TAC:06596
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(Redirected from TAC:08594)
Request for: Approved, Closed | |
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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 ML19326B2771978-03-0909 March 1978 Responds to NRC .Plans Re Asymmetric LOCA Loads Safety Question Underway Since Oct 1975.Requests .Nrc Meeting W/B&W Owners Group in mid-March & Clarification of Requirements in NRC ML19319D3951978-04-10010 April 1978 B&W 177FA Owners Group Asymmetric LOCA Loads Evaluations Programs ML19319D3911978-05-0404 May 1978 Responds to NRC 780125 Request for Schedule for Evaluation of Asymmetric LOCA Loads.Forwards Rept, B&W 177FA Owners Group Asymmetric LOCA Loads Evaluation Program. Util Plans to Use Generic Analyses Where Applicable ML19273A9921978-10-10010 October 1978 B&W 177 Fuel Assembly Owners Group Asymmetric LOCA Loads Evaluation Program,Phase 2. Evaluated Components Include Reactor Pressure Vessel,Fuel Assemblies,Control Rod Drives & Core Flooding Piping ML19273A9831979-01-26026 January 1979 Submits Plan for Proceeding with Phase 2 Re Asymmetric LOCA Loads Program.Forwards Rept B&W 177 Fuel Assembly Owners Group Asymmetric LOCA Loads Evaluation Program,Phase 2 Identified Content & Schedule ML19207A3941979-08-13013 August 1979 Informs of Multiphase Program to Evaluate Effects of Asymmetric LOCA Loads.Program to Be Completed Jul 1980 ML19296B2821980-02-15015 February 1980 Notifies Interim Rept BAW-1597, Effects of Asymmetric LOCA Loadings Responds to NRC 780125 Request.Rept Provides Justification for Continued Operation of Facility.Final Rept Will Be Forwarded by 800701 ML19320A8941980-07-0303 July 1980 Responds to NRC Requesting All PWR Licensees to Evaluate LOCA loads.BAW-1597 & BAW-1621 Submitted 800214 & 0701,respectively,demonstrate Ability of Facility to Maintain Core Coolability in Event of Asymmetric LOCA ML19320A8651980-07-0303 July 1980 Notifies That Evaluation of BAW-1621,re Overall Asymmetric LOCA Loads,Will Be Submitted by 800805 ML19330C2781980-08-0505 August 1980 Advises of Review of BAW-1621, Effects of Asymmetric LOCA Loading - Phase II Analysis. Reactor Head Cable Access Platform Will Be Modified During Refueling Outage to Provide Horizontal Clearance at Svc Support Structure ML15223A7081981-01-0909 January 1981 Forwards Request for Addl Info Re B&W 177-FA Owners Group Submittal on Asymmetric LOCA Loadings.Owners Group Should Convene Another Meeting W/Nrc After Review & Before Submittal.Info Due in 60 Days ML19347D1351981-02-26026 February 1981 Forwards 810109 Request for Addl Info Re B&W 177-FA Owners Groups Submittal on Asymmetric LOCA Loading.Response Should Be Submitted within 60 Days ML19347D3511981-03-11011 March 1981 Notifies That Util Will Provide Formal Response to NRC 810109 Request for Addl Info Re B&W 177-FA Owners Group Generic Submittal on Asymmetric LOCA Loadings by Jul 1981 ML20003E1581981-03-26026 March 1981 Responds to 810109 Request for Addl Info Re B&W 177-FA Owners Group.Requests Technical Review Meeting on 810402-03 in Bethesda,Md to Resolve Remaining Questions ML16138A4971981-04-0909 April 1981 Summary of 810402-03 Meeting W/B&W Owners Group & Vendors in Bethesda,Md Re Proposed Responses to NRC 810109 Info Request Re Asymmetric LOCA Loadings ML20031B3051981-09-24024 September 1981 Advises That Responses Submitted in Util Satisfy Questions Raised from Review of BAW-1621 Rept, Effects of Asymmetric LOCA Loadings-Phase II Analysis 2CAN018406, Comments on 830921 Draft Safeguards Agreement Under Npt Between USA & IAEA Subsidiary Arrangements, Intended to Be Implemented Through Facility License Amend.Markup Copy of Agreement Encl1984-01-23023 January 1984 Comments on 830921 Draft Safeguards Agreement Under Npt Between USA & IAEA Subsidiary Arrangements, Intended to Be Implemented Through Facility License Amend.Markup Copy of Agreement Encl 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 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 ML20215N1671986-10-31031 October 1986 Rev 1 to, Leak-Before-Break Evaluation of Reactor Coolant Loop 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 1981-03-26 | |
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