ML083231018
| ML083231018 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek, Vermont Yankee |
| Issue date: | 04/15/2008 |
| From: | Hufnagel J Exelon Corp |
| To: | Ashley D Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2008-0306 | |
| Download: ML083231018 (2) | |
Text
Donnie Ashley From:
<john.hufnagel@exeloncorp.com> [john.hufnagel@exeloncorp.com]
Sent:
Tuesday, April 15, 2008 4:43 PM To:
Donnie Ashley
Subject:
RE: Draft Telecon rev 2 Follow Up Flag:.
Follow up Flag Status:
Flagged
- Donnie, This looks fine. Thanks.
- John.
Original Message -----
From: D. Ashley [1]
Sent: Tuesday, April 15, 2008 3:40 PM To: Hufnagel Jr, John G
Subject:
Draft Telecon rev 2 John-This is best viewed in HTML....
Please review and comment.
April 7, 2008 The U.S. Nuclear Regulatory Commission staff (NRC or the staff), representatives of AmerGen Energy Company, LLC (AmerGen or the applicant) and Structural Integrity Associates, Inc, held a telephone conference call on April 7, 2008, to discuss the question of industry experience as it relates to metal fatigue and the use of simplified calculations in developing environmental fatigue analyses for the period of extended operation. The conference call was useful in clarifying the applicant's use of these methods During the evaluation of the Vermont Yankee license renewal application and hearing process, the staff has become aware that the industry may be using a non-conservative calculation to evaluate metal fatigue in BWRs.
The calculation involves the use of "Greens Function" and limiting stress component difference (versus using all six stress components) as a simplification to the analysis.
The applicant stated that the only environmental fatigue analysis where Greens Function and limiting stress component difference were used is for the Reactor Recirculation outlet nozzle. None of the other calculations involved the use of Greens Function.
The applicant stated that they were aware of the issue. The applicant stated that they have plans to perform a confirmatory analysis of the outlet nozzle, using the more conservative calculations, to insure that the components cumulative usage factor (CUF) is within specifications.
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The applicant will provide the results of the analysis to the staff. The applicant plans to complete the analysis within 30 days.
April 15, 2008 The U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives of AmerGen Energy Company, LLC (AmerGen or the applicant), held a telephone conference call on April 15, 2008, to continue the discussion of the question of AmerGen's confirmatory analysis of the Reactor Recirculation outlet nozzle as it relates to metal fatigue.
The conference call was useful in clarifying the applicant's plans to perform a confirmatory analysis and the staffs expectations for the documentation of the results of the analysis.
The staff will formalize the questions in a separate request for additional information (RAI) letter which will be sent to the applicant. The applicant understands that they will respond to the questions in a formal letter which will be placed in the official agency records system.
Donnie Ashley NRR/DLR/RPB1 License Renewal Project Manager for Oyster Creek and Plant Vogtle 301-415-3191 dial (nrc.qov
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