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MONTHYEARML19309H8111980-05-0808 May 1980
Forwards IE Info Notice 80-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in Refueling Mode. No Response Required
Project stage: Other
ML19318B8961980-06-0505 June 1980
Responds to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Plant Design Does Not Provide for Automatic Actuation of ECCS Recirculation or Automatic Positioning of Containment Recirculation Sump Valves
Project stage: Other
ML20008E2951980-10-14014 October 1980
Responds to NRC Re Proposed Tech Spec Changes for All Facilities to Provide for Redundancy in Decay Heat Removal Capability.Plant Specs Already Address Concerns & Require No Changes
Project stage: Other
ML20010E8541981-08-14014 August 1981
Requests That Proposed Tech Specs for Redundancy of Decay Heat Removal Capability in All Modes of Operation & Related Safety Analysis Be Submitted within 60 Days.Model Tech Specs to Assist in Preparation of Submittal Encl
Project stage: Other
ML20038B1351981-11-16016 November 1981
Tech Spec Change Request 72 for Amend to License DPR-24 & DPR-27,changing Tech Specs 15.3.1,15.3.3 & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions
Project stage: Other
ML20038B1461981-11-16016 November 1981
Proposed Tech Specs Sections 15.3.1,15.3.3. & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions
Project stage: Other
ML20039C4011981-11-18018 November 1981
Comments on Util Tech Spec Change Request 72,proposing Revision to Tech Spec 15.3.1.A.2(a) Re Redundancy of Decay Heat Removal Sys.Elimination of Decay Heat Removal Capability Above 350 F Inappropriate
Project stage: Other
ML20039C4191981-12-0909 December 1981
Interim Deficiency Rept DER 81-39 Re Unit 1.Gas Stripper by C-E Has Undocumented Section of Pipe & Welds in Violation of ASME Code,Initially Reported 811112.Evaluation & Final Rept Expected by 820129
Project stage: Other
ML20039C3981981-12-21021 December 1981
Forwards Region 3 Comments Re Util Tech Spec Change Request 72
Project stage: Other
ML20040H0251982-01-22022 January 1982
Informs That 811116 Proposed Amend to Tech Specs Re Establishment of Redundancy of Decay Heat Removal Capability During All Modes of Operation Is Unacceptable.Application Should Be Modified
Project stage: Other
ML20052D8061982-05-0303 May 1982
Advises That Westinghouse Will Not File Reply Brief in Response to Wi Environ Decade Brief.Svc List Encl
Project stage: Request
ML20052E9091982-05-0303 May 1982
Revised Application for Amend to Licenses DPR-24 & DPR-27 Consisting of Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities
Project stage: Request
ML20052E9201982-05-0303 May 1982
Proposed Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities
Project stage: Request
ML20027D2131982-07-31031 July 1982
Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2
Project stage: Other
ML20069L7481982-11-0808 November 1982
Safety Evaluation Supporting Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively
Project stage: Approval
ML20069L7521982-11-0808 November 1982
Notice of Issuance & Availability of Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively
Project stage: Other
ML20069L7421982-11-0808 November 1982
Amend 66 & 71 to Licenses DPR-24 & DPR-27,respectively, Upgrading Tech Specs to Provide Redundancy of DHR Capability in All Modes of Operation
Project stage: Other
ML20081D3121983-10-25025 October 1983
Application to Amend Licenses DPR-24 & DPR-27,changing Tech Spec 15.3.1.A to Eliminate Provisions Beyond Basis for Required Operational Components of Rcs.Class II Fee Encl
Project stage: Request
ML20081D3241983-10-25025 October 1983
Proposed Changes to Tech Spec 15.3.1.A Eliminating Provisions Beyond Basis for Required Operational RCS Components
Project stage: Request
ML20086M6131984-02-0202 February 1984
Safety Evaluation Supporting Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively
Project stage: Approval
ML20086M6031984-02-0202 February 1984
Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively, Clarifying Limiting Condition for Operation of Steam Generators & Other DHR Equipment,Indicating Conditions Only Applicable When Fuel Loaded in Core
Project stage: Approval
1981-12-09
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Text
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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 LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 66 to Facility Operating License No. DPR-24, and Amendment No. 71 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.1 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 upgrade the existing Technical Specifications for Point Beach Units 1 and 2 in order to provide for redundancy of decay heat removal during all modes of operation.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the The Commission has Act), and the Commission's rules and regulations.
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 license amendments. Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
'8211170566 825108 PDR ADOCK 05000266
7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR Sl.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
For further details with respect to this action, see,(1) the application for amendments dated November 16, 1981 as modified by letter dated May 3, 1982, (2) Amendment Nos. 66 and 71 to License Nos. DPR-24 and DPR-27, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Docuinent Room,1717 H Street, N.W., Washington, D.C. 20555, and at the Joseph Mann Library, 1516 16th Street, Two Rivers, Wisconsin 54241. 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.
Dated at Bethesda, Maryland, this 8th day of November,1982.
FOR THE NUCLEAR REGULATORY COMMISSION
/)(
t-Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing l
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