ML20137M998
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| ML20137M998 | |
| Person / Time | |
|---|---|
| Issue date: | 04/04/1997 |
| From: | BROOKHAVEN NATIONAL LABORATORY |
| To: | |
| Shared Package | |
| ML20137M973 | List: |
| References | |
| PROJECT-701 RMA97-01, RMA97-01-R00, RMA97-1, RMA97-1-R, NUDOCS 9704080218 | |
| Download: ML20137M998 (235) | |
Similar Documents from Brookhaven National Laboratory | |
|---|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217J6561999-09-24024 September 1999
[Table view]Some use of "" in your query was not closed by a matching "".Rev 1 to Review of Industry Responses to NRC GL 97-06 on Degradation of SG Internals ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20236V8301998-01-31031 January 1998 Review & Evaluation of Historical Fire Protection Licensing Basis Related to Fire Areas Ix,X,Xi,Xv,Xvii & Xviii at Ja FitzPatrick Nuclear Power Plant ML20217J8861997-08-12012 August 1997 Comments on EPRI TR-106387, Evaluation of Irradiated Fuel During Ria Simulation Tests ML20137M9981997-04-0404 April 1997 Final Draft Rev 0 to Conceptual Design for Rd Mod Approval (RMA) 97-01, Impervious Liner for Hfbr Spent Fuel Storage Canal ML20212A3271995-07-21021 July 1995 Rept of Foreign Travel to Japan on 950623-0707 ML20129K1031995-07-10010 July 1995 Exam of Fasteners from Salem Nuclear Generating Station ML20217J8701995-06-30030 June 1995 Trip Rept of 950613-21 Visit to Tokyo,Japan Re Sixth Meeting of Technical Advisory Committee of High-Temp High-Speed Hydrogen Combustion Research Program at Nuclear Power Engineering Corp ML20129E2981995-05-31031 May 1995 Final BNL Technical Rept, Metallurgical Evaluation of FW Nozzle to Safe-End Weld from River Bend Station Unit 1 ML20086C4371995-05-31031 May 1995 Draft, Metallurgical Evaluation of Feedwater Nozzle to Safe-End Weld from River Bend Station,Unit 1 ML20085K1111995-01-31031 January 1995 Pump & Valve IST Program,Rev 14,Second Ten-Yr Interval ML20073G5141994-08-31031 August 1994 Evaluation of Data Base for Sbwr LOCA Events During High Pressure Period of Blowdown Phase, Ltr Rept ML20072D9141994-07-31031 July 1994 Human Factors Engineering Program Review Model ML20067D3311993-08-31031 August 1993 Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20114D0901992-05-31031 May 1992 Volumes I & II of Advanced Control Room Design Review Guideline:Technical Development ML20043B2571988-05-31031 May 1988 Simulations of Lasalle 2 Incident W/Bnl Plant Analyzer. ML18038A0991985-12-13013 December 1985 Sqrt Audit Rept for Nine Mile Point Nuclear Station,Unit 2. ML20244B1391985-09-30030 September 1985 Containment Rock Overbreak/ Overexcavation Seismic Evaluation ML20132D2181985-04-0909 April 1985 Pump & Valve Operability Assurance Audit Technical Evaluation Rept ML20215K4451985-03-31031 March 1985 Oxidation Induced Geochemical Changes in Trench Leachates from Maxey Flats Low Level Radwaste Disposal Site ML20112E4491985-02-11011 February 1985 BNL Technical Review Rept & Handwritten Notes of 850121-25 Insp ML20100B6361985-01-21021 January 1985 Rept on Welding Allegations ML20126J0791984-07-0202 July 1984 Summary of BNL Results for Std Problem 4 (BWR Mark I) ML20132G8241984-06-21021 June 1984 Review of Waterford III Basemat Analysis ML20128G7731984-04-16016 April 1984 Review of Waterford III Basemat Analysis ML20126H8931984-03-13013 March 1984 Handwritten Local Failure Mode of BWR Mark I Drywell Liner Due to Core-Concrete Interaction ML20080T4371983-10-17017 October 1983 Review of Diesel Generator Bldg at Midland Plant ML20080T4221983-09-23023 September 1983 Draft Rept, Review of Diesel Generator Bldg at Midland Plant ML20080S9891983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Verification Program for PG&E Corrective Action ML20080S9911983-09-0101 September 1983 Summary & Evaluation Rept of Rf Reedy Rept, Development of Svc-Related Contractor List for Nonseismic Design Work Performed for Diablo