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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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NRC PDR MMcCoy L PDR NSIC Docket No. 50-336 3 Rdg DEisenhut OELD Nr. W. G. Counsil, Vice President hS10 Nuclear Engineering & Operations JHeltemes Northeast Nuclear Energy Company PMKreutzer-3 P. O. Box 270 RAClark Hartford, Connecticut 06101 MConner ho$e
Dear Mr. Counsil:
We have completed our physics review of the Basic Safety Report (BSR) submitted by your letter dated flarch 6, 1980. This BSR is intended to serve as a feference fuel assembly and safety analysis report for use of Westinghouse fuel assemblies in Millstone Nuclear Power Station, Unit No. 2.
Based on our review, we conclude that the physics portion of the BSR is acceptable for reference in licensing actions for Millstone Unit No. 2.
We expect to complete our review of the remaining sections of the BSR by September 1, 1981. We understand this is an acceptable schedule from your viewpoint.
A copy of our physics section safety evaluation if enclosed.
Sincerely, Original signed by Rober A. Clark Robert f.. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
As stated
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Docket No. 50-336 Mr. W. G. Counsil, Vice President Nuclear Engineering & Operations Northeast Huclear Energy Company P. O. Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
We have completed our physics review of the Basic Safety Report (BSR) submitted by your letter dated March 6, 1980. This BSR is intended to serve as a reference fuel assembly and safety analysis report for use of Westinghouse fuel assemblies in Millstone Nuclear Power Station, Unit No. 2.
Based on our review, we conclude that the physics portion of the BSR is acceptable for reference in licensing actions for Millstone, Unit No. 2.
We expect to complete our review of the remaining sections of the BSR by September 1, 1981. We understand this is an acceptable schedule from your viewpoint.
A copy of our physics.section safety evaluation if enclosed.
Sincerely,
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Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
As stated cc: See next page
"crtheast Nuclear Er.er; Copany Hilliam H. Cuddy, Esquira Mr. John Shediesr.y
- D:y, Berry & Howard Resident Inspectne/ Millstone
. Counselors at Law c/o U.S.fi.R.C.
One Constitution Pla:a P. O. Drawer KY.
Hartford, Connecticut 05103 Niantic, CT CS3S7 Anthony Z. Roisman Mr. Charles Brinkman Natural Resources Defense Council Manager - Washington Nuclear 91715th Street, N.W.
Operations Washington, D. C.
20005 C-E Power Systems Combustion Engineering, Inc.
Mr. Lawrence Bettencourt, First Selectman 4853 Cordell Aven., Suite A-1 Town of Waterford B ethes da,' MD 20014 Hall of Records - 200 Boston Post Road Haterford, Connecticut -06385 Northeast Nuclear Energy Corpany ATTN:
Superintendent Millstone Plant Connecticut Energy Agency Post Office Box 128 ATTN: Assistant Director, Pesearch Waterford, Connecticut 06385 a.nd Polir J evelopmem Department of P'.r.r.ing and Energy Waterford Public Library Policy Rope Ferry Road, Route 156 20 Grand Street Waterford, Connecticut 06385 Hartford, CT 06106 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U.S. Environmental Protection Agency Washington, D. C.
20460 U. S. Environmental Protection Agnecy l
Region I Office ATTN: EIS COORDINATOR l
John F. Kennedy Federal Building Boston, Massachusetts 02203 l
l Northeast Utilities Service Carpany ATTN: Mr. James R. Himmelwright Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101-l l
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