ML20204B638
From kanterella
| ML20204B638 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 08/31/1978 |
| From: | Clare G, Mclane F ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| To: | |
| Shared Package | |
| ML20204B444 | List: |
| References | |
| WARD-D-0165, WARD-D-0165-R01, WARD-D-165, WARD-D-165-R1, NUDOCS 7810170259 | |
| Download: ML20204B638 (69) | |
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|---|---|
Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20028A6141982-09-30030 September 1982
[Table view]Supplementary Manual for F0RE-2M Computer Program. ML20053D2241982-05-28028 May 1982 Safeguards Sys Effectiveness Modeling ML20053D2371982-05-28028 May 1982 SPTH3:Subroutine for Finding Shortest Sabotage Paths. ML20049H8771982-02-28028 February 1982 Summary Rept on Current Assessment of Natural Circulation Capability W/Heterogeneous Core ML20050J0521982-02-0909 February 1982 To Crbr Requirements for Environ Qualification of Class IE Equipment ML20039G8531981-12-31031 December 1981 Assessment of Hypothetical Core Disruptive Accident Energetics in Clinch River Breeder Reactor Project Heterogeneous Reactor Core ML20033A6381981-04-20020 April 1981 To Clinch River Breeder Reactor Plant Requirements for Environ Qualification of Class IE Equipment ML19345B7961980-11-30030 November 1980 Clinch River Breeder Reactor Project Ncvp Pretest Prediction of Fueled Open Test Assembly Temps for Fftf Natural Circulation Test Initiated at 35% Power & 75% Flow. Input Data & Microfiche of Demo Code Program Mods Encl ML19309F3721980-01-31031 January 1980 Final Rept on Base Matls Tests for Cell Liner Steels. ML19211A7491979-12-14014 December 1979 Facility Core Assembly Hot Channel Factors Preliminary Analysis, Revision 3 ML19305D7481979-10-31031 October 1979 Structural Response of Scale Models to Simulated Hypothetical Core Disruptive Accident. Revision 1 ML19305A7801979-01-31031 January 1979 Predicted Steady State Thermal-Hydraulic Performance of Fuel & Blanket Assemblies in Plant Heterogeneous Core, Revision 1 ML20147D9661978-11-30030 November 1978 Closure Head Capability for Structural Margin Beyond Design Base Loading. Results of Tests Indicate That Closure Head Is Capable of W/Standing 661 Mj Structural Margin Beyond Design Base Loads W/Out Structural Failures ML20147D9601978-10-31031 October 1978 Structural Response of Crbrp Scale Models to a Simulated Hypothetical Core Disruptive Accident. Primary Objective of Tests Was to Verify That Scale Models of Subj Reactor Can W/Stand Loads Resulting from Simulation of Hcda ML20204B6381978-08-31031 August 1978 Requirements for Environ Qualification of Class IE Equipment ML19270F6091978-04-30030 April 1978 Analysis of Hypothetical Core Distruptive Events in Clinch River Breeder Reactor Plant ML19331D3271978-01-31031 January 1978 Clinch River Breeder Reactor Plant Fuel Assembly Structural Analysis in Support of Final Design Review ML20063P2821977-12-31031 December 1977 Preliminary Analysis of Heat Generating Blockage in Crbr Fuel & Radial Blanket Assemblies to Determine Detection Requirements ML19281A0671977-02-28028 February 1977 WARD-D-0169, Clinch River Breeder Reactor Plant,Response of Plant to Postulated Loss of One Heat Transport Loop W/ Failure of Both Reactor Shutdown Sys. Addresses Anticipated Event Causing Most Severe Loss of Heat Removal 1982-09-30 Category:TEXT-SAFETY REPORT MONTHYEARML20080S6761984-02-29029 February 1984
[Table view]Draft Site Redress Plan ML20083C8921983-12-27027 December 1983 Final Rept of Crbr Piping & Valve Technical Support Team ML20083M1611983-10-24024 October 1983 Part 21 Rept Re Noncompliance to ASME Code Test Requirement Involving Nuclear Part Not Receiving Pressure Test Prior to Acceptance.Change Control Procedure Revised to Be More Explicit on Types of Documents Utilized ML20085A7361983-07-0606 July 1983 Rev 2 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20023D4071983-05-31031 May 1983 Amend 77 to PSAR ML20076D3201983-05-31031 May 1983 Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins ML20024A1491983-05-31031 May 1983 Safety Evaluation Report Related to the Construction of the Clinch River Breeder Reactor Plant.Docket No. 50-537. (U.S. Department of Energy,Tennessee Valley Authority and Project Management Corporation) ML20072B3561983-05-27027 May 1983 Crbr Erosion & Sediment Control Plan Rept ML20084L9931983-03-31031 March 1983 Rev 5 to Hypothetical Core Disruptive Accident Considerations in Crbrp, Vol 2, Assessment of Thermal Margin