Text

Clinton Power Station, Unit 1, Revision 19 to Updated Safety Analysis Report, Chapter 6, Engineered Safety Features (Redacted)
	ML17354A206
Person / Time
Site:	Clinton
Issue date:	12/20/2017
From:	Rankin J K; Plant Licensing Branch III
To:	; Exelon Generation Co
	Rankin J K, NRR/DORL/LPLIIII, 415-1530
References
	Download: ML17354A206 (587)
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{{#Wiki_filter:CPS/USAR CHAPTER 06 6-i REV. 13, JANUARY 2009 CHAPTER 6 - ENGINEERED SAFETY FEATURES TABLE OF CONTENTS PAGE 6 ENGINEERED SAFETY FEATURES 6.1-1 6.0 GENERAL 6.1-1 6.1 ENGINEERED SAFETY FEATURE MATERIALS 6.1-1 6.1.1 Metallic Materials 6.1-2 6.1.1.1 Materials Selection and Fabrication 6.1-2 6.1.1.1.1 Material Specifications 6.1-2 6.1.1.1.2 Compatibility of Construction Materials with Core Cooling Water and Containment Sprays 6.1-2 6.1.1.1.3 Controls for Austenitic Stainless Steel 6.1-2 6.1.1.2 Composition, Compatibility, and Stability of Containment and Core Spray Coolants 6.1-3 6.1.2 Organic Materials 6.1-3 6.1.2.1 Protective Coatings 6.1-3 6.1.3 References 6.1-4 6.2 CONTAINMENT SYSTEMS 6.2-1 6.2.1 Containment Functional Design 6.2-1 6.2.1.1 Containment Structure 6.2-1 6.2.1.1.1 Design Bases 6.2-1 6.2.1.1.2 Design Features 6.2-2 6.2.1.1.2.1 Protection from the Dynamic Effects of Postulated Accidents 6.2-2 6.2.1.1.2.2 Codes and Standards 6.2-2 6.2.1.1.2.3 Qualification Tests 6.2-2 6.2.1.1.2.4 Protection Against External Pressure Loads 6.2-2 6.2.1.1.2.5 Potential Water Traps Inside Containment 6.2-3 6.2.1.1.2.6 Containment Cooling and Ventilation Systems 6.2-3 6.2.1.1.3 Design Evaluation 6.2-3 6.2.1.1.3.1 Summary Evaluation 6.2-3 6.2.1.1.3.2 Containment Design Parameters 6.2-4 6.2.1.1.3.3 Accident Response Analysis 6.2-4 6.2.1.1.3.3.1 Recirculation Line Break 6.2-5 6.2.1.1.3.3.1.1 Assumptions for Reactor Blowdown 6.2-5 6.2.1.1.3.3.1.2 Assumptions for Containment Pressurization 6.2-6 6.2.1.1.3.3.1.3 Assumptions for Long-Term Cooling 6.2-7 6.2.1.1.3.3.1.4 Initial Conditions for Accident Analysis 6.2-7 6.2.1.1.3.3.1.5 Short-Term Accident Response 6.2-8 6.2.1.1.3.3.1.6 Long-Term Accident Responses 6.2-8 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-ii REV. 13, JANUARY 2009 6.2.1.1.3.3.1.7 Energy Balance During Accident 6.2-10 6.2.1.1.3.3.1.8 Chronology of Accident Events 6.2-10 6.2.1.1.3.3.2 Main Steamline Break 6.2-10 6.2.1.1.3.3.2.1 Assumptions for Reactor Blowdown 6.2-10 6.2.1.1.3.3.2.2 Assumptions for Containment Pressurization 6.2-11 6.2.1.1.3.3.2.3 Assumptions for Long-Term Cooling 6.2-11 6.2.1.1.3.3.2.4 Initial Conditions for Accident Analyses 6.2-11 6.2.1.1.3.3.2.5 Short-Term Accident Response 6.2-11 6.2.1.1.3.3.2.6 Long-Term Accident Responses 6.2-12 6.2.1.1.3.3.2.7 Energy Balance During Accident 6.2-12 6.2.1.1.3.3.2.8 Chronology of Accident Events 6.2-13 6.2.1.1.3.3.3 Hot Standby Accident Analysis 6.2-13 6.2.1.1.3.3.4 Intermediate Size Breaks 6.2-14 6.2.1.1.3.3.5 Small Size Breaks 6.2-15 6.2.1.1.3.3.5.1 Reactor System Blowdown Considerations 6.2-15 6.2.1.1.3.3.5.2 Containment Response 6.2-15 6.2.1.1.3.3.5.3 Recovery Operations 6.2-16 6.2.1.1.3.3.5.4 Drywell Design Temperature Considerations 6.2-16 6.2.1.1.3.4 Accident Analysis Models 6.2-16 6.2.1.1.3.4.1 Short-Term Pressurization Model 6.2-16 6.2.1.1.3.4.2 Long-Term Cooling Mode 6.2-16 6.2.1.1.3.5 High Energy Line Rupture Within the Containment 6.2-16 6.2.1.1.4 Negative Pressure Design Evaluation 6.2-17 6.2.1.1.4.1 Evaluation of Drywell Negative Differential Pressure 6.2-17 6.2.1.1.4.2 Evaluation of Containment Negative Pressure 6.2-18 6.2.1.1.5 Steam Bypass of the Suppression Pool 6.2-19 6.2.1.1.5.1 Introduction 6.2-19 6.2.1.1.5.2 Criteria 6.2-20 6.2.1.1.5.3 Analysis 6.2-20 6.2.1.1.5.4 Bypass Capability Without Containment Spray and Heat Sinks 6.2-21 6.2.1.1.5.5 Bypass Capability With Containment Spray Heat Sinks 6.2-22 6.2.1.1.6 Suppression Pool Dynamic Loads 6.2-23 6.2.1.1.7 Asymmetric Loading Conditions 6.2-24 6.2.1.1.8 Containment Environmental Control 6.2-24 6.2.1.1.9 Postaccident Monitoring 6.2-24 6.2.1.2 Containment Subcompartments 6.2-24 6.2.1.2.1 Design Basis 6.2-25 6.2.1.2.1.1 Drywell Head Cavity 6.2-25 6.2.1.2.1.2 Shield Annulus 6.2-26 6.2.1.2.1.2.1 Recirculation Outlet Line Break 6.2-26 6.2.1.2.1.2.2 Feedwater Line Break 6.2-27 6.2.1.2.1.2.3 Recirculation Inlet Line Break 6.2-27 6.2.1.2.1.3 Containment Pipe Tunnel 6.2-28 6.2.1.2.1.4 RWCU Heat Exchanger Subcompartments 6.2-28 6.2.1.2.1.5 RWCU Valve Subcompartments 6.2-28 6.2.1.2.1.6 RWCU Crossover Pipe Tunnel 6.2-29 6.2.1.2.1.7 RWCU Filter-Demineralizer Holding Pump Compartment 6.2-29 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-iii REV. 13, JANUARY 2009 6.2.1.2.1.8 RWCU Filter-Demineralizer Subcompartments 6.2-29 6.2.1.2.1.9 RWCU Filter-Demineralizer Valve Subcompartment 6.2-29 6.2.1.2.2 Design Features 6.2-29 6.2.1.2.2.1 Drywell Head Cavity 6.2-29 6.2.1.2.2.2 Shield Annulus 6.2-30 6.2.1.2.2.2.1 Recirculation Outlet Line Break 6.2-30 6.2.1.2.2.2.2 Feedwater Line Break 6.2-30 6.2.1.2.2.2.3 Recirculation Inlet Line Break 6.2-31 6.2.1.2.2.3 Containment Pipe Tunnel 6.2-31 6.2.1.2.2.4 RWCU Heat Exchanger Subcompartments 6.2-32 6.2.1.2.2.5 RWCU Valve Subcompartments 6.2-32 6.2.1.2.2.6 RWCU Crossover Pipe Tunnel 6.2-32 6.2.1.2.2.7 RWCU Filter-Demineralizer Holding Pump Subcompartment 6.2-32 6.2.1.2.2.8 RWCU Filter-Demineralizer Subcompartments 6.2-32 6.2.1.2.2.9 RWCU Filter-Demineralizer Valve Subcompartment 6.2-33 6.2.1.2.3 Design Evaluation 6.2-33 6.2.1.2.3.1 Drywell Head Cavity 6.2-33 6.2.1.2.3.1.1 Head Spray Line Break 6.2-33 6.2.1.2.3.1.2 Recirculation Outlet Line Break 6.2-34 6.2.1.2.3.2 Shield Annulus 6.2-35 6.2.1.2.3.2.1 Recirculation Outlet Line Break 6.2-36 6.2.1.2.3.2.2 Feedwater Line Break 6.2-38 6.2.1.2.3.2.3 Recirculation Inlet Line Break 6.2-39 6.2.1.2.3.3 Containment Pipe Tunnel 6.2-40 6.2.1.2.3.4 RWCU Heat Exchanger Subcompartments 6.2-41 6.2.1.2.3.5 RWCU Valve Subcompartments 6.2-41 6.2.1.2.3.6 RWCU Crossover Pipe Tunnel 6.2-41 6.2.1.2.3.7 RWCU Filter-Demineralizer Holding Pump Subcompartment 6.2-42 6.2.1.2.3.8 RWCU Filter-Demineralizer Subcompartments 6.2-42 6.2.1.2.3.9 RWCU Filter-Demineralizer Valve Subcompartments 6.2-42 6.2.1.3 Mass and Energy Release Analysis for Postulated Loss-of-Coolant Accidents 6.2-43 6.2.1.3.1 Mass and Energy Release Data 6.2-43 6.2.1.3.2 Energy Sources 6.2-43 6.2.1.3.3 Reactor Blowdown Model Description 6.2-44 6.2.1.3.4 Effects of Metal-Water Reaction 6.2-44 6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures Inside Containment (PWR) 6.2-44 6.2.1.5 Minimum Containment Pressure Analysis for Performance Capability Studies on Emergency Core Cooling System (PWR) 6.2-44 6.2.1.6 Testing and Inspection 6.2-44 6.2.1.7 Instrumentation Requirements 6.2-44 6.2.2 Containment Heat Removal Systems 6.2-45 6.2.2.1 Design Bases 6.2-45 6.2.2.2 System Design 6.2-46 6.2.2.3 Design Evaluation 6.2-49 6.2.2.3.1 Summary of Containment Cooling Analysis 6.2-50 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-iv REV. 13, JANUARY 2009 6.2.2.4 Tests and Inspections 6.2-51 6.2.2.5 Instrumentation Requirements 6.2-51 6.2.3 Secondary Containment Functional Design 6.2-51 6.2.3.1 Design Basis 6.2-51 6.2.3.2 System Design 6.2-52 6.2.3.3 Design Evaluation 6.2-53 6.2.3.3.1 Standby Gas Treatment System 6.2-53 6.2.3.3.2 Secondary Containment System 6.2-54 6.2.3.3.2.1 Short-Term Pressure History 6.2-54 6.2.3.3.2.2 Long-Term Temperature Analysis 6.2-57 6.2.3.4 Tests and Inspections 6.2-59 6.2.3.5 Instrumentation Requirement 6.2-59 6.2.4 Containment Isolation System 6.2-59 6.2.4.1 Design Bases 6.2-60 6.2.4.2 System Design 6.2-60 6.2.4.3 Design Evaluation 6.2-63 6.2.4.3.1 Introduction 6.2-63 6.2.4.3.2 Evaluation Against General Design Criteria 6.2-63 6.2.4.3.2.1 Evaluation Against Criterion 55 6.2-63 6.2.4.3.2.1.1 Influent Lines 6.2-64 6.2.4.3.2.1.1.1 Feedwater Lines 6.2-64 6.2.4.3.2.1.1.2 HPCS Line 6.2-64 6.2.4.3.2.1.1.3 LPCI and LPCS Lines 6.2-64 6.2.4.3.2.1.1.4 Control Rod Drive Lines 6.2-65 6.2.4.3.2.1.1.5 RHR and RClC Lines 6.2-65 6.2.4.3.2.1.1.6 Standby Liquid Control System Lines 6.2-66 6.2.4.3.2.1.2 Effluent Lines 6.2-66 6.2.4.3.2.1.2.1 Main and RCIC Steamlines 6.2-66 6.2.4.3.2.1.2.2 Reactor Water Cleanup System Lines 6.2-66 6.2.4.3.2.1.2.3 Recirculation System Sample Lines 6.2-67 6.2.4.3.2.1.2.4 RHR Shutdown Cooling Line 6.2-67 6.2.4.3.2.1.3 Summary 6.2-67 6.2.4.3.2.2 Evaluation Against Criterion 56 6.2-67a 6.2.4.3.2.2.1 Influent Lines to Suppression Pool 6.2-68 6.2.4.3.2.2.1.1 LPCS, HPCS, and RHR Test and Pump Minimum Flow Bypass Lines 6.2-68 6.2.4.3.2.2.1.2 RCIC Turbine Exhaust and Pump Minimum Flow Bypass Lines 6.2-69 6.2.4.3.2.2.1.3 RHR Heat Exchanger Vent and Relief Valve Discharge Lines 6.2-69 6.2.4.3.2.2.2 Effluent Lines from Suppression Pool 6.2-69 6.2.4.3.2.2.3 Containment Influent and Effluent Lines 6.2-69 6.2.4.3.2.2.3.1 Combustible Gas Control 6.2-69 6.2.4.3.2.2.3.2 Standby Liquid Control System 6.2-70 6.2.4.3.2.2.3.3 Other Lines 6.2-70 6.2.4.3.2.2.3.4 Containment Atmosphere Monitoring System 6.2.70 6.2.4.3.2.2.4 Summary 6.2-71 6.2.4.3.2.3 Evaluation Against Criterion 57 6.2-71 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-v REV. 13, JANUARY 2009 6.2.4.3.2.4 Evaluation Against Regulatory Guide 1.1 6.2-71 6.2.4.3.3 Failure Mode and Effects Analyses 6.2-71 6.2.4.3.4 Secondary Containment Bypass Leakage 6.2-72 6.2.4.4 Tests and Inspections 6.2-72 6.2.5 Hydrogen Mitigation in Containment 6.2-73 6.2.5.1 Combustible Gas Control System (CGCS) 6.2-73 6.2.5.1.1 Design Bases 6.2-74 6.2.5.1.2 System Design 6.2-75 6.2.5.1.2.1 Principles of Operation 6.2-75 6.2.5.1.2.2 Atmosphere Mixing 6.2-75 6.2.5.1.2.2.1 Location of Combustible Gas Control System Suction and Discharge Points 6.2-76 6.2.5.1.2.3 Containment Atmosphere H2/O2 Monitoring Subsystem Sample Points 6.2-76 6.2.5.1.2.4 Combustible Gas Control System 6.2-77 6.2.5.1.2.4.1 Drywell - Containment Mixing System 6.2-77 6.2.5.1.2.4.2 Hydrogen Recombiner System 6.2-78 6.2.5.1.2.5 Purge System 6.2-79 6.2.5.1.3 Design Evaluation 6.2-79 6.2.5.1.3.1 General 6.2-79 6.2.5.1.3.2 Sources of Hydrogen 6.2-79 6.2.5.1.3.2.1 Short-Term Hydrogen Generation 6.2-80 6.2.5.1.3.2.2 Long-Term Hydrogen Generation 6.2-80 6.2.5.1.3.3 Accident Description 6.2-81 6.2.5.1.3.4 Analysis 6.2-82 6.2.5.1.4 Tests and Inspections 6.2-83 6.2.5.1.5 Instrumentation Requirements 6.2-83 6.2.5.2 Hydrogen Ignition System (HIS) 6.2-83 6.2.5.2.1 Design Bases 6.2-84 6.2.5.2.2 System Description 6.2-84 6.2.5.2.2.1 Location Criteria 6.2-84 6.2.5.2.2.2 Igniter Locations 6.2-85 6.2.5.2.2.3 Igniter Assembly Description 6.2-85 6.2.5.2.2.4 Igniter Supports 6.2-85 6.2.5.2.2.5 Power Supplies 6.2-86 6.2.5.2.3 HIS Component Qualification 6.2-86 6.2.5.2.4 System Operation 6.2-87 6.2.5.2.4.1 Initiation Criteria 6.2-87 6.2.5.2.4.2 Duration of Operation 6.2-87 6.2.5.2.5 Tests and Inspections 6.2-87 6.2.5.2.5.1 Preoperational Testing 6.2-87 6.2.5.2.5.2 Surveillance Testing 6.2-88 6.2.5.2.6 Instrumentation and Controls 6.2-88 6.2.5.2.6.1 Trips 6.2-88 6.2.5.2.6.2 Indication 6.2-88 6.2.5.2.6.3 Alarms 6.2-88 6.2.6 Containment Leakage Testing 6.2-88 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-vi REV. 16, JANUARY 2014 6.2.6.1 Containment Integrated Leak Rate Test 6.2-89 6.2.6.2 Containment Penetration Leak Rate Test 6.2-90 6.2.6.3 Containment Isolation Valve Leak Rate Test 6.2-92 6.2.6.4 Scheduling and Reporting of Periodic Tests 6.2-94 6.2.6.5 Special Testing Requirements 6.2-94 6.2.6.5.1 Drywell Leakage Rate Test 6.2-94 6.2.6.5.2 Bypass Leakage Testing 6.2-95 6.2.6.5.3 Secondary Containment Testing 6.2-95 6.2.6.5.4 Isolation Valve Leakage Control System 6.2-95 6.2.6.5.5 Containment Penetration Draining 6.2-95 6.2.7 Suppression Pool Makeup System 6.2-95a 6.2.7.1 Design Basis 6.2-96 6.2.7.2 System Design 6.2-97 6.2.7.3 System Evaluation 6.2-98 6.2.7.3.1 Initiation 6.2-98 6.2.7.3.2 Long-Term Vent Coverage 6.2-98 6.2.7.3.3 Inadvertent Dump 6.2-98 6.2.7.3.4 Long-Term Heat Sink Capability 6.2-99 6.2.7.3.5 Mode 3 Suppression Pool Makeup 6.2-99 6.2.7.4 Testing 6.2-100 6.2.7.5 Instrumentation 6.2-100 6.2.7.6 Materials 6.2-101 6.2.8 Humphrey Concerns 6.2-101 6.2.9 References 6.2-101 6.3 EMERGENCY CORE COOLING SYSTEM 6.3-1 6.3.1 Design Bases 6.3-1 6.3.1.1 Design Bases and Summary Description 6.3-1 6.3.1.1.1 Performance and Functional Requirements 6.3-1 6.3.1.1.2 Reliability Requirements 6.3-1 6.3.1.1.3 ECCS Requirements for Protection from Physical Damage 6.3-3 6.3.1.1.4 ECCS Environmental Design Basis 6.3-4 6.3.1.2 Summary Descriptions of ECCS 6.3-5 6.3.1.2.1 High-Pressure Core Spray 6.3-5 6.3.1.2.2 Low-Pressure Core Spray 6.3-5 6.3.1.2.3 Low-Pressure Coolant Injection 6.3-6 6.3.1.2.4 Automatic Depressurization System 6.3-6 6.3.2 System Design 6.3-6 6.3.2.1 Schematic Piping and Instrumentation Diagrams 6.3-6 6.3.2.2 Equipment and Component Descriptions 6.3-6 6.3.2.2.1 High-Pressure Core Spray (HPCS) System 6.3-9 6.3.2.2.2 Automatic Depressurization System (ADS 6.3-12 6.3.2.2.3 Low-Pressure Core Spray (LPCS) System 6.3-12 6.3.2.2.4 Low-Pressure Coolant Injection (LPCI) System 6.3-15 6.3.2.2.5 ECCS Discharge Line Fill System 6.3-17 6.3.2.2.6 Gas Management Program 6.3.18 6.3.2.3 Applicable Codes and Classifications 6.3-18 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-vii REV. 19, OCTOBER 2017 6.3.2.4 Materials Specifications and Compatibility 6.3-18a 6.3.2.5 System Reliability 6.3-18a 6.3.2.6 Protection Provisions 6.3-19 6.3.2.7 Provisions for Performance Testing 6.3-20 6.3.2.8 Manual Actions 6.3-20 6.3.3 ECCS Performance Evaluation 6.3-22 6.3.3.1 ECCS Bases for Technical Specifications 6.3-24 6.3.3.2 Acceptance Criteria for ECCS Performance 6.3-24 6.3.3.3 Single Failure Considerations 6.3-25 6.3.3.4 System Performance During the Accident 6.3-25 6.3.3.5 Use of Dual Function Components for ECCS 6.3-25 6.3.3.6 Limits on ECCS Parameters 6.3-26 6.3.3.7 ECCS Analyses for LOCA 6.3-26 6.3.3.7.1 LOCA Analysis Procedures and Input Variables 6.3-26 6.3.3.7.1.1 Description of Models 6.3-26 6.3.3.7.1.2 Analysis Procedure 6.3-27 6.3.3.7.1.3 Input to Analysis 6.3-29 6.3.3.7.2 Accident Description 6.3-30 6.3.3.7.3 Break Spectrum Calculations 6.3-31 6.3.3.7.3.1 Recirculation Line Breaks 6.3-31 6.3.3.7.3.2 Non-Recirculation Line Breaks 6.3-32 6.3.3.7.4 Compliance Evaluations 6.3-32 6.3.3.7.4.1 Licensing Basis PCT Evaluation 6.3-32 6.3.3.7.4.2 Upper Bound PCT Evaluation 6.3-33 6.3.3.7.5 Alternate Operating Mode Considerations 6.3-33 6.3.3.7.5.1 Maximum Extended Load Line Limit (MELLL) 6.3-33 6.3.3.7.5.2 Increase Core Flow 6.3-34 6.3.3.7.5.3 Feedwater Temperature Reduction (FWTR) 6.3-34 6.3.3.7.5.4 Single-Loop Operation (SLO) 6.3-34 6.3.3.7.6 MAPLHGR Limits 6.3-34 6.3.3.7.7 Summary of SAFER/GESTR Analysis Results 6.3-34 6.3.3.7.8 An Analysis to Show that Diversion of ECCS to Containment Cooling at or more than 10 Minutes After a LOCA Will Not Result in Exceeding Any Safety Criteria for the Entire Break Spectrum with Consideration of a Single Failure 6.3-35 6.3.3.7.8.1 Purpose 6.3-35 6.3.3.7.8.2 Analysis Models and Methodology 6.3-35 6.3.3.7.8.3 Analysis Input 6.3-35 6.3.3.7.8.4 Analysis 6.3-35 6.3.3.7.8.5 Conclusions from LPCI Diversion Study 6.3-37 6.3.3.7.9 Inadvertent Closure of the Reactor Recirculation System Line Suction Valve as a Single Failure in the LOCA Analysis, for the Break Size Most Affected by this Failure 6.3-37 6.3.3.8 LOCA Analysis Conclusions 6.3-37 6.3.4 Tests and Inspections 6.3-37 6.3.4.1 ECCS Performance Tests 6.3-37 6.3.4.2 Reliability Tests and Inspections 6.3-37 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-viii REV. 15, JANUARY 2013 6.3.4.2.1 HPCS Testing 6.3-38 6.3.4.2.2 ADS Testing 6.3-39 6.3.4.2.3 LPCS Testing 6.3-39 6.3.4.2.4 LPCI Testing 6.3-39 6.3.5 Instrumentation Requirements 6.3-39 6.3.6 References 6.3-41 6.4 HABITABILITY SYSTEMS 6.4-1 6.4.1 Design Basis 6.4-1 6.4.2 System Design 6.4-2 6.4.2.1 Definition of Control Room Envelope 6.4-2 6.4.2.2 Ventilation System Design 6.4-2 6.4.2.3 Leak Tightness 6.4-2 6.4.2.4 Interaction with Other Zones and Pressure-Containing Equipment 6.4-3 6.4.2.5 Shielding Design 6.4-3 6.4.3 System Operating Procedures 6.4-4 6.4.4 Design Evaluations 6.4-4 6.4.4.1 Radiological Protection 6.4-4 6.4.4.2 Toxic Gas Protection 6.4-5 6.4.4.3 Fire Protection 6.4-7 6.4.5 Testing and Inspection 6.4-7 6.4.6 Instrumentation Requirements 6.4-8 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5-1 6.5.1 Engineered Safety Feature (ESF) Filter Systems 6.5-1 6.5.1.1 Design Bases 6.5-1 6.5.1.1.1 Standby Gas Treatment System 6.5-1 6.5.1.1.2 Control Room HVAC Makeup Air Filter Packages 6.5-5 6.5.1.1.3 Control Room HVAC Recirculation Air Filter Packages 6.5-6 6.5.1.2 System Design 6.5-7 6.5.1.2.1 Standby Gas Treatment System 6.5-7 6.5.1.2.2 Control Room HVAC Makeup Air Filter Packages 6.5-9 6.5.1.2.3 Control Room HVAC Recirculation Air Filter Packages 6.5-11 6.5.1.3 Design Evaluation 6.5-12 6.5.1.3.1 Standby Gas Treatment System 6.5-12 6.5.1.3.2 Control Room HVAC Makeup and Recirculation Air Filter Packages 6.5-13 6.5.1.4 Tests and Inspections 6.5-13 6.5.1.4.1 Standby Gas Treatment System 6.5-13 6.5.1.4.2 Control Room HVAC Makeup Air Filter Packages 6.5-14 6.5.1.4.3 Control Room HVAC Recirculation Air Filter Packages 6.5-16 6.5.1.5 Instrumentation Requirements 6.5-18 6.5.1.5.1 Control Room HVAC Makeup Air Filter Packages 6.5-18 6.5.1.5.2 Control Room HVAC Recirculation Air Filter Packages 6.5-18 6.5.1.5.3 Standby Gas Treatment System Filter Trains 6.5-19 CPS/USAR TABLE OF CONTENTS (Cont'd) PAGE CHAPTER 06 6-ix REV. 15, JANUARY 2013 6.5.1.6 Materials 6.5-19 6.5.2 Containment Spray Systems 6.5-20 6.5.3 Fission Product Control System 6.5-20 6.5.4 Deleted 6.5-20 6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 6.6-1 6.6.1 Components Subject to Examination 6.6-1 6.6.2 Accessibility 6.6-1 6.6.3 Examination Techniques and Procedures 6.6-1 6.6.4 Inspection Intervals 6.6-1 6.6.5 Examination Categories and Requirements 6.6-2 6.6.6 Evaluation of Examination Results 6.6-2 6.6.7 System Pressure Tests 6.6-2 6.6.8 Augmented Inservice Inspection to Protect Against Postulated Piping Failures 6.6-2 6.7 MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (MSIVLCS) 6.7-1 CPS/USAR CHAPTER 06 6-x REV. 13, JANUARY 2009 CHAPTER 6 - ENGINEERED SAFETY FEATURES LIST OF TABLES NUMBER TITLE PAGE 6.1-1 Principal Pressure-Retaining Material for ESF System Components 6.1-5 6.1-2 Organic Materials Within the Primary Containment 6.1-10 6.2-1 Containment Design Parameters 6.2-104 6.2-2 Engineered Safety Systems Information for Containment Response Analyses 6.2-105 6.2-3 Accident Assumptions and Initial Conditions for Containment Response Analyses (Case B2) 6.2-106 6.2-4 Initial Conditions Employed in Containment Response Analyses (Case B2) 6.2-107 6.2-5 Summary of Short-Term Containment Responses to Recirculation Line and Main Steamline Breaks - Minimum ECCS (Case B2) 6.2-109 6.2-6 Summary of Long-Term Containment Responses to Recirculation Line or Main Steamline Breaks (at 2952 MWt) 6.2-110 6.2-6a Summary of Long-Term Containment Response to Recirculation Line and Main Steamline Breaks (at 3543 MWt-Case B2) 6.2-111 6.2-7 Energy Balance for MSL Break Accidents (at 2952 MWt) 6.2-112 6.2-8 Accident Chronology for Main Steamline Break Accident (at 2952 MWt) 6.2-113 6.2-8a Accident Chronology for Main Steamline Break Accident (at 3543 MWt) 6.2-114 6.2-9 Available Containment Heat Sinks 6.2-115 6.2-10 Mass and Energy Release Data for Recirculation Outlet Line Break for Head Cavity Differential Pressure Transient 6.2-116 6.2-11 Mass and Energy Release Data for Head Spray Line Break in Head Cavity 6.2-117 6.2-12 Subcompartment Nodal Description of Head Cavity - Head Spray Line Break 6.2-118 6.2-13 Subcompartment Nodal Description of Head Cavity - Recirculation Line Break 6.2-119 6.2-14 Subcompartment Nodal Description of Biological Shield Annulus - Recirculation Outlet Line Break with Diverter 6.2-120 6.2-15 Subcompartment Nodal Description of Containment Pipe Tunnel - RWCU Line Break 6.2-121 6.2-16 Mass and Energy Release Data for RWCU Line Break in Containment Pipe Tunnel 6.2-122 6.2-17 Mass and Energy Release Data for RWCU Line Break in RWCU Valve and Heat Exchanger Rooms 6.2-123 CPS/USAR LIST OF TABLES (Cont'd) NUMBER TITLE PAGE CHAPTER 06 6-xi REV. 13, JANUARY 2009 6.2-18 Mass and Energy Release Data for RWCU Line Break in Filter-Demineralizer, Filter-Demineralizer Holding Pump, Filter-Demineralizer Valve Rooms and RWCU Crossover Pipe Tunnel 6.2-124 6.2-19 Subcompartment Vent Path Description of Head Cavity - Head Spray Line Break 6.2-125 6.2-20 Subcompartment Vent Path Description of Head Cavity - Recirculation Line Break 6.2-126 6.2-21 Subcompartment Vent Path Description of Biological Shield Annulus - Recirculation Outlet Line Break with Diverter 6.2-127 6.2-22 Subcompartment Nodal Description of Biological Shield Annulus - Feedwater Line Break 6.2-130 6.2-23 Subcompartment Vent Path Description Feedwater Line Break 6.2-132 6.2-24 Subcompartment Vent Path Description of Containment Pipe Tunnel - RWCU Line Break 6.2-134 6.2-25 Subcompartment Nodal Description for Break in RWCU Heat Exchanger Room A (Case 2) 6.2-135 6.2-26 Subcompartment Vent Path Description for Break in RWCU Heat Exchanger Room A (Case 2) 6.2-136 6.2-27 Subcompartment Nodal Description for Break in RWCU Heat Exchanger Room B (Case 5) 6.2-137 6.2-28 Subcompartment Vent Path Description for Break in RWCU Heat Exchanger Room B (Case 5) 6.2-138 6.2-29 Subcompartment Nodal Description for Break in RWCU Heat Exchanger Valve Room A (Case 6) 6.2-139 6.2-30 Subcompartment Vent Path Description for Break in RWCU Heat Exchanger Valve Room A (Case 6) 6.2-140 6.2-31 Subcompartment Nodal Description for Break in RWCU Heat Exchanger Valve Room B (Case 8) 6.2-141 6.2-32 Subcompartment Vent Path Description for Break in RWCU Heat Exchanger Valve Room B (Case 8) 6.2-142 6.2-33 Subcompartment Nodal Description for Break in RWCU Crossover Pipe Tunnel (Case 7) 6.2-143 6.2-34 Subcompartment Vent Path Description for Break in RWCU Crossover Pipe Tunnel (Case 7) 6.2-144 6.2-35 Subcompartment Nodal Description for Break in F/D Holding Pump Room (Case 3) 6.2-145 6.2-36 Subcompartment Vent Path Description for Break in F/D Holding Pump Room (Case 3) 6.2-146 6.2-37 Subcompartment Nodal Description for Break in F/D Room (Case 4) 6.2-147 6.2-38 Subcompartment Vent Path Description for Break in F/D Room (Case 4) 6.2-148 6.2-39 Subcompartment Nodal Description for Break in Filter- Demineralizer Valve Room 6.2-149 CPS/USAR LIST OF TABLES (Cont'd) NUMBER TITLE PAGE CHAPTER 06 6-xii REV. 15, JANUARY 2013 6.2-40 Subcompartment Vent Path Description for Break in F/D Valve Room (Case 1) 6.2-150 6.2-41 Mass and Energy Release Data for Recirculation Outlet With Diverter 6.2-151 6.2-42 Mass and Energy Release Data for Feedwater Line Break in Biological Shield Annulus 6.2-152 6.2-43 Reactor Blowdown Data for Recirculation Line Break 6.2-153 6.2-44 Reactor Blowdown Data For Main Steamline Break 6.2-154 6.2-45 Core Decay Heat Following LOCA for Short-term Containment Analyses 6.2-155 6.2-45a Core Decay Heat Following LOCA for Long-term Containment Analysis 6.2-156 6.2-45b EPU 24-Month Cycle Decay Heat Data (1) 6.2-157 6.2-46 Deleted 6.2-158 6.2-47 Isolation Valve Summary for Lines Penetrating Containment 6.2-160 6.2-48 Combustible Gas Control System Components Design and Performance Data 6.2-183 6.2-49 Inventory of Corrodible Materials Inside the Drywell and Containment 6.2-184 6.2-50a Transient Temperature Envelope in the Drywell and the Corresponding Hydrogen Evolution Rate as a Function of Time for Material Corrosion at pH = 8.6 6.2-185 6.2-50b Transient Temperature Envelope in the Drywell and the Corresponding Hydrogen Evolution Rate as a Function of Time for Material Corrosion at pH = 5.6 6.2-186 6.2-51a Transient Temperature Envelope in the Containment and the Corresponding Hydrogen Evolution Rate as a Function of Time for Material Corrosion at pH = 8.6 6.2-187 6.2-51b Transient Temperature Envelope in the Containment and the Corresponding Hydrogen Evolution Rate as a Function of Time for Material Corrosion at pH = 5.6 6.2-198 6.2-52 Parameters-Used for the Evaluation of Combustible Gases in the Drywell and the Containment After a LOCA 6.2-189 6.2-53 Deleted 6.2-190 6.2-54 Deleted 6.2-191 6.2-55 Deleted 6.2-192 6.2-56 Deleted 6.2-193 6.2-57 Deleted 6.2-194 6.2-58 Deleted 6.2-195 6.2-59 Deleted 6.2-196 6.2-60 Deleted 6.2-197 6.2-61 Deleted 6.2-198 6.2-62 Deleted 6.2-199 6.2-63 Deleted 6.2-200 6.2-64 Deleted 6.2-201 CPS/USAR LIST OF TABLES (Cont'd) NUMBER TITLE PAGE CHAPTER 06 6-xiii REV. 19, OCTOBER 2017 6.2-65 Deleted 6.2-202 6.2-66 Deleted 6.2-203 6.2-67 Subcompartment Nodal Description of Biological Shield Annulus - Recirculation Discharge Line Break 6.2-204 6.2-68 Subcompartment Vent Path Description of Biological Shield Annulus - Recirculation Discharge Line Break 6.2-206 6.2-69 Mass and Energy Release Data for Recirculation Discharge Line Break in Biological Shield Annulus 6.2-208 6.2-70 Recirculation Outlet Line Break With Flow Diverter Force Constants for Force Calculations on the RPV 6.2-209 6.2-71 Recirculation Outlet Line Break With Flow Diverter Force Constants for Force Calculations on Shield Wall 6.2-210 6.2-72 Feedwater Line Break Force Constants for Force Calculations on RPV 6.2-211 6.2-73 Feedwater Line Break Force Constants for Force Calculations on The Shield Wall 6.2-212 6.3-1 Operational Sequence of Emergency Core Cooling Systems for Design-Basis Accident 6.3-43 6.3-2 Significant Input Variables Used in the Loss-of-Coolant Accident Analysis 6.3-44 6.3-3 SAFER/GESTR-LOCA Licensing Results for CPS 6.3-50 6.3-4 Key to Figures in Reference 13 6.3-51 6.3-4A Deleted 6.3-52 6.3-4B Key to Figures in Reference 19 6.3-53 6.3-5 Deleted 6.3-54 6.3-6 Deleted 6.3-55 6.3-7 Single-Failure Evaluation 6.3-56 6.3-8 ECCS Design Parameters for Clinton Power Station 6.3-57 6.3-9 Deleted 6.3-59 6.3-10 Manual Valves in HPCS System 6.3-60 6.3-11 Manual Valves in LPCS System 6.3-62 6.3-12 Analysis Assumptions for Nominal Calculations 6.3-64 6.3-13 Analysis Assumptions for Appendix K Calculations 6.3-65 6.3-14 Plant Operational Parameters Used in the CPS SAFER/GESTR-LOCA Analysis 6.3-66 6.4-1 Control Room Leakage Analysis 6.4-10 6.4-2 Radiation Sources and the Associated Attenuation Parameters Used in the Determination of Control Room Doses 6.4-11 6.5-1 Standby Gas Treatment System 6.5-21 6.5-2 Standby Gas Treatment System Equipment Failure Analysis 6.5-23 6.5-3 Compliance with Regulatory Guide 1.52, Rev. 2 (March 1978) 6.5-25 6.6-1 Preservice Examination Coverage 6.6-3

