TAC:63133
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(Redirected from TAC:64674)
Request for: Approved, Closed | |
Questions Answers Results Other: 05000336/LER-1986-010-02, :on 861006,inconsistency Identified Between Safety Analysis for Control Element Assembly (CEA) & Tech Specs for Modes 3,4 & 5.Caused by Assumption That Hot Zero Power Results for CEA Withdrawn, B12238, Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend, B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor, B12440, Startup Test Rept Cycle 8, ML20207S981, ML20209E851, ML20209F721, ML20211M265, ML20215K241, ML20215N796, ML20215N827 | |
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MONTHYEARB12238, Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend1986-08-29029 August 1986
[table view]Forwards Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation,Large-Break LOCA Evaluation, Per Wg Counsil to DG Eisenhut & EP Rahe to Co Thomas. Analyses Will Be Ref in Proposed License Amend ML20209E8511986-08-31031 August 1986 Item II.K.3.31,NUREG-0737,Small-Break LOCA Evaluation, Large-Break LOCA Evaluation ML20215N8271986-09-30030 September 1986 Rev 2 to Reload Safety Evaluation,Millstone Nuclear Power Station,Unit 2 Cycle 8 B12224, Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid1986-10-20020 October 1986 Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid ML20215K2411986-10-20020 October 1986 Proposed Tech Specs Revising pressure-temp Limits & Max heat-up & cool-down Rates for RCS B12240, Application to Amend License DPR-65,revising Tech Specs to Reduce Frequency of Surveillance Requirement for Determining Reactor Coolant Flow Rate.Fee Paid1986-10-24024 October 1986 Application to Amend License DPR-65,revising Tech Specs to Reduce Frequency of Surveillance Requirement for Determining Reactor Coolant Flow Rate.Fee Paid ML20215N8131986-10-27027 October 1986 Application for Amend to License DPR-65,allowing Reduction in RCS Flow Rate & Reducing Total Integrated Radial Peaking Factor.Forwards Westinghouse Rev 2 to Reload Safety Evaluation Millstone...Unit 2 Cycle 8. Fee Paid B12310, Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor1986-10-27027 October 1986 Proposed Tech Specs Allowing Reduction in RCS Flow Rate from Current Value of 350,000 to 340,000 Gpm & Reducing Total Integrated Radial Peaking Factor ML20215N7961986-10-29029 October 1986 Notice of Consideration of Issuance of Amend to License DPR-65 & Proposed NSHC Determination & Opportunity for Hearing on 861020,24 & 27 Requests to Revise Tech Specs Re Temp Pressure Limits,Surveillance Frequency & RCS Flow 05000336/LER-1986-010-02, :on 861006,inconsistency Identified Between Safety Analysis for Control Element Assembly (CEA) & Tech Specs for Modes 3,4 & 5.Caused by Assumption That Hot Zero Power Results for CEA Withdrawn1986-11-0404 November 1986
A06096, Forwards Addl Justification for 861020 Application to Amend License DPR-65 to Facilitate NRC Review of Small & Large Break Locas.Amend Incorporates Changes Relative to Revised pressure-temp Limit Curves1986-12-0101 December 1986 Forwards Addl Justification for 861020 Application to Amend License DPR-65 to Facilitate NRC Review of Small & Large Break Locas.Amend Incorporates Changes Relative to Revised pressure-temp Limit Curves ML20211M2841986-12-0808 December 1986 Safety Evaluation Supporting Amend 113 to License DPR-65 ML20211M2651986-12-0808 December 1986 Amend 113 to DPR-65,changing Tech Specs to Provide for Revised Temp/Pressure Limits in Tech Spec 3/4.4.9, Pressure /Temp Limits & Tech Spec Figure 3.4-2, RCS Pressure Temp Limitations for 12 Full Power Yrs ML20207S9811987-03-16016 March 1987 Forwards Millstone Nuclear Power Station Unit 2 Startup Test Rept Cycle 8. Plant Achieved Criticality on 861214 & Reached 100% Power on 870101 B12473, Submits Addl Info in Support of 870206 Application for Amend to License DPR-65,revising Tech Specs Re Operability of CRD Mechanisms.High Power Reactor Trip Required Only Under Listed Conditions1987-03-20020 March 1987 Submits Addl Info in Support of 870206 Application for Amend to License DPR-65,revising Tech Specs Re Operability of CRD Mechanisms.High Power Reactor Trip Required Only Under Listed Conditions B12440, Startup Test Rept Cycle 81987-03-31031 March 1987 Startup Test Rept Cycle 8 ML20209F7271987-04-21021 April 1987 Safety Evaluation Supporting Amend 116 to License DPR-65 ML20209F7211987-04-21021 April 1987 Amend 116 to License DPR-65,creating Tech Spec 3/4.1.7, CRD Mechanisms & Changing Tech Spec 3/4.3.1 to Extend Operability & Surveillance Requirements for Reactor Protection Sys Power level-high Trip Function to Mode 3 1986-12-08 | |
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