TAC:45859: Difference between revisions
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StriderTol (talk | contribs) Bureaucrats, checkuser, developer, flow-bot, Interface administrators, observers, oversight, Administrators (Semantic MediaWiki), Curators (Semantic MediaWiki), Editors (Semantic MediaWiki), Suppressors, Administrators 19,637 edits StriderTol Bot change |
StriderTol (talk | contribs) Bureaucrats, checkuser, developer, flow-bot, Interface administrators, observers, oversight, Administrators (Semantic MediaWiki), Curators (Semantic MediaWiki), Editors (Semantic MediaWiki), Suppressors, Administrators 19,637 edits StriderTol Bot change |
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Latest revision as of 04:27, 25 May 2025
Request for: Open | |
Questions Answers Results
Other: ML15238B280, ML17083B090, ML20003G150, ML20008F882, ML20028B293, ML20032E888, ML20062J658, ML20133E265 | |
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MONTHYEARML19345A9371980-11-18018 November 1980
[table view]Requests Meeting W/Nrc on 801210 to Discuss Methods Used for Small Break LOCA Analyses.Detailed Scope & Implementation Schedule Deferred Pending Discussion.Existing Model Meets Code Requirements ML15238B2801981-02-24024 February 1981 Generic Ltr to All B&W Licensees Re Capability of Small Break LOCA Model to Predict Small Break behavior.Post-test Evaluations of L-4-1 & S-07-10D Predictions Requested for Submittal by 810401 ML20037C9881981-03-26026 March 1981 Responds to NUREG-0737 Request for Info Re Detailed Scope & Schedule for Small Break LOCA Analysis.Steam Generator Models Will Be Provided in CRAFT2 Code to Account for Heat Transfer Due to Flow Regimes ML20003G1501981-04-20020 April 1981 Submits Further post-test Analyses of S-07-10D & L3-1 Tests Re Small Break LOCA Model,Per 810224 Request.Evaluating Program to Provide Qualitative Opinion of Impact of Identified Test Uncertainties & Model Conservatisms ML20032E8881981-04-27027 April 1981 Abnormal Transient Operating Procedures for Nuclear Power Plants, Presented to American Power Conference on 810427-29 in Chicago,Il ML20008F8821981-05-0505 May 1981 Addl Response to NRC Re Further post-test Analysis of S-07-10D & L3-1 Tests.Util Will Participate in B&W Owners Group Program & Will Respond to NRC Request by 810601 ML16245A6631981-11-10010 November 1981 Summary of 811023 Meeting W/Utils & B&W in Bethesda,Md Re Experimental Verification of Accident Models.Attendance List & Viewgraphs Encl ML20038D1381981-11-16016 November 1981 Discusses Major Conclusions & Agreements Reached in 811023 Meeting on Verification Testing for SB LOCA Methods.Forwards B&W Technical Paper, Abnormal Transient Operating Procedures for Nuclear Power Plants ML20062J6581982-02-28028 February 1982 Gerda General Test Specs ML20052A0611982-03-25025 March 1982 Summarizes NRC Views Resulting from 811217 Meeting W/B&W Owners Group Re Small Break LOCA Analysis Model & Provides Addl Info for Planning Verification Program. Model Verification Endorsed ML20062J6331982-08-12012 August 1982 Formalizes Proposals Made at 820720 Meeting Re Scope of Program for Resolution of NUREG-0737,Item II.K.3.30, Revised Small Break LOCA Methods to Show Compliance w/10CFR50,App K. Followup Ltr Expected within 3 Wks ML17083B0901982-10-13013 October 1982 Comments on NRC Program to Address Concerns W/Thermal Hydraulic Behavior of B&W Plants During Transients & Accidents.Gerda & SRI-II Facilities as Now Proposed Will Be Inadequate to Address NRC Concerns ML20028B2931982-11-24024 November 1982 Refs Documents Cited in B&W Addressing Requirements of NUREG-0737,TMI Action Plan Item II.K.3.30. Info Adequately Addresses Requirements ML20133E2651985-07-0303 July 1985 Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 Re Small Break LOCA Evaluation Model CRAFT2 (Rev 3).CRAFT2 in Compliance W/Evaluation Criteria of 10CFR50,App K ML20134Q1711985-09-0303 September 1985 Responds to 850722 Request for Confirmatory Response to Issues Re NUREG-0737,Item II.K.3.30 on Small Break LOCA Methods & Use of CRAFT2 Code 1981-05-05 | |
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