ML19339C884

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Requests NRC Approval of ASME Code Case N-295,permitting Use of Existing Const Matls Certified Per Code Editions Dated Earlier than Edition Specified for Const.Unofficial Version of Code Case Encl
ML19339C884
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 02/03/1981
From: Tramm T
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8102120217
Download: ML19339C884 (2)


Text

'

. - - Commonwealth Edison

[ \ On] First Natenal Piaza, Chicago, likno{s

! T 7 Address R; ply to: Post Office Bo< 767

's / Chicago, Illinois 60690 x-February 3, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Utilization of ASME Code Case N-295 NRC Docket Nos. 50-454, 50-455, 50-456 and 50-457

Dear Mr. Denton:

This is to inform you of sur intent to make use of ASME Code Case N-295 so that we may utilize existing construction materials certified in accordance with Code Editions and addenda dated earlier than the one specified for construction. An unofficial copy of the final version of the Code Case is attached.

This Code Case was passed at the Main Committee meeting on October 31, 1980. We understand that no negative ballots have been cast and Council approval is expected in March, 1981. Commonwealth Edison requests that the NRC staff acknowledge acceptability of this Code Case for immediate use at Byron and Braidwond Stations.

The use of this Code Case will permit use of surplus materials procured for other Commonwealth Edison nuclear power plant projects. Timely NRC approval will help maintain orderly scheduling and will have economic benefits. If there are any questions regarding this request, please contact me as soon as possible.

One (1) signed original aca thirty-nine (39) copies of this letter and the attachment are enclosed.

Very truly yours, 5 0 74[

. u

, T. R. Tramm Nuclear Licensing Administrator

_ Pressurized Water Reactors Enclosurel 02878 ';:

8102120 gg r

    • , *FCodo Case N-295 S3ction III, Division 1 Construction NCA-1140, Materials .

l INQUIRY: May existing materials previously produced which had been certified in accordance with Code Editions and .

Addenda earlier than the one specified for construction of items be used.

REPLY: It is the opinion of the Committee that existing materials previously produced and certified in accordance with Code Editions and Addenda earlier than the one specified for construction of Section III, Division 1 ite=s may be used provided all of the following requirements are satisfied:

1) The material (NCA-1220) meets the requirements of a material specification permitted by paragraph 2121 of the applicable subsection of the Code Edition and Addenda specified for construction.
2) The material meets the applicable requirements of Article 2000 of the applicable subsection of the Code Edition and Addenda specified for construction.
3) The materials was produced under the provisions of a Quality System Program which had been accepted by the Society or qualified by a party other than the Society (NCA-3820) in accordance with the requirements of the latest Code Edition and Addenda issued at the time the material was pruduced. Material exempted from portions of the provisions of NCA.3800 by subsubarticle 2610 of the applicable subsection of the Code may be used provided the requirements of (1) and (2) above are met.
4) The N-type Certificate Holder who intends to use the material shall verify that the above requirements

. have been satisfied using test reports and documentation generated at the time the material was produced or by having the required tests and.

examinations performed again, or by having OOC g 3 b^IC additional required tests and examinations performed.

5) The N-type Certificate Holder shall document the review and approval of material used by him as permitted by this case.
6) Materials permitted by this Case shall be reviewed by the Owner or his designee for acceptability to the regulatory and enforcement authorities having jurisdiction at the nuclear power plant site.

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7) This Code Case shall be identified on the applicable Code Data Report Form.

This Ccde Case chall be annulled 6 montas after publicaticn of the revised Code rules.

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