ML14113A082
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i REV. 14, APRIL 2002 LA SALLE COUNTY STATION UPDATED FINAL SAFETY ANALYSIS REPORT Table of Contents VOLUME I CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.0 Introduction and General Description of Plant 1.1 Introduction 1.2 General Plant Description 1.3 Comparison Tables 1.4 Identification of Agents and Contractors 1.5 Requirements for Further Technical Information - Current Concerns 1.6 Material Incorporated by Reference CHAPTER 2 SITE CHARACTERISTICS
2.0 Site Characteristics 2.1 Geography and Demography 2.2 Nearby Industrial Transportation and Military Facilities 2.3 Meteorology 2.4 Hydrologic Engineering VOLUME II CHAPTER 2 (Continued) SITE CHARACTERISTICS 2.5 Geology, Seismology, an d Geotechnical Engineering Appendix 2.5A Selected Structures Outside the 200-mile Radius
LSCS-UFSAR Table of Contents (Continued) ii REV. 15, APRIL 2004 VOLUME III CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.0 Design of Structures, Compo nents, Equipment, and Systems 3.1 Conformance with NRC General Design Criteria 3.2 Classification of Structures, Components, and Systems 3.3 Wind and Tornado Loadings 3.4 Water Level (Flood) Design 3.5 Missile Protection 3.6 Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping 3.7 Seismic Design 3.8 Design of Category I Structures
VOLUME IV
CHAPTER 3 (Continued) DESIGN OF STRUCTURES, COMPONENTS AND SYSTEMS 3.9 Mechanical Systems and Components 3.10 Seismic Qualification of Se ismic Category I Instrumentation and Electrical Equipment 3.11 Environmental Design of Mechanical and Electrical
Equipment Attachment 3.A Deleted Attachment 3.B A Generic Upper Bound ary Probabilistic Analysis of the Effect of Recirculation Pump Missiles on Containment and Equipment in a Typical BWR 5 Mark II General Electric Boiling Water Reactor Nuclear Power Plant
.C Category I Concrete Masonry Walls LSCS-UFSAR Table of Contents (Continued) iii REV. 15, APRIL 2004 VOLUME IV - A CHAPTER 4 REACTOR
4.0 Reactor 4.1 Summary Description 4.2 Fuel System 4.3 Nuclear Design 4.4 Thermal and Hydraulic Design 4.5 Reactor Materials 4.6 Functional Design of Reactivity Control Systems
CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.0 Reactor Coolant System and Connected Systems 5.1 Summary Description 5.2 Integrity of Reactor Coolant Pressure Boundary 5.3 Reactor Vessel 5.4 Component and Subsystem Design VOLUME V CHAPTER 6 ENGINEERED SAFETY FEATURES
6.0 Engineered Safety Features 6.1 Engineered Safety Feature Materials 6.2 Containment Systems 6.3 Emergency Core Cooling Systems 6.4 Habitability Systems 6.5 Fission Product Removal and Control Systems 6.6 Inservice Inspection of ASME Code Class 2 and 3 Components 6.7 Main Steam Isolation Valve Leakage Control System (MSIV-LCS) - Unit 2 deleted, Unit 1 Abandoned in Place 6.8 Main Steam Isolation Valve - Isolated Condenser Leakage Treatment Method Attachment 6.A Annulus Pressurization Attachment 6.B Recirculation System Single-Loop Operation LSCS-UFSAR Table of Contents (Continued) iv REV. 13 VOLUME VI CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS
7.0 Instrumentation and Control Systems 7.1 Introduction 7.2 Reactor Protection System Instrumentation and Control 7.3 Engineered Safety Feature Systems 7.4 Systems Required for Safe Shutdown 7.5 Safety-Related Display Instrumentation 7.6 Other Instrumentation Systems Required for Safety 7.7 Control Systems Not Required for Safety 7.8 Status Displays ATTACHMENT 7.A Analysis of Conformance of Instrumentation and Control Systems with IEEE Criteria
CHAPTER 8 ELECTRIC POWER 8.0 Electric Power 8.1 Introduction 8.2 Offsite Power System 8.3 Onsite Power Systems 8.4 Other Electrical Features and Requirements for Safety
VOLUME VII
