Text

Final Safety Analysis Report Update, Revision 32, Table of Contents
	ML16123A330
Person / Time
Site:	Palisades
Issue date:	04/18/2016
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16120A302	List: ML16120A321; ML16120A325; ML16120A326; ML16120A327; ML16120A344; ML16120A345; ML16120A347; ML16120A359; ML16120A360; ML16120A361; ML16120A362; ML16120A379; ML16120A380; ML16120A381; ML16120A382; ML16120A415; ML16120A416; ML16120A417; ML16120A419; ML16120A420; ML16120A421; ML16120A571; ML16120A573; ML16120A574; ML16120A575; ML16120A588; ML16120A589; ML16120A590; ML16120A591; ML16120A596; ML16120A597; ML16120A598; ML16120A599; ML16120A602; ML16120A603; ML16120A604; ML16120A608; ML16120A609; ML16120A610; ML16123A314; ML16123A315; ML16123A316; ML16123A320; ML16123A321; ML16123A326; ML16123A328; ML16123A329; ML16126A109; PNP 2016-015, Final Safety Analysis Report Update, Revision 32, Table of Contents;
References
	PNP 2016-015
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FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT Revision 30 TABLE OF CONTENTS Page 1 of 5 SECTIONS

1.1 INTRODUCTION

....................................................................................... 1.1-1 1.1.1 GENERAL.................................................................................... 1.1-1 1.1.2 LICENSING HISTORY .................................................................1.1-1 1.2 GENERAL PLANT DESCRIPTION ........................................................... 1.2-1 1.2.1 PLANT SITE ................................................................................ 1.2-1 1.2.2 PLANT ARRANGEMENT ............................................................ 1.2-1 1.2.3 CONTAINMENT ........................................................................... 1.2-2 1.2.4 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) .......................... 1.2-3 1.2.5 TURBINE GENERATOR ...........................................................1.2-10 1.3 IDENTIFICATION OF CONTRACTORS ................................................... 1.3-1 1.4 PRINCIPAL DESIGN CRITERIA ............................................................... 1.4-1 1.4.1 STATION DESIGN ....................................................................... 1.4-1 1.4.2 REACTOR ................................................................................... 1.4-1 1.4.3 PRIMARY COOLANT AND AUXILIARY SYSTEMS ................... 1.4-2 1.4.4 CONTAINMENT SYSTEM ........................................................... 1.4-3 1.4.5 ENGINEERED SAFEGUARDS .................................................... 1.4-3 1.4.6 INSTRUMENTATION AND CONTROL ....................................... 1.4-4 1.4.7 ELECTRICAL SYSTEMS ............................................................ 1.4-4 1.4.8 RADIOACTIVE WASTES AND RADIATION PROTECTION....... 1.4-4 1.4.9 FUEL HANDLING AND STORAGE............................................. 1.4-4 1.4.10 FIRE PROTECTION ....................................................................1.4-4 1.4.11 CIRCULATING WATER SYSTEM ...............................................1.4-5 1.4.12 SECURITY ................................................................................... 1.4-5 1.4.13 EMERGENCY PLANNING...........................................................1.4-5 1.4.14 PLANT OPERATION ...................................................................1.4-5 1.4.15 STRUCTURES ............................................................................ 1.4-6 1.4.16 SINGLE FAILURE CRITERIA...................................................... 1.4-6 1.4.16.1 Licensing Basis........................................................... 1.4-6 1.4.16.2 Active And Passive Failures ...................................... 1.4-7

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT Revision 30 TABLE OF CONTENTS Page 2 of 5 1.4.16.3 Current Design Considerations ................................. 1.4-8 1.5 MAJOR PLANT MODIFICATIONS (DESIGN/CONSTRUCTION) ............ 1.5-1 1.6 INSERVICE INSPECTION ......................................................................... 1.6-1 1.6.1 HISTORICAL BACKGROUND .................................................... 1.6-1 1.6.2 GENERAL.................................................................................... 1.6-1 1.7 RESEARCH AND DEVELOPMENT REQUIREMENTS ............................ 1.7-1 1.7.1 FLOW MIXING AND FLOW DISTRIBUTION .............................. 1.7-1 1.7.2 CONTROL ROD TESTS..............................................................1.7-1 1.7.3 CONTROL ROD DRIVE MECHANISMS ..................................... 1.7-1 1.7.4 FUEL BUNDLE DESIGN ............................................................. 1.7-2 1.7.5 REACTOR VESSEL FLOW TESTS ............................................ 1.7-2 1.8 SPECIAL MAJOR PROGRAMS ............................................................... 1.8-1 1.8.1 SYSTEMATIC EVALUATION PROGRAM .................................. 1.8-1 1.8.1.1 Description of Program ..........................................1.8-1 1.8.1.2 SEP Reviews Confirmed Safety of Palisades Design ..................................................... 1.8-3 1.8.1.3 Continuing Applicability and Interpretation of SEP Information .................................................. 1.8-4 1.8.2 TMI ACTION ITEMS (NUREG-0737) ........................................... 1.8-5 1.8.3 PIPE SUPPORT BASEPLATE DESIGNS USING CONCRETE EXPANSION ANCHOR BOLTS (IE BULLETIN 79-02) ............ 1.8-5 1.8.4 SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS (IE BULLETIN 79-14) ................................. 1.8-6 1.8.5 UNRESOLVED SAFETY ISSUES (NUREG-0410) ...................... 1.8-7 1.8.6 ENVIRONMENTAL QUALIFICATION OF "SAFETY-RELATED" ELECTRICAL EQUIPMENT (EEQ)

(NUREG-0588) (USI A-24) .......................................................... 1.8-8 1.8.7 CONTROL ROOM HABITABILITY (NUREG-0696) ....................1.8-8 1.8.8 EFFECTS OF PIPE RUPTURE (SEP TOPICS III.5.A AND B) .... 1.8-8 1.8.9 STATION BLACKOUT (10 CFR 50.63) (USI A-44) .................... 1.8-9 1.8.10 SAFE SHUTDOWN .....................................................................1.8-9

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT Revision 30 TABLE OF CONTENTS Page 3 of 5 1.8.11 HEAVY LOADS ......................................................................... 1.8-10 1.9 RENEWED FACILITY OPERATING LICENSE ......................................... 1.9-1 1.9.1

SUMMARY

DESCRIPTIONS OF AGING MANAGEMENT PROGRAMS ................................................................................ 1.9-1 1.9.1.1 Nickel Alloy Program .............................................. 1.9-2 1.9.1.2 ASME Section XI, Subsections IWB, IWC, IWD, IWF Inservice Inspection Program ................................ 1.9-3 1.9.1.3 Bolting Integrity Program ....................................... 1.9-3 1.9.1.4 Boric Acid Corrosion Program ............................... 1.9-3 1.9.1.5 Buried Services Corrosion Monitoring Program .. 1.9-4 1.9.1.6 Closed Cycle Cooling Water Program ................... 1.9-4 1.9.1.7 Containment Inservice Inspection Program.......... 1.9-4 1.9.1.8 Containment Leakage Testing Program................ 1.9-5 1.9.1.9 Diesel Fuel Monitoring and Storage Program.......1.9-5 1.9.1.10 Fire Protection Program ......................................... 1.9-6 1.9.1.11 Flow Accelerated Corrosion Program ................... 1.9-6 1.9.1.12 Non-EQ Electrical Commodities Condition Monitoring Program ................................................ 1.9-7 1.9.1.13 One-Time Inspection Program ............................... 1.9-7 1.9.1.14 Open Cycle Cooling Water Program ...................... 1.9-9 1.9.1.15 Overhead Load Handling Systems Inspection Program.................................................................... 1.9-9 1.9.1.16 Reactor Vessel Integrity Surveillance Program .. 1.9-10 1.9.1.17 Reactor Vessel Internals Inspection Program .... 1.9-10 1.9.1.18 Steam Generator Tube Integrity Program ........... 1.9-11 1.9.1.19 Structural Monitoring Program ............................ 1.9-12 1.9.1.20 System Monitoring Program................................. 1.9-12 1.9.1.21 Water Chemistry Program .................................... 1.9-13 1.9.1.22 Inspections of Opportunity for Internal Surfaces Of Selected Components and Corrosion Under Insulation ...............................................................1.9-13 1.9.1.23 Compressed Air Monitoring Program.................. 1.9-14

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT Revision 30 TABLE OF CONTENTS Page 4 of 5 1.9.1.24 Oil Sampling and Analysis ................................... 1.9-14 1.9.1.25 Electrical Equipment Qualification Program....... 1.9-15 1.9.1.26 Fatigue Monitoring Program ................................ 1.9-15 1.9.2

