LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15, Accident Analysis - Table of Contents

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Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 15, Accident Analysis - Table of Contents
ML17046A562
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Site: Salem  PSEG icon.png
Issue date: 01/30/2017
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Public Service Enterprise Group
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Office of Nuclear Reactor Regulation
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LR-N17-0034
Download: ML17046A562 (41)
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Section 15.1 15. 1. 1 15. 1. 2 15.1.2.1 15.1.2.2 15.1.2.3 15.1.3 15.1.4 15.1.5 15. 1. 6 15.1.7 15.1.7.1 15.1.7.2 15. 1. 8 15.1.8.1 15.1.8.2 15.1.8.3 15.1.8.4 SECTION 15 ACCIDENT ANALYSIS TABLE OF CONTENTS Title CONDITION I -NORMAL OPERATION AND OPERATIONAL TRANSIENTS Optimization of Control Systems Initial Power Conditions Assumed in Accident Analyses Power Rating Initial Conditions Power Distribution Trip Points and Time Delays to Trip Assumed in Accident Analyses Instrumentation Drift and Calorimetric Errors -Power Range Neutron Flux Rod Cluster Control Assembly Insertion Characteristics Reactivity Coefficients Fission Product Inventories Activities in the Core Activities in the Fuel Pellet Cladding Gap Residual Decay Heat (ANS-1979) Fission Product Decay Decay of U-238 Capture Products Residual Fissions Distribution of Decay Heat Following Loss-of-Coolant Accident 15. 1. 9 ,_, __ Computer Codes Utilized 15 . 1 . '9. 1 FACTRAN 15-i SGS-UFSAR f 15.1-l 15.1-3 15.1-4 15.1-4 15.1-5 15.1-6 15.1-7 15.1-8 15.1-9 15.1-10 15.1-12 15.1-12 15.1-12 15.1-14 15.1-15 15.1-15 15.1-16 15.1-17 15.1-17 15.1-18 Revision 18 April 26, 2000 Section 15.1.9.2 15.1.9.3 15.1.9.4 15.1.9.5 15.1.9.6 15.1.10 15.2 15.2.1 15.2.1.1 15.2.1.2 15.2.1.3 15.2.1.4 15.2.2 15.2.2.1 15.2.2.2 15.2.2.3 15.2.2.4 15.2.3 15.2.3.1 15. 2_\3. 2 15.2. 3 ,' 3 15.2.3.4 15.2.4 SGS-UFSAR TABLE OF CONTENTS {Cant} LOFT RAN PHOENIX-P ANC TWINKLE THINC References for Section 15.1 CONDITION II -FAULTS OF MODERATE FREQUENCY Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical Condition Identification of Causes and Accident Description Method of Analysis Results-Conclusions Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power Identification of Causes and Accident Description Method of Analysis Results Conclusions Rod Cluster Control Assembly Misalignment Identification of Causes and Accident Description Method of Analysis Results Conclusions Uncontrolled Boron Dilution 15-ii 15.1-21 15.1-21 15.1-22 *15 .1. 22 15.1-24 15.1-24 15.2-1 15.2-2 15.2-2 15.2-5 15.2-7 15.2-7 15.2-8 15.2-8 15.2-10 15.2-11 15.2-12 15.2-13 15.2-13 15.2-15 15.2-15 15.2-17 15.2-18 Revision 18 April 26, 2000 I 15.2.4.1 15.2.4.1.1 15.2.4.1.2 15.2.4.2 15.2.4.2.1 15.2.5 15.2.5.1 15.2.5.2 15.2.5.3 15.2.5.4 15.2.5.5 15.2.6 15.2.7 15.2.7.1 15.2.7.2 15.2.7.3 15.2.7.4 15.2.8 15.2.8.1 15.2.8.2 15.2.8.3 15.2.8.4 SGS-UFSAR TABLE OF CONTENTS (Cont) Malfunction of the Reactor Makeup System: Causes and Accident Description Method of Analysis Conclusions Miscellaneous Malfunctions: Causes, Accident Descriptions and Analyses Conclusions Partial Loss of Forced Reactor Coolant Flow Identification of Causes and Accident Description Method of Analysis Initial Conditions Results Conclusions Startup of an Inactive Reactor Coolant Loop Loss of External Electrical Load and/or Turbine Trip Identification of Causes and Accident Description Method of Analysis Results Conclusions Loss of Normal Feedwater Identification of Causes and Accident Description Method of Analysis Results Conclusions 15-iii 15.2-18 15.2-19 15.2-22 15.2-23 15.2-25 15.2-26 15.2-26 15.2-27 15.2-27 15.2-28 15.2-28 15.2-28 15.2-31 15.2-31 15.2-32 15.2-34 15.2-36 15.2-36 15.2-36 15.2-38 15.2-39 15.2-39 Revision 24 May 11, 2009 15.2.9 15.2.9.1 15.2.9.2 15.2.9.3 15.2.9.4 15.2.10 15.2.10.1 15.2.10.2 15.2.10.3 15.2.10.4 15.2.11 15.2.11.1 15.2.11.2 15.2.11.3 15.2.11.4 15.2.12 15.2.12.1 15.2.12.2 15.2.12.3 15.2.12.4 15.2.13 15.2.13.1 15.2.13.2 15.2.13.3 15.2.13.4 SGS-UFSAR TABLE OF CONTENTS (Cant) Loss of Offsite Power to the Station Auxiliaries Identification of Causes and Accident Description Method of Analysis Results Conclusions Excessive Heat