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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L J ::Tr O%7ll January 16, 1981 Docket No. 50-336 A0ll8h Director of Nuclear Reactor Regulation Attn:
Mr. Robert A. Clark, Chief Operating Reactors Branch #3 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
(1)
W. G. Counsil letter to R. Reid, dated March 6, 1980.
(2)
R. A. Clark letter to W. G. Counsil, dated October 6,1980.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Basic Safety Report (BSR) - Cycle h Northeast Nuclear Energy Company (NNECO) docketed the Basic Safety Report (BSR) in support of the Cycle 4 reload of Millstone Unit No. 2, in Reference (1).
Cycle 4 is the first instance in which Westinghouse has supplied the fuel and safety analyses for a non-Westinghouse nuclear steam supply system (NSSS).
NNECO also informed the NRC Staff, in Reference (1), that the BSR is intended to serve as the reference fuel assembly and safety analysis report for the use of Westinghouse fuel at Millstone Unit No. 2.
In Reference (2), the Staff issued the Safety Evaluation Report (SER) authorizing Cycle 4 operation of Millstone Unit No. 2 with a mixed core of Westinghouse and Combustion Engineering fuel. Contrary to NNECO's request and expectations, it was noted that the Staff has neither fully reviewed the BSR nor accepted it as a referenceable document.
This situation is not fully compatible with future plans for subsequent reloads to be conducted under the provisions of 10CFR50.59 The BSR is a necessary and integral document for successfully implementing these plans, as it serves as the reference fuel and safety analysis report for the use of Westinghouse fuel at Millstone Unit No. 2.
Conducting reloads under the provisions of 10CFR50.59, where appropriate, has been a stated objective of the Commission i
in the past; this further reinforces the need for timely Staff review of Ref-erence (1), which was docketed over ten months ago, to facilitate this process.
In support of these efforts, NNECO respectfully requests that the Staff continue 81012009'13
,' V the review of the BSR such that the potential for a 50 59 reload for Cycle 5 at Millstone. Unit No. 2 can be realized. The present schedule for Cycle 5 startup of Millstone Unit No. 2 is mid-January,1982.
We. trust the appropriate actions will be initiated to support operation of Millstone Unit No. 2 in future fuel cycles, and remain available to respond to any questions you may have.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY i
1711 A%W W. G. Counsil Senior Vice President i
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