SUMMARY

DESCRIPTIONS OF TIME-LIMITED AGING ANALYSES ................................................................................ 1.9-15 1.9.2.1 Reactor Vessel Neutron Embrittlement ...............1.9-16 1.9.2.2 Metal Fatigue ......................................................... 1.9-19 1.9.2.3 Environmental Qualification of Electrical Equipment ..............................................................1.9-38 1.9.2.4 Containment Liner Plate, Metal Containments And Penetrations Fatigue Analysis ..................... 1.9-40 1.9.2.5 Other Plant-Specific Time-Limited Aging Analyses ................................................................. 1.9-42 1.9.3 NEWLY IDENTIFIED STRUCTURES, SYSTEMS, AND COMPONENTS ......................................................................... 1.9-47 REFERENCES ............................................................................................................. 1-1

FSAR CHAPTER 1 - INTRODUCTION & GENERAL DESCRIPTION OF PLANT Revision 30 TABLE OF CONTENTS Page 5 of 5 LIST OF TABLES 1-1 Chronological Licensing Events 1-2 Palisades Design Characteristics (Nominal Values) 1-3 Systematic Evaluation Program (SEP) and Integrated Assessment Program (IAP),

Palisades Plant - NUREG-0820 1-4 Post-TMI Requirements for Consumers Power Company's, Palisades Plant -

NUREG-0737 1-5 Unresolved Safety Issues 1-6 Estimated Use on March 24, 2031 1-7 Estimated RTPTS on March 24, 2031 1-8 Summary of Fatigue Usage Factors at NUREG/CR-6260 Sample Locations Applicable to Palisades 1-9 Long-Term Commitments for License Renewal of Palisades Nuclear Plant 1-10 Listing of Newly Identified Systems, Structures, and Components per 10 CFR 50.37(b)

LIST OF FIGURES 1-1 Sh 1 Plant Site Plan 1-1 Sh 2 Plant Area Plan 1-2 Equipment Location - Reactor Building, Plan of Elevation 570'-0" 1-3 Equipment Location - Auxiliary Building, Radwaste Modifications Plan of Elevation 590'-0" 1-4 Equipment Location - Auxiliary and Reactor Building, Radwaste Modifications Plan of Elevation 607'-6" 1-5 Equipment Location - Auxiliary and Reactor Building, Radwaste Modifications Plan of Elevation 625'-0" 1-6 Equipment Location - Auxiliary Building, Radwaste Modifications Plan of Elevation 649'-0" 1-7 Equipment Location - Reactor Building, Sections A-A, B-B, C-C, D-D and E-E 1-8 Equipment Location - Auxiliary Building, Radwaste Modifications Section F-F 1-9 Equipment Location - Reactor Building, Section G-G 1-10 Equipment Location - Reactor Building, Plan of Elevation 602'-0" and Sections H-H, J-J and K-K 1-11 Equipment Location - Reactor Building, Plan of Elevation 700'-0" 1-12 Sh 1 Equipment Location - Turbine Building, Plan of Elevation 590'-0" 1-12 Sh 2 Equipment Location - Turbine Building, Pump Structure Plan of Elevation 590'-0" 1-13 Equipment Location - Turbine Building, Plan of Elevation 607'-6" 1-14 Equipment Location - Turbine Building, Plan of Elevation 625'-0" 1-15 Equipment Location - Turbine Building, Sections 1-16 Equipment Location - Turbine Building, Sections 1-17 Equipment Location - Auxiliary Building, Radwaste Modifications Sections 1-18 General Arrangement - Condensate and Makeup Demin Building

FSAR CHAPTER 2 - SITE AND ENVIRONMENT Revision 30 TABLE OF CONTENTS Page 1 of 4 SECTIONS 2.1 LOCATION ................................................................................................ 2.1-2 2.1.1 TOPOGRAPHY AND LAND USAGE ............................................. 2.1-2 2.1.2 POPULATION ................................................................................ 2.1-3 2.1.3 NEARBY INDUSTRIAL, TRANSPORTATION AND MILITARY FACILITIES................................................................... 2.1-5 2.2 HYDROLOGY ........................................................................................... 2.2-1 2.2.1 GROUNDWATER ........................................................................... 2.2-1 2.2.2 GENERAL LAKE HYDROLOGY .................................................... 2.2-4 2.3 GEOLOGY ................................................................................................ 2.3-1 2.3.1 PREGLACIAL GEOLOGY..............................................................2.3-1 2.3.2 GLACIAL GEOLOGY .....................................................................2.3-2 2.3.3 FAULTS.......................................................................................... 2.3-3 2.3.4 ENGINEERING GEOLOGY ............................................................2.3-3 2.

3.5 CONCLUSION

S ............................................................................. 2.3-5 2.4 SEISMICITY .............................................................................................. 2.4-1 2.4.1 SITE GEOLOGY ............................................................................. 2.4-1 2.4.2 SEISMIC HISTORY ........................................................................ 2.4-2 2.4.3 DISCUSSION .................................................................................. 2.4-3 2.

4.4 CONCLUSION

S ............................................................................. 2.4-4 2.5 METEOROLOGY ...................................................................................... 2.5-1 2.5.1 GENERAL CLIMATOLOGY OF PALISADES PLANT AREA ........ 2.5-1 2.5.2 METEOROLOGICAL PROGRAM HISTORY ................................. 2.5-3 2.5.2.1 Preoperational Program.......................................... 2.5-3 2.5.2.2 Interim Program ....................................................... 2.5-4 2.5.2.3 Present Program...................................................... 2.5-4

FSAR CHAPTER 2 - SITE AND ENVIRONMENT Revision 30 TABLE OF CONTENTS Page 2 of 4 2.5.3 DISCUSSION OF EXISTING 1977/1978 DATA ............................. 2.5-5 2.5.3.1 Wind Frequency Distributions ...............................2.5-5 2.5.3.2 Stability Wind Roses ...............................................2.5-6 2.5.3.3 Persistence .............................................................. 2.5-6 2.5.3.4 Hourly Data .............................................................. 2.5-7 2.5.3.5 Data Recovery ......................................................... 2.5-8 2.5.4 DIFFUSION CLIMATOLOGY .........................................................2.5-8 2.5.4.1 Turbulence and Diffusion Regimes .......................2.5-8 2.5.4.2 Shoreline Influences ............................................... 2.5-9 2.5.5 SHORT-TERM DISPERSION PARAMETERS ............................... 2.5-9 2.5.5.1 X/Q Determination for TID Analyses.....2.5-9 2.5.5.2 X/Q Determination for AST Analyses..2.5-10 2.5.5.2.1 Offsite X/Q Determination..2.5-11 2.5.5.2.2 Control Room X/Q Determination2.5-12 2.5.6 LONG-TERM DISPERSION PARAMETERS ............................... 2.5-12 2.6 ENVIRONMENTAL SURVEILLANCE ....................................................... 2.6-1 2.6.1 SAMPLE SENSITIVITY .................................................................. 2.6-2 2.6.2 SAMPLE TYPE AND FREQUENCY............................................... 2.6-2 2.6.3 SAMPLING STATIONS ..................................................................2.6-2 2.6.4 SAMPLE TYPES ............................................................................ 2.6-3 2.6.5

SUMMARY

OF PREOPERATIONAL RESULTS............................ 2.6-3 2.6.6 ADJUSTMENTS TO THE ENVIRONMENTAL SURVEY ............... 2.6-5 REFERENCES ............................................................................................................. 2-1

FSAR CHAPTER 2 - SITE AND ENVIRONMENT Revision 30 TABLE OF CONTENTS Page 3 of 4 LIST OF TABLES 2-1 Agricultural Statistics 2-2 Population Related to Selected Land Use Categories 2-3 People per Dwelling by Township and City 2-4 Permanent Resident Population Distribution 2-5 Transient Population Related to Educational Facilities Within 10 Miles of Palisades 2-6 Major Employer's Work Force Distribution Within 10 Miles of the Palisades Plant 2-7 Motels and Cottages Within 10 Miles of Palisades Plant 2-8 Campsites Within 10 Miles of Palisades Plant 2-9 Maximum Probable Population for All Categories 2-10 Population Growth and Density by County 2-11 Field Permeability Test Results 2-12 Analyses of Soil Samples 2-13 Epicenter Distance From Site Versus Reported Intensity 2-14 Stability Class Comparison by Wind Sector 2-15 Meteorological Data Recovery Rates 2-16 Physical Characteristics of the Routine Release Points for the Palisades Nuclear Plant 2-17 Relative Dispersion (X/Q) Values (s/m3) Versus Averaging Time, Turbine Building Vent - Ground Level Release Exclusion Area Boundary 2-18 Relative Dispersion (X/Q) Values (s/m3) Versus Averaging Time, Turbine Building Vent - Ground Level Release Low Population Zone 2-19 Annual Average X/Q (sec/m3) Values, Turbine Building Vent - Ground Level Release 2-20 Detection Capabilities for Environmental Sample Analysis 2-21 X/Q Values (s/m3) - Ground Level Release - Exclusion Area Boundary 2-22 X/Q Values (s/m3) - Ground Level Release - Low Population Zone

