Letter Sequence Other |
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Results
Other: B10408, Informs of Status of Transient & Accident Analyses Review to Determine Steam Generator Operability W/Approx 1,500 Plugged Tubes.All non-LOCA & Small Break Analyses Remain Valid. Analysis of Large Break Scenario Will Be Docketed by 820212, B10420, Forwards Addl Info Supporting Amend to Ol,To Limit Steam Generator Inservice Insps During Cycle 5 Refueling Outage, B10425, Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes, B10581, Describes Activities Currently Planned for 1983 Refueling Outage to Assure Continued Operability of Steam Generators. Any Licensing Action Will Be Initiated in Time to Support Scheduled 830416 Outage, ML20040A554, ML20040A557, ML20040C965, ML20041C396, ML20042C036, ML20042C042, ML20049J152, ML20054F221
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MONTHYEARML20040A5541982-01-12012 January 1982 Steam Generator Eddy-Current Test Results,Jan 10,1982 Project stage: Other ML20040A5501982-01-12012 January 1982 Application to Amend License DPR-65,changing Tech Spec Table 4.4-6 to Delete Category C-3 Tubes from Steam Generator Tube Project stage: Request ML20040C9651982-01-22022 January 1982 Forwards Revised Figures 1-4 Which Define Affected Areas of Steam Generator Tube Bundle to Which Util Proposed to Limit Cycle 5 Refueling Outage Steam Generator eddy-current Exams. Revised Figures Part of Proposal to Limit Inservice Insp Project stage: Other ML20040A5571982-01-31031 January 1982 Proposed Revision to Tech Spec Table 4.4-6,deleting Category C-3 Tubes from Steam Generator Tube Insp Project stage: Other B10408, Informs of Status of Transient & Accident Analyses Review to Determine Steam Generator Operability W/Approx 1,500 Plugged Tubes.All non-LOCA & Small Break Analyses Remain Valid. Analysis of Large Break Scenario Will Be Docketed by 8202121982-02-0404 February 1982 Informs of Status of Transient & Accident Analyses Review to Determine Steam Generator Operability W/Approx 1,500 Plugged Tubes.All non-LOCA & Small Break Analyses Remain Valid. Analysis of Large Break Scenario Will Be Docketed by 820212 Project stage: Other B10384, Forwards Addl Info in Support of Util 820112 Application to Amend OL to Limit Steam Generator Tube Inservice Insps Conducted During Cycle 5 Refueling Outage.Revised Tube Maps of Defects Found During Eddy Current Exams Encl1982-02-0505 February 1982 Forwards Addl Info in Support of Util 820112 Application to Amend OL to Limit Steam Generator Tube Inservice Insps Conducted During Cycle 5 Refueling Outage.Revised Tube Maps of Defects Found During Eddy Current Exams Encl Project stage: Request ML20041B6101982-02-10010 February 1982 Notification of 820216 Meeting W/Util in Bethesda,Md to Discuss Encl Meeting Agenda Re Steam Generator Review Project stage: Meeting B10420, Forwards Addl Info Supporting Amend to Ol,To Limit Steam Generator Inservice Insps During Cycle 5 Refueling Outage1982-02-12012 February 1982 Forwards Addl Info Supporting Amend to Ol,To Limit Steam Generator Inservice Insps During Cycle 5 Refueling Outage Project stage: Other B10425, Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes1982-02-19019 February 1982 Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes Project stage: Other ML20041C3961982-02-28028 February 1982 Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes Project stage: Other B10448, Application for Amend to License DPR-65,providing Daily Sampling for Gross Activity in Each Steam Generator During Cycle 5 Operation to Assure Prompt Detection & Monitoring of Primary to Secondary Leakage1982-03-0404 March 1982 Application for Amend to License DPR-65,providing Daily Sampling for Gross Activity in Each Steam Generator During Cycle 5 Operation to Assure Prompt Detection & Monitoring of Primary to Secondary Leakage Project stage: Request ML20042C0361982-03-0505 March 1982 Amend 73 to License DPR-65,changing Tech Specs to Allow Reactor Heatup for Cycle 5 Operation W/Less than 100% Insp of Tubes in Each Steam Generator Project stage: Other ML20042C0421982-03-0505 March 1982 Notice of Issuance & Availability of Amend 73 to License DPR-65 Project stage: Other ML20042C0381982-03-0505 March 1982 Safety Evaluation Supporting Amend 73 to License DPR-65 Project stage: Approval ML20049J1521982-03-31031 March 