ML19256E518

Fr Notice of Granting of Relief on Interim Basis from ASME Section XI Inservice Insp & Testing Requirements

ML19256E518
Person / Time
Site:	Rancho Seco
Issue date:	10/17/1979
From:	Conner E Office of Nuclear Reactor Regulation
To:
Shared Package
ML19256E516	List: ML19256E515 ML19256E518
References
TAC-10816, NUDOCS 7911070559
Download: ML19256E518 (2)

Text

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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION

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DOCKET NO. 50-312 SACRAMENTO MUNICIPAL UTILITY DISTRICT NOTICE OF GRANTING OF RELIEF FROM ASME SECTION XI INSERVICE INSPECTION TESTING) REQUIREMENTS

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The U. S. Nuclear Regulatory Commission (the Commission) has granted relief from certain requirements of the ASME Code,,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Compo ents" to Sacramento Municipal Utility District. The relief relates to the inservice inspection (testing) program for the Rancho Seco t uclear Generating Station (the facility) located in Sacramento County, California. The ASME Code requirements are incorporated by reference into the Commission's rules and regulations in 10 CFR Part 50.

The relief is effective as of its date of issuance.

The relief is granted on an 'aterim basis, pending completion of our detailed review from those inservice inspection and testing requirements of

. the ASME Code that the licensee has determined to be impractical within the limitations of design, geometry and materials of construction of components, because compliance would result in hardships or unusual difficulties without a compensating increase in the level of quality or safety.

The request for relief complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commissior. has made appropriate findings as 1'"3 046 790L1070 e

759C-01

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0hh required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the letter granting relief.

Prior public notice of this action was not required since the granting of this relief from ASME Code requirements does not involve a.significant hazards consideration.

The Co=nissica has determined that the granting of this relief will not resul.t in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with this action.

For further details with respect ot this action, see (1) the request fer relief dated July 18,1979, and (2) the Commission's letter to the licensee dated October 17,1979.

These items are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D. C. and at the Business and Municipal Department, Sacramento City-County Library, e

828 I Street, Sacramento, California 95814. A copy of item (2) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.

20555, Attention:

Director, Division of Operating Reactors.

Dated at Bethesda, Maryland, this 17th day of October,1979.

FOR THE NUCLEAR REGULATORY COMMISSION c/

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Eber L. C:rr.er, Acting Chief 0:erating Reac crs Branch #4 Division of Ocera:ing Reactors

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