FSAR CHAPTER 2 - SITE AND ENVIRONMENT Revision 30 TABLE OF CONTENTS Page 4 of 4 LIST OF FIGURES 2-1 Population Centers - 1990 Census Over 10,000, 0 to 50 Miles 2-2 Site Layout 2-3 Site Topography, Boring Locations, and Seismic Profiles 2-4 Topography Cross Sections 2-5 Selected Land Use Categories 2-6 Population Centers - 1990 Census Over 1,000, 0 to 50 Miles 2-7 Permanent Residential Population Breakdown (1990) 2-8 Population Distribution (1990), 10 to 50 Miles 2-9 Groundwater Elevations and Area Gradients 2-10 Geologic Map and Cross Section 2-11 1966 Drilling Program, Drill Hole and Cross Section Locations 2-12 1966 Drilling Program, Drill Logs and Soil Penetration Test Results 2-13 1966 Drilling Program, Subsurface Sections 2-14 Regional Structures, Bedrock Geology, Major Faulting and Epicenters 2-15 Compressional (P)Wave Velocities From Seismic Survey 2-16 Seismic Regionalization: Zones of Probable Maximum Intensity (MM) 2-17 Meteorological Tower Locations 2-18 10 Meter Wind Frequency Distribution - Palisades Site, December 1, 1977 through February 28, 1978 2-19 60 Meter Wind Frequency Distribution - Palisades Site, December 1, 1977 through February 28, 1978 2-20 10 Meter Wind Frequency Distribution - Palisades Site, March 1 through May 31, 1978 2-21 60 Meter Wind Frequency Distribution - Palisades Site, March 1 through May 31, 1978 2-22 10 Meter Wind Frequency Distribution - Palisades Site, June 1 through August 31, 1978 2-23 60 Meter Wind Frequency Distribution - Palisades Site, June 1 through August 31, 1978 2-24 10 Meter Wind Frequency Distribution - Palisades Site, September 1 through November 30, 1978 2-25 60 Meter Wind Frequency Distribution - Palisades Site, September 1 through November 30, 1978 2-26 10 Meter Wind Frequency Distribution - Palisades Site, December 1, 1977 through November 30, 1978 2-27 60 Meter Wind Frequency Distribution - Palisades Site, December 1, 1977 through November 30 1978

FSAR CHAPTER 3 - REACTOR Revision 27 TABLE OF CONTENTS Page 1 of 2 SECTIONS

3.1 INTRODUCTION

....................................................................................... 3.1-1 3.2 DESIGN BASES ........................................................................................ 3.2-1 3.2.1 PERFORMANCE OBJECTIVES .................................................... 3.2-1 3.2.2 DESIGN OBJECTIVES................................................................... 3.2-1 3.2.3 DESIGN LIMITS ............................................................................. 3.2-2 3.3 REACTOR DESIGN .................................................................................. 3.3-1 3.3.1 GENERAL

SUMMARY

...................................................................3.3-1 3.3.2 NUCLEAR DESIGN AND EVALUATION ....................................... 3.3-2 3.3.2.1 Reactivity and Control Requirements.................... 3.3-2 3.3.2.2 Reactivity Coefficients ............................................ 3.3-4 3.3.2.3 Control Blade Worths ............................................. 3.3-6 3.3.2.4 Reactivity Insertion Rates....................................... 3.3-7 3.3.2.5 Power Distribution and Power Escalation Rates .. 3.3-7 3.3.2.6 Neutron Fluence on Pressure Vessel .................... 3.3-9 3.3.2.7 Nuclear Evaluation ................................................ 3.3-10 3.3.2.8 Reactor Stability .................................................... 3.3-10 3.3.3 THERMAL-HYDRAULIC DESIGN AND EVALUATION ............... 3.3-14 3.3.3.1 Thermal-Hydraulic Design Criteria ...................... 3.3-14 3.3.3.2 Plant Parameter Variations ................................... 3.3-15 3.3.3.3 Core Flow Distribution .......................................... 3.3-15 3.3.3.4 Trip Set Points ....................................................... 3.3-16 3.3.4 MECHANICAL DESIGN AND EVALUATION ............................... 3.3-17 3.3.4.1 Reactor Internals ................................................... 3.3-17 3.3.4.2 Control Rod Drive Mechanism ............................. 3.3-22 3.3.4.3 Core Mechanical Design ....................................... 3.3-28 REFERENCES ............................................................................................................. 3-1

FSAR CHAPTER 3 - REACTOR Revision 27 TABLE OF CONTENTS Page 2 of 2 LIST OF TABLES 3-1 Primary Stress Limits for Critical Reactor Vessel Internal Structures 3-2 Fuel Bundle Component Description LIST OF FIGURES 3-1 Reactor Arrangement 3-2 Position of Fuel Assemblies and Control Rod Groups in the Palisades Core 3-3 Control Rod Insertion Limits 3-4 Reactivity Difference Between Fundamental and Excited States of a Bare Cylindrical Reactor 3-5 Thermal Neutron Flux at the Center of the Core vs Time 3-6 Damping Coefficient vs Reactivity Difference Between Fundamental and Excited State 3-7 End of Life Axial Oscillations With Doppler Feedback, Full Power (2-Hour Time Steps) 3-8 Split Detector Response to Axial Power Profiles in the Core 3-9 Reactor Core Cross Section 3-10 Reactor Arrangement 3-11 Upper Guide Structure Assembly 3-12 Hold Down Ring 3-13 Control Rod Drive Mechanism 3-14 Fuel Bundle Assembly, Sheet 1 of 2 3-15 Fuel Bundle Assembly, Sheet 2 of 2 3-16 Deleted 3-17 Spacer Assembly, HTP 3-18 UO2 Fuel Rod Assembly 3-19 Fuel Rod Assembly, Gadolinia Bearing 3-20 Control Rod

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 27 TABLE OF CONTENTS Page 1 of 4 SECTIONS

4.1 INTRODUCTION

....................................................................................... 4.1-1 4.2 DESIGN BASIS ......................................................................................... 4.2-1 4.2.1 PERFORMANCE OBJECTIVES AND PARAMETERS FOR NORMAL CONDITIONS ........................................................... 4.2-1 4.2.2 DESIGN CYCLIC LOADS ..............................................................4.2-1 4.2.3 DESIGN SERVICE LIFE CONSIDERATIONS ................................ 4.2-2 4.2.4 CODES ADHERED TO AND COMPONENT CLASSIFICATION ... 4.2-3 4.2.5 SAFETY CONSIDERATIONS OF DESIGN PARAMETERS .......... 4.2-3 4.2.6 PRIMARY COOLANT SYSTEM ASYMMETRIC LOADS ............... 4.2-4 4.3 SYSTEM DESIGN AND OPERATION ...................................................... 4.3-1 4.3.1 GENERAL DESCRIPTION .............................................................4.3-1 4.3.2 INTERFACES WITH OTHER SYSTEMS ....................................... 4.3-2 4.3.3 REACTOR VESSEL ....................................................................... 4.3-3 4.3.4 STEAM GENERATOR ...................................................................4.3-5 4.3.4.1 Steam Generator Tube Degradation ..................... 4.3-8 4.3.4.2 Steam Generator Replacement .............................. 4.3-8 4.3.5 PRIMARY COOLANT PUMPS ....................................................... 4.3-9 4.3.6 PRIMARY COOLANT PIPING ...................................................... 4.3-11 4.3.7 PRESSURIZER ............................................................................ 4.3-13 4.3.8 QUENCH TANK ........................................................................... 4.3-19 4.3.9 VALVES........................................................................................ 4.3-20 4.3.9.1 General Criteria ..................................................... 4.3-20 4.3.9.2 Pressurizer Throttling (Spray) Control Valves .... 4.3-21 4.3.9.3 Power-Operated Relief Valves (PORV) and Block Valves .......................................................... 4.3-22 4.3.9.4 Spring-Actuated Primary Safety Valves ..............4.3-23 4.3.10 ENVIRONMENTAL PROTECTION .............................................. 4.3-24 4.3.11 MATERIALS EXPOSED TO COOLANT ......................................4.3-24 4.3.12 INSULATION ................................................................................ 4.3-24 4.3.13 SYSTEM CHEMICAL TREATMENT ............................................ 4.3-25