Beyond Design Base ML20071F1971983-03-10010 March 1983 Adequacy of Crbr Program Reactor Vessel NDE Insps ML20072B6401983-03-0404 March 1983 Crbr Program Heat Transport Sys Incontainment Piping Reserve Seismic Margins ML20079N3691983-03-0202 March 1983 Amend 76 to PSAR ML20070W2001983-02-28028 February 1983 Corrected Pages to Page Replacement Guide of Amend 75 to PSAR ML20028G4251983-02-28028 February 1983 Amend 75 to PSAR ML20079L5131983-02-10010 February 1983 Sodium Slug Energy Absorption Capability of Modified Crbr Closure Head, Westinghouse Crbr Engineering Study Rept ML20028C2911983-01-31031 January 1983 Crbr PSAR Chapter 17.0-QA,App D Description of NSSS QA Program, Submitted for Inclusion in Amend 75 to PSAR ML20064J9381983-01-0707 January 1983 Crbr Reliability Assurance Activities ML20070H8321982-12-31031 December 1982 Assessment of Unprotected Loss of Flow Accident at End of Cycle-4 in Crbr Heterogeneous Core Design ML20070K6661982-12-31031 December 1982 Amend 74 to PSAR ML20070H8521982-12-23023 December 1982 Freezing of Driver Fuel Upon Entry to Inner Blanket ML20070M0801982-12-21021 December 1982 Reactor Vessel Core Support Cone Structural Integrity ML20057B5651982-12-0909 December 1982 Partially Withheld Commission Paper Re NRDC Vs NRC 82-1962 Re Facility ML20057B5631982-12-0707 December 1982 Partially Withheld Commission Paper Informing Commission of DC Circuit Court Decision Re Facility ML20028B4681982-11-30030 November 1982 Amend 73 to PSAR ML20028E9371982-11-30030 November 1982 Crbr Plant Verification of FORE-2M Computer Code,Part II-Comparison w/EBR-11 Natural Circulation Experiments ML20028B4811982-11-23023 November 1982 Thermal Margin Beyond Design Basis (Tmbdb) Melting Scenario. ML20065S2491982-10-31031 October 1982 Amend 72 to PSAR ML20028A1521982-10-31031 October 1982 Supplement to Final Environmental Statement Related to Construction and Operation of Clinch River Breeder Reactor Plant.Main Report.Docket No. 50-537.(U.S. Department of Energy,Tennessee Valley Authority & Project Management Corp) ML20070C8921982-10-31031 October 1982 Aerosol Release from Sodium-Concrete Reactions. Prototype Hydrogen Filter Preliminary Test Results Encl ML20070C9171982-10-31031 October 1982 Hydrogen Distribution in Breeder Reactor Containments, Summary Rept.Miscellaneous Updates to CRBRP-3,Vol 2 Info on Containment Cleanup Sys & Revised Response to Question CS760.144 on Axisymmetric Distribution of Temps Encl ML20028A6141982-09-30030 September 1982 Supplementary Manual for F0RE-2M Computer Program. ML20027B9471982-09-30030 September 1982 Amend 71 to PSAR ML20083M7271982-08-31031 August 1982 Thermal Margin Beyond Design Base (Tmbdb) Sodium-Concrete Penetration Margins Assessment for Crbr Plant ML20062H0821982-08-31031 August 1982 Limited Const Activities Rept ML20062N5901982-08-31031 August 1982 Amend 70 to PSAR ML20055C1621982-08-13013 August 1982 Recommends Modifying Proposed Decision Granting in Part Exemption from 10CFR50.12 by Adding Provision Re Endangered Species Act ML20057B5371982-08-10010 August 1982 Partially Withheld Commission Paper to Provide Draft Order Concluding Commission Proceeding on DOE Request for Exemption Per 10CFR50.12 ML20062D6121982-08-0404 August 1982 Hypothetical Core Disruptive Accident Considerations in Crbrp:Assessment of Thermal Margin Beyond Design Base, Vol 2,Revision 4 ML20071K4221982-07-31031 July 1982 Amend 69 to PSAR ML20058J0261982-07-30030 July 1982 Page Replacement Guide for Amend 69 to PSAR ML20058E4561982-07-22022 July 1982 Crbr Plant Rept ML20065A3701982-07-16016 July 1982 Draft Revision 1 to Analysis of Nominal Heat Removal Capacity of Crbr in Natural Circulation Mode ML20054K9341982-06-30030 June 1982 Speech Entitled Simulation of Lmfbr ML20063D4631982-06-30030 June 1982 Site Preparation Activities Rept ML20054H8261982-06-30030 June 1982 SITE-SUITABILITY Report in the Matter of the Clinch River Breeder Reactor Plant.Docket No. 50-537 ML20063G8551982-06-30030 June 1982 Updated Pages for Ref 106 of PSAR Section 1.6,CRBRP-3,Vol 2, Hypothetical Core Disruptive Accident Considerations in Crbr:Assessment of Thermal Margin Beyond Design Base ML20024E4851982-06-30030 June 1982 Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, Rev D ML20053C0661982-05-31031 May 1982 Amend 68 to PSAR ML20071E1011982-05-31031 May 1982 LMFBR Program, Fes ML20054G4881982-05-31031 May 1982 Crbr Special Stress & Criteria Considerations, Crbr Engineering Study Rept 1984-02-29 |
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