ML20063N626
| ML20063N626 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/31/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063C546 | List: |
| References | |
| TAC-49449, TAC-49450, NUDOCS 8210040427 | |
| Download: ML20063N626 (3) | |
Text
U 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-266 AND 50-301 WISCONSIN ELECTRIC POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSE AND NOTICE OF GRANTING OF RELIEF FROM CERTAIN REQUIREMENTS OF ASME CODE SECTION XI INSERVICE INSPECTION REQUIREMENTS The U., S.f uclear Regulatory Commission (the Commission) has N
issued Amen.dmeht No. 63 to Facility Operating License No. DPR-24, and Amendment No. 68 to Facility Operating License No. DPR-27 issued to Wisconsin Electric Power Company (the licensee), which revised Tech-nical Specifications for operation of Point Beach Nuclear Plant, Unit Nos. I and 2 (the facilities) located in the Town of Two Creeks, Manitowoc County, Wisconsin.
The amendments are effective 20 days from the date of issuance.
The amendments revise the language of the Technical Specifications -
relating to inservice inspection requirements of safety class components to conform with 10 CFR 50.55a, the Codes and Standards Rule.
The Commission has also granted relie# from certain requirements of the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plan Components" to the Wisconsin Electric Company. The relief relates tc the Inservice Inspection Program for the Point Beach Nuclear Plant Units 1 and 2.
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 the date of issuance.
DESIGITATED ORIGINAL Cortified By 8210040427 820831 PDR ADOCK 05000266 P
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7590-01.The relief relates to certain inservice inspection requirements, pursuant to 10 CFR Section 50.55a(g)(6)(1) of the Commission's regula-tions, involving volumetric, visual and surface examinations of piping, component pressure boundary and support structural integrity.
The aDplication for amendments and requests for relief comply with the standards and requirenents 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 related Safety Evaluation.
Prior public notice of these amendments and requests for relief was not required since they do not involve a signi-ficant hazards consideration.
The Commission has determined that the issuance of the amendment and -
granting of relief will not result in any significant environmental impact and that pursuant to 10 CFR Section 51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this action.
For further details with respect to this action, see (1) the licensee's applications for amendments dated Febrauary 17, 1977 and November 27, 1978,,
(2) the licensee's letters dated May 20, 1977, October 6,1977, February 6, 1979, February 26, 2979, December 14, 1979, October 6,1981 and April 14, 1982, (3) Amendment Nos. 63 and 68 to License Nos. DPR-24 and DPR-27, (4) the Commissicn's letter to the licensee dated and (5) the Conmission's related Safety Evaluation including the attached
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7590-01 '
Technical Evaluation Report prepared by Science Applications Incorporated. ~
All of these items are available for public inspection at the Commission's j
Public Document Room, 1717 H Street, N.W., Washington, D. C.
20555 and at t
the Joseph Mann Library, 1516 16th Street, Two Rivers, Wisconsin 54241.
A copy of items (3), (4) and (5) may be obtained upon request _ addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
- 20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland this 31st day of August, 1982.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing h
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