ML20009B393

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Notice of Granting of Relief from ASME Code Section IX Re Inservice Testing Requirements
ML20009B393
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/29/1981
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20009B390 List:
References
NUDOCS 8107150359
Download: ML20009B393 (2)


Text

7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-285 OMAHA PUBLIC POWER DISTRICT NOTICE OF GRANTING OF RELIEF FROM ASME CODE SECTION XI INSERVICE TESTING REQUIREMENTS 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 Components" to Omaha Public Power District (the licensee), which revised the inservice testing program for the Fort Calr.oun Station, Unit No.1, located in Washington County, Nebraska.

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, and expires on September 25, 1983.

The relief consists of exemption from performing valve exercising at each cold shutdown for check valves SI-159 and SI-160.

In lieu of this, the licensee has visually inspected SI-159 and will be required to visually inspect SI-160 at the next refueling outage and report conditions found.

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 Commission has made appropriate findings as 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 and related Safety Evaluation. The granting of this relief does not involve a significant hazards consideration.

LT107150359 810629 PDR ADOCK 05000285 P

PDR

7590-01

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2-The Commission has determined that the granting of this relief will not result 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 to this action, see (1) the request for relief dated July 9, 1980, as supolemented May 20,1981,(2) the letter to the licensee dated June 29, 1981, and (3) the Commission's related Safety Evaluation. All of these items are available for public inscection at the Commission's Public Document Room, 1717 H Street, N.'.J., Washington, D. C.

20555, and at the W. Dale Clark Library, 215 South 15th Street, Caana, Nebraska 68102. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.

20555, Attention:

Director, Division of Licensing.

FOR THE NUCLEAR REGULATORY COMMISSION

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, Q/M. b' 'c4 Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing e

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