Removal Due to Feedwater Malfunctions Identification of Causes and Accident Description Method of Analysis Results Conclusions Excessive Load Increase Incident Identification of Causes and Accident Description Method of Analysis Results Conclusions Accidental Depressurization of the Reactor Coolant System Identification of Causes and Accident Description Method of Analysis Results Conclusions Accidental Depressurization of the Main Steam System Identification of Causes and Accident Description Method of Analysis Results Conclusions 15-iv 15.2-40 15.2-40 15.2-41 15.2-41 15.2-42 15.2-42 15.2-42 15.2-43 15.2-44 15.2-46 15.2-46 15.2-46 15.2-47 15.2-48 15.2-49 15.2-49 15.2-49 15.2-49 15.2-50 15.2-51 15.2-51 15.2-51 15.2-52 15.2-54 15.2-55 Revision 24 May 11, 2009 Section 15.2.14 15.2.14.1 15.2.14.2 15.2.14.3 15.2.14.4 15.2.15 15.2.16 15.3 15.3.1 15.3.1.1 15.3.1.2 15.3.1.3 15.3.2 15.3.2.1 15.3.2.2 15.3.2.3 15.3.3 15.3.3.1 15.3.3.2 15.3.3.3 15.3.3.4 15.3.4 15.3.4.1 15.3.4.2 SGS-UFSAR TABLE OF CONTENTS (Cont) Title Operation of the Safety Injection System at Power Accident Description Method of Analysis Results Conclusions Turbine Generator Accidents References for Section 15.2 CONDITION III -INFREQUENT FAULTS Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in Large Pipes which Actuates the Emergency Core Cooling System Identification of Causes and Accident Description Analysis of Effects and Consequences Conclusions Minor Secondary System Pipe Breaks Identification of Causes and Accident Description Analysis of Effects and Consequences Conclusions Inadvertent Loading of a Fuel Assembly into an Improper Position Identification of Causes and Accident Method of Analysis Results Conclusions Loss of Forced Reactor Coolant Flow Accident Description Method of Analysis 15-v 15.2-55 15.2-55 15.2-56 15.2-58 15.2-59 15.2-60 15.2-61 15.3-1 15.3-2 15.3-2 15.3-3 15.3-6 15.3-7 15.3-7 15.3-7 15.3-8 15.3-8 15.3-8 15.3-9 15.3-10 15.3-lla 15.3-11a 15.3-11a 15.3-12 Revision 25 October 26, 2010 Section 15.3.4.3 15.3.4.4 15.3.5 15.3.5.1 15.3.5.2 15.3.5.3 15.3.5.4 15.3.6 15.3.6 .. 1 15.3.6.2 15.3.6.3 15.3.7 15.3.8 Results Conclusions TABLE OF CONTENTS (Cent) Single Rod Cluster Control Assembly Withdrawal at Full Power Accident Description Method of Analysis Results Conclusions Accidental Release of Waste Gases Situations Considered Volume control Tank Rupture Analysis Gas Decay Tank Rupture Analysis Accidental Release of Radioactive Liquids References for Section 15.3 Appendix 15.3A Deleted 15.4 15.4.1 15.4.1.1 15.4.1.1.1 15.4.1.1.2 15.4.1.1.3 15.4.1.1.4 15.4.1.2 15.4.1.3 15.4.1.3.1 15.4.1.3.2 15 .. 4.1.3.3 15.4 .. 1.3.4 15.4.1 .. 3.5 15.4.1.3.6 15.4.1 .. 3.7 15 .. 4.1 .. 4 15.4.1.5 SGS-UFSAR CONDITION IV -LIMITING FAULTS Major Reactor Coolant System Pipe Ruptures (Loss-at-Coolant Accident} Identification of Causes and Frequency Classification Deleted Deleted Deleted Deleted Sequence of Events and Systems Operations Thermal Analysis Westinghouse Performance Criteria for ECCS Large Break LOCA Evaluation Model Deleted Deleted Deleted Deleted Deleted Large Break LOCA Input Parameters and Initial Conditions Large Break LOCA Analysis Results 15-vi 15 .. 3-13 15.3-14 15 .. 3-14 15.3-14 15 .. 3-15 15 .. 3-15 15.3-16 15 .. 3-16 15.3-16 15.3-17 15 .. 3-17 15 .. 3-18 15.3-19 15.4-1 15 .. 4-2 15.4-2 15 .. 4-2 15.4-2b 15.4-2b 15.4-3 15.4-3b 15 .. 4-5 Revision 16 January 31, 1998 ( ( __ .

Section 15.4.1.6 15.4.1.7 15.4.1.8 15 .. 4.1.8.1 15.4.1.8.2 15.4.1.8.3 TABLE OF CONTENTS (Cent) Large Break LOCA Transition Core Effects Large Break LOCA Analysis Conclusions Environmental Consequences of a Loss-of-Coolant Accident Sources Method of Analysis Effectiveness of Safeguards for Limiting Activity Release 15 .. 4.1.8.4 Sources Analyzed 15.4.1.8 .. 5 Results 15.4.1.9 Control Room Analyses During a Loss-of-Coolant Accident 15.4.1.9.1 Results 15.4.2 Major Secondary System Pipe Rupture 15.4.2.1 15.4.2.2 15.4.2.3 15.4.2.4 15.4.2.5 15.4.2.6 15.4.3 15.4.3.1 15.4.3.2 15.4.3.3 15.4.3.4 15.4.4 15.4.4.1 15.4.4.2 15.4.4.3 15.4.4.4 15.4.4.5 15.4.4.6 SGS-UFSAR ,. Identification of Causes and Accident Description Method of Analysis Results Core Power and Reactor Coolant System Transient Margin to Critical Heat Flux Offsite Doses Major Rupture of a Main Feedwater Line Accident Description Method of Analysis Results Conclusion Steam Generator Tube Rupture General Description of Accident Methods of Analysis Results Environmental Consequences of a Tube Rupture conclusions 15-vii 15 .. 