RS-08-007, Withdrawal of Relief Request I2R-07

Withdrawal of Relief Request I2R-07

ML080240324
Person / Time
Site:	Braidwood
Issue date:	01/23/2008
From:	Simpson P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-08-007
Download: ML080240324 (2)

Text

Exelon .

Nuclear Exelon Generation www,exeloncorp .com 4300 Winfield Road Warrenville, I L 60555 10 CFR 50.55a RS-08-007 January 23, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

Withdrawal of Braidwood Station Relief Request 12R-07

References:

1. Letter from T. Coutu (Exelon Generation Company, LLC) to U .S . Nuclear Regulatory Commission, "Inservice Relief Program Relief Request 12R-07, Revision 1," dated July 25, 2007

2. Federal Register Notice of Final Rule, "Incorporation by Reference of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Cases," 72 FR 71750, dated December 19, 2007 The purpose of this letter is to withdraw the Reference 1 submittal from U . S. Nuclear Regulatory Commission (NRC) review . Recent changes to 10 CFR 50.55a, "Codes and standards," have eliminated the need for a specific request to adopt an American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Nuclear (N) Code Case .

In the Reference 1 submittal, Exelon Generation Company, LLC (EGC) requested relief from the ASME Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components ." The request was made in accordance with 10 CFR 50.55a, paragraph (a)(3)(i) on the basis that alternative methods would provide an acceptable level of quality and safety . Specifically, EGC proposed a revision to a previously approved Braidwood Station Relief Request, 12R-07, to make use of ASME Code Case N-706, "Alternative Examination Requirements of Table IWB-2500-1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers ." At the time of the Reference 1 submittal, Code Case N-706 was not addressed in either Regulatory Guide 1 .147, Revision 14, "Inservice Inspection Code Case Acceptability" or in 10 CFR 50 .55a and therefore could not be used without NRC approval.

U. S. Nuclear Regulatory Commission January 23, 2008 Page 2 Subsequent to the Reference 1 submittal, the NRC approved a rule change (Reference 2) to 10 CFR 50.55a endorsing Regulatory Guide 1 .147, Revision 15, which provides generic approval, without restrictions, of Code Case N-706 . This rule change was effective as of January 18, 2008 . With generic approval of Code Case N-706, Braidwood Station Relief Request 12R-07 is no longer required and therefore EGC is withdrawing this licensing action from NRC review .

EGC is providing the State of Illinois with a copy of this letter to the designated State Official .

There are no Regulatory Commitments contained in this response .

If you have any questions about this letter, please contact Mr. David Chrzanowski at (630) 657-2816 .

Patrick R. Simpson Manager - Licensing