Canyon Nuclear Power Plant,Unit 1 Prior to 780601,Phase II ML20080S9941983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Verification of Design Analysis Hosgri Spectra ML20080S9981983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept Diablo Canyon Unit 1 Idvp - Soils - Intake Structure ML20080T0031983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Soil - Outdoor Water Storage Tanks ML20080T0051983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Small Bore Piping Rept ML20080T0131983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Idvp Valves ML20080T0091983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - HVAC Components ML20080T0161983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Idvp - HVAC Duct & Supports Rept ML20053C8691982-05-27027 May 1982 Radiation Damage Studies on Natural Rock Salt from Various Geological Localities of Interest to Radwaste Disposal Program ML20053C8591982-05-27027 May 1982 Recent Studies in Radiation Damage Formation in Snythetic Sodium Chloride & Natural Rock Salt for Radwaste Disposal Applications, Article from Scientific Basis for Nuclear Waste Mgt, Vol 1 ML19350A2341981-01-15015 January 1981 Some Very Preliminary Results of Short-Term Analysis (3-Wk Study) of Hydrogen Combustion During Degraded Core Accidents in Sequoyah Nuclear Power Plant in Presence of Glow Plugs. 1999-09-24 Category:TEXT-SAFETY REPORT MONTHYEARML20217J6561999-09-24024 September 1999
[Table view]Some use of "" in your query was not closed by a matching "".Rev 1 to Review of Industry Responses to NRC GL 97-06 on Degradation of SG Internals ML20195H5581999-06-30030 June 1999 Proceedings of the TWENTY-SIXTH Water Reactor Safety Information Meeting.Plenary Sessions,Pressure Vessel Research,Severe Accident Research,Fission Product Behavior, Nuclear Materials Issues and Health Effects Research ML20195H5651999-06-30030 June 1999 Proceedings of the TWENTY-SIXTH Water Reactor Safety Information Meeting.Digital Instrumentation and Control,The Halden Program,Structural Performance, and PRA Methods and Applications ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20203C8631999-01-31031 January 1999 Risk Profile Methodology of Plant Configurations and Pilot Applications: Lessons Learned ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20153D4031998-07-31031 July 1998 Technical Review of RISK-INFORMED, PERFORMANCE-BASED Methods for Nuclear Power Plant Fire Protection Analyses.Draft Report for Comment ML20247E4571998-04-30030 April 1998 Proceedings of the TWENTY-FIFTH Water Reactor Safety Information MEETING.Thermal-Hydraulic Research and Codes, Digital Instrumentation and Control, Structural Performance ML20247E5921998-03-31031 March 1998 Proceedings of the TWENTY-FIFTH Water Reactor Safety Information Meeting.Human Reliability Analysis and Human Performance Evaluation, Technical Issues Related to Rulemakings, Risk-Informed, Performance-Based Initiatives ML20247E6161998-03-31031 March 1998 Proceedings of the TWENTY-FIFTH Water Reactor Safety Information Meeting.Plenary Sessions,Pressure Vessel Research,Bwr Strainer Blockage and Other Generic Safety Issues,Environmentally Assisted Degradation of Lwr ML20236V8301998-01-31031 January 1998 Review & Evaluation of Historical Fire Protection Licensing Basis Related to Fire Areas Ix,X,Xi,Xv,Xvii & Xviii at Ja FitzPatrick Nuclear Power Plant ML20217J8861997-08-12012 August 1997 Comments on EPRI TR-106387, Evaluation of Irradiated Fuel During Ria Simulation Tests ML20137M9981997-04-0404 April 1997 Final Draft Rev 0 to Conceptual Design for Rd Mod Approval (RMA) 97-01, Impervious Liner for Hfbr Spent Fuel Storage Canal ML20107B1201996-03-31031 March 1996 Proceedings of the TWENTY-THIRD Water Reactor Safety Information Meeting.Plenary Session, High Burnup Fuel Behavior, Thermal Hydraulic Research ML20098C0901995-09-30030 September 1995 Transactions of the TWENTY-THIRD Water Reactor Safety Information Meeting