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| number = ML14113A082
| number = ML14113A082
| issue date = 04/11/2014
| issue date = 04/11/2014
| title = LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Table of Contents and List of Effective Pages
| title = Updated Final Safety Analysis Report, Revision 20, Table of Contents and List of Effective Pages
| author name =  
| author name =  
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
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=Text=
=Text=
{{#Wiki_filter: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
{{#Wiki_filter: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  


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  
===1.0 Introduction===
and General Description of Plant   1.1 Introduction   1.2 General Plant Description  1.3 Comparison Tables  


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 
===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


VOLUME IV
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 


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  
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   
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  
   .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  
===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


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
===7.6 Other===
Instrumentation Systems Required for Safety 7.7 Control Systems Not Required for Safety  


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
===7.8 Status===
Displays ATTACHMENT 7.A Analysis of Conformance of Instrumentation and Control Systems with IEEE Criteria


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


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   
===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
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  
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
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
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16.0  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
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  
LSCS-UFSAR Table of Contents (Continued) vii REV. 15, APRIL 2004 APPENDIX G REACTOR RECIRCULATION SYSTEM  
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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  
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
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 H DELETED - Moved to Fire Protection Report (FPR)
APPENDIX I INFORMATION RELEVANT TO KEEPING LEVELS OF RADIOACTIVITY IN EFFLUENTS TO UNRESTRICTED AREAS  
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  
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  
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 K INTERIM OFFSITE POWER ARRANGEMENT LSCS-UFSAR Table of Contents (Continued) viii REV. 19, APRIL 2012 APPENDIX L REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT  

Latest revision as of 13:39, 17 March 2019

Updated Final Safety Analysis Report, Revision 20, Table of Contents and List of Effective Pages
ML14113A082
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/11/2014
From:
Exelon Generation Co
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML14113A099 List:
References
RS-14-128
Download: ML14113A082 (171)
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Text

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

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