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 27 TABLE OF CONTENTS Page 2 of 4 4.4 SYSTEM DESIGN EVALUATION ............................................................. 4.4-1 4.4.1 DESIGN MARGIN ........................................................................... 4.4-1 4.4.2 PREVENTION OF BRITTLE FRACTURE...................................... 4.4-2 4.5 TESTS AND INSPECTIONS ..................................................................... 4.5-1 4.5.1 GENERAL ...................................................................................... 4.5-1 4.5.2 NIL DUCTILITY TRANSITION TEMPERATURE DETERMINATION ..................................................................... 4.5-1 4.5.3 SURVEILLANCE PROGRAM......................................................... 4.5-2 4.5.4 NONDESTRUCTIVE TESTS .......................................................... 4.5-7 4.5.5 ADDITIONAL TESTS .....................................................................4.5-9 4.5.6 INSERVICE INSPECTION ............................................................4.5-10 4.5.7 NDTT OF OTHER PRIMARY SYSTEM COMPONENTS ............. 4.5-13 4.5.8 NONDESTRUCTIVE TESTS OF OTHER PRIMARY SYSTEM COMPONENTS ....................................................................... 4.5-13 4.6 OPERATING LIMITATIONS...................................................................... 4.6-1 4.7 PRIMARY COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION .............................................................................................. 4.7-1 4.7.1 LEAK DETECTION ........................................................................ 4.7-1 4.7.2 OPERATOR ACTION FOLLOWING LEAK DETECTION.............. 4.7-2 4.8 PRIMARY COOLANT GAS VENT SYSTEM............................................. 4.8-1 REFERENCES ............................................................................................................. 4-1

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 27 TABLE OF CONTENTS Page 3 of 4 LIST OF TABLES 4-1 Primary Coolant System Parameters 4-2 Primary Coolant System Code Requirements 4-3 Reactor Vessel Parameters 4-4 Steam Generator Parameters 4-5 Secondary Safety Valve Parameters 4-6 Primary Coolant Pump Parameters 4-7 Piping List 4-8 Pressurizer Parameters 4-9 Pressurizer Normal Level Control Program/Pressurizer Backup Level Control Program 4-10 Pressurizer Safety Valve Parameters 4-11 Quench Tank Parameters 4-12 Actuator-Operated Throttling Valve Parameters 4-13 Actuator-Operated Block Valve Parameters 4-14 Pressurizer Power-Operated Relief Valve Parameters 4-15 Materials Exposed to Coolant 4-16 Primary Coolant Chemistry 4-17 Summary of Specimens Provided for Each Exposure Location / Summary of Specimens Provided for Each Supplemental Surveillance Capsule 4-18 Primary Coolant System Preservice Quality Assurance Program 4-19 Primary Coolant System Inspection CE Requirements 4-20 Reactor Vessel Surveillance Coupon Removal Schedule

FSAR CHAPTER 4 - PRIMARY COOLANT SYSTEM Revision 27 TABLE OF CONTENTS Page 4 of 4 LIST OF FIGURES 4-1 Sh 1 Piping and Instrumentation Diagram, Primary Coolant System 4-1 Sh 2 Piping and Instrumentation Diagram, Primary Coolant System 4-2 Reactor Vessel 4-3 Steam Generator 4-4 Primary Coolant Circulating Pump 4-5 Deleted 4-6 Enlarged View of Pump Seal Area 4-7 Primary Coolant Pump Characteristics Curve 4-8 Pressurizer 4-9 Temperature Control Program 4-10 Pressurizer Level Set Point vs TAVG 4-11 Location of Surveillance Capsule Assemblies 4-12 Typical Surveillance Capsule Assembly 4-13 Typical Charpy Impact Compartment Assembly 4-14 Typical Tensile - Monitor Compartment Assembly 4-15 Variable LTOP Setpoints

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 1 of 15 SECTIONS 5.1 GENERAL DESIGN CRITERIA ..................................................................... 5.1-1 5.

1.1 INTRODUCTION

............................................................................ 5.1-1 5.1.2 GROUP I: OVERALL REQUIREMENTS (CRITERIA 1-5) ............ 5.1-2 5.1.2.1 Criterion 1 - Quality Standards and Records ........ 5.1-2 5.1.2.2 Criterion 2 - Design Bases for Protection Against Natural Phenomena .................................. 5.1-3 5.1.2.3 Criterion 3 - Fire Protection.................................... 5.1-3 5.1.2.4 Criterion 4 - Environmental and Missile Design Bases .......................................................... 5.1-4 5.1.2.5 Criterion 5 - Sharing of Structures, Systems and Components ..................................................... 5.1-5 5.1.2.6 Conclusions ............................................................ 5.1-5 5.1.3 GROUP II: PROTECTION BY MULTIPLE FISSION PRODUCT BARRIERS (CRITERIA 10-19) ...................................................... 5.1-5 5.1.3.1 Criterion 10 - Reactor Design ................................. 5.1-5 5.1.3.2 Criterion 11 - Reactor Inherent Protection ............ 5.1-6 5.1.3.3 Criterion 12 - Suppression of Reactor Power Oscillations.............................................................. 5.1-6 5.1.3.4 Criterion 13 - Instrumentation and Control ........... 5.1-7 5.1.3.5 Criterion 14 - Reactor Coolant Pressure Boundary ................................................................. 5.1-8 5.1.3.6 Criterion 15 - Reactor Coolant System Design ..... 5.1-8 5.1.3.7 Criterion 16 - Containment Design ........................ 5.1-9 5.1.3.8 Criterion 17 - Electrical Power Systems................ 5.1-9 5.1.3.9 Criterion 18 - Inspection and Testing of Electrical Power Systems..................................... 5.1-11 5.1.3.10 Criterion 19 - Control Room ................................. 5.1-12 5.1.3.11 Conclusions .......................................................... 5.1-13 5.1.4 GROUP III: PROTECTION AND REACTIVITY CONTROL SYSTEMS (CRITERIA 20-29) ...................................................... 5.1-13 5.1.4.1 Criterion 20 - Protection System Functions ....... 5.1-13 5.1.4.2 Criterion 21 - Protection System Reliability and Testability ....................................................... 5.1-14 5.1.4.3 Criterion 22 - Protection System Independence ........................................................ 5.1-15 5.1.4.4 Criterion 23 - Protection System Failure Modes ........................................................ 5.1-16 5.1.4.5 Criterion 24 - Separation of Protection and Control Systems.................................................... 5.1-16 5.1.4.6 Criterion 25 - Protection System Requirements for Reactivity Control Malfunctions..................... 5.1-17 5.1.4.7 Criterion 26 - Reactivity Control System Redundancy and Capability ................................. 5.1-17 5.1.4.8 Criterion 27 - Combined Reactivity Control Systems Capability ............................................... 5.1-18 5.1.4.9 Criterion 28 - Reactivity Limits ............................ 5.1-18

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 2 of 15 5.1.4.10 Criterion 29 - Protection Against Anticipated Operational Occurrences ..................................... 5.1-19 5.1.4.11 Conclusions .......................................................... 5.1-19 5.1.5 GROUP IV: FLUID SYSTEMS (CRITERIA 30-46) ...................... 5.1-20 5.1.5.1 Criterion 30 - Quality of Reactor Coolant Pressure Boundary ............................................... 5.1-20 5.1.5.2 Criterion 31 - Fracture Prevention of Reactor Coolant Pressure Boundary ................................. 5.1-21 5.1.5.3 Criterion 32 - Inspection of Reactor Coolant Pressure Boundary ............................................... 5.1-22 5.1.5.4 Criterion 33 - Reactor Coolant Makeup ............... 5.1-22 5.1.5.5 Criterion 34 - Residual Heat Removal ................. 5.1-23 5.1.5.6 Criterion 35 - Emergency Core Cooling .............. 5.1-24 5.1.5.7 Criterion 36 - Inspection of Emergency Core Cooling System ..................................................... 5.1-25 5.1.5.8 Criterion 37 - Testing of Emergency Core Cooling System ..................................................... 5.1-25 5.1.5.9 Criterion 38 - Containment Heat Removal .......... 5.1-26 5.1.5.10 Criterion 39 - Inspection of Containment Heat Removal System ................................................... 5.1-27 5.1.5.11 Criterion 40 - Testing of Containment Heat Removal System ................................................... 5.1-27 5.1.5.12 Criterion 41 - Containment Atmosphere Cleanup .................................................................. 5.1-28 5.1.5.13 Criterion 42 - Inspection of Containment Atmosphere Cleanup Systems ............................ 5.1-28 5.1.5.14 Criterion 43 - Testing of Containment Atmosphere Cleanup Systems ............................ 5.1-29 5.1.5.15 Criterion 44 - Cooling Water................................. 5.1-29 5.1.5.16 Criterion 45 - Inspection of Cooling Water System and Criterion 46 - Testing of Cooling Water System ........................................................ 5.1-30 5.1.5.17 Conclusions .......................................................... 5.1-30 5.1.6 GROUP V: REACTOR CONTAINMENT (CRITERIA 50-57) ...... 5.1-31 5.1.6.1 Criterion 50 - Containment Design Basis............ 5.1-31 5.1.6.2 Criterion 51 - Fracture Prevention of Containment Pressure Boundary ........................ 5.1-32 5.1.6.3 Criterion 52 - Capability for Containment Leakage Rate Testing ........................................... 5.1-32 5.1.6.4 Criterion 53 - Provisions for Containment Testing and Inspection ......................................... 5.1-33 5.1.6.5 Criterion 54 - Piping Systems Penetrating Containment .......................................................... 5.1-33 5.1.6.6 Criterion 55 - Primary Coolant Pressure Boundary Penetrating Containment .................... 5.1-34 5.1.6.7 Criterion 56 - Primary Containment Isolation ..... 5.1-35 5.1.6.8 Criterion 57 - Closed System Isolation Valves..................................................................... 5.1-36 5.1.6.9 Conclusions .......................................................... 5.1-38