CPS/USAR LIST OF FIGURES NUMBER TITLE CHAPTER 06 6-xiv REV. 15 JANUARY 2013 6.2-1 Effective Blowdown Area for Recirculation Line Break 6.2-2 Short-Term Pressure Response Following a Recirculation Line Break 6.2-3 Short-Term Temperature Response Following a Recirculation Line Break 6.2-4 Deleted 6.2-5 Short-Term Vent Flow Following a Recirculation Line Break 6.2-6 Long-Term Pressure Response Following a Recirculation Line or Main Steamline Break (at 2952 MWt) 6.2-6a Long-Term Pressure Response Following a Recirculation Line Break (at 3543 MWt) 6.2-6b Long-Term Pressure Response Following a Main Steamline Break (at 3543 MWt) 6.2-7 Long-Term Drywell Temperature Response Following a Recirculation Line or Main Steamline Break (at 2952 MWt) 6.2-7a Long-Term Temperature Response Following a Recirculation Line Break (at 3543 MWt) 6.2-7b Long-Term Temperature Response Following a Main Steamline Break (at 3543 MWt) 6.2-8 Long-Term Suppression Pool Temperature Response Following a Recirculation Line or Main Steamline Break (at 2952 MWt) 6.2-9 RHR Heat Removal Rate Following a Recirculation Line or Main Steamline Break(at 2952 MWt) 6.2-9a RHR Heat Removal Rate Following a Recirculation Line Break (at 3543 MWt) 6.2-9b RHR Heat Removal Rate Following a Main Steamline Break (at 3543 MWt) 6.2-10 Effective Blowdown Area for Main Steamline Break 6.2-11 Short-Term Pressure Response Following a Main Steamline Break 6.2-12 Short-Term Temperature Response Following a Main Steamline Break 6.2-13 Deleted 6.2-14 Short-Term Vent Flow Following a Main Steamline Break 6.2-15 Suppression Pool Temperature Response for DBA and Blowdown Following Hot Standby Operation (at 2952 MWt) 6.2-16 Short-Term Pressure Response Following an Intermediate Size Break (at 2952 MWt) 6.2-17 Short-Term Temperature Response Following an Intermediate Size Break (at 2952 MWt) 6.2-18 Schematic of the RHR Containment Cooling System Analytical Model (Minimum ECCS) 6.2-19 Maximum Allowable Steam Bypass Leakage Area Without Containment Spray or Heat Sink 6.2-20 Containment Pressure Following a Small Break with Steam Bypass (with Containment Spray and Heat Sinks) 6.2-21 Nodalization Schematic for Sacrificial Shield AnnulusPressurization Analysis - Recirculation Outlet Line Break CPS/USAR LIST OF FIGURES (Cont'd) NUMBER TITLE CHAPTER 06 6-xv REV. 13, JANUARY 2009 6.2-22 Nodalization Schematic for Sacrificial Shield Annulus Pressurization Analysis - Feedwater Line Break 6.2-23 Pressure Response Within Flow Diverter (Recirculation Outlet Line Break) 6.2-24 P vs. Log T for Node 1 (Recirculation Outlet Line Break) 6.2-25 P vs. Log T for Node 2 (Recirculation Outlet Line Break) 6.2-26 P vs. Log T for Node 3 (Recirculation Outlet Line Break) 6.2-27 P vs. Log T for Node 4 (Recirculation Outlet Line Break) 6.2-28 P vs. Log T for Node 5 (Recirculation Outlet Line Break) 6.2-29 P vs. Log T for Node 6 (Recirculation Outlet Line Break) 6.2-30 P vs. Log T for Node 7 (Recirculation Outlet Line Break) 6.2-31 P vs. Log T for Node 8 (Recirculation Outlet Line Break) 6.2-32 P vs. Log T for Node 9 (Recirculation Outlet Line Break) 6.2-33 P vs. Log T for Node 10 (Recirculation Outlet Line Break) 6.2-34 P vs. Log T for Node 11 (Recirculation Outlet Line Break) 6.2-35 P vs. Log T for Node 12 (Recirculation Outlet Line Break) 6.2-36 P vs. Log T for Node 13 (Recirculation Outlet Line Break) 6.2-37 P vs. Log T for Node 14 (Recirculation Outlet Line Break) 6.2-38 P vs. Log T for Node 15 (Recirculation Outlet Line Break) 6.2-39 P vs. Log T for Node 16 (Recirculation Outlet Line Break) 6.2-40 P vs. Log T for Node 17 (Recirculation Outlet Line Break) 6.2-41 P vs. Log T for Node 18 (Recirculation Outlet Line Break) 6.2-42 P vs. Log T for Node 19 (Recirculation Outlet Line Break) 6.2-43 P vs. Log T for Node 20 (Recirculation Outlet Line Break) 6.2-44 P vs. Log T for Node 21 (Recirculation Outlet Line Break) 6.2-45 P vs. Log T for Node 22 (Recirculation Outlet Line Break) 6.2-46 P vs. Log T for Node 23 (Recirculation Outlet Line Break) 6.2-47 P vs. Log T for Node 24 (Recirculation Outlet Line Break) 6.2-48 P vs. Log T for Node 25 (Recirculation Outlet Line Break) 6.2-49 P vs. Log T for Node 26 (Recirculation Outlet Line Break) 6.2-50 P vs. Log T for Node 27 (Recirculation Outlet Line Break) 6.2-51 P vs. Log T for Node 28 (Recirculation Outlet Line Break) 6.2-52 P vs. Log T for Node 29 (Recirculation Outlet Line Break) 6.2-53 P vs. Log T for Node 30 (Recirculation Outlet Line Break) 6.2-54 Pressure Response of Nodes 31, 32 and 34 (Recirculation Outlet Line Break) 6.2-55 through 6.2-56 Deleted 6.2-57 Cross Section of Shield Annulus at Level of Reactor Recirculation Piping 6.2-58 Cross Section of Shield Annulus at Level of Main Steam and Feedwater Piping 6.2-59 Flow Diverter Sleeve - Operating Details 6.2-60 through 6.2-63 Deleted CPS/USAR LIST OF FIGURES (Cont'd) NUMBER TITLE CHAPTER 06 6-xvi REV. 13, JANUARY 2009 6.2-64 Average Head Cavity Pressure - Spray Line Break 6.2-65 Average Drywell Pressure - Spray Line Break 6.2-66 Average Wetwell Pressure - Spray Line Break 6.2-67 Pressure Differential Across Bulkhead Plate - Spray Line Break 6.2-68 Nodalization Schematic for Recirculation Line Break in Drywell for Head Cavity Pressurization Study 6.2-69 through Deleted 6.2-71 6.2-72 Pressure Differential Across Bulkhead Plate - Recirculation Line Break 6.2-73 Nodalization Overlay for Recirculation Line Break 6.2-74 Nodalization Overlay for Feedwater Line Break 6.2-75 Nodalization for Original Recirculation Line Break Analysis 6.2-76 "Equivalent" Nodalization (Case A) 6.2-77 Azimuthal Pressure Distribution (at centerline Recirculation Outlet Nozzle) Original Data and Case A 6.2-78 Axial Pressure Distribution Original Data and Case A 6.2-79 Simplified Nodalization (Case B) 6.2-80 Azimuthal Pressure Distribution (at Centerline Recirculation Outlet Nozzle) Case A and Case B 6.2-81 Axial Pressure Distribution Case A and Case B 6.2-82 Complex Nodalization (Case C) 6.2-83 Azimuthal Pressure Distribution (at Centerline Recirculation Outlet Nozzle) Case A and Case C 6.2-84 Axial Pressure Distribution (Case A and Case C) 6.2-85 Annulus Nodalization for Recirculation Outlet Line Break 6.2-86 Annulus Nodalization for Feedwater Line Break 6.2-87 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 1, 2, 3 and 4 6.2-88 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 5, 6, 7 and 8 6.2-89 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 9, 10, 11, 12, 13 and 14 6.2-90 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 15, 16, 17, 18, 19 and 20 6.2-91 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 20, 21, 22, 23, 24 and 25 6.2-92 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 25, 26, 27, 28 and 29 6.2-93 RPV Loading Feedwater Line Break - Transient Pressures for Vols. 30, 31, 32 and 33 6.2-94 Nodalization Schematic for RWCU Line Break in Filter- Demineralizer Rooms 6.2-94A Nodalization Schematic For RWCU Line Break in the Containment Pipe Tunnel 6.2-95 Deleted CPS/USAR LIST OF FIGURES (Cont'd) NUMBER TITLE CHAPTER 06 6-xvii REV. 13, JANUARY 2009 6.2-96 Nodalization Schematic for RWCU Line Break in Heat Exchanger Rooms Nos. 1 and 2 6.2-97 Deleted 6.2-98 Deleted 6.2-99 Nodalization Schematic for RWCU Line Break in RWCU Valve Rooms Nos. 1 and 2 6.2-100 Deleted 6.2-101 Deleted 6.2-102 Nodalization Schematic for RWCU Line Break in RWCU Crossover Pipe Tunnel 6.2-103 Deleted 6.2-104 Nodalization Schematic for RWCU Line Break in Filter-Demineralizer Holding Pump Room 6.2-105 Deleted 6.2-106 Deleted 6.2-107 Deleted 6.2-108 Nodalization Schematic for RWCU Line Break in Filter-Demineralizer Valve Room 6.2-109 Deleted 6.2-110 Nodalization Schematic for Head Spray Line Break in Drywell Head Cavity 6.2-111 through Deleted 6.2-114 6.2-115 Vessel Blowdown Flow Rate Following a Recirculation Line Break 6.2-116 Vessel Blowdown Flow Rates Following a Main Steamline Break 6.2-117 Sensible Energy in the Reactor Pressure Vessel and Internal Metals Following a Main Steamline Break 6.2-118 Deleted 6.2-119 Deleted 6.2-120 Spray Nozzle Coverage Charts 6.2-121 Spray System Areal Coverage 6.2-122 Spray System Areal Coverage 6.2-123 Typical Containment Penetrations 6.2-124 Deleted 6.2-125 The Total Residual Decay Power as a Fraction of Operating Power versus Time (pH = 5.6, pH = 8.6) 6.2-126 The Beta, Gamma, and Beta Plus Gamma Energy Release Rates as a Function of Time 6.2-127 The Integrated Energy Release of Beta, Gamma, and Beta Plus Gamma as a Function of Time (pH = 5.6, pH = 8.6) 6.2-128a Integrated Amount of Hydrogen Produced in the Drywell Versus Time (pH = 5.6) 6.2-128b Integrated Amount of Hydrogen Produced in the Wetwell Versus Time (pH = 5.6) 6.2-129a The Integrated Amount of Hydrogen Produced in the Drywell Versus Time (pH = 8.6) 6.2-129b The Integrated Amount of Hydrogen Produced in the Wetwell Versus Time (pH = 8.6) 6.2-130a The Concentration of Combustibles as a Function of Time (pH = 5.6) CPS/USAR LIST OF FIGURES (Cont'd) NUMBER TITLE CHAPTER 06 6-xviii REV. 15, JANUARY 2013 6.2-130b The Concentration of Combustibles as a Function of Time (pH = 8.6) 6.2-131 Deleted 6.2-132 Secondary Containment Boundary 6.2-133 Deleted 6.2-134 Deleted 6.2-135 Deleted 6.2-136 Deleted 6.2-137 Deleted 6.2-138 Deleted 6.2-139 Deleted 6.2-140 Deleted 6.2-141 Deleted 6.2-142 Deleted 6.2-143 Low-Pressure Core Spray P&ID with Outside of Containment Boundary 6.2-144 High-Pressure Core Spray P&ID Showing Outside of Containment Boundary 6.2-145 Reactor Core Isolation Cooling System P&ID Showing Outside of Containment Boundary 6.2-146 Combustible Gas Control System P&ID Showing Outside of Containment Boundary 6.2-147 Residual Heat Removal System P&ID Showing Outside of Containment Boundary 6.2-148 Nodalization Schematic for Sacrificial Shield Annulus Pressurization Analysis - Recirculation Inlet Line Break 6.2-149 Annulus Nodalization for Recirculation Inlet Line Break 6.2-150 P vs. Log T for Node 1 (Recirculation Inlet Line Break) 6.2-151 P vs. Log T for Node 2 (Recirculation Inlet Line Break) 6.2-152 P vs. Log T for Node 3 (Recirculation Inlet Line Break) 6.2-153 P vs. Log T for Node 4 (Recirculation Inlet Line Break) 6.2-154 P vs. Log T for Node 5 (Recirculation Inlet Line Break) 6.2-155 P vs. Log T for Node 6 (Recirculation Inlet Line Break) 6.2-156 P vs. Log T for Node 7 (Recirculation Inlet Line Break) 6.2-157 P vs. Log T for Node 8 (Recirculation Inlet Line Break) 6.2-158 P vs. Log T for Node 9 (Recirculation Inlet Line Break) 6.2-159 P vs. Log T for Node 10 (Recirculation Inlet Line Break) 6.2-160 P vs. Log T for Node 11 (Recirculation Inlet Line Break) 6.2-161 P vs. Log T for Node 12 (Recirculation Inlet Line Break) 6.2-162 P vs. Log T for Node 13 (Recirculation Inlet Line Break) 6.2-163 P vs. Log T for Node 14 (Recirculation Inlet Line Break) 6.2-164 P vs. Log T for Node 15 (Recirculation Inlet Line Break) 6.2-165 P vs. Log T for Node 16 (Recirculation Inlet Line Break) 6.2-166 P vs. Log T for Node 17 (Recirculation Inlet Line Break) 6.2-167 P vs. Log T for Node 18 (Recirculation Inlet Line Break) 6.2-168 P vs. Log T for Node 19 (Recirculation Inlet Line Break) 6.2-169 P vs. Log T for Node 20 (Recirculation Inlet Line Break) CPS/USAR LIST OF FIGURES (Cont'd) NUMBER TITLE CHAPTER 06 6-xix REV. 13, JANUARY 2009 6.2-170 P vs. Log T for Node 21 (Recirculation Inlet Line Break) 6.2-171 P vs. Log T for Node 22 (Recirculation Inlet Line Break) 6.2-172 P vs. Log T for Node 23 (Recirculation Inlet Line Break) 6.2-173 P vs. Log T for Node 24 (Recirculation Inlet Line Break) 6.2-174 P vs. Log T for Node 25 (Recirculation Inlet Line Break) 6.2-175 P vs. Log T for Node 26 (Recirculation Inlet Line Break) 6.2-176 P vs. Log T for Node 27 (Recirculation Inlet Line Break) 6.2-177 P vs. Log T for Break Node (Recirculation Inlet Line Break) 6.2-178 Containment Pressure vs. Log T (Recirculation Inlet Line Break) 6.2-179 Single Line Diagram Igniter Power Supply for One Division 6.2-180 Reactor Pressure Vessel & Internals Horizontal Beam Math Model AP Event 6.2-181 Drywell, Shield Wall & Pedestal Horizontal Beam Math Model AP Event 6.2-182 Annulus Nodalization For Recirculation Outlet Line Break 6.2-183 Annulus Nodalization For Feedwater Line Break 6.2-184 Break Location Feedwater Line Break 6.2-185 Break Location Recirculation Line Break 6.2-186 Clinton AP-FW Line Break Overall Load Resoluion Time History on RPV at Elevation 484'5" X-Dir 6.2-187 Clinton AP-FW Line Break Overall Load Resolution Time History on RPV at Elevation 484'5" Y-Dir 6.2-188 Clinton AP-FW Line Break Overall Load Resolution Time History on RPV at Elevation 484'5" About X-Axis 6.2-189 Clinton AP-FW Line Break Overall Load Resolution Time History on RPV at Elevation 484'5" In X-Dir 6.2-190 Clinton AP-FW Line Break Overall Load Resolution Time History on BSW at Elevation 484'5" In X-Dir 6.2-191 Clinton AP-FW Line Break Overall Load Resolution Time History on BSW at Elevation 484'5" In Y-Dir 6.2-192 Clinton AP-FW Line Break Overall Load Resolution Time History on BSW at Elevation 484'5" About X-Axis 6.2-193 Clinton AP-FW Line Break Overall Load Resolution Time History on BSW at Elevation 484'5" About Y-Axis 6.2-194 Clinton AP-RC Line Break Overall Load Resolution Time History on RPV at 135'5" X-Dir 6.2-195 Clinton AP-RC Line Break Overall Load Resolution Time History on RPV at 135'5" X-Axis 6.2-196 Clinton AP-RC Line Break Overall Load Resolution Time History on BWS at 135'5" X-Dir 6.2-197 Clinton AP-RC Line Break Overall Load Resolution Time History on BWS at 135'5" About X-Axis 6.2-198 Sampling Point Locations (Section G-G) 6.2-199 Sampling Point Locations (Section D-D) 6.3-1 Deleted 6.3-2 Deleted CPS/USAR LIST OF FIGURES (Cont'd) NUMBER TITLE CHAPTER 06 6-xx REV. 13, JANUARY 2009 6.3-3 Head Versus High Pressure Core Spray Flow Used in LOCA Analysis 6.3-4 Deleted 6.3-5 Deleted 6.3-6 Head Versus Low Pressure Core Spray Flow Used in LOCA Analysis 6.3-7 Head Versus Low Pressure Coolant Injection Flow Used in LOCA Analysis for 1 Pump Only 6.3-8 Deleted 6.3-9 Normalized Decay Power 6.3-10 Flow Diagram of LOCA Analysis Using SAFER/GESTR 6.3-11 CPS ECCS Configuration 6.3-12 through Deleted 6.3-78 6.3-79 HPCS Pump Characteristic Curve 6.3-80 LPCS Pump Characteristic Curve 6.4-1 Deleted 6.4-2 Deleted 6.4-3 Isometric Drawing of the Control Room and Other Structures 6.5-1 Containment Gas Control Boundary Wind Patterns and Coefficients as a Function of 6.5-2 Secondary Containment Leakage as a Function of Wind Speed 6.7-1 through Deleted 6.7-3 6.7-4 Effect of Bleed-Off Line Length on Decompression of Main Steamline Between Isolation Valves. CPS/USAR CHAPTER 06 6-xxi REV. 13, JANUARY 2009 CHAPTER 6 - ENGINEERED SAFETY FEATURES DRAWINGS CITED IN THIS CHAPTER*

