Letter Sequence Other |
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Results
Other: A01155, Forwards Nonproprietary & Proprietary Versions of Test Rept, Hydraulic Flow Test of Model C Prototype Fuel Assembly. Application & Affidavit for Withholding Encl.Proprietary Rept Withheld (Ref 10CFR2.790), A01183, Submits Info Re Justification of Measurement Uncertainty Values for Axial Shape Index,Pressure,Temp,Flow & Power,In Response to NRC 801006 Request, A01184, Submits Resolution of Cycle 4 Startup Commitments,Re Effect of Predicted Bundle Deformation on Heat Transfer from Fuel Rods During Reflooding Stage of LOCA, A01848, Advises That Licensee Will Not Propose License Amend to Tech Specs,Section 5 to Include Guide Tube Sleeving Requirements for Fuel Assemblies Located Under Control Element Assemblies.Current Fixes Adequate, B10342, Part 21 Rept Re Resistance Temp Detectors (RTD) & Associated Signal Processing Equipment Scheduled for Installation During Refueling Outage in Early 1983.Steps Taken to Ensure Reliable RTD Operation in Interim Listed, 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, B10425, Forwards Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes, B10427, Advises That Evaluations of Clad Collapse & Fission Gas Pressure Have Been Performed for C-E Fuel to Be Utilized During Cycle 5, B10433, Submits Addl Info Supporting 820204 Cycle 5 non-LOCA Transient Analyses Results for Addl Plugged Steam Generator Tubes,Per Request.Increasing Number of Tubes Do Not Require Tech Spec Mods, ML19350A511, ML20031C479, ML20040A520, ML20041C396, ML20042C153, ML20042C157
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MONTHYEARA01183, Submits Info Re Justification of Measurement Uncertainty Values for Axial Shape Index,Pressure,Temp,Flow & Power,In Response to NRC 801006 Request1981-01-0808 January 1981 Submits Info Re Justification of Measurement Uncertainty Values for Axial Shape Index,Pressure,Temp,Flow & Power,In Response to NRC 801006 Request Project stage: Other A01155, Forwards Nonproprietary & Proprietary Versions of Test Rept, Hydraulic Flow Test of Model C Prototype Fuel Assembly. Application & Affidavit for Withholding Encl.Proprietary Rept Withheld (Ref 10CFR2.790)1981-03-0606 March 1981 Forwards Nonproprietary & Proprietary Versions of Test Rept, Hydraulic Flow Test of Model C Prototype Fuel Assembly. Application & Affidavit for Withholding Encl.Proprietary Rept Withheld (Ref 10CFR2.790) Project stage: Other ML19350A5111981-03-31031 March 1981 Nonproprietary Version of Hydraulic Flow Test of Model C Prototype Fuel Assembly Project stage: Other A01184, Submits Resolution of Cycle 4 Startup Commitments,Re Effect of Predicted Bundle Deformation on Heat Transfer from Fuel Rods During Reflooding Stage of LOCA1981-06-0808 June 1981 Submits Resolution of Cycle 4 Startup Commitments,Re Effect of Predicted Bundle Deformation on Heat Transfer from Fuel Rods During Reflooding Stage of LOCA Project stage: Other ML20005A9541981-06-22022 June 1981 Submits Physics Review of 800306 Basic Safety Rept.Rept Intended to Serve as Ref Fuel Assembly & Safety Analysis Rept.Rept Acceptable for Ref in Licensing Actions.Review Will Be Completed by 810901 Project stage: Approval A01848, Advises That Licensee Will Not Propose License Amend to Tech Specs,Section 5 to Include Guide Tube Sleeving Requirements for Fuel Assemblies Located Under Control Element Assemblies.Current Fixes Adequate1981-09-11011 September 1981 Advises That Licensee Will Not Propose License Amend to Tech Specs,Section 5 to Include Guide Tube Sleeving Requirements for Fuel Assemblies Located Under Control Element Assemblies.Current Fixes Adequate Project stage: Other ML20031C4791981-09-28028 September 1981 Provides Info Re Guide Tube Wear Experienced in Sleeved C-E, Sleeved Westinghouse,Low Flow C-E & Inset Westinghouse Fuels,Per 801006 Commitment,In Support of Continued Operation W/Modified Guide Tubes in Cycle 5 Project stage: Other ML20031G3521981-10-15015 October 1981 Forwards Supplementary Steam Generator Insp Program - Cycle 5 Reload,Per Amend 61 to License DPR-65 Project stage: Supplement ML20031G3561981-10-31031 October 1981 Supplementary Steam Generator Insp Program - Cycle 5 Reload Project stage: Supplement B10348, Application to Amend Tech Specs for License DPR-56,revising Section 3/4.9.8 Re Shutdown Cooling & Coolant Circulation During Refueling Operations to Increase Flexibility During Leak Testing1981-12-0202 December 1981 Application to Amend Tech Specs for License DPR-56,revising Section 3/4.9.8 Re Shutdown Cooling & Coolant Circulation During Refueling Operations to Increase Flexibility During Leak Testing Project stage: Request B10342, Part 21 Rept Re Resistance Temp Detectors (RTD) & Associated Signal Processing Equipment Scheduled for Installation During Refueling Outage in Early 1983.Steps Taken to Ensure Reliable RTD Operation in Interim Listed1981-12-0808 December 1981 Part 21 Rept Re Resistance Temp Detectors (RTD) & Associated Signal Processing Equipment Scheduled for Installation During Refueling Outage in Early 1983.Steps Taken to Ensure Reliable RTD Operation in Interim Listed Project stage: Other ML20040A3471981-12-24024 December 1981 Forwards Request for Addl Info Necessary to Complete Review of Reload Safety Analysis for Cycle 5 Operation.Info Should Be Submitted by 820111 Project stage: RAI ML20040E2041982-01-12012 January 1982 Forwards Safety Evaluation of Westinghouse Basic Safety Rept.Transient Analysis for Startup of