4-7 15.4-8 15.4-16 15.4-16 15.4-18 15.4-21 15.4-22a 15.4-24 15.4-27 15.4-30 15 .. 4-31 15.4-31 15.4-33 15.4-38 15.4-38 15.4-40 15.4-40 15.4-43 15.4-43 15.4-45 15.4-47 15.4-49 15.4-49 15.4-49 15.4-50 15.4-52 15.4-52 15.4-53 15.4-55 Revision 16 January 31, 1998 Section 15.4.5 15.4.5 .. 1 15.4.5.2 15.4.5 .. 3 15.4.5.4 SGS-UFSAR TABLE OF CONTENTS ( Cont) Title Single Reactor Coolant Pump Locked Rotor and Reactor Coolant Pump Shaft Break Identification of Causes and Accident Description Method of Analysis Locked Rotor Results Conclusions 15-viia 15.4-56 15.4-56 15.4-57 15.4-60 15.4-60 Revision 16 January 31, 1998 SGS-UFSAR f THIS PAGE INTENTIONALLY BLANK 15-viib Revision 10 July 22, 1990 15.4.6 15.4.6.1 15.4.6.2 15.4.6.3 15.4.6.3.1 15.4.6.3.2 15.4.6.3.3 15.4.6.3.4 15.4.7 15.4.7.1 15.4.7.2 15.4.7.3 15.4.7.4 15.4.8 5. 4. 8.1 15.4.8.1.1 TABLE OF CONTENTS (Cant) Fuel Handling Accident Identification of Causes and Accident Description of Effects and Consequences Conclusions Radiation Doses Solid Radwaste Gaseous Releases Personnel Exposures Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly ection) Identification of Causes and Accident of Effects and Consequences Results Conclusions Containment Pressure Reactor Coolant Method of Breaks 15.4.8.1.2 Mass and Releases from the Reactor Coolant System 15.4.8.1.3 Heat Sinks 15.4.8.1.4 LOCA Containment Pressure and Temperature Results 15.4.8.2 15.4.8.2.1 15.4.8.2.2 15.4.8.2.3 15.4.8.2.4 15.4.8.3 15.4.8.4 15.4.8.4.1 15.4.8.4.2 15.4.9 15.5 15.5.1 SGS-OFSAR Mass and Energy Releases to Containment Following a Steamline Accident Description Method of Analysis Results Conclusions Subcompartment Pressure Analysis Miscellaneous Minor Reactor Coolant Loss of Normal Containment Cooling References for Section 15.4 ANTICIPATED TRANSIENTS WITHOUT SCRAM References for Section 15.5 15-viii 15.4-61 15.4-61 15.4-61 15.4 63 15.4-63 15.4-63 15.4-64 15.4-64 15.4-64 15.4-64 15.4-69 15.4-74 15.4-77a 15.4-77a 15.4-77a 15.4-77a 15.4-79 15.4-94 15.4-101 15.4-104 15.4-104 15.4-105 15.4-111 15.4-112 15.4-112 15.4-113 15.4-113 15.4-113 15.4-114 15.5-1 15.5-1 Revision 24 May 11, 2009 Table 15.1-1 15.1-2 15.1-3 15.1-4 15.1-5 15.1-6 15.2-1 15.2-2 15.2-3 15.3-1 15.3-1a 15.3-2 15.3-2a 15.3-3 15.3-3a 15.3-4 15.3A-l 15.3A-2 SGS-UFSAR LIST OF TABLES Title Nuclear Stearn Supply System Power Ratings Summary of Initial Conditions and Computer Codes Used Trip Points and Time Delays to Trip Assumed in Accident Analysis Determination of Maximum Overpower Trip Point -Power Range Neutron Flux Channel Based on Nominal Setpoint Considering Inherent Instrumentation Errors DELETED DELETED Time Sequence of Events for Condition II Events DELETED Natural Circulation Flow Small Break LOCA Analysis Time Sequence of Events (Unit 1) Small Break LOCA Analysis Time Sequence of Events (Unit 2) Input Parameters Used in the ECCS Analyses (Unit 1) Input Parameters Used in the ECCS Analyses (Unit 2) Small Break LOCA Analysis Fuel Cladding Results (Unit 1) Small Break LOCA Analysis Fuel Cladding Results (Unit 2) Time Sequence of Events for Complete Loss of Flow Events DELETED DELETED 15-ix Revision 24 May 11, 2009 Table 15.4-1 15.4-2 15.4-3 15.4-4 15.4-5 15. 4-5A 15.4-58 15.4 -5C 15.4-50 15.4-5E 15.4-6 15. 4-6A 15.4-68 15. 4-7 15.4-7A I 15.4-7B 15.4-7C I 15.4-8 15.4-9 SGS-UFSAR LIST OF TABLES (Cent) Title Time Sequence of Events for Condition IV Events Large Break LOCA Analysis Results Containment Data Large Break LOCA Analysis RCS to Containment Mass and Energy Releases for Limiting Case Large Break LOCA (Excluding Accumulator/SI Spill} Broken Loop Accumulator/Pumped SI to Containment Mass and Energy Releases for Limiting Case Large Break LOCA Deleted Loss-of-Coolant Analysis Parameters and Assumptions Loss-of-Coolant Accident Dose Consequences Salem Control Room Dispersion F'actors for LOCA Analysis Deleted Summary of Results for Locked Rotor Transients Locked Rotor Accident Parameters and Assumptions Locked Rotor Accident Dose Consequences Main Steam Pipe Rupture Parameters and Assumptions Main Steam Pipe Rupture Dose Consequences Steam Generator Tube Rupture Accident Parameters and Assumptions Steam Generator Tube Rupture Accident Dose Consequences Deleted Breathing Rates 15-x Revision 23 October 17, 2007 *