CHAPTER 9 AUXILIARY SYSTEMS 9.0 Auxiliary Systems 9.1 Fuel Storage and Handling 9.2 Water Systems 9.3 Process Auxiliaries 9.4 Heating, Ventilation, and Air Conditioning 9.5 Other Auxiliary Systems CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 10.0 Steam and Power Conversion System 10.1 Summary Description 10.2 Turbine Generator 10.3 Main Steam Supply System 10.4 Other Features of Steam and Power Conversion System LSCS-UFSAR Table of Contents (Continued) v REV. 13 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT
11.0 Radioactive Waste Management 11.1 Source Terms 11.2 Liquid Waste Management Systems 11.3 Gaseous Waste Management Systems 11.4 Solid Waste Management System 11.5 Process and Effluent Radiological Monitoring and Sampling Systems CHAPTER 12 RADIATION PROTECTION 12.0 Radiation Protection 12.1 Ensuring that Occupational Radiation Exposures Are as Low as Reasonably Achievable 12.2 Radiation Sources 12.3 Radiation Protection Design Features 12.4 Dose Assessment 12.5 Health Physics Program VOLUME VIII
CHAPTER 13 CONDUCT OF OPERATIONS
13.0 Conduct of Operations 13.1 Organizational Structures of Licensee 13.2 Training 13.3 Emergency Planning 13.4 Review and Audit 13.5 Plant Procedures 13.6 Plant Records 13.7 Industrial Security
CHAPTER 14 INITIAL TEST PROGRAM 14.0 Initial Test Program LSCS-UFSAR Table of Contents (Continued) vi REV. 15, APRIL 2004 CHAPTER 15 ACCIDENT ANALYSES
15.0 Accident Analyses 15.1 Increase in Heat Removal by the Secondary System 15.2 Decrease in Heat Removal by the Secondary System 15.3 Decrease in Reactor C oolant System Flow Rate 15.4 Reactivity and Power Distribution Anomalies 15.5 Increase in Reactor Coolant Inventory 15.6 Decrease in Reactor Coolant Inventory 15.7 Radioactive Release from Subsystems and Components 15.8 Anticipated Transients Without Scram (ATWS) 15.9 Loss of All Alternating Current Power (Station Blackout) 15.A Unit 1 Cycle 2 Safety Analyses 15.B Unit 2 Safety Analyses
CHAPTER 16 TECHNICAL SPECIFICATIONS
16.0 Technical Specifications
CHAPTER 17 QUALITY ASSURANCE 17.0 Quality Assurance APPENDIX A GLOSSARY APPENDIX B CONFORMANCE TO REGULATORY GUIDES APPENDIX C ANALYSIS OF HIGH-ENERGY LINE BREAKS OUTSIDE PRIMARY CONTAINMENT APPENDIX D PLANT NUCLEAR SAFE TY OPERATIONAL ANALYSIS APPENDIX E CONSTRUCTION MATERIAL STANDARDS AND QUALITY CONTROL PROCEDURES APPENDIX F COMPUTER PROGRAMS F.0 Computer Programs for Structural Analysis and Design F.1 Concrete F.2 CSEF-III F.3 DAPS-II F.4 DYNAS F.5 DYNAX LSCS-UFSAR Table of Contents (Continued) via REV. 15, APRIL 2004 F.6 EASE F.7 EMBANK F.8 INDIA F.9 SETTLE F.10 KALSHEL F.11 LAFD F.12 MESHG F.13 PLFEM-II F.14 QUAD4 F.15 RGS F.16 SEPOL F.17 SHAKE F.18 SLOPE F.19 SLSAP F.20 SOR-III F.21 SSANA F.22 STAND F.23 STRESS F.24 STRUDL-II F.25 TEMCO F.26 WARLOC F.27 PIPSYS F.28 PENAN F.29 FAST F.30 REFERENCES
LSCS-UFSAR Table of Contents (Continued) vii REV. 15, APRIL 2004 APPENDIX G REACTOR RECIRCULATION SYSTEM
G.0 Reactor Recirculation System G.1 Introduction G.2 Recirculation System Design Description G.3 System Design Evaluations G.4 Testing G.5 Recirculation Pump Trip and Flow Control Features G.6 Transient Analysis G.7 References
ATTACHMENT G.A REACTOR RECIRCULATION SYSTEM DESIGN DRAWINGS ATTACHMENT G.B FAILURE MODES AN D EFFECTS ANALYSES VOLUME IX
APPENDIX H DELETED - Moved to Fire Protection Report (FPR)
APPENDIX I INFORMATION RELEVANT TO KEEPING LEVELS OF RADIOACTIVITY IN EFFLUENTS TO UNRESTRICTED AREAS
AS LOW AS REASONABLY ACHIEVABLE APPENDIX J ANALYSIS OF THE EFFECTS OF MODERATE ENERGY LINE THROUGH WALL LEAKAGE CRACKS OUTSIDE PRIMARY CONTAINMENT
J.0 Introduction J.1 Moderate Energy Lines J.2 Plant Areas and Equipment Affected by MELB J.3 Spray Shield J.4 Effects of Flooding J.5 Conclusion
APPENDIX K INTERIM OFFSITE POWER ARRANGEMENT LSCS-UFSAR Table of Contents (Continued) viii REV. 19, APRIL 2012 APPENDIX L REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT
APPENDIX M ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT
APPENDIX N INTERIM SECONDARY CONTAINMENT APPENDIX O CONTROL OF HEAVY LOADS