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MONTHYEARML19345A9371980-11-18018 November 1980
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
Project stage: Meeting
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
Project stage: Other
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
Project stage: Request
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
Project stage: Other
ML20032E8881981-04-27027 April 1981
Abnormal Transient Operating Procedures for Nuclear Power Plants, Presented to American Power Conference on 810427-29 in Chicago,Il
Project stage: Other
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
Project stage: Other
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
Project stage: Meeting
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
Project stage: Meeting
ML20062J6581982-02-28028 February 1982
Gerda General Test Specs
Project stage: Other
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
Project stage: Meeting
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
Project stage: Meeting
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
Project stage: Other
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
Project stage: Other
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
Project stage: Other
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
Project stage: Request
1981-05-05
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esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 s street. Box 15330, sacramento. Califomia 95813; (916) 452-3211 November 18, 1980 C.;
Director of Nuclear Reactor Regulation Attention: Darrell G. Eisenhut, Directot Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1 TMI Action Plan Item II.K.3.30
Dear Mr. Eisenhut:
The District has reviewed your letter of October 31, 1980, which provided us a copy of I!UREG-0737, " Clarification of TMI Action Plan Requirements". We have reviewed the applicable fUREG's as requested in Item II.K.3.30 of this document. We believe the existing Small Break LOCA model as approved by the NRC staff fully meets the requirements of 10 CFR 50, Appendix K.
We do plan, however, to review several aspects of the methods used for Small Break LOCA analyses for possible improvement. We have deferred development of a detailed scope and schedule for this effort until we have the opportunity to discuss this action with your staff. We, therefore, propose that a meeting be held with the staff on December 10, 1980.
Please contact us through normal channels to make the final arrange-ments.
Sincerely,
$bArKaQtts W. S. Bossenmaier Acting General Manager 1
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