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 3 of 15 5.1.7 GROUP VI: FUEL AND RADIOACTIVITY CONTROL (CRITERIA 60-64) ........................................................................ 5.1-39 5.1.7.1 Criterion 60 - Control of Releases of Radioactive Materials to the Environment .......... 5.1-39 5.1.7.2 Criterion 61 - Fuel Storage and Handling and Radioactivity Control ............................................ 5.1-40 5.1.7.3 Criterion 62 - Prevention of Criticality in Fuel Storage and Handling ........................................... 5.1-41 5.1.7.4 Criterion 63 - Monitoring Fuel and Waste Storage................................................................... 5.1-42 5.1.7.5 Criterion 64 - Monitoring Radioactivity Releases ................................................................ 5.1-42 5.1.7.6 Conclusions .......................................................... 5.1-43 5.1.8 OVERALL CONCLUSION ........................................................... 5.1-43 5.2 CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS .... 5.2-1 5.

2.1 BACKGROUND

INFORMATION ................................................... 5.2-1 5.2.1.1 Classification Overview .......................................... 5.2-1 5.2.1.2 Original Palisades Design Review ......................... 5.2-2 5.2.2 CONSUMERS DESIGN CLASSIFICATIONS ................................ 5.2-3 5.2.2.1 Design - Class 1 ...................................................... 5.2-3 5.2.2.2 Design - Class 2 ...................................................... 5.2-4 5.2.2.3 Design - Class 3 ...................................................... 5.2-4 5.2.2.4 Design - Palisades Modifications .......................... 5.2-4 5.2.2.5 Inservice Inspection................................................ 5.2-5 5.2.2.6 Service Quality Group Classification .................... 5.2-5 5.2.2.7 Service - Electrical and Instrumentation and Controls Equipment Classification........................ 5.2-5 5.2.2.8 Safety-Related Classification ................................. 5.2-6 5.2.2.8.1 Safety-Related ......................................................... 5.2-6 5.2.2.8.2 Important to Safety ................................................. 5.2-6 REFERENCES ............................................................................................... 5.2-7 5.3 WIND AND TORNADO LOADINGS .............................................................. 5.3-1 5.3.1 WIND .............................................................................................. 5.3-1 5.3.1.1 Design Parameters.................................................. 5.3-1 5.3.1.2 Forces on Structures .............................................. 5.3-1 5.3.2 TORNADO ..................................................................................... 5.3-2 5.3.2.1 Design Parameters.................................................. 5.3-2 5.3.2.2 Forces on Structures .............................................. 5.3-2 5.3.3 PLANT REEVALUATION .............................................................. 5.3-3 REFERENCES ............................................................................................... 5.3-4

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 4 of 15 5.4 WATER LEVEL DESIGN ............................................................................... 5.4-1 5.4.1 FLOODING FROM NATURAL SOURCES .................................... 5.4-1 5.4.1.1 Description of Events ............................................. 5.4-1 5.4.1.2 Effects on Consumers Design Class 1 Structures and Safety-Related Equipment ........... 5.4-1 5.4.2 FLOODING AND WETTING FROM PLANT SOURCES ............... 5.4-2 REFERENCES ............................................................................................... 5.4-4 5.5 MISSILE PROTECTION ................................................................................. 5.5-1 5.5.1 TORNADO MISSILES.................................................................... 5.5-1 5.5.1.1 Design Parameters.................................................. 5.5-1 5.5.1.1.1 Containment Structure, Auxiliary Building, Turbine Building........................... 5.5-1 5.5.1.1.2 Intake Structure ............................................ 5.5-2 5.5.1.1.3 Auxiliary Building Radwaste Addition ........ 5.5-2 5.5.1.1.4 Auxiliary Building TSC/EER/HVAC Addition ......................................................... 5.5-3 5.5.1.1.5 Diesel Fuel Oil Storage Tank Housing ....... 5.5-3 5.5.1.1.6 Condensate Storage Tank......5.5-3 5.5.1.2 Structural Considerations ........................... 5.5-4 5.5.1.3 Plant Reevaluation .................................................. 5.5-4 5.5.1.3.1 Review Parameters ...................................... 5.5-4 5.5.1.3.2 Summary ....................................................... 5.5-5 5.5.2 TURBINE MISSILES ...................................................................... 5.5-6 5.5.2.1 Background ............................................................. 5.5-6 5.5.2.2 High-Pressure Turbine Missiles............................. 5.5-6 5.5.2.3 Low-Pressure Turbine Missiles ............................. 5.5-7 5.5.2.4 Turbine Overspeed Protection System ................. 5.5-8 5.5.3 INTERNALLY GENERATED MISSILES ........................................ 5.5-8 5.5.3.1 Containment Missiles ............................................. 5.5-8 5.5.3.2 Plant Reevaluation .................................................. 5.5-9 5.5.4 SITE PROXIMITY MISSILES ....................................................... 5.5-10 REFERENCES ............................................................................................. 5.5-12 5.6 DYNAMIC EFFECTS OF PIPE RUPTURE .................................................... 5.6-1 5.6.1 DEFINITIONS ................................................................................. 5.6-1 5.6.2 DESIGN BASES ............................................................................ 5.6-2 5.6.2.1 Systems in Which Design Basis Failures Occur .. 5.6-2 5.6.2.2 Identification of Essential Systems and Components ............................................................ 5.6-2 5.6.2.3 Limiting Conditions ................................................ 5.6-3 5.6.2.4 Safety Evaluation .................................................... 5.6-4 5.6.3 CRITERIA USED TO DEFINE BREAKS ....................................... 5.6-5 5.6.3.1 ASME Section III, Class 1 Piping ........................... 5.6-5 5.6.3.2 ASME Section III Class 2 and 3 Piping (other than between containment isolation valves) ........ 5.6-6 5.6.3.3 Non-nuclear Class Piping....................................... 5.6-7 5.6.3.4 Piping Penetrating Containment............................ 5.6-8

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 5 of 15 5.6.4 PROTECTIVE MEASURES ........................................................... 5.6-9 5.6.5 JET IMPINGEMENT..................................................................... 5.6-10 5.6.6 PLANT MODIFICATION LINE-BREAK ANALYSIS .................... 5.6-11 5.6.6.1 Plant Modifications Involving High- or Moderate-Energy Piping ....................................... 5.6-11 5.6.6.2 Plant Modifications Involving Essential Systems and Components ................................... 5.6-11 5.6.7 HISTORY OF PALISADES HIGH-ENERGY LINE-BREAK ANALYSIS ................................................................................... 5.6-11 5.6.7.1 High-Energy Line Breaks Outside Containment .......................................................... 5.6-11 5.6.7.2 High-Energy Line Breaks Inside Containment ... 5.6-15 5.6.7.3 Moderate-Energy System Pipe-Break Evaluation .............................................................. 5.6-16 REFERENCES ............................................................................................. 5.6-18 5.7 SEISMIC DESIGN .......................................................................................... 5.7-1 5.7.1 SEISMIC INPUT ............................................................................. 5.7-1 5.7.1.1 Design Bases .......................................................... 5.7-1 5.7.1.2 Ground Design Response Spectra ........................ 5.7-2 5.7.1.3 Floor Design Response Spectra ............................ 5.7-2 5.7.1.4 Damping Values ...................................................... 5.7-3 5.7.2 SEISMIC ANALYSIS OF MAJOR CP CO DESIGN CLASS 1 STRUCTURES ............................................................................... 5.7-4 5.7.2.1 Containment Building ............................................. 5.7-5 5.7.2.2 Auxiliary Building.................................................... 5.7-6 5.7.3 SEISMIC ANALYSIS OF OTHER CP CO DESIGN CLASS 1 STRUCTURES ............................................................................... 5.7-7 5.7.3.1 Turbine Building...................................................... 5.7-7 5.7.3.1.1 CP Co Design Class 1 Portion..................... 5.7-7 5.7.3.1.2 CP Co Design Class 3 Portion..................... 5.7-7 5.7.3.2 Intake Structure ....................................................... 5.7-9 5.7.3.3 Auxiliary Building Radwaste Addition .................. 5.7-9 5.7.3.4 Auxiliary Building TSC/EER Addition.................. 5.7-10 5.7.3.5 Other Auxiliary Building Additions...................... 5.7-12 5.7.3.6 CP Co Design Class 1 Tank Foundations ........... 5.7-12 5.7.3.7 Miscellaneous Frames and Trusses .................... 5.7-12