  • 15.4-10 15.4-11 15.4-12 15.4-12A 15.4-12B 15.4-13 15.4-14 15.4-15 15.4-15A 15.4-15B 15.4-16 15.4-17 15.4-lS 15.4-19 15.4-20 SGS-UFSAR LIST OF TABLES (Cont) DELETED DELETED Parameters Used in the Analysis of the Rod Cluster Control Assembly Ejection Accident Rod Ejection Accident Parameters and Assumptions Rod Ejection Accident Dose Consequences LOCA Mass and Energy Release Analysis System Parameters Initial Conditions Safety Injection Flow For LOCA Containment Analyses DELETED Blowdown Mass and Energy Releases -Double-ended Hot Leg Break Blowdown Mass and Energy Releases -Double-ended Pump Suction Break Reflood Mass and Energy Releases -Double-ended Pump Suction Break (Minimum Safeguards) Reflood Mass and Energy Releases -Double-ended Pump Suction Break (Maximum Safeguards) Post-Reflood Mass and Energy Releases Suction Break Minimum Safeguards Post-Reflood Mass and Energy Releases Suction Break Maximum Safeguards Double-ended Pump Double-ended Pump Passive Heat Sinks For Containment Integrity Analyses 15-xi Revision 24 May 11, 2009 15.4-21 15.4-22 15.4-23 15.4-24 15.4-25 15.4-26 15.4-27 15.4-28 15.4-29 15.4-30 15.4-31 15.4-32 15.4-33 15.4-34 SGS-UFSAR LIST OF TABLES (Cont) Title Structural Heat Sinks LOCA Containment Results (Loss-of-offsite power assumed) Parameters During Reflood Double-ended Pump Suction Break Minimum Containment Parameters Parameters Reflood -Double-ended Pump Suction Break -Maximum Containment Initial Conditions for MSLB DELETED Mass Balance Balance Sa Mass Balance Energy Balance Safeguards Mass Balance Balance Double-ended Pump Suction Break Minimum Double-ended Pump Suction Break Minimum Double-ended Pump Suction Break Maximum Double-ended Pump Suction Break Maximum Double-ended Hot Leg Break Double-ended Hot Break Containment Fan Cooler Unit Performance -Containment 15-xii Revision 24 May 111 2009 Figure 15.1-1 15.1-2 15.1-3 15.1-4 15.1-5 15.1-6 15.1-7 15.1-8 15.1-9 15.2-1 15.2-2 15.2-3 SGS-UFSAR f LIST OF FIGURES Title Illustration of Overtemperature and Overpower Protection Rod Position versus Time on Reactor Trip Normalized RCCA Reactivity Worth versus Percent Insertion Normalized RCCA Reactivity Worth versus Time after Reactor Trip Integrated Doppler Power Coefficient Used in Accident Analysis Residual Decay Heat Fuel Rod Cross Section Deleted Deleted Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical Condition Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from a Subcritical Condition Deleted 15-xiii Revision 18 April 26, 2000 Figure 15.2-4 SGS-UFSAR LIST OF FIGURES {Contd) Title Transient Response for Uncontrolled Rod Withdrawal from Full Power Terminated by High Neutron Flux Trip (75 PCM/SEC) 15-xiiia Revision 18 April 26, 2000 { \ I L THIS PAGE INTENTIONALLY BLANK 15-xiiib SGS-UFSAR Revision 7 July 22, 1987 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 15.2-15 15.2-16 15.2-17 15.2-18 15.2-19 SGS-UFSAR LIST OF FIGURES {Cont) Transient Response for Uncontrolled Rod Withdrawal from Full Power Terminated by High Neutron Flux Trip (75 PCM/SEC) Transient for Uncontrolled Rod Withdrawal from Full Power Terminated by LiT Trip {3 PCM/SEC) Transient for Uncontrolled Rod Withdrawal from Full Power Terminated by Overtemperature LiT Trip (3 PCM/SEC) Effect of Reactivity Insertion Rate on Minimum DNBR for a Rod Withdrawal Accident from 100 Percent Power Effect of Insertion Rate on Minimum DNBR for a Rod Withdrawal Accident from 60 Percent Power Effect of Insertion Rate on Minimum DNBR for a Rod Withdrawal Accident from 10 Percent Power Transient Response to Dropped Rod Cluster Control Assembly DELETED All All All Loop DELETED DELETED DELETED DELETED Operating, Two Loops Coasting Down Operating, Two Loops Coasting Down , Two Loops Down 15-xiv Revision 24 May 11, 2009 Figure 15.2-20 15.2-21 15.2-22 15.2-23 15.2-24 15.2-25 15.2-25a 15.2-25b 15.2-25c 15.2-26 15.2-27 15.2-28a 15.2-28b 15.2-28c SGS-UFSAR LIST OF FIGURES (Cont) Title Loss-of Load Accident with Automatic Pressure Control Minimum Feedback (BOL) Loss-of Load Accident with Automatic Pressure Control Minimum Feedback (BOL) Loss-of Load Accident with Automatic Pressure Control Minimum Feedback (BOL) Loss-of Load Accident without Automatic Pressure Control Minimum Feedback . ( BOL) Loss-of Load Accident without Automatic Pressure Control Minimum Feedback (BOL) Loss-of Load without Automatic Pressure Control Primary Pressurization Case Loss-of Load with Automatic Pressurization Case Loss-of Load with Automatic Pressurization Case Loss-of Load with Automatic Pressurization Case DELETED DELETED Loss of Normal Feedwater Loss of Normal Feedwater Loss of Normal Feedwater 15-xv Pressure Pressure Pressure Control Secondary Control Secondary Control Secondary Revision 24 May 11, 2009 Figure 15.2-28d 15.2-28e 15.2-28f 15.2-29 15.2-29a 15.2-29b 15.2-29c 15.2-29d 15.2-29e 15.2-29! 