The listed drawings are included as "General References" only; i.e., refer to the drawings to obtain additional detail or to obtain background information. These drawings are not part of the USAR. They are controlled by the Controlled Documents Program. DRAWING* SUBJECT 762E260AC Process Diagram MSIV Leakage Control System 762E425AC Process Diagram Residual Heat Removal 762E454 High Pressure Core Spray 762E467AC Low Pressure Core Spray M01-1105 General Arrangement - Basement Floor Plan M01-1106 General Arrangement - Grade Floor Plan El. 737'-0" M01-1107 General Arrangement - Mezzanine Floor Plan El. 762'-0" M01-1108 General Arrangement - Main Floor Plan' M01-1109 General Arrangement - Miscellaneous Floor Plans M01-1111 General Arrangement - Sections "C-C", "D-D", and "E-E" M01-1524 Radiation Shielding Design - Containment Building El 800'-0" M01-1526 Radiation Shielding Design - Containment Building El 825'-0" M05-1002 Main Steam M05-1004 Reactor Feedwater System M05-1010 Circulating Water System M05-1012 Cycled Condensate Storage M05-1032 Component Cooling Water M05-1037 Fuel Pool Cooling and Cleanup System M05-1039 Fire Protection M05-1040 Instrument Air M05-1045-12 Postaccident Sampling & Analysis System (PASS)

M05-1048 Service Air Piping and Instrumentation Diagram M05-1052 Shutdown Service Water M05-1060 Suppression Pool Cleanup System M05-1065 Breathing Air System M05-1069 Suppression Pool Cleanup System M05-1070 Main Steam Isolation Valve-Leakage Control System M05-1073 Low Pressure Core Spray System M05-1074 High Pressure Core Spray System M05-1075 Residual Heat Removal System M05-1076 Reactor Water Clean-up System M05-1077 Standby Liquid Control System M05-1078 Control Rod Drive System M05-1079 Reactor Core Isolation Cooling System M05-1080 Fuel Transfer System M05-1102 Control Room HVAC M05-1105 Standby Gas Treatment System M05-1109 Drywell Cooling Chilled Water System M05-1110 Drywell Purge M05-1111-1 Containment Building HVAC System M05-1111-4 Combustible Gas Control System Equipment Room Cooling CPS/USAR CHAPTER 06 6-xxii REV. 13, JANUARY 2009 CHAPTER 6 - ENGINEERED SAFETY FEATURES DRAWINGS CITED IN THIS CHAPTER* DRAWING* SUBJECT M05-1117 Station Chilled Water System M06-1075-6 Containment Spray System, Spray Nozzle Orientation and Spray Header Plan View M06-1075-11 Containment Spray System - Spray Header Plan View M27-1305 Containment Building Piping - Elevation 816'-7" M27-1306 Containment Building Piping - Elevation 803'-3" (Lower Elevation) M27-1311 Containment Building Piping Plan - Elevations 770'0" to 828'-3" M27-1312 Containment Building Piping - Section 1-1 M27-1314 Reactor Head Piping Plan Elevation 804' 1/4"

CPS/USAR CHAPTER 06 6.7-1 REV. 12, JANUARY 2007 6.7 MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (MSIVLCS) Note: As a result of the re-analysis of the Loss of Coolant Accident (LOCA) using Alternative Source Term (AST) Methodology, it is no longer necessary to credit the Main Steam Isolation Valve Leakage Control System (MSIVLCS) for post-LOCA activity leakage mitigation. The system has been left in place as a passive system and is not required to perform any safety function. CPS/USAR CHAPTER 06 6.8-1 REV. 13, JANUARY 2009 SECTION DELETED N +-" -<t' w a: <t' <i w a: al CPS-USAR TIME (sec) REVISION 10 OCTOBER 2002 Figure 602-lo Effective Blowdown Area for Recirculation Line Break 40 I A DtYWell I ---Wetwell I *.*** " containment --* -* OW-Cont (paid) I . .........___ --..........____ 35 30 -* 25 .. I ; 20 I j ... J ,, -"" ti ........ 15 10 5 0 "'--.. __ ,,_ ____ , ; I \ ""-"-.....,_ _____ .,..._ _ ___ .,.. ___

I .\.***-* "' ......... -I -* * " -.,.. ' I Cl '* * ,.,.. I I ' II I I
I I
I
I 0 5 .. ....... --*-* -*-**--*-*-*------....... 10 15 nrn* (HC) . '---. .... ---. 20 ..... -*-*-..... . _, '* ...._ 25 30 FIGURE 6.2-2: SHORT-TERM PRESSURE RESPONSE FOLLOWING A RECIRCULATION LINE BREAK D ::::0 nrri -1< 0 ........... CDV> Ill ........... ::::0 D z N 00 N () lJ (/) I c (/) )> ::::a CPS USAR CLINTON RSLB COO IDtP RESPCNE CEPUl 350 . * ! 1 . . 250 1 .... -.... I l -I I --.... ... so. .... I I I I I I I I I o. LO. 20. TIME SECONDS CLINTON POWER STATION FIGURE 6.2-3 SHORT-TERM TEMPERATURE RESPONSE FOLLOWING A RECIRCULATION LINE BREAK ' I -I '50. Revision 10 October 2002 IJ?Yt.ELL TEl"fERAl ..RE TEtfERAl1 .RE 10.

CPS/USAR REV. 10,October 2001

Figure 6.2-4 Deleted CJ) ' co .....J uJ t--< .:r. 3: 0 .....J l.J... I-z uJ > CPS USAR CLINTON RSLB VENT FLOH RATES <EPU> l AIR' z VAF'Ol I LIOJID Revision 19 October 201 7 / O.B 0 * ., o. o. l 10. 20. 30. TIME SECONDS CLINTON POWER STATION FIGURE 6.2-5 SHORT-TERM VENT FLOW FOLLOWING A RECIRCUIJffION LINE BREAK '10. 30 25 la 'iii ,,g. w 20 a: :::> (/) (i) UJ a: Q.. ............... _ MIN ECCS -------ALL ECCS 15 10 5 .... ____________________________________________ .._ ____________________ .... ______________ ..... TIME (sec) FIGURE 6.2-6. LONG-TERM PRESSURE RESPONSE FOLLOWING A RECIRCULATION LI () "'Cl Ul I c:::: Ul ::r>i ::0 D::::o () f"Tl -I < O,___. CD (./) f"Tl ,___. ::::oo NZ 0 _,.. Oo N < ..... i BO. 10. 20. ' I ' . . .. --.... --.... .... -I-o. 1.

