TAC:54199
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Other: 05000336/LER-1983-007, Updated LER 83-007/01T-1:on 830318,nonconservative Safety Analysis Assumption Discovered in Steam Generator Tube Rupture Analysis.Radiological Consequences of Reanalysis Being Analyzed, A03722, Forwards Addl Info Re Effects of Loss of Offsite Power on Steam Generator Tube Rupture & Main Steam Line Break Analyses, B10960, Discusses Steam Generator Tube Rupture Reassessment for Cycle 6 Operation.Radiological Doses Will Be Increased as Result of Lower Reseat Pressure.Releases Expected to Be Significantly Below 10CFR100 Criteria, B11003, Informs That Util QA-verified 831212 Reanalysis of Steam Generator Tube Rupture Event.Reported Results Remain Valid. Verification Completed Prior to Startup for Cycle 6, B11098, Provides Summary of Radiological Results Re Steam Generator Tube Rupture Reanalysis.Table Containing Doses for All Analyzed Cases Encl, ML20087K388, ML20116E663 | |
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MONTHYEAR05000336/LER-1983-007, Updated LER 83-007/01T-1:on 830318,nonconservative Safety Analysis Assumption Discovered in Steam Generator Tube Rupture Analysis.Radiological Consequences of Reanalysis Being Analyzed1983-12-0909 December 1983
[table view]Updated LER 83-007/01T-1:on 830318,nonconservative Safety Analysis Assumption Discovered in Steam Generator Tube Rupture Analysis.Radiological Consequences of Reanalysis Being Analyzed B10960, Discusses Steam Generator Tube Rupture Reassessment for Cycle 6 Operation.Radiological Doses Will Be Increased as Result of Lower Reseat Pressure.Releases Expected to Be Significantly Below 10CFR100 Criteria1983-12-12012 December 1983 Discusses Steam Generator Tube Rupture Reassessment for Cycle 6 Operation.Radiological Doses Will Be Increased as Result of Lower Reseat Pressure.Releases Expected to Be Significantly Below 10CFR100 Criteria B11003, Informs That Util QA-verified 831212 Reanalysis of Steam Generator Tube Rupture Event.Reported Results Remain Valid. Verification Completed Prior to Startup for Cycle 61984-01-17017 January 1984 Informs That Util QA-verified 831212 Reanalysis of Steam Generator Tube Rupture Event.Reported Results Remain Valid. Verification Completed Prior to Startup for Cycle 6 A03635, Forwards Info & Comments in Response to 831114 Request for Various Confirmatory Evaluations & Justification for Analytical Models Utilized in Cycle 6 Safety Analyses1984-02-0101 February 1984 Forwards Info & Comments in Response to 831114 Request for Various Confirmatory Evaluations & Justification for Analytical Models Utilized in Cycle 6 Safety Analyses ML20087K3881984-03-13013 March 1984 Submits Details of Followup Actions on Amend 90 to License DPR-65.Adequate Justification Provided to Demonstrate Applicability of Current Large Break LOCA Evaluation for Operation W/O Thermal Shield B11098, Provides Summary of Radiological Results Re Steam Generator Tube Rupture Reanalysis.Table Containing Doses for All Analyzed Cases Encl1984-04-13013 April 1984 Provides Summary of Radiological Results Re Steam Generator Tube Rupture Reanalysis.Table Containing Doses for All Analyzed Cases Encl ML20098B7771984-09-14014 September 1984 Forwards Info to Resolve Concerns Identified During Feb 1984 Meeting Re Large Break Loss of Coolant,Steam Line Break & Steam Generator Tube Rupture Accident Evaluations Submitted to Support Cycle 6 Operation,Per Amend 90 to License DPR-65 ML20112B5431985-01-0909 January 1985 Responds to NRC 831230 Request for Addl Info.Assumption of Complete Mixing Not Concern from DNB Standpoint for Facility Since No Boiling Occurred in Hot Channel for Steam Line Breaks W/Different Mixing Factors ML20116E6631985-04-22022 April 1985 Discusses Followup Actions to SER for Amend 90 to License DPR-65.New Steam Line Break Generator Tube Rupture Analysis Will Be Submitted for Review 4 Months After Startup from Current Refueling Outage A03722, Forwards Addl Info Re Effects of Loss of Offsite Power on Steam Generator Tube Rupture & Main Steam Line Break Analyses1985-11-0808 November 1985 Forwards Addl Info Re Effects of Loss of Offsite Power on Steam Generator Tube Rupture & Main Steam Line Break Analyses ML20212M5601987-01-21021 January 1987 Advises That 840914,850102 & 1108 Supplemental Cycle 6 Analyses Sufficient for Satisfying NRC Request for Confirmatory Calculations.Acceptance of Retran Model Should Not Be Construed as Acceptance for Future Licensing 1984-04-13 | |
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