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 6 of 15 5.7.4 SEISMIC ANALYSIS OF CP CO DESIGN CLASS 1 PIPING ..... 5.7-13 5.7.5 SEISMIC ANALYSIS OF MAJOR CP CO DESIGN CLASS 1 SYSTEM AND COMPONENTS ................................................... 5.7-16 5.7.5.1 Primary Coolant System ....................................... 5.7-16 5.7.5.1.1 Reactor Vessel Assembly .......................... 5.7-17 5.7.5.1.2 Steam Generators ...................................... 5.7-17 5.7.5.1.3 Primary Coolant Pumps ............................. 5.7-17 5.7.5.1.4 Pressurizer .................................................. 5.7-17 5.7.5.1.5 Primary Coolant System Piping ................ 5.7-18 5.7.5.1.6 Pressurizer Quench Tank .......................... 5.7-18 5.7.5.1.7 Pressurizer Safety and Power-Operated Relief Valves ............................................... 5.7-18 5.7.5.2 Other Major CP Co Design Class 1 Systems and Components .......................................................... 5.7-18 5.7.6 SEISMIC ANALYSIS OF SPENT FUEL STORAGE RACKS ...... 5.7-19 5.7.6.1 Region 1 Racks ..................................................... 5.7-19 5.7.6.2 Region 2 Racks (See Section 9.11) ...................... 5.7-21 5.7.7 SEISMIC ANALYSIS AND TESTING OF OTHER CP CO DESIGN CLASS 1 COMPONENTS ............................................. 5.7-22 5.7.7.1 Electrical Equipment and Instrumentation ......... 5.7-24 5.7.7.2 Tanks...................................................................... 5.7-24 5.7.7.3 Appendages to CP Co Design Class 1 Components .......................................................... 5.7-24 5.7.7.4 Overhead Cranes .................................................. 5.7-25 5.7.7.5 Containment Air Locks ......................................... 5.7-25 5.7.8 SEISMIC ANALYSIS OF BURIED STRUCTURES AND COMPONENTS ............................................................................ 5.7-25 5.7.9 SEISMIC INSTRUMENTATION ................................................... 5.7-25 REFERENCES ............................................................................................. 5.7-26 5.8 CONTAINMENT STRUCTURE ...................................................................... 5.8-1 5.8.1 DESIGN BASIS .............................................................................. 5.8-1 5.8.2 GENERAL DESCRIPTION ............................................................ 5.8-2 5.8.3 LOADS AND LOAD COMBINATIONS .......................................... 5.8-6 5.8.3.1 Containment Structure Concrete ........................... 5.8-6 5.8.3.1.1 Construction Condition ............................... 5.8-6 5.8.3.1.2 Working Stress Condition ........................... 5.8-6 5.8.3.1.3 Yield Strength Condition ............................. 5.8-7 5.8.3.2 Liner Plate System .................................................. 5.8-9 5.8.3.2.1 Liner Plate ..................................................... 5.8-9 5.8.3.2.2 Liner Plate Anchors ..................................... 5.8-9 5.8.3.3 Penetrations .......................................................... 5.8-10

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 7 of 15 5.8.4 ANALYSIS ................................................................................... 5.8-10 5.8.4.1 Containment Structure Concrete ......................... 5.8-10 5.8.4.1.1 General ........................................................ 5.8-10 5.8.4.1.2 Axisymmetric Loads .................................. 5.8-11 5.8.4.1.3 Nonaxisymmetric Loads ............................ 5.8-15 5.8.4.2 Prestressing System............................................. 5.8-15 5.8.4.2.1 Tendon Anchorage Zones ......................... 5.8-15 5.8.4.3 Liner Plate System ................................................ 5.8-19 5.8.4.3.1 Liner Plate ................................................... 5.8-19 5.8.4.3.2 Liner Plate Anchors ................................... 5.8-19 5.8.4.4 Penetrations .......................................................... 5.8-20 5.8.5 DESIGN ........................................................................................ 5.8-21 5.8.5.1 Design Basis ......................................................... 5.8-21 5.8.5.2 Containment Structure Concrete ......................... 5.8-23 5.8.5.2.1 General Criteria .......................................... 5.8-23 5.8.5.2.2 Construction Condition ............................. 5.8-24 5.8.5.2.3 Working Stress Condition ......................... 5.8-25 5.8.5.2.4 Yield Strength Condition ........................... 5.8-26 5.8.5.2.5 Results ........................................................ 5.8-31 5.8.5.3 Prestressing System............................................. 5.8-31 5.8.5.3.1 Tendons ...................................................... 5.8-31 5.8.5.3.2 Tendon Anchorage Zones ......................... 5.8-33 5.8.5.4 Liner Plate System ................................................ 5.8-34 5.8.5.4.1 General ........................................................ 5.8-34 5.8.5.4.2 Liner Plate ................................................... 5.8-35 5.8.5.4.3 Liner Plate Anchors ................................... 5.8-36 5.8.5.4.4 Brackets ...................................................... 5.8-38 5.8.5.5 Penetrations .......................................................... 5.8-38 5.8.6 PENETRATIONS ......................................................................... 5.8-39 5.8.6.1 Design Basis ......................................................... 5.8-39 5.8.6.2 General Description .............................................. 5.8-39 5.8.6.2.1 Personnel and Equipment Openings ........ 5.8-40 5.8.6.2.2 Other Openings .......................................... 5.8-41 5.8.6.3 Design Criteria ...................................................... 5.8-42 5.8.6.3.1 Concrete Openings .................................... 5.8-42 5.8.6.3.2 Steel Penetrations ...................................... 5.8-42 5.8.6.4 Analysis and Design ............................................. 5.8-45 5.8.6.4.1 Small Penetrations ..................................... 5.8-46 5.8.6.4.2 Large Penetrations ..................................... 5.8-48 5.8.6.4.3 Other Design Details .................................. 5.8-51

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 8 of 15 5.8.7 CONSTRUCTION......................................................................... 5.8-52 5.8.7.1 Materials ................................................................ 5.8-52 5.8.7.1.1 Concrete ...................................................... 5.8-52 5.8.7.1.2 Reinforcing Steel ........................................ 5.8-53 5.8.7.1.3 Prestressing Tendons and Hardware ....... 5.8-54 5.8.7.1.4 Liner Plate ................................................... 5.8-54 5.8.7.1.5 Steel Penetrations ...................................... 5.8-54 5.8.7.1.6 Sheathing Filler .......................................... 5.8-55 5.8.7.2 Quality Control ...................................................... 5.8-55 5.8.7.2.1 Concrete Mix Design .................................. 5.8-55 5.8.7.2.2 Concrete Materials ..................................... 5.8-56 5.8.7.2.3 Concrete ...................................................... 5.8-57 5.8.7.2.4 Reinforcing Steel and CADWELD Splices......................................................... 5.8-57 5.8.7.2.5 Prestressing Tendons and Hardware ....... 5.8-58 5.8.7.2.6 Liner Plate ................................................... 5.8-59 5.8.7.2.7 Steel Penetrations ...................................... 5.8-60 5.8.7.2.8 Sheathing Filler .......................................... 5.8-60 5.8.7.3 Construction Methods .......................................... 5.8-60 5.8.7.3.1 Governing Codes ....................................... 5.8-60 5.8.7.3.2 Concrete ...................................................... 5.8-61 5.8.7.3.3 Reinforcing Steel and CADWELD Splices......................................................... 5.8-61 5.8.7.3.4 Prestressing System .................................. 5.8-62 5.8.7.3.5 Liner Plate ................................................... 5.8-63 5.8.7.4 Construction Problems ........................................ 5.8-64 5.8.7.4.1 Cracking at Welds in Containment Liner Plate ................................................... 5.8-64 5.8.8 CONTAINMENT STRUCTURE TESTING ................................... 5.8-68 5.8.8.1 Integrated Leak Rate Testing ............................... 5.8-68 5.8.8.1.1 Historical Summary .................................... 5.8-68 5.8.8.1.2 Regulatory Basis for Current Program ..... 5.8-70 5.8.8.1.3 Type A Test Performance Under Option B ...................................................... 5.8-71 5.8.8.2 Local Leakage Rate Testing ................................. 5.8-71 5.8.8.2.1 Historical Summary .................................... 5.8-72 5.8.8.2.2 Regulatory Basis for Current Program ..... 5.8-73 5.8.8.2.3 Scope of the Type B and C Testing Program ......................................... 5.8-73 5.8.8.2.4 Performance Based Type B and C Program Overview ...................................... 5.8-74 5.8.8.3 Prestressing System Surveillance....................... 5.8-75 5.8.8.3.1 Basis for Program ...................................... 5.8-75 5.8.8.3.2 Surveillance Period .................................... 5.8-76 5.8.8.3.3 Surveillance Guidelines ............................. 5.8-76 5.8.8.3.4 Acceptance Criteria.................................... 5.8-79 5.8.8.3.5 Historical Summary .................................... 5.8-80