J I I I I I I I IIl OIW uro 1 .nw.1 CPS EPU ' (M PRESSH:. R9...B HlN ECCS , ""' PRESSURE. a --* -., .. -.. --. ,, -2. !. ... s. LOB TIME SEC Figure 6.2-6a. LOng-Term Pressure Response Following a Recirculation Line Break (at 3543 MWt) n v (/) I c: (/) )> ::::0 0 ::0 () rri _, < 0 ,_... CD V> rri ,,__. ::0 0 NZ: 0 __,.. 80

< ...... I 60. 10. 20. I ' . .. -.. --... i---I I I I I I I I I 0, '* llL DO'PllE flDD l Jiil., CPS EPU ra.B HlN ECCS ' ' r-....__ . 2 .. '5 .. LOG TIME -SEC I 04 PRES9JE I i lo J ---* --I --I ---s. Figure 6.2-6b. Long-Term Pressure Response Following a Main Steamline Break (at 3543 MWt) () v (./) I c: (./) )> ::::0 D::::o () rrl -; < o .......... CIJ (/) rrl .......... ::::oo NZ 0 --" u: w a: :::> I-<( a: w c. w I-200 160 140 180 /--...-... .......... .......... , '" ' ..................... ______ ALLECCS MIN ECCS 120 100 _______________________ ..... ______________________ .._ ____________________ _. ______________ _, 103 104 105 1o6 TIME (sec) FIGURE 6.2-7. LONG-TERM DRYWELL TEMPERATURE RESPONSE FOLLOWING A RECIRCULATION LINE OR MAIN STEAMLINE (') ltj en I 0 en g; 0 :::0 () fTl -I < o ........ OJ (./) fTl ........ :::0 0 z N 0 __,. Oo N CPS EPU RS..B MlN ECCS ' Doi AlR!PACE. 'TB"P 1 ""1 AIRSPACE leP ' s> TEMP 300. u.. I 200. m ....... 100. 1. 2. 3. "'* 5. IJL OOW L06 TIME -SEC Qi:ZD l Jl"!ll.I Figure 6.2-7a. Long-Term Temperature Response Following a Reciculation Line Break Cat 3543 Mtlt) () u (./) I c (./) )> ::::0 O::::o () rll _, < o_ OJ (/) rll ........ :::0 0 NZ 0 __,. CPS EPU ttLB MJN ECCS

lJ.J AIRSP'ACE TErf' I ""' AIR!PACE TElf
l:P TEl1P '300. l.J.. I 200. I 100. 1. 2. '!S .. .. . s. Ill OfNE LOG TIME -SEC Cl220 J. ..... Figure 6.2-7b. Long-Term Temperature Response Following a Main Steamline Break (at 3543 MWt) 0 v (./) I c (./) ):> ::::0 D::::o () [Tl -I < o ......... OJ (./) [Tl ......... ::::0 0 NZ O_,.

u.. CL LU 0:: :::> 0:: w 0.. :e LU ,.... 200 180 160 140 120 -" ', ', '--105 100 104 1o3 TIME (sec) MIN eccs 106 FIGURE 6.2-8. LONG-TERM SUPPRESSION POOL TEMPERATURE RESPONSE FOLLOWING A RECIRCULATION LINE OR MAIN STEAMLINE BREAK (AT 2952 MWT) () ""d en d c:r.i D::::o () fT"1 --l < o_ CD (/) fT"1 -::::oo NZ 0-" Oo N u ::I .... co "b .... w a: <( w ::t 10 8 6 4 ------............. ------..................... ALL ECCS 2 MIN ECCS 0 103i--104 106 io5 TIME (sec) FIGURE 6.2-9. RHR HEAT REMOVAL RATE FOLLOWING A RECIRCULATION LINE OR MAIN STEAMLINE n I c en g; 0 :::0 () fTl -l < o ....... OJ (/) fTl -.... :::0 0 NZ 0 _,. ...... i2 co I J-< 6. *101 't

2. o. ---------I I 11 I I I t I ,' 1. 81L lJOl!l,t,I 0&20 L 11'SB.'I CPS EPU RS..B MlN E.CCS I 2. LOS TIME I 1-E"T REMOVAL Rll.1'E I -/ I r...-* 3. .. . s. SEC Figure 6.2-9a. RHR Heat Removal Rate Following a Recirculation Line Break (at 3543 MWt) () lJ (/) I c (/) )> ::::0 D;::o () Ill -1 < o ......... OJ (/) Ill .......... ::::oo NZ 0--"

I=! tc 6. *101 ., . 2. -----,_ ---o. 1. t t 11 I I I I I .. IJL Ol'Pll[ U20 L .1121." CPS EPU MS..8 KlN ECCS .. 2. LOG TIME & m-R t£AT REMOVfL RATE ' --/ .. 3. 4t. s. SEC Figure 6.2-9b. RHR Heat Removal Rate Following a Main Steamline Break (at 3543 MWt) n v (./) I c (./) )> :::::0 D::::o n rn -l < o_ OJ (./) rn_ ::::oo NZ 0 __,. <( w a: <( :il <( w a: m CPS-USAR TIME (sed REVISION 10 OCTOBER 2002 MSIV'S FULLY CLOSED Figure 602-10. Effective Blowdown Area for Main Steamline Break MSLB 10211/. EPU 40--------------------------------------------------""'T-----------, -Orywell ---wetwen 35 ...... containment -* -* OW.Cont (psld) 2511 I I I I I =:--........J 'ii l -! 20 I .... I -.., ,,, ' .. { ! ... ______ J ______ J ___ :-__ t ____ _J 15 * .. .. * * * * * ' . I \ . . -*-*-........... \ ...... .... -.. ........ I 10 ti ' -*-*-*-*-*-*-*-*-1 k ________ _..,._ ________ 0 s 10 15 20 25 30 Tlme(sec) FIGURE 6.2-11. SHORT-TERM PRESSURE RESPONSE FOLLOWING A MAINSTEAM LINE BREAK () v (/) I c (/) )> ::::0 O::::o () [Tl -l < 0 ,_..... DJ (/) [Tl ,_..... ::::oo NZ 0 __.. Oo N '350. I 250. I L1.. en tjj 0:: (!) lSO * < .... ... er: ... -ii t l: ------I I I I I I I I I so. o .. 5.\T 00l9( 05.U l US2.2 CLINTON MSLB CCliT 1'EJ1P RESPO<< <EPUl ' I

I TIME SECONDS -a 30. 1 t:RYW:LL TEt'PERAT ..RE a a.E.T\.El.L TEf1'ERAT .RE 40. n u l/) I c: l/) )> ::::0 FIGURE 6.2-12. SHORT-TERM TEMPERATURE RESPONSE FOLLOWING A MAINSTEAM LINE BREAK 0 ::::0 () rll --1 < 0 ,_. OJ l/) rll ,_. ::::0 0 NZ 0 _,, 2o CPS/USAR REV. 10,October 2001

Figure 6.2-13 Deleted c.n ' .._ z UJ > J.2 *l 01 CLINTON MSLB VENT FLOW RA TES (EPIJ) 1 AIR 1 VAPCA I LICJJID o. LO .. 20. '50. 4'0

TIME SECONDS OW l H'SU FIGURE 6.2-14. SHORT-TERM VENT FLOW FOLLOWING A MAINSTEAM LINE BREAK () -0 (/') I c (/') )> ::::0 O;:::o () rll -l < O,_,_. CD (/') rll ......... ::::oo NZ 0 __,. 2o u:: e.. w 0:: ::i .... <( 0:: w 0... w .... ...J 0 0 a.. 200 150 100 CPS-USAR OBA AT FULL POWER REVISION 10 OCTOBER 2002 LOCA FOLLOWING 1/2 hr HOT STANDBY 50.._ ______ .._ ____ ...... --.... 10 12 14 0 2 FIGURE 6.2-15. 4 6 8 TIME (hr) SUPRESSION POOL TEMPERATURE RESPONSE FOR OBA AND FOR BLOWDOWN FOLLOWING HOT STANDBY 60 t--501--40 t---;:; *;.:; E: w 0:: I <J :J V,) ttj U') LJ.J Cl.l 0:: I 0.. q Cf.) > I T DRYWELL : WEiWELL 10t-I rg ;o fT1 -I < O,___. g; (/) ;oc; 0 10-1 100 101 102 1a3 104 TIME (sec) FIGURE 6.2-16. SHORT-TERM PRESSURE RESPONSE FOLLOWING AN INTERMEDIATE SIZE BREAKf (AT 2952 MWT)

LL CL. w a: <( a: w 0.. w I-300 200 100 101 0 104 TIME (sec) FIGURE 6.2-17. SHORT-TERM TEMPERATURE RESPONSE FOLLOWI 102 1a3 AN INTERMEDIATE SIZE BREAK (j l"lj Cll I c Cf) D::::o () fT1 -I < o ........ CD (.f) fT1 -::::oo NZ 0 _,, Oo N REACTOR PRESSURE CPS-USAR VESSEL HEAT EXCHANGER Figure 6.2-18. Schematic of the RHR Containment Cooling System Analytical Model (Minimum ECCS) 10 8 5 w (.!) <( :.I'. <( w ..J en 6 en <( c.. >-aJ ..J ..J w >-cc c 4 2 4 5 6 BREAK AREA (ft2) Figure 6.2-19. Maximum Allowable Steam Bypass Leakage Area Without Containment Spray or Heat Sink 7 n "t:1 en I c:: en !l:" 8 -.. :::::> Lt.I t:: fu !? Ul & f; . 0 CD -0 ...... . C> N REVISION 10 OCTOBER 2002 VISd -3MISS3Md FIGURE 6.2-20 ... "'u l'.H w ::c ..... t-(!) 0 .. .....I Al 52 60 NOTE: See Table 6.2-14 for a description of the nodes and Table 6.2-21 for a description of the vent paths. 58 31 53 34 59 57 32 54 55 51 42 33 24 14 4 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-21 56 NODALIZATION SCHEMATIC FOR SACRIFICIAL SHIELD ANNULUS PRESSURIZATION ANALYSIS -RECIRCULATION OUTLET LINE BREAK NOTE: See Table 6.2-22 for a description of the nodes and Table 6.2-23 for a description of the vent paths. CLINTON POWER STATIO.N UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-22 NODALIZATION SCHEMATIC FOR SACRIFICIAL SHIELD ANNULUS PRESSURIZATION ANALYSIS -FEEDWATER LINE BREAK '. i I . i ---**. ----** . **--***t* ----* **-.. ' / I I I I .. *\ u C\l W. 'o CfJ w =:1 I-.... ! _ _. ____ .___....__..l--___ ____ ......11\ OOl 009 OOS 001' 008 OOZ 001 0 t CJ I Sd l 31n1t198CI CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-23 PRESSURE RESPONSE WITHIN FLOW DIVERTER {RECIRCULATION OUTLET LINE BREAK) u NW b(f) . .,., w L: ______ ....... ____ ........ ........ Ot B 9 t Z 0 z-t-(0 Sdl llijM 013IHS dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-24 VS. LOG T FOR NODE 1 (RECIRCULATION OUTLET LINE BREAK) I j i - -+-r---r-, -I ! -I ! I I ! ! I I I -i i I /-*--*-*-*-L------l----i : , I I t I -! -----*--. ------. t-I I I i I I --.: __ :-[---------*----!-----.. L, __ ! l . -l I I I \ --------+-----*---;-----------+-----------------*-i---*-1 I I ---! I I . -----f --. -------*----------t----------i ! -1*-. i--1 I ! l I i I i I. -I I I I ---r--! I -. *}. I ! ------*-i------t--i f ***----<.**-- *----- --------r ----**-*-*-... *-------! l i. ! ! I .. **---!--.... '. .. I ! *-----------*----*. -*--t i I ---i ----*------*-----------*-----------l i I -I *: --*- ----:*------*1 *-------:--*--J_ ___ _ I ! i i -------;----*---**---*----*-i - -------------------------*i-i . I i I I I I I . ----f -----------i-i ; . i 'a *---*u NW 'a (f) w L: I-Ot Q I * (at sd r s i t z o z-t-013IHS dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-25 VS. LOG T FOR NOOE 2 (RECIRCULATION OUTLET LINE BREAK) 'b *-1 I I ... T i ! . (. -*-**---**i----I I I I I I ..... J ....... -... 1-I ! I --.. *-*-**--*-t---*-**** I i l . l ! i I I .. -i -l I I I i .. . f ..... --*** ... i I I .-1. I i . . i I ----------**r---* I i I . -l --1 l *1*. I --------............... L *-*---*-----------*---+----**---< i i . i I ...*........ *-*-*** ----! l I ' -*-----------r* ---+ _ _, *-*-*-* +--*" ....... +******--**** ; I i i **r I i . I u c-i W' 10 (f) (Y) 'a *a i B ! 9 l v 2 0 ( 0 t Sd) 013 I HS dOI 2-v-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-26 VS. LOG T FOR NODE 3 (RECIRCULATION OUTLET LINE BREAK) Ot ***-t *---*--.. --.. I I i I. -'o ... -**' (_)' c-J w, 'o(J)! -j ..* ------. l t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-27 VS. LOG T FOR NOOE 4 (RECIRCULATION OUTLET LINE BREAK) !:bi .---....... ---.-------------..----....---r--.....,.--,..--.,.---, .. --, : I : l ! I I i I I ! . . 1 . I . . . l -*-*-----+--------____ ; _______ _ -----------!-----; ___ *-- --* .. : .. ---- -*--____ ; __ ---**-\-------. i ' i I -I ! I i I ------ --I I I i ----: -I I I i ---+-! ! l ****-**--T-* i ----t--* I Ot 1 1' : . 1 i. i 11 ! . --+-----1 ! : ! I .. i-. -. *** !

I * : l -t i I I I . ---l----. -... j i . -* \ -! I l I I .( .. ! i I ! I . ' i I i ' *-+** I l I -i l . ! I I --r---I I . l i l .. -**** *****-** --* !* ............ ----**+**--. i I i i i I -----***** *-* ....... f *-...... *--* -. **-1.-... . I i l. ! ! u N wl bwl I-(T') I I ' 0 ! g I 9 I tr ' z 0 coisd) lll:JIM 013IHS d01 z-v-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-28 6P VS. LOG T FOR NODE 5 (RECIRCULATION OUTLET LINE BREAK) ct:il r--....--...--'"""'I"'-..... ""i i l. --*-r I I I I -. " -----* 1 **** i I i . I i i I ' l -'a u NW 'ow w E I-.. _ ..... --------*--**----*--**+ Ot I . i i I i -. *-*----i----* *- ----(Y) 'a g 9 t ' z 0 v-(0 Sd) 013IHS dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-29 AP VS. LOG T FOR NODE 6 (RECIRCULATION OUTLET LINE BREAK)

! ! i I I 1*** I J *****************+************ I ........ ( ............ , .... . --r----***** *-*-"***-\ i ; i i I . ******il ...... ;*** **t* i 1 I I ! l . -.. ! I *. j L. ... .-. I *01 .,.I Ot Q: 9: t z 0 C 0 I Sd )' lli:PM 013 I HS dOI t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-30 VS. LOG T FOR NODE 7 (RECIRCULATION LINE BREAK) L. . ----* -.. ! i I. I I I I **1** ...... ****-****. i . ' i I ... .!.. .. ... **--.. . . ............ --l i i I . ___ .. _,) I 1 l I i l *r*-* ! . i i ----+**-** ! I j i I *****+** I ' t. I i 1-.... , ........ i . I i l i -r I I I ... 1. -.) -i ' ' I ... i-i * --........ _ ... I .......... . i ---*--+ ............. " . . .. ...... --.... .. ..... _ ......... -.. +--***--*---** U: N Wi b(f)I w E I-'< I-QC B t 9 *V i Z 0 (OtSdl llQfM 013IHS dOi v-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-31 6P VS. LOG T FOR NODE 8 (RECIRCULATION OUTLET LINE BREAK) I ! I ! ! I I . r----.. ---*:--....... ......... .. l . I <-** ! * .. i ----*j I i I i i i .. f *-\ t*-----**** : I ! I ... -----L-.. ______ ]_ ______ _ l l I l. ! i i I ........... ., ........ __ .. --................. i ...... -........... . I l i I i I ---*r . I.. i . w ::E I-...,. I 'o' Ol 8 f 9 I V: 2 0 ( 0 I Sd ), llJM 013 I HS dO CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-32 VS. LOG T FOR NODE 9 (RECIRCULATION OUTLET LINE BREAK) I I I J *******-** t ********** ; .. ! I I I I t ........* -....... . -,. t-*-*-.... i i l .. **-**i. ***-Ot . [ .. .. _. -** i .... **-! 'a I l u c:-.1 w, bro' ... B , 9 1' . 2 0 z-v-COlSdl 118M dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-33 6P VS. LOG T FOR NODE 10 (RECIRCULATION OUTLET LINE BREAK) ....... ....... i I i i ! . -i I i 1' i --.. .. :-.. ---*-_._ --\ I I I .. r**-, -*-*-*+*-*** l i ! ! I I I I i I **-*-r* I ! i i *-- ! I ***.. j -* -L i **-*-*-*{"*** --. I l I ! ** j t---*-**** --....... --t ...... *-**. -**-* -I l ! . I , ; ---**---1****-***---* -* *-****-* . I ' I i . . I i l i j i l I i I --*-r*-** ** * :*** *****t****-* j l t : I i -l. -. ! t. I, i ' ,1 i .J ***--+-*-* *l*. ----** ..... *i-* I i i I f l ***-i-... i i I

1 i I * * * **** -l ---r I J
i I -*****-**-*-**. **--* 1*--******* i I I 1 I I I **.**. j ..**. *-.. l \ i. -1 I ....... -**** ..... ****i*-* .... I I ! .*. 1. *********-**-... *******---l*-*****-**** \. I i --**1 *. l i : I t I . i -'a -1 u CN W 'ow .-.rt'i---*** Ot B l :g 1 t l G 0 ( 0 I Sd )' 118M 013 I HS dO t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-34 AP VS. LOG T FOR NODE 11 (RECIRCULATION OUTLET LINE BREAK).

-*----11' ... **+--------*----******-f-*-------*--. -* I I i I i l -** ---**---... I --*-*---l---------------* ----*--*-*-----+----Ot ! ! I i . DI c-.J w b(/) **Y -* I I. B: 9 ! v i. 0 (a 1 sd l. 118M 013 I HS dO tr-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-35 VS. LOG T FOR NODE 12 (RECIRCULATION OUTLET LINE BREAK) ,.....-..,....--,-----,.--,---..,....-...,..-....... j l i i I -f ' I j II \ ***********+-+-----------*--*-** -*-****--*-****-----**-* -l.-*r* -*. --*--* *--T-i i f' I ---1 . . ; *--' - *-! i I ---------+------*---* ; ....... -i I ! - I J I ... ) . L. I .. ! ! I . I u N w b<n w L: ....... I-i . 'i' "Of' bl _o_t_-+--____ B _ _,i __ ,,__9 _ _,, __ ...._,_....__ ....... _G_ ....... _ __.__o_ ....... _ __._. _G_-----';:'/ CO l Sd l. 118M 013 I HS dOI CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-36 8P VS. LOG T FOR NODE 13 (RECIRCULATION OUTLET LINE BREAK) . i i I \ i i* .....**.. ***** ...... +* I l ! .. l. I ! i +** j i . l I i 1-... -.. l ' i *I-------....... _ -; i . I **u NW bcn (T) 'o w E I-.... j """ b ....... B; 91 t '. 3 0 Ot coisdJ dO 'v-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-37 VS. LOG T FOR NODE 14 (RECIRCULATION OUTLET LINE BREAK)

.. **t ---(T) 'o w E I-""' 'o -..-.,.__ __ ..._ __ ...... ---------------*-'ot B l 9: ir Z 0 z-C Q 1 Sd)

lll:fM 013 I HS SSGH:J;t:J dO/ CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-38 6P VS. LOG T FOR NODE 15 (RECIRCULATION OUTLET LINE BREAK) ct,, --......--..---.....---.--------.---....------.-----.,.....---.-1 I I I . I *-***1 ** * ********** *r*** . **-i*** ** ** *r ** ** t**
i * ** _, I I i . I **---**-----*-** --r-********* ..... . ! . I I r* ... ! *---**-***+*---** .. *j ... **!*****--*-****! .. ***-*-*.. -i i . *+** I i l i I i I I ..... *-;-*--. ----******-r-**---**
I I i I ********1-*-****--."** I I I I I ........ l ... i I I I I I I ... *-***--*-*** ... r--****--*** i i I .. -**-*** *-*-i i . I i ! . ! I .... 'o u IN W b(f) . ..... ***** .... *1*--*-** 1* --***-*** ..... ! ! i *--**l
l :ot 8 I ' 9 . l ' 1' , Z 0 co1Sdl Oti3IHS dO z-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-39 VS. LOG T FOR NODE 16 (RECIRCULATION OUTLET LINE BREAK)

.---......---...-----...---..---.....---.---....-----.----..----..---...----r---. --1 I I ------------r-----l ! j i -------: -Ot l i i I r --1 I I I -i i i ----, *-*-. **-* .. i ' *I 1**** 1 ' ** I r -**j *** -i I . .,. ( __ __: __________ [ __________ J ______ _ I I : I I I ' I i ! i ' . -* -*---. t . i i* *-*u c-1 w 'o<n 1r-w E ,_;.., CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-40 VS. LOG T FOR NODE 17 (RECIRCULATION OUTLET LINE BREAK) ,--_,_ __ ,__ ____ ,__ ____ ,__ ______________________ ! u c-J W! bUJi (T") 'o .... w :E I-bi ....... _, 01 B ; 9 t l 0 COlSdl 118M 013IHS dO t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-41 VS. LOG T FOR NODE 18 (RECIRCULATION OUTLET LINE BREAK) . 11 I . i I l l I *-*** ----*;----* ****-r*-*-*;--* --*-T .. .J., ..... .