15.2-30 15.2-31 15.2-32 15.2-33 15.2-34 SGS-UFSAR LIST OF FIGURES (Cant) Title Loss of Power to the Station Auxiliaries Loss of Power to the Station Auxiliaries Loss of Power to the Station Auxiliaries Deleted Single-Loop Feedwater Control Valve Malfunction from Hot Full Power Conditions with Manual Rod Control Single-Loop Feedwater Control Valve Malfunction from Hot Full Power Conditions with Manual Rod Control Single-Loop Feedwater Control Valve Malfunction from Hot Full Power Conditions with Manual Rod Control Multi-Loop Feedwater Control Valve Malfunction from Hot Full Power Conditions-with Manual Rod Control Multi-Loop Feedwater Control Valve Malfunction from Hot Full Power Conditions with Manual Rod Control Multi-Loop Feedwater Control Valve Malfunction from Hot Full Power Conditions with Manual Rod Control Excessive Load Increase without Control Action, Beginning of Life Excessive Load Increase without Control Action, Beginning of Life Excessive Load Increase without Control Action, End of Life Excessive Load Increase without Control Action, End of Life Excessive Load Increase with Control Action, Beginning of Life 15-xvi Revision 18 April 26, 2000 ---***---*-

LIST OF FIGURES (Cont) 15.2-35 Excessive Load Increase with Control Action, Beginning of Life 15.2-36 Excessive Load Increase with Control Action, End of Life 15.2-37 Excessive Load Increase with Control Action, End of Life 15.2-38 Accidental RCS Depressurization 15.2-39 Accidental RCS 15.2-40 DELETED 15.2-41 DELETED 15.2-42 DELETED 15.2-43A DELETED 15.2-43B DELETED 15.2-43C DELETED 15.2-44 Spurious Actuation of Safety Injection System at Power 15.2-45 Spurious Actuation of Safety Injection System at Power 15.2-46 DELETED 15.3-1 Code Interface for Small Break Model 15.3-2 Small Break Hot Rod Power Shape Unit 1 15.2-2a Small Break Hot Rod Power Shape Unit 2 15.3-3 Small Break Safety Injection Flow Rate Unit 1 15.3-3a Small Break Safety Injection Flow Rate Unit 2 15-xvii SGS-UFSAR Revision 24 May 11, 2009 15.3-4 15.3-4a 15.3-5 15.3-5a 15.3-6 15.3-6a 15.3-7 15.3-7a 15.3-8 15.3-Sa 15.3-9 15.3-10 15.3-11 15.3-12 SGS-UFSAR LIST OF FIGURES (Cont) Reactor Coolant System Depressurization Transient (2-Inch Break, High TAVG) Unit 1 Reactor Coolant System Depressurization Transient (3-Inch Break) Unit 2 Core Mixture Level {2-Inch Break, High TAVG) Unit 1 Core Mixture Level (3-Inch Unit 2 Clad Average Temperature -Hot Rod (2-Inch Clad Hot Rod {3-Inch Break) Unit 2 Core Exit Steam Flow (2-Inch Break, High TAVG) Unit 1 Core Exit Steam Flow (3-Inch Break) Unit 2 Heat Transfer Coefficient -Hot Rod (2-Inch Break, High TAVG) Unit 1 Heat Transfer Coefficient Deleted Deleted Deleted Deleted Hot Rod (3-Inch Break) Unit 2 15-xviii Revision 25 October 26, 2010 LIST OF FIGURES (Cent} Title 15.3-13 Deleted 15.3-14 Complete Loss of Flow Undervoltage Event 15.3-15 Complete Loss of Flow Undervoltage Event 15.3-16a Complete Loss of Flow Underfrequency Event 15.3-17 15.3-17a 15.3-18 15.3-18a 15.3-19 15.3-19a 15.3-20 15.3-21 15.3-22 15.3-23 15.3-24 SGS-UFSAR Fluid Temperature -Hot Spot (2-Inch Unit 1 Fluid -Hot Spot (3-Inch Unit 2 Cold Leg Break Mass Flow (2-Inch Break, High TM8} Unit 1 Cold Leg Break Mass Flow (3-Inch Break} Unit 2 ECCS Pumped Safety Injection (2-Inch Break, High TMG) Unit 1 ECCS Pumped Safety Injection (3-Inch Break) Unit 2 Reactor Coolant System Depressurization Transient (4-Inch High Unit 1 Core Mixture Level (4-Inch High TAvG) Unit 1 Clad Average Temperature -Hot Rod (4-Inch Break, High Unit 1 Core Exit Steam Flow {4-Inch Break, Unit 1 Heat Transfer Coefficient -Hot Rod {4-Inch Break, High TAvG) Unit 1 15-xix Revision 25 October 26, 2010 15.3-25 15.3-26 15.3-27 15.3-28 15.3-29 15.3-30 15.3-31 15.3-32 15.3-33 15.3-34 15.3-35 15.3-36 15.3-37 