TAC:06596
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Request for: Approved, Closed | |
Results Other: ML20138H876, ML20138H895, ML20148A525, ML20148A533, ML20155J779, ML20196L189, ML20210V194, ML20215N162, ML20215N167, ML20235Z787, ML20236A065, ML20236R788 | |
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MONTHYEARML20236A0651975-10-15015 October 1975
[table view]Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days ML20155J7791976-01-0505 January 1976 Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl ML20148F2811976-06-0707 June 1976 Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads ML20244A6211978-01-25025 January 1978 Forwards Background & Current Status of Review of Asymmetric LOCA Loads for PWR Facilities & Revised Request for Addl Info on Subj ML20151J0531984-06-0606 June 1984 Forwards Request for Addl Info Re Asymmetric LOCA Loads. Addl Info Needed in Order to Complete Safety Evaluation of plant-specific LOCA Analysis.Response Requested by 840731 ML20138H8951985-06-30030 June 1985 Rev 0 to Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept ML20138H8761985-10-25025 October 1985 Forwards Rev 0 to 01-0300-1395, Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept ML20210V1941986-09-25025 September 1986 Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation ML20235Z7871986-10-15015 October 1986 Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty ML20215N1671986-10-31031 October 1986 Rev 1 to, Leak-Before-Break Evaluation of Reactor Coolant Loop ML20215N1621986-10-31031 October 1986 Forwards Rev 1 to Impell Corp 01-0300-1395, Leak-Before- Break Evaluation of Reactor Coolant Loop, Final Rept. Analysis Revised to Comply w/NUREG-1061,Vol 3 ML20236J8741987-08-0404 August 1987 Forwards Request for Addl Info Re Util Proposed Application of Leak Before Break Methodology to Eliminate Dynamic Effect of Postulated Primary Loop Pipe Ruptures from Design Basis, Per GDC-4.Response Requested within 30 Days of Ltr Receipt ML0311505101987-08-0404 August 1987 Withdrawn NRC Generic Letter 1987-014: Operator Licensing Examinations ML20238B5121987-08-25025 August 1987 Responds to NRC 870804 Request for Addl Info Re Elimination of Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility.Addl Time Will Be Required to Evaluate & Adequately Address Each Item of Request ML20236R7881987-11-20020 November 1987 Advises That Addl Info Requested in NRC Will Not Be Provided on 871231,per .Util Has Changed Contractors for leak-before-break Analysis in Order to Obtain Clarifications.Submittal Will Be Made by 880130 ML20148A5331988-03-0303 March 1988 Requests That Proprietary WCAP-11699 Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl ML20148A5251988-03-14014 March 1988 Forwards Proprietary WCAP-11699 & Nonproprietary WCAP-11700, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Trojan Plant, leak-before-break Analysis Final Repts ML20196L1891988-06-29029 June 1988 Advises That Proprietary WCAP-11699 Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 880314 Request ML20151T4041988-08-0505 August 1988 Forwards Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis for Facility,Per Util 851025 & 861031 leak-before-break Evaluations & WCAP-11699 1986-10-31 | |
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