I : I I . I ; I ' 1
I i . I ii I I ' I I i -----*-t**-**-** ... L **----------!. ---*--* -i \ i !* -------i I l I l ***--***-**+*--***-.... i I I I I *---*t i I ....... **I I j . t i 1 I I I i I. I i .. -r *---*** I I . *t** i ! i __ f ____
i ---**-... ______ _ l I l. ! ***-t* -__ ; _______ L .. . t I i -... ** .. . .. l. j -;-* ........... **t .. i I l i I I ! i I ..*.. \ ......... **-***-* . I i 1 i I I .. ****+-! i ! ---*-** -. _J ******* I -b w E ......... I-....... Ot 8 (01Sdl 9 1' z 0 t-118M 013IHS dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-42 VS. LOG T FOR NODE 19 (RECIRCULATION OUTLET LINE BREAK)

%' -I I ..... -+****** I I i ***r*****-**** I I .. -****-***t** .. ** I I :-*-******1 I I I. I I i ***-****--*1***-***** ! ----**** ---------.l .. I I i i ' .. i l l --r -T I ! i i **r*--* . I . *I ..... I. I I j I I I : j

I ! i I I i I ! I l ****-t*. l l i ! ! i . . *-** *. . . . . ... , ... *-*-* -*-***-*** ...... ****+ --.. **t --i i i l l ' I . ----*1-* .............. .. --. I l --*-*----*--' *--t-----I . -**---r. -**-* . -*************-******--.t. i i u C'.J w boo , .......... -. . . , . -**** ... **-******-* *r*. *---*****-* .. *****--** --{ ................ . l------*r I 1 i .. I I ! -i . ! ' "! ... * ** , **. t -------*----i I . r** :o t 9 I *9 I t I l 0 (OiSd). dO t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-43 VS. LOG T FOR NODE 20 (RECIRCULATION OUTLET LINE BREAK) r--..,....--r--....,.--,.----....-------------------**"" I .. ! ' -----*----****-*--...... .. I I . t * . . i i ! : i i -.j ....... _ ... . I \. i 1 i *[*** .. ; .... --i-; I I i I ..... L---: i ' I . ' -'o w E I-..,. 'o '---+--"'---+---'--.....i..--'-----i.-- -----.L------L---....:..-..J Qt B 9 l 1' ; l 0 CO Sdl ll8M 013IHS dOi 6-1'-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-44 VS. LOG T FOR NODE 21 (RECIRCULATION OUTLET LINE BREAK) i I I . ****--*-+*-*-***** . ) ! l i ...... --1 *-* ---* ' I .. ! Ot e 9 t I l 0 COISdl 118M dO I -1 L ! I ! I i *-* ! ... I .... ! --+ ---------I z-i i. _I ';!I I u c-J w b<n I-t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-45 6P VS. LOG T FOR NODE 22 (RECIRCULATION OUTLET LINE BREAK) i r ) . ! --***t-*--***---** .... *----*--**--r *-**----****-*** -------*----------*---t ) I ! i I ! --*----t-* I l i \ ** ***-_ _( * --_____ :_ * ---*--f-------* ........ J .. -----*-L .. I ! i *------/--.. . .... . -\ I ________ J _________________ L_ I j' ! ! l .. i-.. l ! I **-t* *-... ***-** *-* r-* --* 1 I I
l *I I I I I ........... ****** .......... !. .. I j -*a u IN W b(f) .,,. ('I') 'a I ! I 1! i I I 0 9 I f i G Q .o t 9 COlSdl 2-t-118M dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-46 6P VS. LOG T FOR NODE 23 (RECIRCULATION OUTLET LINE BREAK)

I --------r----1 I l ______ _j -----..... . I I I ! *t-** ... -.. -! i i ! I ---l-1 l I ****** 1----.... -I i --- ------'a i ! I I . .. ---i i j --*-*----... -*-----**--t---*-----. . I l I I I .... 1 -* **** j. --' i ----+---..... l ! **-+*-' i. I -*.. , **------------i I I I I . -- --*. -.* -------+-***-**-*** i I .. I ! u ('J w b(/) (Y) w E . """4 .,.__ 'a v-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-47 VS. LOG T FOR NODE 24 (RECIRCULATION OUTLET LINE BREAK) ,..---.,..----,__,___._...,.__ ___ Ot I . I -I I ---*-*-****--*-*-r------*-z-\ : i l *+**. I \**--i I -'o (_) c-J w b(f) t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-48 VS. LOG T FOR NODE 25 (RECIRCULATION OUTLET LINE BREAK) i -! ----: -i l i -I I ------------j--__________ " _________ _ i 1 1 I I 1-------------**--*---I I I --! I i **----------*-* -**--*-t--***---* i [ . i --------**--------+---: l u <:-' w b(J) ----*---!-------; ___ --t-. -+ -I 1 i I ! ------*--*--j----! I i --I I I -----j--! i --I I j i i I ------i-i j --I -I -_[ ---*---* ----t . ---------. -f ---. ----!" I i I t -' -' I ..... 'o ........ ..... g I 9 i_ v I 2 0 Ot r 0 I Sd J 013 I HS dO 2-t-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-49 VS. LOG T FOR NODE 26 (RECIRCULATION OUTLET LINE BREAK) I I i I ---**---+-**-* -*---**

I***-*-* .. ;. ------t *---* -. ---1 I ; I . . ii --r --j-* : .. -l -; l i ! -*-*----+-*-***----c-*----** ..... /*-*-** ---+-*-* .. *-*-*. ,. -' I ' I ' I I I I I I t i ' **1*** ! 1 i i ! 1 1--i ! l ! I I ! I ........... -r*-..... . . \--* .. ***----****** l I -__ J_ _L_ I 1 I I I I . f .... ....... . .. ; ........... . t l l i L. ... **+*--** I --1 ! i --. i I I ; I ---r-* . ***--t------------* -I i I *-I I I : I -*--{---------i j I 'a w E ..... +*-*-** . --(I") 'a t--'a Qt B \ .g : v . Z 0 (OlSdJ lltlM 013IHS dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-50 6P VS. LOG T FOR NODE 27 (RECIRCULATION OUTLET LINE BREAK)

'Ot j* I ! i *--*+**-*-***:-**-B ! .9 i v i l 0 (QjSdl dO : . I (.J c-1 w b (.{) ('t) *o . ..... v-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-51 6P VS. LOG T FOR NODE 28 (RECIRCULATION OUTLET LINE BREAK) I I : , ' I : f : i ! : I I ' I I I I l ' I ----------t---- ----_J.._. ------------* -.... -----* 1---. -----. --*----*----. ---------' I ' I : I I I . _

i .j .. 11.. .'. . J L J _ 1rl * .. J L. . . .. 1 +I I I I ' I *I : i I I i i i I ; ....... J. l *j* I l 1 t I I i I ! I I i I b 1 *
r * *l -* 1 1 ** * **** *** **** r * -. 1
I . ! I i i I I I -*l . * --*-** --*----*-----....... ......................... . I i I I i I I * ................... T ........... . I I l .. _ .. _ *--r .. ** L*****-.**--****4****-** ... ) .. ***u iO I I ! ! I* ! i t I . .
t ---*-*-r ** *-----1 I ! I I . I t i I I i . i . T I i ! I I. -----*\--I 1 I ! -.. -1 ! i I t I I ........... -j 1 I I .... .I. I ! I I. l I I ... ............... 1 ...... .. I I I i w L: j;....j I-('f) ' _*;!1 BI 9 / 1 i l 0 (01SdJ llHM J13IHS dGJ, CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-52 6P VS. LOG T FOR NODE 29 (RECIRCULATION OUTLET LINE BREAK)

...... ...... ..... ..---..... ...... --...,-..--t-*""-1 II I . r:..... ! . , --+--; .. 1--: __ J ..... *I I I i -______ L --* . -T----! t I I *--t . !*-' . --*-r------------l.. i I \_. i I j . . I . I I I L i I *-**-*r** i 1 . l. ! Ll °" w bcn w E 1--Ol a s I t, z o t-. (Q)Sd, 118M dO CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-53 VS. LOG T FOR NODE 30 (RECIRCULATION OUTLET LINE BREAK) l -----[----. . .. -I . ----------+-----------\ ----i l l i --r l i -l--i I i I I --* *j-----1 '1 i l l ! *-------*--------------.,.-------;----* I ! I I ; '. I ! ! .. **t****-.. I i. **-r**-----\ . . . --i ---u c..i W, 'o Cf) (Y) 'o .... ' 'oi ...... -1 9Z ZZ OZ Bt 9t Zt CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-54 PRESSURE RESPONSE OF NODES 31 , 32 AND 34 (RECIRCULATION OUTLET LINE BREAK) CPS - USAR Revision 12 January 2007

Figures 6.2-55 and 6.2-56 have been deleted. . ' i L_ Revision 12 January 2007 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPO!llT FIGURE 6.2-57 CROSS SECTION OF SHIELD ANNULUS AT LEVEL OF REACTOR RECIRCULATION PIPING

' Revision 12 January 2007 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-58 CROSS SECTION OF SHIELD ANNULUS AT LEVEL OF MAIN STEAM AND FEEDWATER PIPING Revision 12 January 2007 Cl.INT ON UPDATED POWER ST SAFETY ANA ATION L'l'SIS REPORT FIGURE 6.2-59 DIVERTER SLEEVE -OPERATING DETAILS CPS - USAR Revision 12 January 2007

Figures 6.2-60 and 6.2-63 have been deleted. 86 96 N .... ,..-.... u UJ Cf) .._.., 0 .... UJ ::E: ....... I-66 OG St 9t (VISd) CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-64 AVERAGE HEAD CAVITY PRESSURE -SPRAY LINE BREAK tl C>J -,..... u w U) .._,, 0 -w ::E: I-Ol 61 Qt lt 91 (VISd) CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-65 AVERAGE ORYWELL PRESSURE -SPRAY LINE BREAK CD ...... cc ...... .,,. -CN -....-.. u UJ (/) ..._,, 0 -UJ I-o::> o* tz e*oz 9'0Z t*oz z*oz (VISd) CLINTON POWER STATION UPDATED SAF"ETY ANALYSIS REPORT FIGURE 6.2-66 AVERAGE WETWELL PRESSURE -SPRAY LINE BREAK 0 1' t Zt N ID ID .... * .... N ... ........._ u UJ en ......... 0 ... UJ I-ID Ol (GISd) CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-67 PRESSURE DIFFERENTIAL ACROSS BULKHEAD PLATE -SPRAY LINE BREAK NOTE: See Table 6.2-13 for a description of the nodes and Table 6.2-20 for a description of the vent paths. CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-68 NODALIZATION SCHEMATIC FOR RECIRCULATION LINE BREAK IN DRYWELL FOR HEAD CAVITY PRESSURIZATION STUDY CPS/USAR CHAPTER 06 REV. 12, JAN 2007

FIGURES 6.2-69 THROUGH 6.2-71 HAVE BEEN DELETED 0 l 9 .... (0 ,,--.... u w U) ........... lJ) w I-s (GISd) CLINT 0 N POWER STATION UPDATED SAF'ETY REPORT FIGURE 6.2-72 PRESSURE DIFFERENTIAL ACROSS BULKHEAD PLATE -RECIRCULATION LINE BREAK

1 "-<:;:----_J__ ---*'1 "-""'. I I 1 nln 1lv 11 II 111 at " 1
Ii\, .:..: "' 2 *I I 23 I gl 2 I .*. f t 'l. ---l--- --24 ----------Gn:Ti 5 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-73 NODALIZATION OVERLAY FOR RECIRCULATION LINE BREAK
l

'-I f i --- ---1 1 " " ___ _ ... -ijj .J --'rl ;, ---;1<-----11'-1 £1 I 1 I 1 " t ;:.oT -.Ji i --:---_.-::-

tj --u I ! It;. 1 ;' . ----------.l I t: .I I :ti t \i14 I , '-f.P. 1 I CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-74 NODALIZATION OVERLAY FOR FEEDWATER LINE BREAK 0 f'f) I \ I :---, ___ __, ___ ---"' N OJ N N r---N ---N "l I") ..-: r-,.._; v-N r-r-r--t-r-CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-75 NODALIZATION FOR ORIGINAL RECIRCULATION LINE BREAK ANALYSIS 0 ------------------0 <1l I 1-i 0.1 (f, " .., m r-r-r-00 ..9 ...9 0() l") r<) N -0 0 I I I I I -..., i?t <Tl 00 "' r-I"-r-: -9 <} vi r-._9 r-,...... CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6. 2-76 11EQUIVALENT11 NODALIZATION (CASE A) 0 \ll N 0 0 f'J 0 ,,, c 0 G -()o
0 9 *n "' Cl ID -(J) I i:i 'c:. Hn 1--cJ .. ;:J V) Ir' i a !'b c '() '* 0 .----"----i .., I 0 117 "' P-i 0 o 8 a u o ;::J "' Vl if! 8 N Q If) Q a 0 '" 'b ,.., 0 0 CLINTON POWER STATION UPDATED SAF'ETY REPORT ., FIGURE 6. 2-77 AZIMUTHAL PRESSURE DISTRIBUTION (AT Q_RECIRCULATION OUTLET NOZZLE) ORIGINAL DATA AND CASE A 0 50 100 150 p. .. ) ;s,.13 *--0 50 JOO 150 t=o.oc; s.-c e-o*-15* Ptps.ia._)) ---0 SO /00 I.SO t=L:>.losec 8>=0°-1s* 755. "2'}1'--_.___ __ 0 50 100 t--0.01 su, e= 1s'-3o* _J -----__ ]--,--_____ -. 50 100 t=o.o5.5ec ,e.-15*.30° -------150 -p c..) Tss.<901--------'-'-------------15*0 so 100 t=O.IOStc 6J*j)*.30° '"P < ps1a.) CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6. 2-78 AXIAL PRESSURE DISTRIBUTION ORIGINAL DATA AND CASE A

-_, !V1 00 ,.,; 00 r--6') f'-w OJ _, I '-0 0J -If) --N I J CLINTON POWER STATION UPDATED SA FE TY ANALYSIS REPORT FIGURE 6.2-79 SIMPLIFIED NODALIZATION (CASE B) 2 u "' "' 0 ,0 -°' Cl ,, 0 tJ '9 . Q ,--., I 0 0 0 0 8 c 0 ('J (" v b ro© 'o I!! 'b j !::! I.I' 0 'b G a> '* .µ b '9 'o "' --o 0 8 5' 8 0 0 0 \1) "' V) (l t_ "' (") "' -J 0 v   "1SS.2'3 1----LI---.-----,-------.*-o 50 10(; 150 p ( p:.iG.) 802.23 ! ,__ ___ _.._._ ___ -----I l'S'l 1:3 -----..U....,.-----,-*-*-----,.. . o So 100 150 t El. 0"-15° \=' q>:. lc.) 801.23' t:O,OI, &: 15'-30' --:J ___ .,_ *---*-.--*-0 '>C ICC I')() {_: 0.05 e: 15"-30° p(p>rc.) J 1----1 '---** ----*-*------------1 _ - -------, I 0 )O I 0() t..' 0.10) e: 1s"-30" CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6. 2-81 AXIAL PRESSURE DISTRIBUTION CASE A AND CASE B r-I I 0) - q) ! I

I .1 ('(} N ... N '< 00 M .,,; (() <J> 00 r--r-!'--II) ['<) -U ..q-I <::! -----! I 0 -Cl (IJ N I -I I ' I "N '-" IY) 0 ::r t-r--"-' "' ;::: a r--t-t-r--r--r--r--I ' rn -d') co "" N 1j c) r--CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-82 COMPLEX NODALIZATION (CASE C)

I' --;::; 6 8 P-;; I.fl _::; f<l rn I* 1-; 0 0 £)---l<l 0 ('1 N 0 \fl r" 0 VI N 8 g <" -----_ij B 0 N 2 J Q} -,., 0 *'.) Ol 0 s II --t-J b n 6 -0 0 0 £ Ill -'b ':2_ c J .t'J* l() °o 0 <Tl 0 .. 'b ;...J -.l> 'b I: ") (} a l<l 00 b </) 0 0 "' 0 0 +' a --" CLINTON POWER STATION UPDATED SAF'ETY ANALY'SIS REPORT FIGURE 6.2-83 AZIMUTHAL PRESSURE DISTRIBUTION (AT Q_ RECIRCULATION OUTLET NOZZLE) CASE A AND CASE C 80223 15:5".'2. 0 S"IJ I (JO *, 50 C 50 100 t = o.01J Cl"--1s0 ... ) t:O,DI ;9:\5°-30° -----*--'1 ! 1$.'9 1-I ... ------.---------...-o 50 100 f50 0 50 100 t :o. OS J 5 ° 0°-lS 0 °P C.pSt11) t .-Q,Q SJ e: I 5°-30° 8:>? '"' I I I ---------=--== -i . --, I I I--------------*. l 755,29.-------'-,--*------.. ----*-.---75'5.2 9 0 5o 100 i')O 0 'P(p51'1.J 5D 1DO l : o. Io J 8 ° \ 5

3 o' CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-84 AXIAL PRESSURE DISTRIBUTION (CASE A AND CASE C) 31 N3 EB
26 27 28 E9 EB EB NlO 21 22 i3 E9 Ei EB N6 16 17 18 EB EB EB 11 12 13 33 Nl EB EB EB EB N2 N2 6 7
8 EB EB E9 l 2 3 EB EB EB I / I I \ / / oo , 3 0 ° ,, 60 ° \ ' -EL. ao*2 1-211 N3 32
EB N2 N9 I 90° 29 ED 24* EB 19 EB 14 EB 9 EB 4 E9 -* EL. 30 E9 -EL. 25 EB N6 -EL. 20 EB -* EL. 15 EB Nl -EL
EL. EB -EL. 5 E9 742'-8" CLINTON POWER STATION FINAL SAFETY* ANALYSIS REPORT FIGURE 6. 2-85 ANNULUS NOOALIZATION FOR RECIRCULATION OUTLET LINE BREAK

0 0 r--C.J Cl 0 . v CN 0 0 ... CN ({) cog er. I OJ ..... ....... ',,') *O LJ) a 0 C'I .... a 0 Cl) 1 0 /l \\ CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-87 .RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. l, 2, 3 AND 4 0 0 lJ) N 0 lJ) N N Cl 0 0 N UJ a:. I!"--...... CJ) *t::: a... c: lJ) ... 0 lJ) . ('J .... 0 0 0 i o-B. 'I I I\ I I 'I jY I I 1 7tli o-s.* Utl -l. 10°* 1 o-** 10 TIME,SECBNOS CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-88 RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. 5, 6, 7 AND 8 0 0 lJ) N 0 If) N N 0 0 a N (f) '* a: . I c--, ..... (f) *Cl Q_ c; tfJ Cl ln N CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-89 RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. 9, 10, 11, 12, 13 AND 14 a Cl In ...,.. 0 0 0 (T') 0 IJ) . Cl Cl 1 o-e... ' 1 o-'* 1 o-'* 10°* TIME,SECBNDS CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-90 RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. 15, 16, 17, 18, 19 AND 20 CJ) 0 0 0 \I) .... 0 0 l/) N 0 C) . 0 a -*O CL t; 0 lJ) 0 0 lJ) (\I 24 CLINTON POWER STATION UPDATED SAF'ETY REPORT FIGURE 6. 2-91 RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. 20, 21, 22, 23, 24 AND 25 0 0 \/) (T) 0 0 0 (') 0 0 l/) C\I (/) mo to