15.3-38 15.3-39 15.3-40 15.3-41 I SGS-UFSAR LIST OF FIGURES (Cont) Title Fluid Temperature -Hot ( 4-Inch Break, High TAvG) Oni t 1 Cold Leg Break Mass Flow (4-Inch Break, High Unit 1 ECCS Pumped ection (4-Inch High TAvG) Unit 1 Reactor Coolant High TAvG) Oni t 1 zation Transient (3-Inch Core Mixture Level (3-Inch Break, High TAvG) Unit 1 Clad Average Temperature -Hot Rod (3-Inch Break, High TAw) Unit 1 Core Exit Steam Flow (3-Inch High ) Unit 1 Heat Transfer Coefficient -Hot Rod (3-Inch Break, Fluid Temperature -Hot Spot (3-Inch TAvG) Unit 1 Cold Leg Break Mass Flow ( 3-Inch Break, High TAvG) Unit 1 ECCS Pumped Safety Injection (3-Inch Break, High Unit 1 Reactor Coolant System Depressurization Transient (1.5-Inch Break, High TAvG) Unit 1 Core Mixture Level (1.5-Inch Break, High TAw) Unit 1 Clad Hot Rod (1.5-Inch Break, TAvG) Unit 1 Core Exit Steam Flow (1.5-Inch High TAvG) Unit 1 Heat Transfer Coefficient -Hot Rod ( 1. 5-Inch Break, High TAvG) Unit 1 Fluid -Hot ( 1. 5-Inch Break, High TAvG) Unit 1 15-xixa Revision 24 May 11, 2009 Figure 15.3-42 15.3-43 15.3-44 15.3-45 15.3-46 15.3-47 15.3-48 15.3-49 15.3-50 15.3-51 15.3-52 15.3-53 15.3-54 15.3-55 15.3-56 15.3-57 15.3-58 15.3-59 SGS-UFSAR LIST OF FIGURES (Cont) Title Cold Leg Break Mass Flow (1.5-Inch Break, High TAvG) Unit 1 ECCS Pumped Safety Injection (1.5-Inch Break, High Unit 1 Reactor Coolant System Depressurization Transient (2-Inch Break, Low TAvG) Unit 1 Core Mixture Level (2-Inch Break, Low TAvG) Unit 1 Clad Average Temperature -Hot Rod {2-Inch Break, Low 1 Core Exit Steam Flow (2-Inch Break, Low Unit 1 Heat Transfer Coefficient -Hot Rod (2-Inch Break, Low TAvG) Unit 1 Fluid Temperature -Hot Spot (2-Inch Break, Low Unit 1 Cold Leg Break Mass Flow (2-Inch Break, Low Unit 1 ECCS Pumped Injection (2-Inch Break, Low TAvG) Unit 1 Core Power Transient Reactor Coolant System Depressurization (4-Inch Break) Unit 2 Core Mixture Level (4-Inch Break) Unit 2 Clad Average Temperature -Hot Rod (4-Inch Break) Unit 2 Core Exit Steam Flow (4-Inch Break) Unit 2 Heat Transfer Coefficient -Hot Rod (4-Inch Break) Unit 2 Fluid Temperature -Hot Spot (4-Inch Break) Unit 2 Cold Leg Break Mass Flow (4-Inch Break) Unit 2 15-xixb Revision 24 May 11, 2009 15.3-60 15.3-61 15.3-62 15.3-63 15.3-64 15.3-65 15.3-66 15.3-67 15.3-68 15.3A 15.4-1 15.4-2 15.4-3 15.4-4 15.4-4A 15.4-48 15.4-4C 15.4-5 SGS-UFSAR LIST OF FIGURES {Cont) ECCS Pumped Safety Injection (4-Inch Break) Unit 2 Reactor Coolant System Depressurization Transient {2-Inch Break) Unit 2 Core Mixture Level (2-Inch Break) Unit 2 Clad Average -Hot Rod {2-Inch Break) Unit 2 Core Exit Steam Flow {2-Inch Break) Unit 2 Heat Transfer Coefficient -Hot Rod {2-Inch Break) Unit 2 Fluid Temperature -Hot Spot {2-Inch Break Unit 2 Cold Leg Break Mass Flow (2-Inch Break) Unit 2 ECCS Pumped Injection (2-Inch Break) Unit 2 All Figures Deleted Containment Wall Heat Transfer Coefficient {C0= 0.4 DECLG, Minimum SI I High TAVG) Break Flow (Co Break Energy (Co DELETED Fluid Quality (Co Fluid Quality (Co Fluid Quality (Co Fluid Quality (Co 0.4 DECLG, High TAvG) 0.4 DECLG, High TAvG) 0.4 DECLG, Minimum SI, 0.4 DECLG, Minimum SI, 0.4 DECLG, Minimum SI, 0.6 DECLG, Minimum SI, 15-xixc High TAvG) High TAvG) Low TAvG) High TAvG) Revision 24 May 11, 2009 15.4-6 15. 4-6A 15.4-7 15.4-7A 15.4-78 15.4-7C 15.4-8 15.4-9 15. 4-9A 15.4-10 15.4-10A 15.4-108 15.4-10C 15.4-11 15.4-12 15.4-12A 15.4-13 15. 4-13A 15.4-138 SGS-UFSAR LIST OF FIGURES (Cont) Fluid Quality (C0 = 0.8 DECLG, Minimum SI, High DELETED DELETED Mass Velocity (Co 0.4 DECLG, Minimum SI, High TAvG) Mass Velocity (Co 0.4 DECLG, Maximum SI, High TAvG) Mass Velocity (Co 0.4 DECLG, Minimum SI, Low TAvG} Mass Velocity (Co 0.6 DECLG, Minimum SI, High TAvG) Mass Velocity (Co 0.8 DECLG, Minimum SI, High TAvG) DELETED DELETED Heat Transfer Coefficient (C0 0. 4 DECLG, Minimum SI, High TAvG) Heat Transfer Coefficient (Cn 0.4 DECLG, Maximum SI, High TAvG) Heat Transfer Coefficient (C0 0. 4 DECLG, Minimum SI, Low TAvGl Heat Transfer Coefficient (C0 0. 6 DECLG, Minimum SI, High TAvG) Heat Transfer Coefficient (C0 0. 8 DECLG, Minimum SI, High TAvG) DELETED DELETED Core Pressure (C0 0. 4 DECLG, High TAvG) Core Pressure (C0 0. 4 DECLG, Low TAvG) 15-xixd Revision 24 May 11, 2009 15.4-14 Core Pressure 15.4-15 Core Pressure 15.4-16 DELETED 15.4-16A Break Flow (Cn 15.4-16B Break Flow {CD 15.4-17 Break Flow (Co 15.4 18 Break Flow (Co SGS-UFSAR LIST OF FIGURES (Cont) (CD 0.6 DECLG, Minimum SI, High TAvG) 0.8 DECLG, Minimum SI, High 0.4 DECLG, High 0.4 DECLG, Low TAvG) 0.6 DECLG, Minimum SI, TAvGl 0.8 DECLG, Minimum SI, High TAvG) 15-:xx Revision 24 May 11, 2009 Figure 15.4-19 15.4-19A 15.4-198 15.4-20 15.4-21 15.4-22 15.4-22A 15.4-228 15.4-22C 15.4-23 15.4-23A 15.4-24 15.4-25 15.4-25A 15.4-258 l5.4-25C 15.:4-26 15.4-26A 15.4-27 SGS-UFSAR f LIST OF FIGURES (Cont) Deleted Core Pressure Drop (C0 = 0.4 OECLG, High TAVG) Cora Pressure Drop (C0 = 0.4 DECLG, Low TAVG) Core Pressure Drop (C0

