Category:GENERAL EXTERNAL TECHNICAL REPORTS
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Pages in category "GENERAL EXTERNAL TECHNICAL REPORTS"
The following 200 pages are in this category, out of 8,402 total.
(previous page) (next page)A
- A000364, Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of ABWR Design
- A08995, Rev 1 to Auxiliary Initiation Event Analysis
- A10089, Investigation of Engine Bearing Distress in Fairbanks-Morse Emergency Diesel Generators at Fermi-II Power Plant, Phase 1:Insp & Preliminary Conclusions
- A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station
- A34600, Hydrodynamic Mass & Acceleration Drag Vol of Vermont Yankee ECCS Strainers
- AECM-84-0103, Comprehensive Rept on Standby Diesel Generators - Significant Activities to Enhance & Verify Reliability
- AECM-85-0191, Evaluation of Unprotected Supports Exposed to Elevated Temps Associated W/Postulated Fires
- AECM-87-0015, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 861231
- AECM-87-0102, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 870331
- AECM-87-0163, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 1987
- AECM-88-0021, Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-1231
- AECM-89-0165, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 890630
B
- B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1
- B12020, Summary of Results of Haddam Neck Probabilistic Safety Study
- B12024, :Response to Info Requested Re Station Blackout, Technical Review
- B12480, Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl
- B12619, Bimonthly Progress Rept 5:New Switchgear Bldg Const
- B12844, Rev 0 to Spent Fuel Pool Capacity Expansion Project Description & Sar
- B12965, Drywell Insulation Study
- B12983, Natural Circulation Sys Comparison Rept
- B130172, Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair
- B130178, Demonstration of Compliance W/10CFR50,App G for LaSalle Unit 2 Plate Matl
- B13678, Boron Dilution Analysis,Cycle 4
- B14005, SDC Auto-Closure Interlock Removal at Millstone Unit 2
- B212880, Plant-Specific Details Re ATWS Mitigation Sys Actuation Circuitry for Millstone Unit 3
- B51956, 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations
C
E
- ELV-00511, Criticality Analysis of Vogtle Fresh Fuel Racks
- ET-NRC-92-3663, Nonproprietary AP600 Response to NRC Staff Concerns Re High Pressure Full Height Integral Testing
- ET-NRC-92-3784, AP600 Conformance Assessment W/Alwr Utility Requirements Document,Vol Iii,Rev 3
- ET-NRC-93-3965, Nonproprietary AP600 Sensitivity Analyses
- ET-NRC-93-3990, Nonproprietary, AP600 RCS Leak PRA Evaluation
L
- L-01-014, Structural Evaluation of AR Nuclear One-Unit 1 Spent Fuel Storage Facility for Consolidated Fuel Storage
- L-02-013, Structural Evaluation of Arkansas Nuclear One-Unit 2 Spent Fuel Storage Facility for Consolidated Fuel Storage
- L-02-032, Equivalent Usage Factor for Equipment Qualification
- L-09-100, Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept
- L-09-102, Design Rept for Recirculation Sys Weld Overlay Repairs at Brunswick Steam Electric Plant,Unit 1
- L-13-103, Rev 0 to Design Rept for Recirculation Sys Weld Overlay Repairs at Brunswick Steam Electric Plant Unit 1
- L-13-104, Rev 1 to Design Rept for Weld Overlay Repairs at Brunswick Steam Electric Plant Unit 2
- L-17-103, Rev 0 to Statistical Evaluation of Postulated Flaws at Brunswick Steam Electric Plant,Unit 1
- L-18-120, Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi
- L-19-103, Rev 1 to Analysis of Unrepaired Flow Indications at Brunswick Steam Electric Plant,Unit 2
- L-30-100, Rev 2 to Design Rept for Recirculation Sys Weld Overlay Repairs & Flaw Analysis at Brunswick Steam Electric Plant Unit 1
- L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
- L-93-036, Licensing Submittal to Support Replacement SG TS Changes for Vsns
- L-96-158, Rev 2 to Jm Farley Nuclear Plant Units 1 & 2 Licensing Rept for TS Changes Associated W/Revised Core Limits,Revised Trip Setpoints & Inclusion of RAOC Control Strategy
- L-97-215, SG Secondary Side Loose Object Safety Evaluation
- LD-83-020, Nonproprietary Response to NRC Questions for CESSAR-F Statistical Combination of Uncertainty in Thermal Margin Analysis for Sys 80
- LD-88-015, Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design
- LD-88-049, Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region
- LD-88-144, Radiological Survey Rept - Wooded Area C-E,Inc Property, Windsor, Ct
- LD-92-095, Draft Sys 80+ Design Certification Piping Analysis Specification
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