C.1 ...... (JJ
C::> l/) .... C> 0 0 ... 0 0 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-92 RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. 25, 26, 27, 28 AND 29 0 0 . 0 Cl 0 <N (f) ** (QO a:U: l r-..... CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS, REPORT FIGURE 6.2-93 RPV LOADING FEEDWATER LINE BREAK -TRANSIENT PRESSURES FOR VOLS. 30, 31, 32 AND 33 REVISION 6 July 1995 4. F/D Room 1 1. F/D Valve Room
t. F/D Holding Pump Room 3. Containment NOTE: -Fil 1 Junction *for Break -Flow Path 0 -Node Figure 4: See Table 6.2-37 for a description of the nodes and Table 6.2-38 for a description of the vent paths. Flow Scheme for RWCU Line Break in F/D Rooms (Case 4) CLINTON POWER STATION UPOATEO SAFETY ANALYSIS REPORT FIGURE 6.2-94 NODALIZATION SCHEMATIC FOR RWCU LINE BREAK IN FILTER-DEMINERALIZER ROOMS 5 Containment \ '" (2) 7 Figure 1 Nodalization Schematic -&-ITJ-Node i REVISION 6 July 1995 Junction j Heat sink K CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-94A NODALIZATION SCHEMATIC FOR RWCU LINE BREAK IN THE CONTAINMENT PIPE TUNNEL CPS/USAR REV. 10,October 2001 Figure 6.2-95 Deleted REVISION 6 July 1995 RWCU HX Room B 2. RWCU HX Room B 3. Containment -Fi 11 Junction for Break 6, -,Flow Path 0 -Node Flow Scheme-for RWCU line Break in RWCU Heat Exchanger Room B (Case 5) 4. RWCU over Pipe Tunnel -Flow Path o -Node 1. RWCU HX Room A. -Fill Junction for Break 2. RWCU HX Valve Room A 3. Containment Flow Scheme for RWCU line Break in RWCU Heat Exchanger Room A (Case 2) NOTE: See Tables 6.2-25 and 6.2-27 for a description of the nodes and Tables 6.2-26 and 6.2-28 for a description of the vent paths. CLINT 0 N POWER STATION UPO"TEO SAFETY ANALYSIS REPORT FIGURE 6.2-96 NOOAlIZATION SCHEMATIC FOR RWCU LINE BREAK IN HEAT EXCHANGER ROOMS NOS. 1 ANO 2 CPS/USAR REV. 10,October 2001

Figures 6.2-97 and 6.2-98 Deleted

4. RWCU over Pipe Tunnel l. RWCU HX Room B -Flow Path o-Node RWCU HX Valve Room B -Fill Junction for Break 3. Containment REVISlON 6 July 1995 Flow Scheme for RWCU Line Break in RWCU Heat Exchanger Valve Room B {Case 8) 1. RWCU HX Room A-2: RWCU HX Valve Room A -Fil 1 Junction for Break Flow Scheme for RWCU Line Break in RWCU Heat Exchanger Valve Room A (Case 6) NOTE: 3. Containment CLINTON POWER STATION UPOATEO SAFETY ANALYSIS REPORT See Tables 6.2-29 and 6.2-31 for a description of the nodes and Tables 6.2-30 and 6.2-32 for a description of the vent paths. FIGURE 6.2-99 NOOALIZATION SCHEMATIC FOR RWCU LINE BREAK IN RWCU VALVE ROOMS -NOS. 1 ANO 2 CPS/USAR REV. 10,October 2001 Figures 6.2-100 and 6.2-101 Deleted

4. RWCU over Pipe Tunnel -Fi 11 Junction for Break -Flow Path 0 -Node 1. RWCU HX Room A* 2: RWCU HX Valve Room A 3. REVISlON 6 July 1995 Figure 7: Flow Scheme for RWCU Line Break in RWCU Crossover Pipe Tunnel (Case 7) NOTE: See Table 6.2-33 for a description of the nodes and Table 6.2-34 for a description of the ver.t paths. CLINTON POWER STATION UPQATED SAFETY ANALYSIS REPORT FIGURE 6.2-102 NOOALIZATION SCHEMATIC FOR RWCU LINE BREAK IN RWCU CROSSOVER PIPE TUNNEL CPS/USAR REV. 10,October 2001 Figure 6.2-103 Deleted

1. f/D Valve Room 6., -flow Path 0 -Node NOTE: 2. f/D Holding Pump Room -fill Junction for Break figure 3: flow Scheme for RWCU line Break in Holding Pump Room (Case 3) REVISION 6 July 1995 3. Containment See Table 6.2-35 for a description of the nodes and Table 6.2-36 for a of the vent paths. CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6*. 2-104 NOOALIZATION SCHEMATIC FOR RWCU LINE BREAK IN FILTER-DEMINERALIZER HOLDING PUMP ROOM CPS/USAR REV. 10,October 2001 Figures 6.2-105 and 6.2-107 Deleted NOTE: 1. F/O Valve Room -Fill Junction for Break _ -Flow Path o -Node Figure 1: See Table 6.2-39 for a description of the nodes and Table 6.2-40 for a description of the vent paths. 2. F/0 Holding Pump Room Flow Scheme for RWCU Line Break in F/0 Valve Room (Case l) REVISION _6 July l99S I 3. Containment CLINTON POWER STATION U.POATEO SAFETY ANALYSIS REPORT FIGURE 6.2-108 NOOALIZATION SCHEMATIC FOR LINE BREAK IN FILTER-DEMINERALIZER VALVE ROOM CPS/USAR REV. 10,October 2001

Figure 6.2-109 Deleted NOTE: See Table 6.2-12 for a description of the nodes and Table 6.2-19 for a description of the vent paths. CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-110 NODALIZATION SCHEMATIC FOR HEAD SPRAY LINE BREAK IN DRYWELL HEAD CAVITY CPS/USAR REV. 10,October 2001

Figures 6.2-111 through 6.2-114 Deleted CJ) ........ a rr z '5. 1101 2. 1. --... ... -----1 L ' .. "' I -o. -1 1 a, 1 I 1 1 t

o. 10. 20. Si\Y 00103 Q21't l Clh3.6 TIME SECONDS I LIOJ1D i STEAM °'o. FIGURE 6.2-115. VESSEL BLOWDOWN FLOW RATE FOLLOWING A RECIRCULATION LINE BREAK () -0 l/) I c: l/) )> ::::0 D:::::o () fTl o ........ OJ (./) fTl ......... :::::oo NZ 0 ___,,

< 0 _J co 3. 1104 2. 1. I I I *-. ' I CLINTON MSLB BLCJ.l:Xl.N Fla.I RA TE IEPUl I I -I J ' LIOJID I STEAM ' I o ......... ...-.......... o. LO. 20. 30. '10. 51\Y 06JSIC OWL 1152.2 TIME SECONDS FIGURE 6.2-116. VESSEL SLOWDOWN FLOW RATES FOLLOWING A MAIN STEAM LINE BREAK n v (./) I c (./) J> ;o 0 :::0 n rri -I < 0,........ OJ (./) fTl ,........ :::0 0 NZ 0 __,, 180.0 1-40.0 i 120.0 -0 :t. > 100.0 I Ill i5 800 i . m eo.o '° i 40.0 20.0 0.0 10 ---....... ' i°".., .... , ' ' " ... .... -r--... ......... I"-. r-.._ *i.-.... ...__ -100 tQQQ 1QQQQ iOOOOQ TIME (SECONDS) FIGURE 6.2-117. SENSIBLE ENERGY IN THE REACTOR PRESSURE VESSEL AND INTERNAL METALS FOLLOWING A MAIN STEAM LINE BREAK 1000000 n -0 (./) I c: (./) :r> :::0 0 () -i < o ......... CD V> rri ......... :::0 0 NZ 0 -"' CPS - USAR Revision 12 January 2007

Figures 6.2-118 and 6.2-119 have been deleted. EL. 9'-.:;" EL.8S':¥-t0" I I 1---1 I I I I I I I I I I I I ---, i!ONE!. t I I I I I \ \\ \ , \----,.1 I I \ / /OUTER. HEAOER I I Revision 12 January 2007 INNER HEADER ---SPRAY 20* DOWN -----SPRAY ao* DOWN -=--SPRAY eo* DOWN ---SPRAY 20* DOWN OUTER HEADER ---SPRAY 20* DOWN -----SPRAY ao* DOWN ----SPRAY eo* DOWN --SPRAY 20* DOWN CLINT 0 N POWER STATION UPOATEO SAF'ETY ANALYSIS REPORT FIGURE 6.2-120 SPRAY NOZZLE COVERAGE CHARTS IN R,Z PLANE DRAWN WITH ALL NOZZLE ORIENTATIONS AND BROUGHT INTO ONE PLANE NOTE Revision 12 January 2007 THIS FIGURE REPRESENTS SECTION 1'A-Au Of FIGURE 6.2-120. CLINTON POWER STATION UPDATED SAFETY AN.f.LYSIS REPORT FIGURE 6.2-121 SPRAY SYSTEM AREAL COVERAGE IN A PLANE 10 FEET BELOW THE RESPECTIVE HEADERS Revision 12 January 2007 NOTE THIS FIGURE REPRESENTS SECTION "B-B" OF FIGURE 6.2-120. CLINT 0 N POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-122 SPRAY SYSTEM AREAL COVERAGE AT ELEVATION 862'-6" FROM MAIN STEAM LINE PENETRATION 1 MC-5 1 MC-6 1 MC-7 1 MC-8 MAIN STEAM 1C 1 A 1 D 1 B INSTRUMENTATION LINE V3 1E32-F327C 1 E32-F327A 1 E32-F327D 1E32-F327B H.P. VENT VJ V5 L!J L,P,ORAIN vs 1E32-F330A 1E32-F329A 1E32-F330C 1 E32-F329C TO MS IV LEAKACE CONTROL SYSTEM REVISION 9 NOVEMBER 2000 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-123 TYPICAL CONTAINMENT PENETRATIONS !SHEET 1 OF 3> -+,;Mm,P-_ TO INSTRUMENTATION INS ICE CONTAINMENT PENETRATION 1 MC-156 1 MC-165 1MC-167 1 MC-168 1 MC-177 1 MC-1 79 1 MC-1 BO 1 MC-200 TEST CONNECT ION LEXCESS FLOW CHECK VAL VE EXCESS FLOW CHECK TEST CONNECTION VALVE VALVES 1VG056B NONE 1VR016A 1VR016B NONE 1VR01BA 1VG057B NONE 1VR01BB NONE 1E51-F377B 1E51-F437A 1E51-F437B 1 E22-F332 1E22-F381A 1E22-F381B 1E22-F330 NONE 1 E51 -F377A NONE REVISION 9 NOVEMBER 2000 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-123 TYPICAL CONTAINMENT PENETRATIONS !SHEET 2 OF 31 INSIDE CONTAINMENT PENETRATION 1 MC-49 1 MC-50 1 MC-69 1 MC-70 1 MC-169 VI V1 ORA026 OMC009 1RE022 1RF022 1VR036 1 VR041 V2 ORA027 OMC010 1 RE021 1RF021 1VR035 1VR040 TO INSTRUMENTATION V2 NONE 1MC011 NONE NONE NONE REVISION 9 NOVEMBER 2000 CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-123 TYPICAL CONTAINMENT PENETRATIONS (SHEET 3 OF 3 l CPS/USAR REV. 9,November 2000

Figure 6.2-124 Deleted Decay Heat Comparison 1.90E-02 1.?0E-02 :! 1.soE-02 IA: uiro I 'i:" Q) a. 1.30E-02 *"-e 0 (.) '5 1.10E-02 i "'-:: I c 0 ; CJ [ 9.00E-03 *I a"' '--l ... Q) 7.ooE-03 I I >. CG CJ Q) c 5 OOE-03 ! "A: H5l:. 3.00E-03 --* 1.00E-03 1----------,...----------,---------=-l 1.0 10.0 100.0 1000.0 Time After LOCA [hr] FIGURE 6.2-125. THE TOTAL RESIDUAL DECAY POWER AS A FRACTION OF OPERATING POWER VERSUS -tr-Reg. Guide 1.70 Decay Heat -S-Decay n u (/) I c (/) )> ::::0 0 :::0 () fTl --1 < o ......... OJ (/) fTl ......... :::0 0 z N 0 _,, Oo N §"' ::E -.s Cl.I en ca Cl> >. e> Cl> c w Cl.I C) ca '-Cl> > < Average Energy Release Rates 16 14 _,_ __ ,,,. _ .. __ ,.,,. ___________ ... _ ... -*-*****--**--*--**---* 10 8**-*-* 6* 4 2 0 1.00E-01 1.00E+OO 1.00E+01 1.00E+02 Time After LOCA [Hour] FIGURE 6.2-126. THE BETA, GAMMA, AND BETA PLUS GAMMA ENERGY AS A FUNCTION OF TIME ,--------**-****------*1 *-e-seta - Gamma I "!:. () -0 (/) I c (/) J> :::0 0 :::0 () rri -l < o ........ OJ (/) rri ........ :::::oo NZ O__,, Oo N Integrated Energy Release Rates -:!!: -Q) 1;; 0:: 15 i-Q) en cu (I.) Qi 0:: e I Q.) 'A 10 *l b(' ::;= 'O Q.) -CJ .s .5 5 a 100 200 300 400 500 600 700 800 Time After LOCA [Hour] FIGURE 6.2-127. THE INTEGRATED ENERGY RELEASE OF BETA. GAMMA. AND BETA PLUS GAMMA AS A FUNCTION OF TIME *-*--*-------*---**-----1 !-a-Beta I 0 v (./) I c (./) J> :::0 0 :::0 0 fT1 -l < 0 ........ CD V> fT1 ........ :::0 0 NZ 0 -->. Oo N 180.0 160.0 -140.0 Q) 0 E .6 ;::. 120.0 c: 0 ; ('IS .... 100.0 Q) (.!) s::: Q) en 80.0 e "C :::c: "C 60.0 Q) -en Q) -.E 40.0 20.0 0.0 0 100 Integrated Amount of Hydrogen Produced in Drywell for EPU (pH 5.6) 200 300 400 500 Time After LOCA [hr] FIGURE 6.2-128A 600 700 n v (/) I c: (/) )> ::::0 ' Reaction -*-*1 -a-Radiolytic ! -e-Aluminum Corrosion \ I -&--Zinc Corrosion D::::o () [Tl -l < 0 ,__. OJ (/) [Tl ,__. ::::oo NZ 0-" 2o Integrated Amount of Hydrogen Produced in Wetwell for EPU (pH 5.6) 'i' 0 E I .a 60.0 50.0 ;:::. 40.0 -c 0 Q,) c G) C> 30.0 c Q,) tn e "O >. :::c -g 20.0 -e tn .e .5 10.0 o.o I imoJoeoo o al o o o o Io o o o lo o o I o e I o o I j 0 100 200 300 400 500 600 700 Time After LOCA [hr] FIGURE 6.2-1286 () -0 (/) I c (/) )> ::::0 Radjolytic -S-Aluminum Corrosion D;::o (") fT1 -1 < o ......... DJ (/) fT1 ......... :::0 0 NZ 0-" Integrated Amount of Hydrogen Produced in Drywall for EPU (pH 8.6) 180.0 -------.------...,-----r-----,------r---160.0 ';' 140.0 0 E I .c .::::. 120.0 c 0 +:: E 100.0 Cl) C!> c Cl) g> 80.0 -11.. "C :r: 'i 60 0 --. C"CS .... C> .s .5 40.0 20.0. 0.0 I 0 100 200 300 400 500 600 Time After LOCA [hr] FIGURE 6.2-129A 700 ('"") u (/) I c (/) )> ::::0 --f:r-Zr*Water Reaction a-Radiolytic -e-Aluminum Corrosion Zinc D::::o ('"") f1l -l< O,__, CD (.f) f1l ........ ::::oo NZ O___,, 100.0 90.0 80.0 I 'i' 0 e ..0 70.0 c:. c 0 ; E Cl,) c Cl,) (!) c Cl,) CJ e 60.0 40.0 :c "tS C1) 30.0 CJ .s .5 20.0 10.0 I I I I

Integrated Amount of Hydrogen Produced in Wetwell for EPU (pH 8.6) I I I 0 u (./) I I I ,./ I I I I c (./) )> ::::0 I l I /I I I -a-Radiolytic -S-Aluminum CorrosionJ 0.0 0 100 200 300 400 500 600 700 Time After LOCA [hr] FIGURE 6.2-1296 0 ::::0 () r1l -l < 0......., CD (./) r1l ........, ::::oo NZ 0 __,. 2o 10.00 9.00 8.00 -7.00 e... c: C1> en 6.00 0 ... "C :c .... 5.00 -c C1> C1> a.. 4.00 C1> E :I 0 > 3.00 2.00 -1.00 0.00 I 0 -Containment Hydrogen Concentration for EPU (pH 5.6) 10 100 1000 Time After LOCA [hr] FIGURE 6.2-130A () -0 (./) I c (./) )> ::::0 --+-Drywell Uncontrolled -e-wetwell Uncontrolled -a-Dryvvell Controlled --tr-Wetwell Controlled D::::o () rri --1 < o ......... OJ V> rri ......... ::::oo NZ 0 _,. Oo N 10.00 9.00 8.00 ...... 7.00 e... c Q) C> 6.00 0 .. "C >. J: -5.00 c: cu Q) a. 4.00 Q) E = 0 > 3.00 2.00 -1.00 0.00 0 Containment Hydrogen Concentration for EPU (pH 8.6) 10 100 1000 Time After LOCA [hr] FIGURE 6.2-1308 () lJ (./) I c (./) )> ::::0 J Drywell Uncontrolled 1-e-wetwell Uncontrolled -a-Drywell Controlled Wetwell Controlled 0 :::0 () rri _, < O,__, OJ (/) rri .......... :::0 0 NZ 0 _,. Oo N CPS - USAR Revision 12 January 2007

Figure 6.2-131 has been deleted. © , -@ o I -Revision 12 January 2007 &.i::::_::::.i.------1 ,... -*---&-----*-*----PtG. *.2 32--&. Sl!T. 5 -.:.oc.-.--..... --*-. ............. _ ... __ -CLINTON POWER STATION UPDATED SArETY ANALYSIS REPORT FIGURE 6.2-132 SECONDARY CONTAINMENT BOUNDARY (SHEET 1 of 6) T r 1:1 Revision 12 January 2007 CLINTON POWER STATION UPDATED SAFETY ANAl.YSIS REPORT FIGURE 6.2-132 SECONDARY CONTAINMENT BOUNDARY (SHEET 2 of 6)

r. . '.J

I ' *n ,.. .. * '" ... .. ... ,,. * ... ... .. .. .. * .. * .... * * ... .... 10 GPM 1E12D331 ECCS SUCTION STRAINER K-28888 OVT51 DE COJff DISTANCE CONT. INSIDE <ONT. 18130003 REACTOR PRESSURE VESSEL K-2801 DRYWHL PENETRATION REVISION 18 OCTOBER 2016 /"//////, INDICATES THE BOUNDARY OF THE CLOSED LOOP OUTSIDE OF CONTAINMENT. * * * *

INDICATES PIPING CONNECTED TO THE CLOSED LOOP OUTSIDE OF CONTAINMENT WHICH LEAVES THE SECONDARY CONTAINMENT. NOTE: ALTHROUGH HIGH POINT VENTS AND LOW POINT DRAINS ARE NOT SHOWN AS PART OF THE CLOSED LOOP, THEY ARE PART OF THE LOOP UP TO THE FIRST BLOCK VALVE. LPO oo 11-P21A ILP2lB LPC5 FLUSH AND PIPING DRAIN 191:;-0003 L.w.L, 730'-ll" CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-143 LOW-PRESSURE CORE SPRAY (LPCS) P&ID WITH OUTSIDE OF CONTAINMENT BOUNDRY 11111 1 .. '

