ML20236X858

Forwards SER Accepting Confirmation of Revised Feedwater Nozzle Crack Growth Analysis for Plant,Unit 1,per & Suppl

ML20236X858
Person / Time
Site:	Fermi
Issue date:	08/05/1998
From:	Kugler A NRC (Affiliation Not Assigned)
To:	Gipson D DETROIT EDISON CO.
Shared Package
ML20236X860	List: ML20236X858 ML20236X861
References
GL-81-11, TAC-MA0211, TAC-MA211, NUDOCS 9808100326
Download: ML20236X858 (3)

Text

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2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30684 4001 8O ,

. . . . . ,o August 5, 1998 Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detioit Edison Company 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

CONFIRMATION OF FEEDWATER NOZZLE CRACK GROWTH ANALYSIS (FERMI-2) (TAC NO. MA0211)

Dear Mr. Gipson:

By letter dated December 1,1997, as supplemented by letter dated June 24,1998, you submitted confirmation of a revised feedwater nozzle crack growth analysis for Fermi Unit 2.

The information was in response to an NRC request for confirmation of the revised analysis with new operating data on thermal cycles. The NRC also requested that you submit the analysis for review 6 months prior to the end of 12 operating years.

The original analysis submitted in 1989 demonstrated that the oostulated crack would grow to 1.0 inch in ? 9 operating years. For the analysis you used estimated or assumed thermal cycles based on tne limited actual data available at that time. The crackcawth analysis did not satisfy the Generic Letter (GL) 81-11 criterion of limiting growth of a postulated 0.25-inch deep crack to a depth no greater than 1.0 inch in 40 years, in 1992 you used updated thermal cycle data for a revised analysis and demonstrated that the postulated crack would grow to a 1.0 inch depth in 38.3 years. Since the analysis res.ults were close, but did not satisfy the criterion in GL 81-11, the staff determined that the overall methodology was acceptable; but confirmation of the analysis was required. You also committed to follow the feedwater nozzle inspection schedule and examination specified in j NUREG-0619, "BWR [ Boiling-Water Reactor) Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," in order to monitor the structural integrity of the feedwater nozzles in the interim.

The current submittal includes additional operating thermal cycle data. The analysis of the new data resulted in a new cycle projection and an estimated crack growth to 0.8 inch in 40 years of plant operation. This is less than the growth limit in GL 81-11.

The NRC staff has completed its review and concludes that the confirmation of the revised feedwater nozzle crack growth analysP, is acceptable and satisfies the criterion !n GL 81-11.

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i D. R. Gipson August 5, 1998 A copy of the related safety evaluation is enclosed. This completes the staff effort on this issue and closes TAC No. MA0211.

Sincerely, Original signed by Andrew J. Kugler, Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosure:

Safety Evaluation cc w/ encl: See next page DISTRIBUTION:

Docket File PUBLIC PD31 Rdg E. Adensam (EGA1)

B. Burgess, Rill A. Lee OGC.

ACRS SEDB (TLH3)

DOCUMENT NAME: G:\WPDOCS\ FERMI \FE-A0211.SE To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" =

~ Copy with attachment / enclosure "N" = No copy-i' OFFICE PM:PD31 E LA:PD31 E D:PD3-1 lE.

NAME AKugler.db O,\ ft- CJamerson G(/ CACarpenterM i i DATE 07/23/98 U 07/ 2 i/98 [j 07/M) /98 OFFICIAL RECORD COPY 1

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Mr. Douglas R. Gipson Fermi 2 Detroit Edison Company cc:

John Flynn, Esquire Senior Attorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Emergency Management Division 963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Reg!on !!!

- U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Norman K. Peterson Director, Nuclear Licensing Detroit Edison Company Fermi 2 - 280 TAC 6400 North Dixie Highway Newport, Michigan 48166 August 1997

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