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 9 of 15 5.8.8.4 Structural Integrity Test........................................ 5.8-84 5.8.8.4.1 Basis for Test.............................................. 5.8-84 5.8.8.4.2 Test Guidelines........................................... 5.8-85 5.8.8.4.3 Objectives ................................................... 5.8-85 5.8.8.4.4 Test Data and Results ................................ 5.8-86 5.8.8.4.5 Summary ..................................................... 5.8-88 5.8.8.5 Liner Plate and Penetration Surveillance Program ................................................................. 5.8-89 5.8.8.5.1 Basis for Program ...................................... 5.8-89 5.8.8.5.2 Surveillance Period .................................... 5.8-89 5.8.8.5.3 Details of Program ..................................... 5.8-90 5.8.8.5.4 Summary ..................................................... 5.8-90 5.8.8.6 End Anchorage Concrete Surveillance ............... 5.8-91 5.8.8.6.1 Basis for Program ...................................... 5.8-91 5.8.8.6.2 Surveillance Period .................................... 5.8-91 5.8.8.6.3 Surveillance Locations .............................. 5.8-92 5.8.8.6.4 Details and Results .................................... 5.8-92 5.8.8.6.5 Summary ..................................................... 5.8-93 5.8.9 STEAM GENERATOR REPLACEMENT CONSTRUCTION OPENING ..................................................................................... 5.8-93 5.8.9.1 General Description .............................................. 5.8-93 5.8.9.2 Containment Reevaluation ................................... 5.8-94 5.8.9.3 Materials ................................................................ 5.8-96 5.8.9.3.1 Concrete ...................................................... 5.8-96 5.8.9.3.2 Reinforcing Steel ........................................ 5.8-97 5.8.9.3.3 Prestressing Tendons and Hardware ....... 5.8-98 5.8.9.3.4 Liner Plate and Hardware ......................... 5.8-98 5.8.9.3.5 Sheathing Filler .......................................... 5.8-98 5.8.9.4 Quality Control ...................................................... 5.8-98 5.8.9.4.1 Concrete Mix Design .................................. 5.8-98 5.8.9.4.2 Concrete Materials ..................................... 5.8-99 5.8.9.4.3 Concrete .................................................... 5.8-100 5.8.9.4.4 Reinforcing Steel and CADWELD Splices....................................................... 5.8-100 5.8.9.4.5 Prestressing Tendons.............................. 5.8-101 5.8.9.4.6 Liner Plate ................................................. 5.8-101 5.8.9.4.7 Sheathing Filler ........................................ 5.8-102 5.8.9.5 Construction Methods ........................................ 5.8-102 5.8.9.5.1 Governing Codes ..................................... 5.8-102 5.8.9.5.2 Concrete .................................................... 5.8-102 5.8.9.5.3 Reinforcing Steel and CADWELD Splices....................................................... 5.8-102 5.8.9.5.4 Prestressing System ................................ 5.8-103 5.8.9.6 Containment Testing .......................................... 5.8-103 5.8.9.6.1 Integrated Leak Rate Testing .................. 5.8-103 5.8.9.6.2 Structural Integrity Test ........................... 5.8-103

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 10 of 15 5.8.10 CONTAINMENT STRUCTURAL INTEGRITY SURVEILLANCE PROGRAM .................................................... 5.8-104 5.8.10.1 Requirement for Metal Containment Examinations ....................................................... 5.8-104 5.8.10.2 Requirements for Concrete Containment Examinations ....................................................... 5.8-104 5.8.10.2.1 Surveillance of Unbonded Post-Tensioning System .................................. 5.8-104 5.8.10.2.2 Surveillance of Containment Structural Concrete .................................. 5.8-104 REFERENCES ........................................................................................... 5.8-105 5.9 OTHER STRUCTURES.................................................................................. 5.9-1 5.9.1 DESIGN CRITERIA ........................................................................ 5.9-1 5.9.1.1 CP Co Design Class 1 Structures .......................... 5.9-1 5.9.1.1.1 Design Methods............................................ 5.9-1 5.9.1.1.2 Loads and Load Combinations ................... 5.9-2 5.9.1.2 CP Co Design Class 2 Structures .......................... 5.9-4 5.9.1.3 CP Co Design Class 3 Structures .......................... 5.9-4 5.9.1.4 Loads Common to All Structures .......................... 5.9-5 5.9.2 CONTAINMENT INTERIOR STRUCTURES ................................. 5.9-5 5.9.2.1 General Description ................................................ 5.9-5 5.9.2.2 Loads ....................................................................... 5.9-6 5.9.2.3 Analysis and Design ............................................... 5.9-8 5.9.2.4 Materials of Construction ..................................... 5.9-10 5.9.3 AUXILIARY BUILDING ................................................................ 5.9-10 5.9.3.1 General Description .............................................. 5.9-10 5.9.3.2 Loads ..................................................................... 5.9-11 5.9.3.3 Analysis and Design ............................................. 5.9-12 5.9.3.4 Materials of Construction ..................................... 5.9-13 5.9.4 TURBINE BUILDING AND INTAKE STRUCTURE ................... 5.9-13 5.9.4.1 General................................................................... 5.9-13 5.9.5 AUXILIARY BUILDING RADWASTE ADDITION ........................ 5.9-13 5.9.5.1 General Description .............................................. 5.9-13 5.9.5.2 Analysis and Design ............................................. 5.9-14 5.9.5.3 Materials of Construction ..................................... 5.9-14 5.9.6 AUXILIARY BUILDING TSC/EER/HVAC ADDITION .................. 5.9-14 5.9.6.1 General Description .............................................. 5.9-14 5.9.6.2 Loads and Load Combinations ............................ 5.9-15 5.9.6.2.1 Loads ........................................................... 5.9-15 5.9.6.2.2 Load Combinations .................................... 5.9-16 5.9.6.3 Analysis and Design ............................................. 5.9-17 5.9.6.4 Materials of Construction ..................................... 5.9-18 REFERENCES ............................................................................................. 5.9-19

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 11 of 15 5.10 SYSTEMS AND COMPONENTS ................................................................. 5.10-1 5.10.1 DESIGN CRITERIA FOR CP CO DESIGN CLASS 1 SYSTEMS AND COMPONENTS ................................................................... 5.10-1 5.10.1.1 CP Co Design Class 1 Piping ............................... 5.10-1 5.10.1.2 CP Co Design Class 1 Pipe Supports.................. 5.10-3 5.10.1.3 Other CP Co Design Class 1 Systems and Components .......................................................... 5.10-5 5.10.1.4 Interim Operability Criteria ................................... 5.10-6 5.10.2 DESIGN CRITERIA FOR CP CO DESIGN CLASS 2 AND CLASS 3 SYSTEMS AND COMPONENTS ................................. 5.10-6 5.10.2.1 CP Co Design Class 2 ........................................... 5.10-6 5.10.2.2 CP Co Design Class 3 ........................................... 5.10-6 5.10.3 ANCHORAGE MODIFICATIONS FOR SAFETY-RELATED SYSTEMS AND COMPONENTS ................................................. 5.10-7 5.10.3.1 Piping Systems ..................................................... 5.10-7 5.10.3.1.1 1974 Review ................................................ 5.10-7 5.10.3.1.2 1979 Reanalysis.......................................... 5.10-7 5.10.3.1.3 Revision of Seismic Piping Criteria -

ASME Section III, Code Case N-411 .......... 5.10-8 5.10.3.1.4 Inspection and Enforcement Bulletins ..... 5.10-9 5.10.3.2 Masonry Walls ..................................................... 5.10-11 5.10.3.2.1 History ....................................................... 5.10-11 5.10.3.2.2 Identification ............................................. 5.10-11 5.10.3.2.3 Reevaluation ............................................. 5.10-11 5.10.3.2.4 Modifications ............................................ 5.10-11 5.10.3.3 Electrical Equipment........................................... 5.10-12 5.10.3.3.1 History ....................................................... 5.10-12 5.10.3.3.2 Identification............................................. 5.10-12 5.10.3.3.3 Evaluation and Modifications ................. 5.10-13 5.10.4 QUALITY CONTROL ................................................................. 5.10-13 5.10.4.1 Shop Welding ...................................................... 5.10-13 5.10.4.2 Field Welding....................................................... 5.10-14 5.10.4.3 Inspection of Piping ............................................ 5.10-15 5.10.4.4 Field Inspection of Mechanical Components, Electrical Components and Instrumentation .... 5.10-16 REFERENCES ........................................................................................... 5.10-17