LWL 730'-ll' 1E12D331 1£120331 ECCS SUCTION STRAINER K-28888 11113*0003 fiEAClOO m:ss.JlE VESSEL K-280! IE22COOI HPCS Pl.MP K-260! r--*--------------, ! I NUCLEAR .SAFETY RELATED ITEMS .uE SHOWN ON THIS DRAWING 1 fOI SAfflY ClASSl!llCAIDI SH PIPING, -** VAi.Yi. Ol .IHS-U5'$.I NOU *tHI& r l I D1C & I OtAGIAMS fOt *Ht ( & I 'llHCTIOH SfMIOU All SHOWN OH OlAWIHG MIO-j2!i UHllSS OTMUWIH HOTlO. SHEET -& **** .. NQ. .l.U -.... I IU2. 001 0-"&' tf.JM8Ell IE22f035 IEZZF039 IE22FOl<I REVISION 14 JANUARY 2011 RBJEF \(6.1.\IE DATA VALVE SET Bl.OW MAKE I. TYPE SIZE PRESSURE DOWN CAPNCITY (PS I) DRESSER I** .. '/4id XFM&*NC 3007 550-PSIG. FIXED 81GPM. DRESSER 3/4.1975-3!3-t4-2J 1_,,..xl' JO GPM -XFA&D*NC3007 500 PSIG, FIXED fU'"'=er< 21 3/<l"x1' XFM9-HC3007 00 PSIG FIXED I!> GPM. :!..!he t&1munt. * **** ..... ENGINEERING NOTES: I. CHECK VN.VE IE22-f024 SHAU. BE LOCATtD AT ELEVATION BELOW THE SUPPRESSlON POOL LOW WATER LEVEL (730'-1 I"). 2. AU. PRESSURE RELIEF VALVES SHALL BE REMOVABLE FOR TESTING. J. ALL CHECK VN.VES EXTERIOR TO THE CONTAINMENT SHAU 8£ TESTABLE TO VERIFY FREE MOVEMENT OF THE VALVE DISC. VALVE LOCATION SHOUlO EASILY ACCOMMOOAT£ THIS MANUAL TESTING. 4. "MllllMN. DISTAl'IC£* THAT THE PIPING DESIGNER SHOULD HOLO THE INIJICAT£0 OISTANCE TO 8£ 1'S M!NIMN. 1'S PRACTICALLY POSS/Bl£, WITH CDNS10£RATION FOR ISi ACCESS. 5. 1£22-R002 IS ABANDONED IN Pl.ACE. SEE FOOR LHl-4162-1 6. £QUAUZJNG IS OPENEO 8Y ENERGIZING THE AIR SOLENOID LOCN.LY FIELD NOTES: I. VALVE IE22fD2J SHALL BE INSTN.LED WITH THE PACKING GlANO OH THE UPSTREAM SIDE Of THE VN.V£ DISC. 2. TEMPORARY IN LINE STRAllER (CONICAL TYPE) & OlfFERENTlAL PR£SSURE GAUGE 1'S SHOWN INSTALlEO OURING PR£-QP. & INITIAL START UP TESTING ONLY. (SEES & L STD. NF-270.9.1) REI.IOI/£ FOR NORI.IN. PLANT OPERATION & CAP & WELO GAUGE PR£SSUR£ SENSING LINES 1'S 3. FOR HPCS LOGIC SEE GE DWG. 828£314. 4. SPOOl PIECE FOR TEMPORARY IN LINE STRAINER FOR PRE-OP & INITIAL START UP TESTING ONt Y. REI.IOI/£ STRAINER FOR NORMAL Pl.ANT OPERATION. 5. RESTRICTING ORIFICE SIZES INOCATEO AR£ Fffi 11.!TiAl SYSTEM STAAT uP ONLY. AOJLIST 1'S NECESSARY TO MEET HYORAIA.IC REQUIREMENTS. 6. SUND FLANGE FOR HYffiOSTATIC PRESSURE TEST ONLY. REMOVE FOR NORMAL PLANT OPERATION. CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-144 HIGH-PRESSURE CORE SPRAY P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY Note: POOL. Althou9h high point vents and low point drains are not shown as part of the closed loop, they are part of the loop up to the first block valve. 1E12D331 ECCS SUCTION STRAINER ****** K-28888 Indicates the boundary of the closed loop outside of tainment. Indicates p1p1ng connected to the closed loop outside of containment which leaves the secondary containment. m13f:)(;)(n REACTOR PRESSURE VESSEL K-2801 eacoo:s Rel C WQER LEG RW K -282G.
I* ,au PAESS:IJR£ fl£UF IN.lift SHM.l E l. AU. O!EO \WYU: Olt"SU OF TH! COHNMEHT IE i::saa.f 10 "8WT '1IEt lilOll9elT °' 1'H( DIS(. \lllUj( lOC'Jlll<lN (ASlt't ....UM. fES1lll(.. l ..... Wil mtMf((" M£MS M ....... , gQA,O tO.D M NKATEO CIS1NfC£ 10 II[ AS llS; PIW'.tlOIU.Y "POS$11LE WITH '1'1'El'I 10 m M:C:US, S. MAXM.M 1'0ll\tl.. lMl./ll M M R)..LOlllll(. Pt>! lNS SIWJ. IE iO I'm: I Rl5JA,IRl!l38. IRl53C &1Rl101A. '-IJWOlillM lJllll( Uf l8Gtf Of 'nC Piii'( IAl41A ........ lJlj(Mt llJIQlf Of PIP8 llUHA IC/ IAl<IOA MICJ..

6 R£f 1* flllll L*H lltMA. IR140A Me lltfl'tA Fl8.D NOnS : REVISION 12 JANUARY 2007 I* TEMPORMT IN l.l4f M'£) NCI DlfflR9lfW. lllSllltLe> iNf-uP Tur-OllU. AOllOWE Riil N()AliilAL flUW OP£RAnk,.IM! CN' llMI MU> AS {sa s t. tm. w. ZJO.u) l. RJR AOC UlCIC SU ;.1, "'°"* .... *A$SOQJll8) e:uPMEMI': SIZES NIE RIA MlW. Sl'Nl'f-Ul" !IOIMllt. Of'Uil,1'10N .AlllUS1' 1Mt: MWOAilUUC 1WE"21A) i **--l"'UIHT Of'll['lltATl()tf.;. ' 8. l.OCATE TE* 111: 3 l-N010£l eio.ow lffJ l<S CLOSE 10 TM: llEFUE..INIJ BUU<HE;IO AS l'OSSl8lE. i__,,,,....-,...,..... SUJlll! llQllllM QJifG NUCUAa SAJ1TY 111.AJID "8d Ml ,..,_.ON RIIS -SUl NII '1.#K.I. I* lllll'llM 0SC "'911' tO I( DlllCTID 1l;lllUC CIJUML. 'IUllll£ DHilJSf UI( --!tWJ. k 10 f1tON ll'S1lllilll SU <:I Ql8JC INK TO ttC n.-.. etW.l!ii1 <RMi POI', ,.,, at OUk WJllf 10. JWI, .. .... lolll'llYc:uiWAllCllll -...... ...... .,. ra1ac:*1..,..._11G1 RllCll =::.=-.::.-:: CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-145 REACTOR CORE ISOLATION COOLING SYSTEM P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY E D c B A 8 't:.,01* SOW lndiC*tes the boundarv of the elo*ed loop out*ide of" taim.ent. Indicates pini!ICI connected to the eloaed looti outside of containment Which 1-*e* the secondary COQtairnent. Althouqh high point vents lov point drains are not shown ** part of tbe cloaed loop. they are pa.rt Of the loop up to the firat block valve. IA ' DRY WELL BULKHEAD "Ei..so5*5j0' 1 i----------ORYWELL WALL---------11 *1H6 010 B CONTAINMENT llf60100 SUPPRESSION POOL. 10 HOfUZONTl..L SPARGO. FVRW. ev P.t. NOTE: I. WHE"I UNIT Z. 15 INSTALi.ED, ""LVES IHGO°'-AND I HG007 SHALL l!.E LOCKED CLOSl!.D, A"ID VALVES A>ID 2.HG007 SAALL !1£ LOCKED OPL"I. 8 r------WEIR. IHG05C 86 IHGO CA VENTS " ORYWELL BULKHEAD a.eos*-s:io' QHGOISA HYDROGE.N RE.COMBINER K-l862 -.----, I c.::r*--. u.u.a-Paoo J I I 11 Ii

t MGOS.5"-6 Q. ____________ J 1 tHC.06A.C 10 " s . IHl3 *P&76 ___ j CONTAINMENT r;l;;:;HG;;;O'i!f nl""-, SUPPRESSIO"I POOi.. NOTE* n<E P&I wt-i.1 DI--TME C&I IUGOO:I FUNCT---S -SHOWN ON DIA-UNllSS On<E-SE NOTID. -n -UI a DIAGllAM Hl'HINCI -SltOWN .. 'IMI SY-.. 3 2. REV. 2 SEPT. 1990 IHG02CA & IHG02.CB CGCS HYDROGEN COMPRESSORS K_:..2663 M05*2.0f.3 E*6 M05*2.0 E.*8 "AUi. &.oc;,. lfi--,----------<11-.CC-NTR.OL. &LO<it. OHGOISA I IMl3 .. Pel:JO TIVJIJCLE L L_-µq LJ :moueLE !'eoo 'CLINT 0 N -POWER S-TA*TIO N UPDATED SAFE.TY ANALYSIS REPORT FIGURE 6.2-146 COMBUSTIBLE GAS CONTROL SYSTEM P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY (SHEET l of 2) c B E 0 c B llDHS t'.90"2-5011'1 A.lthou9h hi9h point vents and 10¥ point drains are not shown as part of the closed loop, they are part of the loop up to the first block valve. OHGOISB CGCS H'IDROGE.1-l RECOMBINE.R K-2.862. 2.HG02.CA & 2.HG02.CB CGCS tlYDROGE.N COMPRE.S50RS 2.A & 2.B K-2. 8.b2.. DRYWELL SULt<HEA.0 EL.!103'*5)/o" DRY WELL BULK.MEA.0 REV. 2 SEPT. 1990 1----------DRYWELL WALL---------t ..... E*t lndiclltes the t-oundarv of the* loco outside of taimient. lndicatf'S oit1inq connected to the clolte<! loon OUt!iide of containrnf'"t whicl'> le.aves the secondarv containl"lent. h OHGOISB 2. Ol-\O:io1A'2. -I 10 -I 2.MGO&AD 10 81 P.c. . t---1;;:-=-:'.:::f"--' H0Rl1.0NTAL1 SP .. RGU, !-------WEIR WALL -------! HG05C.A I. ' SUPPRE.S>SION POOL VENTS NOTES,: I. WMEH Utf11' 2. ,, VALVES IMG006 A.ND tMGOO,. ,H-..Ll &£ l..OC.KID CLO&EO, ANC VA.LYES ZHG006' .. NO 2.HG001 Sll .. LL 8E LOCKED OPEM. NOff, TM( r & I DIC & I OtAGIAMS Fe. fHE C & I FUNCTION '-S AM SHOWN ON DIA-MIO-zoc;;3 UN\ISS OnEIWISE NOTEO. SHHT NUMIH & DIAGIAM HFHINCE All SHOWN .. THI FUNCTION STM90l. IA IA IA IA CONTAINMENT iHORIZO>IT*I. SP,.ll.<>Ell. FURM. P.C. ._.,,._.,.....-+----I VENTS SUPPRE .... ION POOL WEIR W"LL A.NNULUS CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-146 COMBUSTIBLE GAS CONTROL SYSTEM P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY (SHEET 2 of 2) 0 c B F E . ta2BOOI-' D HT.EXCH. ' M05*1075 ' s.<r<< c-1 c IE12C002A RHR PUMP IA IE120301A SLCTlO'I STRAINER IndlcotH roundarv of the elo&fl!d loop outside of tAit'Pent. ***** liv'ic*tes oi.rinq connected to tht" loon OUt$itt,.. of eontairvMmt which leavtts the secondarv contaiN'l:*nt:. Although hiqh pcint vents and luw point drains a.re not shown as part of the closed loop. th-ey p.trt e! the toop u;> to !ust block valve . 4 I .fONTAINMGNT ! 18130003 REACTOR PRE$URE VESSEL L.I.. I I N 12 J NU RY 2 07 FIGURE 6. 2-147 RESIDUAL HEAT REMOVAL SYSTEM P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY E 0 1813*0003 B/'\OCP BlObCP lfl.1?.*0003 REACTOR PRE.SSURE: VESSEL K*Z.BOI PT*1C9 RELIEF VALVE VALVE HUMBER MAKE & TYPE IEl2F0258 ORESSER 1970*213*1 2) *XFA32*NC3007 IE12f030 *XFA32

NC3007 !El2F017B -XFA:32 -Nl.."3007 DATA ivALVE SET SIZE (IN.) PRESSURE I 484 PSIG. I ISl!7 PSlG. 200 PSIG. ...... ::... ............ FW.llR 5UPAAESS!ON PML IEl2.C002.El RHR PUMP IB K-2.BOI REVISION 12 JANUARY 2007 *-GPM. 66 GPM. 42 GPM. 43 GPM. CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-'147 RESIDUAL HEAT REMOVAL SYSTEM P&IO SHOWING OUTSIDE OF CONTAINMENT BOUNDARY SHEET 2 OF 4 :z 0. (\J t.iJ 1813-0003 LWL 730-11° u lC ! 8 .. i !! .. " i 1E12D331 (I i .. 1113--0003 IVC10R \£SSEl... K-280! 1E12COOl WATER LEG PUii' K-28268 1E120331 REVISION 18 OCTOBER 2016 182C002C RHR PUMP IC ECCS SUCTION STRAINER K-28888 RELIEF VALVE DATA **** !0£120 fo zg/ SPACE'{ ?tm"E F"IUL -Ind1c:at.e* the tound*cy of the c:losed loop oqt.al.de of -tairmant IDOa.c.ata p1p1ng C'Onnect:ed to tbe clo.ed loop oatsl.de of t llhich lM'"* ODl'ltalml*nt: ... Pt.IDIC&I---Cal ___ _._ ......... ---.. MAKE & TYPE SIZE ITY 1£1ZfVZ5C IEIZflOt Alt1\01.19h b po1n.t. *enta and low Po ot O uns ue nat shmm os psrl:. ic:>f the cloMd loop they aire part of tho loop ap to tbe bluc:k <<1** . I I ' I I I I 1 I . I I 0 PAESstJffE GPM 1/2 x 1 464 PSIG 6!0 GPM 213 1-1 21 '/ 2 x 1 100 PSIG 30 GPM *-F0'9 E14'jlMEER)Nllt NOT£. l IEJZ j CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-147 RESIDUAL HEAT REMOVAL SYSTEM P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY CSHEET 3 OF 4 l SHUTDOWN M05-1052. S!lT.2. E-1 .,\USAR\rev12'AG6 l47-4.dgn 11/16'20l505:35:57PM _i_ -FROM RHR LOGIC IE12BOOIB RHR HEAT EXCHANGER K-2801 i I I I I I I I I I I I I I I ,---------_ _J ' I I I IE12BOOIB IRf%ABllf.!. $MT * .S C-5 IE12BOOIA RH R HEAT EXCHANGER K-2.801 IE12BOOIA r I I I I I I l_J I REVIS ION 12 JANUARY 2007 POOL. 5HTI B*4 \ L12':>w**<-AR. llt..Jii:$ tRJ.llD7AIJ?.>f<. T'O 1!21-1G7A£.'!>,4c." (AO EXQ.IJDED) l

12 SIMILAR LINES IRH67AA 314" TO IRH67AM .. (AI EXCWDED) CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-147 RESIDUAL HEAT REMOVAL SYSTEM P&ID SHOWING OUTSIDE OF CONTAINMENT BOUNDARY (SHEET 4 OF 4)
' @ 26 ' ' ' . @ 21 -22 -j ' j' @ 16 -17 -H J * @ @ 11 12 --I -- j' j ' -29 @ -I (10)_ 6 -,.© .,© 1 CD 2 --28 j ' @ 27 --H ' ' @ @ -23 -24 ---' ' j ' -18 -19 ----' . a @ 13 14 -----J
J * @ @ 9 ----j' ,,(j) CD 0 CD CD 4 --CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-148 NODALIZATION SCHEMATIC FOR SACRIFICIAL SHIELD ANNULUS PRESSURIZATION ANALYSIS -RECIRCULATION INLET LINE BREAK j' @ 25 a 20 j' 15 Jl 19 10 J