  • 0.6 OECLG, Minimum SI, High TAVG) Core Pressure Drop (C
  • 0.8 DECLG, MinLmum SI, High T ) D AVG Deleted Clad Average Temperature (C0
  • 0.4 DECLG, Minimum SI, High TAVG) (VANTAGE+ with IFMs fuel) Clad Average Temperature (CD
  • 0.4 DECLG, Maximum SI, High TAVG) Clad Average Temperature (C0 = 0.4 DECLG, Minimum SI, Low TAVG) Clad Average Temperature {C0
  • 0.6 DECLG, Minimum SI, High TAVG) Deleted Clad Average Temperature (CD
  • 0.8 DECLG, Minimum SI, High TAVG) Deleted Fluid Temperature (Co -0.4 Fluid Temperature (CD -0.4 Fluid Temperature (C
  • D 0.4 Fluid Temperature (CD = 0 .. 6 Deleted Fluid Temperature (CD = 0.8 DECLG, Minimum SI, High TAVG) DECLG, Maximum SI, High TAVG) OECLG, Minimum SI, Low TAVG) DECLG, Minimum SI, High TAVG) DECLG, Minimum SI, High T ) AVG 15-xxi Revision 15 June 12, 1996 Figure 15.4-28 15.4-28A 15.4-288 15.4-29 15.4-30 15.4-31 15.4-31A 15.4-318 15.4-31C 15.4-32 15.4-32A 15.4-33 15.4-34 15.4-34A 15.4-348 15.4-34C 15.4-35 15.4-3SA SGS-UFSAR LIST OF FIGURES (Cent) Deleted Core Flowrate (C c D 0.4 DECLG, High TAVG) Core Flowrate (CD
  • 0.4 DECLG, Low TAVG) Core Flowrate (CD c 0.6 DECLG, Minimum SI, High TAVG} Core Flowrate (CD -0.8 DECLG, Minimum SI, High TAVG} Deleted Water Level (CD -0.4 DECLG, Minimum SI, High TAVG) Water Level (CD -0.4 DECLG, Maximum SI, High TAVG) Water Level (C
  • 0 0.4 DECLG, Minimum SI, Low T ) AVG Water Level (CO = 0.6 DECLG, Minimum SI, High TAVG) Deleted Water Level (CD
  • 0.8 DECLG, Minimum SI, High TAVG) Deleted Flood Rate Flood Rate Flood Rate Flood Rate Deleted (C
  • D 0.4 DECLG, Minimum SI, (CD = 0.4 DECLG, Maximum SI, (CD -0.4 OECLG, Minimum SI, (C0
  • 0.6 DECLG, Minimum SI, 15-xxii High TAVG) High TAVG) Low TAVG) High TAVG) Revision 15 June 12, 1996 f Figure 15.4-36 15.4-37 15.4-37A 15.4-378 15.4-38 15.4-39 15.4-40 15.4-40A 15.4-408 ,__ 15.4-40C 15.4-41 15.4 -41A 15.4-42 15.4-43 15.4-4 3A 15.4-438 15.4-43C 15.4-44 15.4-44A SGS-UFSAR LIST OF FIGURES (Cont) Title Flood Rate (C0 0. 8 DECLG, Minimum SI, High TAvG) Deleted Accumulator Flow (C0 0. 4 DECLG, High TAvG) Accumulator Flow (C0 0. 4 DECLG, Low TAvG) Accumulator Flow (C0 0.6 DECLG, Minimum SI, High TAvG) Accumulator Flow (C0 0. 8 DECLG, Minimum SI, High TAvG) Deleted Pumped ECCS Flow (Reflood) (Co 0. 4 DECLG, Minimum SI, High TAvG) Pumped ECCS Flow (Reflood) (C0 0. 4 DECLG, Maximum SI, High TAvG) Pumped ECCS Flow (Reflood) {C0 0. 4 DECLG, Minimum SI, Low TAvG} Pumped ECCS Flow (Reflood) (Co 0. 6 DECLG, Minimum SI, High TAvG) Deleted Pumped ECCS Flow (Reflood) {C0 0. 8 DECLG, Minimum SI, High TAvG} Deleted Containment Pressure {C0 0. 4 DECLG, Minimum SI, High TAvG} Containment Pressure (C0 Containment Pressure (C0 Containment Pressure (C0 Deleted 0.4 DECLG, Maximum SI, High TAvG) 0. 4 DECLG, Minimum SI, Low TAvG) 0. 6 DECLG, Minimum SI, High TAvG) 15-xxiii Revision 15 June 12, 1996 Figure 15.4-45 15.4-46 15.4-46A 15.4-468 15.4-47 15.4-47A 15.4-478 15.4-47C I 15.4-48 15.4-49 15.4-50 15.4-SOA 15.4-SOB 15.4-SOC 15.4-500 15.4-SOE 15.4-SOF SGS-UFSAR LIST OF FIGURES (Cont) Title Containment Pressure (C0 0.8 DECLG, Minimum SI, High T1wG) Deleted Power (Co """ 0. 4 DECLG, High TAvG) Power (C0 0. 4 DECLG, Low TAvG) Power (C0 0. 6 DECLG, Minimum SI, High TAvG) DELETED DELETED DELETED Variation of kef£ with Moderator Temperature -Unit 2 Variation of Reactivity with Power at Constant Core Average Temperature Variation of kef£ with Moderator Temperature -Unit 1 DELETED DELETED DELETED DELETED DELETED DELETED 15-xxiiia Revision 19 November 19, 2001 -

