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MONTHYEARB11453, Forwards Addl Info Re SER Confirmatory Item 70 Concerning 260 Series Questions on QA Program During Operational Phase, Per Discussion During 850129 Telcon.Item Resolved1985-03-0101 March 1985 Forwards Addl Info Re SER Confirmatory Item 70 Concerning 260 Series Questions on QA Program During Operational Phase, Per Discussion During 850129 Telcon.Item Resolved Project stage: Request ML20133D9321985-07-24024 July 1985 Safety Evaluation Supporting Amend 12 to CPPR-113 Project stage: Approval ML20133D9361985-07-24024 July 1985 Notice of Issuance of Amend 12 to CPPR-113 Project stage: Approval ML18143B4431985-08-30030 August 1985 Submits Addl Info to Complete 850208 & 0520 Responses to Generic Ltr 83-28,Item 2.2 Re Description of industry-wide Approach to Vendor Interface Program Per Mar 1984 Nutac Recommendations Project stage: Request ML20138G7341985-09-26026 September 1985 Environ Assessment & Finding of No Significant Impact Supporting Exemption from Portion of GDC 4 Requirements of 10CFR50,App a Re Need to Analyze Large Primary Loop Ruptures as Structural Design Basis Project stage: Approval ML18144A0111985-11-0505 November 1985 Requests Partial Exemption from GDC 4,eliminating Protection Against Dynamic Effects of Postulated Pipe Rupture on Primary Sys Components & Piping,Per Generic Ltr 84-04. Snubbers Will Be Removed During 1986 Refueling Outage Project stage: Other ML18144A0441985-11-30030 November 1985 VEPCO Surry Units 1 & 2 Safety Balance Assessment for Elimination of RCS Main Loop Pipe Break Protective Activities Project stage: Other ML18144A0421985-11-30030 November 1985 VEPCO Surry Units 1 & 2 RCS Loads & Component Support Margins Evaluation of Elimination of RCS Main Loop Pipe Break Protective Devices Project stage: Other ML18144A0431985-11-30030 November 1985 VEPCO Surry Units 1 & 2 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices Project stage: Other ML18144A0401985-12-0303 December 1985 Forwards Repts in Support of 851105 Request for Exemption from GDC 4,eliminating Protection Against Dynamic Effects of Postulated Pipe Rupture on Primary Sys Components & Piping Project stage: Request ML18144A1531985-12-27027 December 1985 Notifies That Supplemental Info Re Partial Exemption Request for GDC 4 Discussed During 851219 Meeting Will Be Submitted by 860115.List of NRC Questions Encl Project stage: Supplement ML18149A0191986-01-14014 January 1986 Forwards Addl Info Re Request for Partial Exemption from GDC 4,per 851219 Meeting Project stage: Meeting ML18149A1441986-04-30030 April 1986 Application for Amends to Licenses DPR-32 & DPR-37,revising Tech Specs to Add License Condition Authorizing Rev to Reactor Coolant Pump & Steam Generator Support Design to Mitigate Pipe Rupture Events Project stage: Request ML18149A1461986-04-30030 April 1986 Proposed Tech Specs,Authorizing Rev to Reactor Coolant Pump & Steam Generator Support Design.Safety Evaluation Encl Project stage: Other ML18149A1431986-04-30030 April 1986 Forwards Discussion of Current Practices Re Use of 35% Enriched Oxygen w/open-circuit self-contained Breathing Apparatus to Meet Requirements of 10CFR20.103 in Response to 860327 Request.Fee Paid Project stage: Request ML18149A1641986-05-19019 May 1986 Summary of 851219 Meeting W/Util,Paul Munroe Energy Plants, Westinghouse & S&W in Bethesda,Md to Discuss Util 851105 & 1203 Submittals Re Exemptions from GDC 4.Presentation Handout Encl Project stage: Meeting ML20206J1021986-06-16016 June 1986 Safety Evaluation Supporting Amends 108 to Licenses DPR-32 & DPR-37 Project stage: Approval ML20206J0961986-06-16016 June 1986 Amends 108 to Licenses DPR-32 & DPR-37,permitting Plant Operation W/Reactor Coolant Pump & Steam Generator Supports Redesigned Per 860512 Amend to GDC-4,10CFR50,App a (51FR12502) Project stage: Other 1985-07-24
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-423 NORTHEAST NUCLEAR ENERGY COMPANY, ET. AL.*
NOTICE OF ISSUANCE OF AMENDMENT TO CONSTRUCTION PERMIT
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The U.S. Nuclear Regulatory Commission (the Comission) has issued Amend-ment flo.'12 to Construction Permit No. CPPR-113 for Millstone Nuclear Power Station, Unit 3.
The amendment modifies the construction permit to reflect issuance, by the Comission, of an Exemption dated June 5,1985. The amendment is effective as of the date of issuance.-
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations. The Comission has made appropriate findings as required by:the Act and the Comission's regulations in 10 CFR Chapter I, which is set forth in the amendment.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards
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consideration.
- The following are the holders of Construction Permit No. CPPR-113:
Central Maine Power Company, Central Vermont Public Service Corporation, Chicopee Municipal Lighting Plant, City of Burlington, Vermont, Connecticut Municipal Electric Energy Cooperative, The Connecticut Light and Power Company, Fitchburg Gas and Electric Light Company, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, Northeast Nuclear Energy Company, Public Service Company of New Hampshire, The United Illuminating Company, Vennont Electric Cooperative, Inc., The Village of Lyndonville Electric Department, Western Massachusetts Electric Company, and Vermont Electric Generation and Transmission Cooperative Inc.
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, For further details with respect to the action, see (1) the application for amendment dated March 1,1985,(2) Amendment No. 12 to Construction Permit CPPR-113, (3) the Commission's related Safety Evaluation, (4) the Exemption dated June 5,1985, and (5) the Notice of Environmental Assessment and Finding of No Significant Impact dated May 29, 1985. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D.C. 20555, and at the Local Public Document Room at the Waterford Public Library, Rope Ferry Road, Route 156, Waterford, Connecticut.
In addition a copy of items (2), (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, Office of Nuclear Reactor Regulation.
Dated at Bethesda, Maryland, this 24thday of July 1985.
FOR THE NUCLEAR REGULATORY COMMISSION
_ ORIGINAL SIGUED BY B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing L
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t, JUL 2 41985 ISSUANCE OF AMENDMENT 12 FOR MILLSTONE UNIT 3 DATEu DISTRIBUTION
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