1982 Proposed Tech Spec Page 3/4 7-8,providing Daily Sampling for Gross Activity in Each Steam Generator During Cycle 5 Operation to Assure Prompt Detection & Monitoring of Primary to Secondary Leakage Project stage: Other ML20054F2211982-06-0202 June 1982 Forwards Cycle 5 Refueling Outage Steam Generator Profilometry Insp Results,Per Util .Results Confirm Integrity of Steam Generator Tubes & Supports & Assure Continued Applicability of Design Basis Analyses Project stage: Other B10581, Describes Activities Currently Planned for 1983 Refueling Outage to Assure Continued Operability of Steam Generators. Any Licensing Action Will Be Initiated in Time to Support Scheduled 830416 Outage1982-11-19019 November 1982 Describes Activities Currently Planned for 1983 Refueling Outage to Assure Continued Operability of Steam Generators. Any Licensing Action Will Be Initiated in Time to Support Scheduled 830416 Outage Project stage: Other B10724, Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Inservice Insp1983-03-14014 March 1983 Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Inservice Insp Project stage: Request 1982-02-28
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7590-01 o
l UNITED STATES NUCLEAR REGULATORY COMMISSION l
I DOCKET NO. 50-336 I
NORTHFAST NUCLEAR ENERGY COMPANY, ET AL.
NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY
}
OPERATING LICENSE l
i 4
1 The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 73 to Facility Operating License No. OPR-65, issued to Northeast i
Nuclear Energy Company, the Connecticut Light and Power Company, the Hartford l
I Electric Light Company, and the Western Massachusetts Electric Company (the
]
licensee), which revised Technical Specifications for operation of the Millstone
~
Nuclear Power Station, Unit No. 2 (the facility) located in the Town of katerford, Connecticut. The amendment is effective as of the date of issuance.
The amendment changes the Technical Specifications to allow reactor heatup i
for Cycle 5 operation with less that 100 percent inspection of the tubes in each steam generator based on the results of the tube inspection program reported in tne application and additional reporting requirements on primary-to-secondary stcan generator leakage rates. The Cycle 5 reload enendment will be i ssued under separate cover.
The applications for the amendnent comply with the standards and require-j
'I nents of the Atonic Energy Act of 1954, as amended (the Act), and the Connis-sicn s rules anc reguiations. Tne Canaission nas made appropriate findings as required by the Act and the Commission'.s rules and regulations in 10 CFR
,j Chapter I, which are set forth in the license amendment. Prior public notice i
of this amendment was not required since tne amendnent does not involve a i
significant hazards consideration.
l l
8203300108 820305 I
PDR ADOCK 05000336 PDR p
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7590-01
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The Commission has determined that the issuan'ce o' this amendment f
j will not result in any significant environmental impact and that ij pursuant to 10 CFR $51.5(d)(4) an environmental impact s,tatement or negative declaration and environmental impact appraisal need not be i
prepared in connection with issuance of this amendment.
.I
'l i
For further detail' with respect to this action, see (1) the 1
l applications for amendment dated January 12 and March 4,1982 as modified 1
j-by letters dated January 22, February 2,12 and March 1, 1982, (2) Amendment
- I No. 7 3 to License No. OPR-65, and (3) the Commission's related Safety Evalua-
. '1 tion. All of these items are available for public inspection at the Commis-sion's Public Document Room,1717 H Street. N.W., Washington, D.C. and at the Uaterford Public Library, Rope Ferry Road, Waterford, Connecticut.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. ' uclear Regulatory Commission, "ashington, D.C.
20555, Attention:
Director, Division of Licensing.
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1 Dated at Bethesda, Maryland, this 5th day of March,1982.
I FOR THE '!UCLEAR REGULATORY COMMISSICt!
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.m Robert A. Clark, Chief
. l Operating Reactors Branch #3 3
Division of Licensing j
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