the inspection coverage limitations and their impact on examination volume coverage. If you have any questions, please contact Stephen P. Sands, at (301) 415-3154 Sincerely, IRA by MDavid fori Stephen P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.

50-373 and 50-374 cc: Distribution via Listserv DISTRIBUTION PUBLIC LPL3-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrLAEWhitt Resource RidsNrrPMLaSalle Resource S. Meighan, NRR RidsOgcRp Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrDciCvib Resource RidsNrrDorlLpl3-2 Resource Accession No. ML083220249

• wi comments OFFICE LPL3-2/PM LPL3-2/LA DCI/CVIB/BC LPL3-2/BC NAME SSands MDavid for EWhitt MMitchell

• RGibbs DATE 11/19/08 11/20/08 11/20/08 11/20/08 OFFICIAL RECORD COpy