ML20195C411

Discusses 980825 Gpu Submittal of Proposed Mod for Ocnpp Core Support Plate Which Involved Installation of Wedges During 17R Outage.Licensee Intends to Use Recommendations of BWRVIP-25 & BWRVIP-50.SE Accepting Proposed Mod Encl

ML20195C411
Person / Time
Site:	Oyster Creek
Issue date:	11/06/1998
From:	Thomas C NRC (Affiliation Not Assigned)
To:	Roche M GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20195C414	List: ML20195C411 ML20195C427
References
TAC-MA3409, NUDOCS 9811170106
Download: ML20195C411 (2)

Text

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  , i                                                     November 6, 1998 Mr. Mich2cl B. Rocha Vice Prssidrnt and Diractor GPU Nuclsar, Inc.

Oyster Creek Nuclear Generating Station P.O Box 388 Forked River, NJ 08731

SUBJECT:

CORE SUPPORT PLATE WEDGE MODIFICATION FOR OYSTER CREEK NUCLEAR GENERATlHG STATION (TAC NO, MA3409)

Dear Mr. Roche:

By letter dated August 25,1998, as supplemented by letter dated September.14,1998, GPU Nuclear, Inc., (GPU or licensee) submitted a proposed modification for the Oyster Creek Nuclear Generating Station (OCNGS) core support plate which involved the installation of wedges during the 17R outage, for NRC staff review and approval. The licensee intends to use the recommendations of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines "BWR Core Plate Inspection and Flaw Evaluation Guidelines, BWRVIP-25," dated December 27,1996, and " Top Guide / Core Plate Repair Design Criteria (BWRVIP-50)," dated May 14,1998, in the performance of the examination, evaluation, and modification during the 17R outage. Your letter also provides the results of GPU's evaluation and determination that the proposed modification does not involve an unreviewed safety question pursuant to 10 CFR 50.59. 1 Pursuant to 10 CFR 50.55a(a)(3)(i), the staff finds that the requested action is an acceptable alternative to Section XI of the ASME Boiler and Pressure Vessel Code and provides an acceptable level of quality and safety. This determination is subject to the understanding that the staff has not yet completed its reviews of BWRVIP-25 and BWRVIP-50, and that concerns , could be identified during those reviews that may require plant specific consideration.  ; I Enclosed is the NRC staffs review and evaluation of the licensee's submittal. If you have questions regarding the Safety Evaluation, please call Ronald B. Eaton on (301) 415-3041.  ! Sincerely, f T. Colburn for Cecil O. Thomas Director

                                                                     ~

Project Directorate 1-3 l Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation - Docket No. 50-219 I

Enclosure:

As stated l cc: See next page l DISTRIBUTION 6 Docket FileN THarris (e-mail SE TLH3) k PUBLIC OGC l l PDI-3 r/f ACRS I JZwolinski CHehl, RI . REaton TClark DOCUMENT NAME: G:\EATON\MA3409.SER gD( To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachm_ eat / enclosure "N" - No copy l 0FFICE PDI-3/PM Lil / l PDI-3/LA ja3 l {., OGWdIld.-{ 3 PDI-3/D T7!v", lNAME REston \ h ) ' TClark V # L '2W # M CThomas F A ll DATE lt/ h */98 // / (3 /98 ll / {p /G3 # ' // / h /98V 0FFICIAL RECORD COPY 9811170106 981106'

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! M. Roche GPU Nuclear, Inc. cc: Emest L. Blake, Jr., Esquire , Shaw, Pittman, Potts & Trowbridge 1 2300 N Street, NW ' Washington, DC 20037 Regional Administrator, Region 1

   - U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 i

BWR Licensing Manager l GPU Nuclear Corporation 1 Upper Pond Road j Parsippany, NJ 07054 ' Mayor Lacey Township 818 West Lacey Road Forked River, NJ 08731 i Licensing Manager

   - Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.

P.O. Box 388 Forked River, NJ 08731 Resident inspector c/o U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 09731 Kent Tosch, Chief New Jersey Department of

      - Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 l

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