ML20212A3271995-07-21021 July 1995 Rept of Foreign Travel to Japan on 950623-0707 ML20129K1031995-07-10010 July 1995 Exam of Fasteners from Salem Nuclear Generating Station ML20217J8701995-06-30030 June 1995 Trip Rept of 950613-21 Visit to Tokyo,Japan Re Sixth Meeting of Technical Advisory Committee of High-Temp High-Speed Hydrogen Combustion Research Program at Nuclear Power Engineering Corp ML20086C4371995-05-31031 May 1995 Draft, Metallurgical Evaluation of Feedwater Nozzle to Safe-End Weld from River Bend Station,Unit 1 ML20129E2981995-05-31031 May 1995 Final BNL Technical Rept, Metallurgical Evaluation of FW Nozzle to Safe-End Weld from River Bend Station Unit 1 ML20083N4711995-04-30030 April 1995 Proceedings of the TWENTY-SECOND Water Reactor Safety Information Meeting.Plenary Session, Advanced Instrumentation & Control Hardware & Software, Human Factors Research, IPE & PRA ML20083N4811995-04-30030 April 1995 Proceedings of the TWENTY-SECOND Water Reactor Safety Information Meeting.Severe Accident Research, Thermal Hydraulic Research for Advanced Passive Lwrs, High-Burnup Fuel Behavior ML20081J4991995-03-31031 March 1995 Proceedings of the Third International Workshop on the Implementation of ALARA at Nuclear Power Plants.Held at Hauppauge, Long Island, New York ML20085K1111995-01-31031 January 1995 Pump & Valve IST Program,Rev 14,Second Ten-Yr Interval ML20073G5141994-08-31031 August 1994 Evaluation of Data Base for Sbwr LOCA Events During High Pressure Period of Blowdown Phase, Ltr Rept ML20072D9141994-07-31031 July 1994 Human Factors Engineering Program Review Model ML20073S4721994-05-31031 May 1994 Workshop on Environmental Qualification of Electric Equipment ML20067D3311993-08-31031 August 1993 Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20101Q3091992-06-30030 June 1992 Proceedings of the Nineteenth Water Reactor Safety Information Meeting ML20114D0901992-05-31031 May 1992 Volumes I & II of Advanced Control Room Design Review Guideline:Technical Development ML20073G1161991-04-30030 April 1991 Proceedings of the Eighteenth Water Reactor Safety Information Meeting ML20043B3791989-05-23023 May 1989 Simulations of Recent LaSalle-2 Incident W/Bnl Plant Analyzer, for Presentation at Society for Computer Simulation 1989 Eastern Multiconference in Tampa,Fl on 890328-31 ML20246D5591989-03-31031 March 1989 Proceedings of the Sixteenth Water Reactor Safety Information Meeting ML20245A2261989-03-31031 March 1989 Proceedings of the Sixteenth Water Reactor Safety Information Meeting ML20245A2611989-03-31031 March 1989 Proceedings of the Sixteenth Water Reactor Safety Information Meeting ML20245A2051989-03-31031 March 1989 Proceedings of the Sixteenth Water Reactor Safety Information Meeting ML20245A2351989-03-31031 March 1989 Proceedings of the Sixteenth Water Reactor Safety Information Meeting ML20236B5021989-02-27027 February 1989 Matls & Degradation Modes in Alternate Low Level Waste Disposal Facility, Presented at Waste Mgt 890227-0302 Conference in Tucson,Az ML20043B2571988-05-31031 May 1988 Simulations of Lasalle 2 Incident W/Bnl Plant Analyzer. ML20150A6761988-02-29029 February 1988 Proceedings of the Fifteenth Water Reactor Saftey Information Meeting ML20212C5401987-02-28028 February 1987 Proceedings of the Fourteenth Water Reactor Safety Information Meeting ML20211Q1921987-02-28028 February 1987 Proceedings of the Fourteenth Water Reactor Safety Information Meeting ML20211L0921987-02-28028 February 1987 Proceedings of the Fourteenth Water Reactor Safety Information Meeting ML20211L1041987-02-28028 February 1987 Proceedings of the Fourteenth Water Reactor Safety Information Meeting ML20211L1421987-02-28028 February 1987 Proceedings of the Fourteenth Water Reactor Safety Information Meeting ML20211Q2061987-02-28028 February 1987 Proceedings of the Fourteenth Water Reactor Safety Information Meeting 1999-09-24 |
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