ML090280055

Oyster Creek, Submittal of Analytical Evaluation in Accordance with IWB-3134(b)

ML090280055
Person / Time
Site:	Oyster Creek
Issue date:	01/21/2009
From:	Cowan P B Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-09-011
Download: ML090280055 (2)

Text

Exelkn.Exelon Nuclear www.exeloncorp.com 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.55a RA-09-011 January 21, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

Submittal of Analytical Evaluation in Accordance with IWB-3134(b)

In accordance with the American Society of Mechanical Engineers (ASME) Code,Section XI, 1995 Edition through 1996 Addenda, IWB-3134(b)

("Review by Authorities"), Oyster Creek Nuclear Generating Station is submitting an analytical evaluation associated with the recirculation suction (reactor pressure vessel outlet) nozzle-to-safe end weld (N1A).As discussed in the attached report, an analytical evaluation of an indication was performed to disposition an indication associated with the recirculation suction (reactor pressure vessel outlet) nozzle-to-safe end weld (N1A). The indication is circumferentially oriented, measured by ultrasonic testing to be approximately 12.1 inches long with a depth of 0.20 inches taken from the clad base metal interface.

The indication is located 0.6 inches upstream of the weld centerline (nozzle side), which would place it in the low alloy steel. The nozzle-to-safe end weld is a dissimilar metal weld joining the low alloy steel nozzle to the stainless steel safe end with an Alloy 182 weld. The Mechanical Stress Improvement Process (MSIP) was applied to this weld in 1994, although it was not taken credit for in the evaluation.

As concluded in this evaluation, the required safety factors will be maintained during operation with this indication over the next two operating cycles, by which time the flaw will be further evaluated in accordance with code requirements.

There are no new regulatory commitments contained in this letter.A404-7 U. S. Nuclear Regulatory Commission January 21, 2009 Page 2 of 2 If you have any questions or require additional information, please contact Tom Loomis (610-765-5510).

Respectfully, Pamela B. Cowan Director -Licensing

& Regulatory Affairs Attachment

-Analytical Evaluation cc: S. J. Collins, Administrator, USNRC, Region I (w/attachment)

M. S. Ferdas, USNRC Senior Resident Inspector, OCNGS (w/attachment)

G. E. Miller, USNRC (w/attachment)