ML20059L057

Discusses Re Staff Interim Fatigue Curves from NUREG/CR-5999, Interim Fatigue Design Curves for Carbon Low-Alloy & Austenitic Stainless Steels in LWR Environments, as Well as Other Related Comments

ML20059L057
Person / Time
Issue date:	01/26/1994
From:	Russell W Office of Nuclear Reactor Regulation
To:	Rasin W NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT &
References
RTR-NUREG-CR-5999 NUDOCS 9402030088
Download: ML20059L057 (2)

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'3f.9 2"615 Mr. William H. Rasin Vice President & Director Technical Division Nuclear Management and Resources Council 1776 Eye St;eet, N.W., Suite 300 Washington, D.C. 20006-3706

SUBJECT:

NRC FATIGUE ACTION PLAN By letter dated December 20, 1993, you forwarded comments regarding the staff's interim fatigue curves from NUREG/CR-5999, " Interim Fatigue Design Curves for Carbon, Low-Alloy and Austenitic Stainless Steels in LWR Environments," as well as other related comments concerning the adequacy of the fatigue design of metal components.

Your letter was in response to requests made during a meeting between NUMARC and the NRC staff on September 17, 1993, regarding the subject NRC Fatigue Action Plan'(FAP).

Currently, the staff is proceeding with the actions as delineated in the FAP.

The FAP was created because it was mutually recognized by both NUMARC and the NRC staff that the fatigue issues raised in the license renewal arena were more appropriately applicable to operating reactors. As a consequence, the FAP prescribes a timely schedule to address these fatigue concerns.

Consistent with Long-Term Actions II.4 and 11.5 of the FAP, the staff is currently assessing the fatigue adequacy of example reactor coolant system components'by performing analyses utilizing both the current ASME Code fatigue design curves as well as the NUREG/CR-5999 interim curves. The use of the interim curves by the staff are for internal comparative purposes.

4 The staff has not yet developed a position regarding the implementation of the interim curves. Such a position will be developed following completion of the FAP actions.

The technical considerations in your letter, as well as any others received by the staff, will be appropriately considered during the development of that position.

Recognizing the complexity of the fatigue issues, the staff has solicited relevant information from various industry sources. The staff plans to periodically meet with the industry groups involved with these issues, and to obtain their input regarding the results of the staff's analysis. We would expect that the technical issues you raised will be included in these discussions. Specific meetings will be arranged once the staff has progressed enough with the objectives of the FAP such that these meetings would be mutually beneficial, g

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. William H. Rasin :

If you have any further questions / suggestions please contact: Mr. Terence L.

Chan, Chief, Piping and Pipe Support Section, Mechanical Engineering Branch, at (301) 504-2169.

Sincerely, ORIGINAL SIGNED BY W.T. RUSSELL William T. Russell, Associate Director for Inspection and Technical Assessment Office if Nuclear Reactor Regulation Distribution:

Central Files NRC PDR CPaul 93-69 WHodges WRussell KBohrer YT-0282 BDLiaw LShao TChan JFair EMEB RF/CHRON RParkhill

• See previous concurrence page.

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NAME RParkhill TChan JNorberg WHodges PTKuo DATE 01/04/94 01/21/94 01/24/94 01/25/94 01/24/94 0FFICE DD:DE:RES*

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ADT;NRBq NAME JCraig LShao WRbell DATE Q]/24/94 01/24/94 l /1994

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