ML20003J078
| ML20003J078 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/23/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003J073 | List: |
| References | |
| NUDOCS 8105080413 | |
| Download: ML20003J078 (2) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-409 DAIRYLAND POWER COOPERATIVE NOTICE OF GRANTING OF RELIEF FROM CERTAIN REQUIRD1ENTS 0F ASME CODE SECTION XI INSERVICE (TESTING) REQUIREMENTS The U. S. Nuclear Regulatory Comission (the Comission) has granted relief from certain requirements of the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components" to the Dairylanu Power Cooperative. The relief relates to the Inservice (Testing) Program for the Lacrosse Boiling Water Reactor Ur it No.1 (the facility) located in Vernon County, Wisconsin.,The ASME Code requirements are incorporated by reference into the Comission's rules and regulations in 10 CFR Part 50. The relief is effective as of its date of issuance.
The relief allows postponement of cartain inservice valve testing requirements, pursuant to 10 CFR 50.55a(g)(6)(1) of the Comission's regulations.
Tte raquests for relief comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission'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 relief from ASME Code requirements does not involve a significant hazards consideration.
The Comission has determined that the granting of relief will not result ia 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 issuance of this action.
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. For further details with respect to this action, see (1) the licensee's letters dated July 27, 1979 January 21, 1980, January 30,1980, July 14 1980, and November 19,1980,(2) the Comission's letter to the licensee dated April 23,1981, and (3) the Comission's related Safety Evaluation. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N. W., tiashington, D. C.
20555 and at the Lacrosse Public Library, 800 Main Street, Lacrosse, Wisconsin 54601. A copy of items (2) and (3) may be obtained upon request addressed to the U. S.
Nuclear Regulatch Comission, Washington, D. C.
20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this 23rd of April,1981.
FOR THE NUCLEAR REGULATORY COMMISSION fiig7 -l
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a Denriisl.'Crut h' field, Operating Reactors Branch #5 Division of Licensing t
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