9 5 29 28 CONTAINMENT EL. 802 I 2 II .N3 t-2_6 _____ ....,... ___ --4.,._2_7 _________ ___.._ EL. 7 9 4' N4

N4 NS NS 21 22 23 24 2S 77 8 I -EL. N6 N6 .,.1_6 _ __._1_7 __ ..... 1_s ___ ..... _19 ____ -+_2_0 ____ .... _ EL. 7 6 2 , 0 II 7 8 9 10 __ _._ ____ EL. 7 S2' II 6 1 2 3 4 s __ __..___ ____________ ___.. _______ EL. 7 4 2 I 8" 90° 112.S0 142.S0 180° 22S0 I 270° CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-149 ANNULUS NODALIZATION FOR RECIRCULATION INLET LINE BREAK
-oz 91 z l 8 0 -*o -,.-..... (f) q :z: 0 u w (f) w I--1 (GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-150 8P VS. LOG T FOR NODE 1 (RECIRCULATION INLET LINE BREAK) l ! I -'o -(t) UJ I-I 'o -tZ Ol 91 Zl 8 t 0 (OISd) llVM 013IHS dV CLINTON POWER STATION UPDATED SAF'E.TY ANALYSIS REPORT FIGURE 6. 2-151 VS. LOG T FOR NODE 2 (RECIRCULATION INLET LINE BREAK) -I -'o -N 'o -(") 'o en 0 z. 0 u UJ en UJ ::2:: I--Ol 9 ! l! B 0 v-(GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-152 VS. LOG T FOR NODE 3 (RECIRCULATION INLET LINE BREAK) oz 9 l Z t B 1' 0 (GISd) llVM Ql3IHS dV -b ..... .......... (/) Q z 0 u UJ (/) UJ ::E: I-v-' CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-153 6P VS. LOG T FOR NODE 4 (RECIRCULATION INLET LINE BREAK) --'o -('t) *o .......... U) Cl z: . 0 u w U) w I--oz 9 t Zt B 0 (GISd) 11VM G13IHS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-154 VS. LOG T FOR NODE 5 (RECIRCULATION INLET LINE BREAK) -'o -,,...... (/) Cl z c-.1 0 bU -w (/) ..... 'o w I--09 OS Ot 01:: oz 0 I 0 01-(GISd) llVM Gl3IHS dV CLINTON POWER STATION I UPDATED SAF'ETY REPORT FIGURE 6.2-155 VS. LOG T FOR NODE 6 (RECIRCULATION INLET LINE BREAK) -oz St Zl B 1' 0 (GISd) llVM Gl3IHS SSOHJV dV .... b -CN 'o -,,...-.. . (/) 0 z 0 u w (/) w :E I-(Y') 'o -CLINTON POWER STATION UPDATED SAFETY AN*LYSIS REPORT FIGURE 6.2-156 8P VS. LOG T FOR NODE 7 (RECIRCULATION INLET LINE BREAK) 9:i .... .... b ..... (r) Cl z 0 u UJ (/) UJ I-b .... oz 9l Zt g 0 (GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-157 VS. LOG T FOR NODE 8 (RECIRCULATION INLET LINE BREAK) -.... b ..... (I") 'o ,...--.. (/) Q z 0 u w (/) w I--Ol 9l 2:! B 1' 0 v-(GISd) llVM Gl3IHS SSOHJV dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6. 2-158 VS. LOG T FOR NODE 9 * (RECIRCULATION INLET LINE BREAK) 'b -.... 'o .... N bl -.......... (./) 0 z: 0 u w (./) w I-(Tl 'o -oz 91 Zt B 0 1'-(GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-159 VS. LOG T FOR NODE 10 (RECIRCULATION INLET LINE BREAK) 9:J --'o -',.-..... (/) 0 z c-J I Q bl u -1 "<t" 'a .......... UJ I--09 OS Ot 08 oz ot 0 ot-(QISd) llVM 013IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-160 VS. LOG T FOR NODE 11 (RECIRCULATION INLET LINE BREAK) 'b -b -......... (/) Q 1z io u UJ (/) UJ I;:: (f') 'o -oz St Zl 8 '\1 0 v-(CTISd) llVM CT13IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-161 6P VS. LOG T FOR NODE 12 (RECIRCULATION INLET LINE BREAK) 9::i (GISd) llVM Gl3IHS dV ,..-..... Cf) Cl z 'O 1.u 'w Cf) '--" w I-CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-162 6P VS. LOG T FOR NODE 13 (RECIRCULATION INLET LINE BREAK) I % I t--'o -,....... N 'o ..... (t} 'o U) Q z 0 u w U) w ::E: I-..... Ol 9t Zl 9 t 0 t-(QISd) llVM Gl31HS dV CLINTON POWER STATION UPDATED SAFETY REPORT FIGURE 6.2-163 VS. LOG T FOR NODE 14 (RECIRCULATION INLET LINE BREAK) ..-'o .... N *o .... ('f') 'o .......... (/) 0 z 0 u w (/) w ........ I--Ol 9t lt B t 0 (GISd) llVM Gl31HS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-164 VS. LOG T FOR NODE 15 (RECIRCULATION INLET LINE BREAK) <=ti --b .... .o *u UJ en UJ I-(") *o -oz 9t ll g v 0 v-(QISd) llVM Ql3IHS dV CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-165 VS. LOG T FOR NODE 16 (RECIRCULATION INLET LINE BREAK} CtJ -..... 'o -N 'o ..... ......... (/) 0 z: 0 u . w I (f) '--" w I-('f) 'o -tz oz 9t Zl 8 t 0 t-(GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-166 VS. LOG T FOR NODE 17 (RECIRCULATION INLET LINE BREAK) 'b --'o -N b -(/) Cl z 0 u w (/) 1W I-(") *o -Ol 9l Zt 8 t> 0 (GISd) llVM Ql3IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-167 VS. LOG T FOR NODE 18 (RECIRCULATION INLET LINE BREAK) Ct, -oz 91 Zl B v 0 (OISd) llVM 013IHS dV -b -N 'o ..... v-,.......... (/) 0 z !O u LU (/) "---" LU I-CLtNTON POWER STATION UPDATED SAFETY REPORT FIGURE 6. 2-168 6P VS. LOG T FOR NODE 19 (RECIRCULATION INLET LINE BREAK) 9::i --b -,,..-.... . Cf) Cl z: 0 u I UJ UJ :E: I-(r') *o -oz 91 Zl B 0 (GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-169 6P VS. LOG T FOR NODE 20 (RECIRCULATION INLET LINE BREAK) .... vz oz 91 Zl B 0 .... b ..... (I") 'o .... ....-.. Cf) Q z 0 u UJ Cf) UJ I-(GISd) llVM Gl3IHS dV CLINTON STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-170 !:IP VS. LOG T FOR NODE 21 (RECIRCULATION INLET LINE BREAK) 9:J --*o -,..-.,. (/) 0 z: 0 u w Cf) (Yl 'o -oz 91 ll B t 0 (GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAFETY AN ALY SIS REPORT FIGURE 6. 2-171 VS. LOG T FOR NODE 22 (RECIRCULATION INLET LINE BREAK) -b -(I") *o w :::?: I--oz 91 Zl B v 0 v-(GISd) llVM Ql3IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-172 VS. LOG T FOR NODE 23 (RECIRCULATION INLET LINE BREAK) q, -Ol 91 ll B 0 .... 'o -N 'o -t>---(/) 0 z 0 u LU (/) LU ::E: I-(GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6. 2-173 VS. LOG T FOR NODE 24 (RECIRCULATION INLET LINE BREAK) (I") 'o UJ ::E: I--tz oz 9t 61 0 (GISd) llVM Gl3IHS dV CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-174 VS. LOG T FOR NOOE 25 (RECIRCULATION INLET LINE BREAK) 9:, -.... 'o .... N 'o -(T') b ,....,, (/) Q z 0 u UJ (/) UJ I--s z 0 t-z-(GISd) llVM Gl3IHS dV CLINT 0 N POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-175 VS. LOG T FOR NODE 26 (RECIRCULATION INLET LINE BREAK) Cb -... 'o -N 'o -(t) 'o ...-.... Cf) 0 z 0 u UJ Cf) UJ ::E: I--s 0 t-z-(GISd) llVM Gl3IHS CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-176 VS. LOG T FOR NODE 27 (RECIRCULATION INLET LINE BREAK) .... b .... ,.-... U) Q z c-J 0 bu .... UJ (I') b .... ..... 'o U) UJ ::E: I-.... OZt oot OB 09 01' OZ . 0 oz-(GISd) llVM Gl3IHS dV CLINT 0 N POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-177 VS. LOG T FOR BREAK NODE (RECIRCULATION INLET LINE BREAK) --b ... N b -C'l b ,.,..... (/) 0 z 0 u UJ (/) UJ ::E: I--Bl Ol st Zl 8 0 (VISd) 1N3WNIV1NOJ CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.2-178 CONTAINMENT PRESSURE VS. LOG T (RECIRCULATION INLET LINE BREAK) .r: E *-0 0 u a: c co Ci I'--c -0 ?o c oE E 0 0 a: (/) ..... 0 0 <ti ..... c 0 0 (/) QJ x 0 ro c 0 0 c :::J .., c 0 w*.;:: ..... :::J .c (/) *-(/).::: <ti(/) 00 I I I (/) ..... QJ c Ol 0 f-L-----------480VAC Class 1E MCC -(/) c c QJ 0 E .... c <ti --QJ c c 0 Q) 0 a_ \. (/) ..... -(/) *-u c QJ Ol QJ -LL QJ <ti 3: -6 >. ..... > Ou c 0;::; f-CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.2-179 SINGLE LINE DIAGRAM IGNITER POWER SUPPLY FOR ONE DIVISION c Q) E c <ti c 0 0 Ol c u :::J ro >. ..... <ti x :::J <l'. CPS-USAR __ . ibP Df= 'IESSC:l.. MV.D -' l !D S"'l"a. \.\ LE.::G-ENO l ..,...., .... .....,y,-.... ._OH""*"""" I ' ..-:§),--i ,._... I --C---Hl).J(ri: ! 1 -----. CUGIO ME:ME.ER I -o
_ IJJl,.U POl:-."'T l 0 Mf:'.ltSEP. Reactor Pressure Vessel and Internals Horizontal Figure 6.2-180 Beam Math Model AP Event 8Z. [§ e+ 85 G1 11 //./I CPS-USAR K4 ... 12. c-+t7EJ i3 (fil 74 71 '" '" 1--"lr----' 211;111211111 1 I o-W-&x;., U/)M Fl':t.E:D NOPE f;! '4 65 9 c kJ ,. 54-(:7 (@ tS "---,, 69 Kl [@ iO -1 f! t7'1 \!;?CF=' /,,,'"/;/// Figure 6.2-181: Drywell, Shield and Pedestal Horizontal Beam Math Model AP Event 26 E9 t 21 E9 16 EB lC 31 EB 21 EB .-. -22 N6 I. 7 EB y N3 0 28 EB 23 © 18 EB CPS-USAR N3 32 0 EB 29 30 E9 EB * ... 24 25 EB 0 EB j6 19 20 E9 E9 11 I 12 13 I 14 15 l 33 EB I EB EB I E9 EB N -'!:'. 802'-2" ;;'T -_..,_ _EL . 784'-3'-i" -EL. -EL

7 6 3 ' -5 II ;,..N2 ... N2 ,!.N2 .'12 If. 6 I 7

9 10 I 'l/ ) -.... -t w " -\--ffi- - ---$---EL. 758 ===:L. 757 1 2 3 5 t. EB EB EB EB Figure 6.2-1a2\ Annulus Nodalization For Recirculation Outlet Line Break f N3 N3 N3 NJ *

0 * * \ I / 'rj to'* (IQ c EL. ?94.04'-t1 ro °' I I N EB EB ED EB EB EB EB I 1--' 26 27 28 29 30 31 )) co __w EL. 796.00'-13( .5f)' l58]-f -=--= ---1 )::> ---N*if 41>>. -N"S" ::I EL. 782.75'-::I EB EB i:::: __. 15 l6fXI. ED ffi i:::: ED , ___ n 21 22 Vl = EL. 778.27'-17 . IJ_ --12 0 0.. N6 N6 I N6 OJ __. (') ...... 8j N ffi E9 EB E9 E9 ltj OJ (/) rt I ...... 9 10 11 12 13 14 c::: 0 ::I (/) EL. 770.00'-::z:,. -ti ::c:i 0 -s ,, ro EB I ro ED EB ED 0.. OJ 5 6 7 8 rt <D ) Nl N2 N2 N2 N2 N2 Nl N2 N2 IN2 N2 N2 Nl r EL. 759.29'-..... ::I (j) I

I I

co N9 N9 -s <D OJ I I I A" EB E9 EB E9 1 2 3 4 t EL. 743 .17 ' -01) 90° 1U0° 270° 360° 270° (Global) CPS-USAR t N y 90° .,._ __ (Global) Figure 6.2-184 Break Location Feedwater Line Break t N CPS-USAR ' I I 1 "' 67.5° goo __ _,_Y 112.5° -Axis of Sy!:r:etry for An.alysis Figure 6.2-1851 Break Location Recirculation Line Break CPS..,..USAR I *-.-----! ------l------*--------I I --! i ,. _ _..) --*1 l'-0 0 IJ} 0 0 :::r ("") _L 0 c (Yi I 0 -r.::J 0J I CJ ___ ---t=========t.1-=--t-1 0 0 0 0 0J oootx 0 0 ('J I , <::J I J I 0 0 -I I :-..J D 0 rD I Figure 6.2-186i Clinton AP-FW Line Break Overall Load Resolution Time History on RPV at Elevation 484.5 in. X-Dir. I 0 ...... x u UJ Ul UJ z f-
-I I I I I I t --1 J___ I 0 =t* ----CPS-USAR I I I I I J I ; . I \ r-.. I ( lJ le [::> I I I I 0 C\J C_ r-----.. C> c=:= I I I I I ! -l I 0 N I 0 ::::!4 I OOOIX (81) 3Jl:!CU I 0 CD I I I I 0 OJ I Figure 6.2-1871 Clinton Line Break Overall Load Resolution Time History on RPV at Elevution 484.5 in. Y-Dir. ' 0 0 (.£) 0 0 LD 0 OM :::!'I 0 ...... 0 0 (r) 0 0 0J 0 0 0 u 1.J.J c.n w L. >--< I-I J_ _ CPS-USAR I ___ _i___ ! ' I ------c----I ' CJ c---0 0 lD 0 0 :::!'M 0 0 (I) 0 0 0J J_ 0 9oa ( 81-* fJI) HJ3WOW. Figure 6.2-188 Clinton AP-FW Line Break Overall Load Resolution Time History on RPV at Elevation 484.5 in. About X-Axis co I I 0 ...... >< u LLJ <.n w :::E: ........ I-I -f-----I T l --0 U1 <:::: I 0 0 CPS-USAR I I ! ! I -j I I I j ) ( f \ l/ ( I I I I i 0 Lf) I I i 0 I -1 I I _c=> ---...... ----I 0 L'l I I 0 0 ..--. I 1 I i I 1 I 0 Lfl 0 0 lO 0 0 U1 0 0 ::j1 7 CJ 0 (') 0 0 (\j 0 G 0 ....... >< u LU (f) 12.J :z: ......... f-Figure 6.2-1891 Clinton AP-FW Line Break Overall Load Resolution Time History on RPV at Elevation 484.5 in. In X-Oir. I CPS-USAR I -i---I ! I I I I I ( I ' T I ( I I I -;-I I I I 1 I I ! -----I ( r------_ [:> I c -0 0 lO < td I Ul L!.J 'L ,....._, I- ---* ---J_ _____ l _____ l i ! ' ' l j I I i ! I I -r I I I l -, l I I I 0 aJ I CPS-USAR ) i )J \ D -........_ D c_ 0 --t===:r -a OOOIX ( 81 l a :::t< I I I I I I *o (XJ I a 0 lO a 0 LJJ a 0 :::r' 0 a CD a a (\J 0 0 0 Figure 6.2-191j Clinton AP-HI Line Break Overall Load Resolution Time History on BSW at Elevation 484.5 in. In Y-Dir. M I 0 ....... >< u w en UJ L: f-CPS-USAR J_ _J I CJ -+---.-----------i __ __.__ __ __,__ __ , a -t-------+------+------+-------+-------t-a lO M 0 a :::r' I c ..-1 :>< Du 0 w I en 1 C\J =:;r _._ ___ --; _____ _._l ___ 0 ::t' CJ ::!' CD CD I I gOIX (81-NI) Figure 6.2-1921 Clinton AP-FW Line Break Overall Load Resolution Time History on BSW at Elevation 484.5 in. About X-Axis _i ---_._ --I CPS-USAR ____ __! ___ _ _ L _____ I I I I I 0 0 ('.J -I I ( v I \ D c: --r--c ---b3 --0 0 0 90IX (91-NI) 1N3WOW I I 0 0 I 0 0 (\J I Figure 6.2-193 Clinton AP-FW Line Break Overall Load Resolution 0 0 CD 0 0 lD 0 0 ::r (T'J ' 0 ..... >< Ou Ow en en a 0 (\J 0 0 0 w :z 1---i f--Time History on BSW at Elevation 484.5 in. About Y-Axis CPS;_USAR ___ _J__ _J ; I .::::-; ---i I I I I i I I I I I I I I I I I l ) -I ( I b I T ......_ L==>' I i I I i i I I i l l_ ___ ' I -----1 I I
I 0 0 0 0 0 0 0 (\J GOOtX: [811 Figure 6.2-194\ Clinton AP-RC Line Break Overall Load Resolution Time History on RPV at 135.5 in. X-Oir. I I ' 0 0 0J I '=' ['--0 0 (D 0 0 L[) M I Cl 0 :::t' 0 u 0 Lu (I) (.[) LL.: ::z 1--1 f-0 0 (\J
. ---: -I T I I -L I I I I I I I I ; T I __J_ I I I I I CJ :::t' CPS-USAR I I ! I I I I I I I I I \ I <:l-1 I ----1 I *"" -I -"' c; I I 0 0 (\J 9otx 0 0J I Figure Clinton AP-RC Line Break Overall Load Resolution Time History on RPV at 135.5 in. About X-Aixis I I I I I 0 ::::r I 0 0 lO 0 0 !JJ M I :o 0 ...... CJ x ::i' 0 '._) c LLJ 01 c..n w 2: ......... f-0 0 (\J I I I I I J I I _.._ I l I I a a (\! c= *< ------I J 0 a CPS-USAR J \ D I <_ !:' c-h T a I 0 a oootx ( 81 J Jt!CL:l *=:::. Figure 6.2-196 Clinton AP-RC Line Break Overall Load Resolution Time Hisory on BHS at 135.5 in. X-Dir. I I I I I I I I I I 0 0 (\! I a 0 CD a 0 l.[) ("') I C> ..... ax 0 ::i' a 0 (Y) 0 0 (\J l:::J 0 0 u w <n w L: !---; I- ' I I ' I I ! i I I ' I l l ; i I j -I I ' l I ! ; l i -l I l ' l t l ; i CPS-USAR ) / "---t> I I i 0 (.Q I Figure 6.2-197 Clinton AP-RC Line Break Overall Load Resolution Time History on at 135.5 in. About X-Axis 0 0 (.Q 0 c u, M 010 0 ...... _,.. >< _J 0 u 0 w (Y) en w L: >--< !-0 0 N CLINTON POWER STATION UPOATEO SAFETY ANALYSlS REPORT FIGURE 6.2-198 SAMPLING POINT LOCATIONS (SECTION G-G) CLINTON POWER STATION UPOATEO SAFETY ANALYSIS REPO"T FIGURE 6.2-199 SAMPLING POINT LOCATIONS (SECTION D-D) CPS/USAR REV. 10, October 2001 Figures 6.3-1 and 6.3-2 Deleted 1000 800 600 400 200 CPS-USAR Revision 9 January 2001 0 ....... ....... 0 500 1000 Figure 6.3-3 1500 2000 2500 Flow(GPM) 3000 3500 4000 4500 5000 Head verses High Pressure Core Spray Flow Used in LOCA Analysis CPS/USAR REV. 10, October 2001 Figures 6.3-4 and 6.3-5 Deleted 250 200 150 '-" '..r. > 100 50 500 Figure 6.3-6 CPS-USAR 2000 2500 Flow(GPM) 3000 3500 4000 Revision 9 January 2001 4500 5000 Head verses Low Pressure Core Spray flow Used in LOCA Analysis 250 200 c (ii a. Qi 150 c .... Q> > 0 "O .. Q> J: Qi II) II) Q> > Q> 100 .. .... :i Ill Ill Q> .... a. 50 2000 CPS-USAR 3000 Flow(GPM) 4000 Revision 9 January 2001 5000 6000 Figure 6.3-7 Head versus Low Pressure Coolant Injection Flow Used in LOCA Analysis for 1 Pump Only CPS/USAR REV. 10, October 2001 Figure 6.3-8 Deleted 1 L... 0.8 0 n. >. Cll u Q) 0 0.6 "'O Q) .!::! -m E 0.4 -0.2 Revision 9 CPS-USAR January 2001 \.. 1971 ANS--+ io%(Appendix K) ' ----* -1979 ANS (Nominal) 0 --*---**. 0.01 0.1 1 10 100 1000 10000 Time After Break (seconds) Figure 6.3-9 Normalized Decay Power LAMB SHORT-TERM THERMAL HYDRAULIC TRANSIENT MODEL OUTPUT CORE AVERAGE PRESSURE CORE INLET FLOW CORE INLET ENTHALPY SCATffASC TRANSIENT CRITICAL POWER MODEL CPS-USAR GESTR-LOCA FUEL ROD THERMAUMECHANICAL DESIGN OUTPUT GAP CONDUCTANCE ROD INTERNAL PRESSURE Revision 9 January 2001 SAFER LONG-TERM THERMAL HYDRAULIC TRANSIENT MODEL OUTPUT OUTPUT PCT WATER LEVEL RESPONSE LOCATION AND TIME OF PRESSURE BOILING TRANSITION HEAT TRANSFER COEFFICIENT LOCAL OXIDATION Figure 6.3-10 Flow Diagram of LOCA Analysis Using SAFER/GESTR MHPCS \_!-J DIG I I I I I I CPS-USAR MLPCI WD/G I I -------------------L------------------1 I Revision 9 January 2001 ML PCS \j_)otG I I I *I I Figure 6.3-11 CPS ECCS Configuration CPS/USAR CHAPTER 06 REV. 12, JAN 2007
FIGURES 6.3-12 THROUGH 6.3-78 HAVE BEEN DELETED 3.0 2.0 ... ..... NPSH REQUIRED AT 3 ft ABOVE MOUNTING FLANGE :i::: 1.0 le z 0 90 % PUMP EFFICIENCY 80 3000 70 2500 60 ("") '"O en I E 2000 c:: .,,, >-en 50 (.) > 0 < w J: ..I 1500 z :::t:l w Q 40 LL LL < w ... 0 ... 1000 30 500 3000 20 BHP AT SP GR* 1.0 0 2000 10 .:..... :::t:l i:: (!) ::i < 1000 0 Cb -* C/l 6000 7000 ...... c;* ::i ....:z 0 4000 5000 2000 1000 3000 GALLONS PER MINUTE ....:z Figure 6.3-79. HPCS Pump Characteristic Curve 2.0 ... ... l.O J: NPSH REQUIRED AT POINT 3 ft ABOVE MOUNTING FLANGE z 1200 0 90 % PUMP EFFICIENCY 1100 80 1000 70 900 60 ... () a 800 50 >-"tJ < u CJ) UJ z I J: UJ c:: ...I u CJ) < 700 40 LL ::z:,. I-u. 0 UJ I-600 30 500 1500 20 CL J: 8HP AT SP 1.0 UJ 400 1000 10 < er !XI 300 500 0 0 1000 2000 3000 4000 5000 6000 7000 GALLONS PER MINUTE Figure 6.3-80 LPCS Pump Characteristic Curve CPS/USAR REV. 10, November 2001 Figures 6.4-1 and 6.4-2 Deleted CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.4-3 ISOMETRIC DRAWING OF THE CONTROL ROOM AND OTHER STRUCTURES Vo po fUE.L BL DC-,. v I -P",. , ',, 1 _/: . -{-o*._ :"__.,+ \': : -PLAN .----_)-----* -(i.:.C1C.8 ELEVATION Aux. GL OCi. 4 0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 f).. PL(ll2 f vo2) 1. .97 .77 .41 .1 -.3 -.62 -.9 -1.15 -1.2 -1.1 -1.0 -.6 -.15 .15 .15 .1 .1 .1 CLINTON POWER STATION UPDATED SAF'ETY ANALYSIS REPORT FIGURE 6.5-1 CONTAINMENT GAS CONTROL BOUNDARY WIND PATTERNS AND COEFFICIENTS AS A FUNCTION OF 8 4000 Wind Speed (mph) REVISION 7. JUNE 1997 -+-Infiltration (cfm) J-11-Exfiltration (cfm) -A-Sum (cfm) CLINTON POWER STATION UPDATED SAFETY ANALYSIS REPORT FIGURE 6.5-2 SECONDARY CONTAINMENT LEAKAGE AS A FUNCTION OF WINO SPEED CPS/USAR REV. 10, October 2001 Figures 6.7-1 through 6.7-3 Delete -;; *;;; ..!:-w a: ::> (/) (/) w a: n. w z ::i <( w I-(/) 35 30 25 20 15 10 5 0 0 0 psig 20 40 CPS-USAR 60 ELAPSED TIME (sec) 1.5 in. DIAMETER SCHEDULE 160 BLEED-OFF PIPE EQUIVALENT 80 100 Figure 6.7-4. Effect of Bleed-off Line Length on Decompression of Main Steam Line Between Isolation Valves. 120 }}

ML17354A206

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