Inactive Reactor Coolant Pump,Excess Load & Loss of Normal Feedwater Acceptable Project stage: Approval B10382, Application to Amend License DPR-65,revising Tech Spec Section 3/4.1.1 Re Shutdown Margin Required in Modes 1-41982-01-14014 January 1982 Application to Amend License DPR-65,revising Tech Spec Section 3/4.1.1 Re Shutdown Margin Required in Modes 1-4 Project stage: Request ML20040A5201982-01-30030 January 1982 Proposed Revision to Tech Spec Section 3/4.1.1,changing Limiting Condition for Operation,Surveillance Requirements & Bases for Shutdown Margin Required in Modes 1-4 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 ML20041E1141982-02-18018 February 1982 Forwards Safety Evaluation Re Reactor Fuels & Thermal Hydraulic Sections of Basic Safety Rept (Bsr).Reactor Fuel Design & Thermohydraulic Characteristics Including Transient & Accident Analyses Addressed in Bsr Acceptable Project stage: Approval A02239, Forwards Requested Addl Info Re Response to TMI Action Item I.A.1.1., Shift Technical Advisor.Info Consists of Name,Nuclear Experience,College Courses Completed & Training for Each Nondegreed Shift Technical Advisor1982-02-19019 February 1982 Forwards Requested Addl Info Re Response to TMI Action Item I.A.1.1., Shift Technical Advisor.Info Consists of Name,Nuclear Experience,College Courses Completed & Training for Each Nondegreed Shift Technical Advisor Project stage: Request 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 B10433, Submits Addl Info Supporting 820204 Cycle 5 non-LOCA Transient Analyses Results for Addl Plugged Steam Generator Tubes,Per Request.Increasing Number of Tubes Do Not Require Tech Spec Mods1982-02-23023 February 1982 Submits Addl Info Supporting 820204 Cycle 5 non-LOCA Transient Analyses Results for Addl Plugged Steam Generator Tubes,Per Request.Increasing Number of Tubes Do Not Require Tech Spec Mods Project stage: Other B10427, Advises That Evaluations of Clad Collapse & Fission Gas Pressure Have Been Performed for C-E Fuel to Be Utilized During Cycle 51982-02-23023 February 1982 Advises That Evaluations of Clad Collapse & Fission Gas Pressure Have Been Performed for C-E Fuel to Be Utilized During Cycle 5 Project stage: Other ML20041C3961982-02-28028 February 1982 Large Break Loca/Eccs Performance Results W/Addl Plugged Steam Generator Tubes Project stage: Other ML20042C1561982-03-0505 March 1982 Safety Evaluation Supporting Amend 74 to License DPR-65 Project stage: Approval ML20042C1571982-03-0505 March 1982 Notice of Issuance & Availability of Amend 74 to License DPR-65 Project stage: Other ML20042C1531982-03-0505 March 1982 Amend 74 to License DPR-65,authorizing Cycle 5 Operation & Amending App a Tech Specs Project stage: Other 1981-09-11
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION I
DOCKET NO. 50-336 NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.7 4 to Facility Operating License No. DPR-65, issued to Northeant Nuclear Energy Company, the Connecticut Light and Power Company, the Hartford Electric Light Company, and the Western Massachusetts Electric Company (the licensee), which revised Technical Specifications for operation of'the Millstone
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Nuclear Power Station, Unit No. 2 (the facil'ity) iClated'in the Town of Waterford,
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Connecticut. The amendment is effective as of the date of issuance.
The amendment changes the Technical Specifications to authori.:e Cycle 5 operation at 2700 MWt with a mixed core with two-thirds Westinghouse fuel and one-third Combustion Engineering fuel and modified (sleev.ed, raduced flow and insert) guide tubes for the control elemcat assemblies. The amendment also
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incorporates changes resulting 'from the analysis of the Cycle 5 reload with
Westinghouse fuel, removes the. requirements for mid-cycle moderator tempera-ture coefficient determination, redefines the fully withdrawn position of the regulating ;ontrol rods, and modifies the pressurizer level operational band.
The applications for the amendment comply with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commis-sion'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 siet forth in the license amendment.
Prior public notice of.this amendment was not required since the amendment does not involve a significant hazards consideration.
8203300279 820305 PDR ADCKK OTH)DO336
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_q 7590-01 2-1 The Commission has determined that the issuance of this amendment will not result in 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 amendment.
For further details with respect to this action, see (1) the applications 1
for amendment dated December 17, 1981 and January 14, 1982, as supplemented, (2) Amendment No. 7 4 to License No. DPR-65, and (5) the Commission's related Safety Evaluation. All of these items are a'vaila'lE fo'r public inspection b
at the Commission's Public Document Room, 1717 H Street, N.W.," Washington, D.C. and at the Waterford Public Library, Rope Ferry Road, Waterford, Connecticut.
A copy of it' ems'(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 5th day of March,1982.
FOR THE NUCLEAR REGULATORY COMMISSION
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} Robert' AY'Clafk, Chief.
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Operating Reactors Branch #3 Division of Licensing O
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