Figure 15.4-SlA 15.4-518 15.4-51C 15.4-510 15.4-51E 15.4-51F 15.4-52A 15.4-528 15.4-52C 15.4-520 15.4-52E 15.4-52F SGS-UFSAR LIST OF FIGURES {Cont) Title Steam Line Break at Exit of Steam Generator with Offsite Power Stearn Line Break at Exit of Stearn Generator with Offsite Power Steam Line Break at Exit of Stearn Generator with Offsite Power DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED DELETED 15-x:x.iiib Revision 19 November 19, 2001 Figure 15. 4-53A 15.4-538 15.4-53C 15.4-53D 15.4-53E 15.4-53F 15.4-54 15.4-55 15.4-56 15.4-57 15.4-58 15.4-59 SGS-UFSAR LIST OF FIGURES (Cont) Title DELETED DELETED DELETED DELETED DELETED DELETED DELETED Power (Co 0.8 DECLG, Minimum SI, High Tavg) Clad Average Temperature {Vantage 5H without IFMs fuel} Clad Average Temperature (Vantage SH without IFMs, with IFBA fuel} Clad Average Temperature (Vantage + with IFMs and IFBA fuel) DELETED 15-xxiv Revision 19 November 19, 2001 -

Figure 15.4-60 15.4-60A 15.4-608 15.4-60C 15.4-600 15.4-60E 15.4-60F 15.4-60G 15.4-60H 15.4-61 SGS-UFSAR LIST OF FIGURES (Cant) Title Deleted Major Rupture of a Main Feedwater Pipe With Offsite Power Major Rupture of a Main Feedwater Pipe With Offsite Power Major Rupture of a Main Feedwater Pipe With Offsite Power Major Rupture of a Main Feedwater Pipe With Offsite Power Major Rupture of a Main Feedwater Pipe Without Offsite Power Major Rupture of a Main Feedwater Pipe Without Offsite Power Major Rupture of a Main Feedwater Pipe Without Offsite Power Major Rupture of a Main Feedwater Pipe Without Offsite Power Break and Injected Mass Flow Rates 15-xxiva Revision 19 November 19, 2001 I THIS PAGE INTENTIONALLY BLANK 15-xxivb SGS-UFSAR Revision 11 July 22, 1991 Figure 15.4-62 15.4-63 15.4-64 15.4-65 15.4-66 15.4-67 15.4-68 15.4-69 15.4-70 ( 15.4-71 15.4-72 SGS-UFSAR LIST OF FIGURES (Cant) DELETED DELETED DELETED DELETED DELETED DELETED Single Reactor Coolant Pump Locked Rotor Single Reactor Coolant Pump Locked Rotor Single Reactor Coolant Pump Locked Rotor DELETED -DELETED 15-xxv Revision 18 April 26, 2000 Figure 15.4-73 15.4-74 15.4-75 15.4-76 15.4-77 15. 4-78A 15.4-788 15.4-79 15.4-80 15.4-81 15.4-82 15.4-83 15.4-84 SGS-UFSAR LIST OF FIGURES (Cont} Title DELETED DELETED DELETED RCCA Ejection Accident, Beginning of Life, Hot Full Power RCCA Ejection Accident, Beginning of Life, Hot Zero Power RCCA Ejection Accident, End of Life*, Hot Full Power RCCA Ejection Accident, End of Life, Hot Zero Power Schematic of REFLOOD Code -19 Element Loop Model Transient Core Inlet Temperature versus Time after Bottom of Core Recovery Variation in Temperature Rise, Turnaround Time, and Quench Time with Elevation Fraction of Inlet Coolant Flow Leaving Core as a Steam/Water Mixture versus Time after Bottom of Core Recovery Energy Balance Model Post Reflood Loop Resistance Model 15-xxvi Revision 18 April 26, 2000 ( '--

15.4-85 15.4-86 15.4-87 15.4-88 15.4-89 15.4-90 15.4-91 15.4-92 15.4-93 15.4-94 15.4-95 15.4-96 15.4-97 15.4-98 SGS-UFSAR LIST OF FIGURES (Cont) DELETED Salem Unit 2 Double-ended Pump Suction Break with Minimum Safeguards Containment Pressure Salem Unit 2 Double-ended Pump Suction Break with Minimum Safeguards Containment Steam Temperature Salem Unit 2 Double-ended Pump Suction Break with Maximum Safeguards Containment Pressure Salem Unit 2 Double-ended Pump Suction Break with Maximum Safeguards Containment Steam Temperature Salem Unit 2 Double-ended Hot Leg Break Containment Pressure Salem Unit 2 Double-ended Hot Leg Break Containment Steam Temperature DELETED Pump Curves for Auxiliary Feed Pumps/Steam Driven Pump Curves -Auxiliary Feed Pump/Electrical Driven DELETED Fan Cooler Heat Removal Rate Steam Line Rupture Mass and Energy Releases DER, Feedwater Control Valve Failure 30% Power, 4. 6 Containment Response to Steam Line Rupture -30% Power, 4. 6 ft2 DER, Feedwater Control Valve Failure 15-xxvii Revision 24 May 11, 2009 Figure 15.4-99 15.4-100 15.4-101 15.4-102 15.4-103 15.4-104 15.4-105 15.4-106 15.4-107 15.4-108 SGS-UFSAR LIST OF FIGURES (Cont) Title ---Steam Line Rupture Mass and Energy Releases -102% Power, 0.6 ft2 Small DER, Main Steam Isolation Valve Failure Containment Response to Steam Line Rupture -102% Power, 0.6 ft2 Small DER, Main Steam Isolation Valve Failure Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted 15-xxviii Revision 15 June 12, 1996 ... -

Figure 15.4-109 Deleted 15.4-110 Deleted 15.4-111 Deleted SGS-UFSAR LIST OF FIGURES (Cont) 15-xxix Revision 9 July 22, 1989 I I '

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