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 12 of 15 LIST OF TABLES 5.2-1 Palisades System of Classification for Structures/Systems/Components 5.2-2 Structures Classification 5.2-3 Mechanical System/Component Classification 5.2-4 Electrical Systems/Component Classification 5.2-5 Instrumentation and Control/Component Classification 5.3-1 Tornado Design Pressures 5.4-1 Safety-Related Equipment That Requires Protection From Flooding Due to Failures of Nonclass 1 Systems 5.5-1 Class 1 Structures Wall and Roof Thickness 5.5-2 Burst Probability for Each LP Rotor and Total Unit at 120% Rated Speed 5.6-1 High-Energy Pipe Failures Outside Containment - Summary of Operating Stresses - Main Steam 5.6-2 High-Energy Pipe Failures Outside Containment - Summary of Operating Stresses - Feedwater 5.6-3 High-Energy Pipe Failures Outside Containment - Summary of Operating Stresses - Main Steam Dump 5.6-4 Summary of Eliminated Hardware Resulting from Application of Generic Letter 87-11, "Relaxation of Arbitrary Pipe Rupture Requirements" 5.7-1 List of Computer Codes 5.7-2 Material Damping Values for Various Materials and Types of Construction 5.7-3 Material Damping Values for Various Class 1 Structures 5.7-4 Auxiliary Building TSC/EER Addition Summary of Modal Parameters Flexible Base Analysis 5.7-5 Comparison of Specifications for Seismic Requirements 5.7-6 Major Class 1 Components Seismic Loads 5.7-7 Class 1E Electrical Equipment and Instrumentation Seismic Loads 5.7-8 Class 1 Tanks Seismic Loads 5.7-9 Safety-Related Hydraulic Shock Suppressors (Snubbers) 5.7-10 Safety-Related Mechanical Shock Suppressors (Snubbers) 5.8-1 Containment Structure Summary of Concrete and Reinforcing Steel Stresses 5.8-2 Containment Structure Tendon Anchorage Zone Reinforcement Stresses 5.8-3 Containment Structure Liner Plate Anchor Analysis 5.8-4 Containment Penetrations and Appendix J Test Requirements 5.9-1 Major Equipment Supports, Materials of Construction 5.10-1 Class 1 Systems or Portions Thereof Included in the 1974 Review of As-Built Pipe Supports 5.10-2 Systems Containing Safety-Related Piping

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 13 of 15 LIST OF FIGURES 5.5-1 Deleted 5.5-2 Deleted 5.7-1 OBE Horizontal Design Ground Response Spectrum (Housner) 5.7-2 Taft Ground Response Spectrum Versus Housner Ground Response Spectrum (SSE), 4% Damping 5.7-3 Taft Ground Response Spectrum Versus Housner Ground Response Spectrum (SSE), 7-1/2% Damping 5.7-4 Containment Building Dynamic Model 5.7-5 Containment Shell Maximum Seismic Responses (OBE) Comparison of Responses for Fixed Base and Coupled Models 5.7-6 Auxiliary Building, N-S Mathematical Model 5.7-7 Auxiliary Building, E-W Mathematical Model 5.7-8 Electrical Penetration Enclosure, N-S and E-W Dynamic Models and Maximum Seismic Responses (OBE) 5.7-9 Turbine Building, E-W Dynamic Models 5.7-10 Turbine Building, E-W Fundamental Modeshapes, Outside Walls 5.7-11 Turbine Building, E-W Direction, Maximum Seismic Responses (SSE) 5.7-12 Auxiliary Building Radwaste Addition, Dynamic Models 5.7-13 Auxiliary Building TSC/EER Addition, Dynamic Model 5.7-14 Auxiliary Building TSC/EER Addition, Maximum Seismic Responses (OBE) 5.8-1 Sh 1 Containment Structure, Typical Cross Section 5.8-1 Sh 2 Containment Structure, Typical Cross Section 5.8-2 Containment Structure, Typical Piping Penetrations 5.8-3 Containment Structure, Typical Electrical Penetrations 5.8-4 Containment Structure, Reinforcing and Tendon Plan Adjacent to Equipment Hatch 5.8-5 Sh 1 Containment Structure, Tendon Hardware Assembly, Horizontal and Dome Tendons, Shop Buttonheaded End 5.8-5 Sh 2 Containment Structure, Tendon Hardware Assembly, Horizontal and Dome Tendons, Field Buttonheaded End 5.8-5 Sh 3 Containment Structure, Tendon Hardware Assembly, Vertical Tendons, Shop Buttonheaded End 5.8-5 Sh 4 Containment Structure, Tendon Hardware Assembly, Vertical Tendons, Field Buttonheaded End 5.8-6 Containment Structure, Personnel Air Lock 5.8-7 Containment Structure, Escape Air Lock 5.8-8 Containment Structure, Equipment Hatch Door 5.8-9 Containment Structure, Finite Element Mesh 5.8-10 Containment Structure, DBA Thermal Gradients Across Containment Wall, No Insulation

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 14 of 15 5.8-11 Sh 1 Containment Structure, Isostress Plot, Dome and Wall, D + Fi 5.8-11 Sh 2 Containment Structure, Isostress Plot, Dome and Wall, D + Ff + 1.15P 5.8-11 Sh 3 Containment Structure, Isostress Plot, Dome and Wall, D + Ff + 1.5P + Ta 5.8-11 Sh 4 Containment Structure, Isostress Plot, Dome and Wall, D + Ff + T a 5.8-12 Sh 1 Containment Structure, Isostress Plot, Wall and Base Slab, D + Fi 5.8-12 Sh 2 Containment Structure, Isostress Plot, Wall and Base Slab, D + Ff + 1.15P 5.8-12 Sh 3 Containment Structure, Isostress Plot, Wall and Base Slab, D + Ff + 1.5P + Ta 5.8-12 Sh 4 Containment Structure, Isostress Plot, Wall and Base Slab, D + Ff + Ta 5.8-13 Sh 1 Containment Structure, Stress Resultants, Dead Load (D) 5.8-13 Sh 2 Containment Structure, Stress Resultants, Final Prestress (Ff) 5.8-13 Sh 3 Containment Structure, Stress Resultants, DBA Pressure (P) 5.8-13 Sh 4 Containment Structure, Stress Resultants, DBA Temperature (Ta) 5.8-14 Containment Structure, Finite Element Mesh for Buttress, Plane Strain Analysis 5.8-15 Sh 1 Containment Structure, Buttress Isostress Plot, Maximum Compressive Stresses 5.8-15 Sh 2 Containment Structure, Buttress Isostress Plot, Minimum Compressive or Maximum Tensile Stresses 5.8-16 Sh 1 Containment Structure, Model for Liner Plate Analysis 5.8-16 Sh 2 Containment Structure, Model for Liner Plate Analysis 5.8-17 Containment Structure, Results From Tests on Liner Plate Anchors 5.8-18 Containment Structure, Thermal Gradient at Main Steam Penetration 5.8-19 Containment Structure, Loads on Pipe Penetrations 5.8-20 Containment Structure, Stress Concentrations at Equipment Hatch Opening 5.8-21 Containment Structure, Liner Plate, Weld Cracking at Backing Strip Discontinuities 5.8-22 Sh 1 Containment Structure, Liner Plate Test Sample, Elevation 600'0",

Azimuth 113° 5.8-22 Sh 2 Containment Structure, Liner Plate Test Sample, Elevation 600'0",

Azimuth 275° 5.8-23 Sh 1 Containment Structure, Liner Plate, Inspection and Method of Repair, Elevation 583' 6" 5.8-23 Sh 2 Containment Structure, Liner Plate, Inspection and Method of Repair, Elevation 588' 6" 5.8-23 Sh 3 Containment Structure, Liner Plate, Inspection and Method of Repair, Elevation 590' 0" 5.8-24 Containment Structure, Location and Identification of Eleven Surveillance Tendons for One- and Three-Year Surveillances

FSAR CHAPTER 5 - DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS Revision 31 TABLE OF CONTENTS Page 15 of 15 5.8-25 Sh 1 Containment Structure, Structural Integrity Test Inside Hoop Strain Profiles, Typical Section 5.8-25 Sh 2 Containment Structure, Structural Integrity Test Outside Meridional Strain Profiles, Typical Section 5.8-26 Containment Structure, Pressure Test Displacement Profiles 5.8-27 Sh 1 Containment Structure, Pressure Test Tendon Load Change 5.8-27 Sh 2 Containment Structure, Pressure Test Tendon Load Change 5.8-28 Containment Structure, End Anchorage Surveillance Program, Crack Surveillance Locations 5.8-29 Construction Opening Plan, Elevations, and Sections 5.8-30 Construction Opening Tendon Detensioning and Post Tensioning Sequence 5.8-31 Miscellaneous Gas Supply Systems 5.9-1 Containment Structure, Interior Construction

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMS Revision 29 TABLE OF CONTENTS Page 1 of 3 SECTIONS 6.1 SAFETY INJECTION SYSTEM ................................................................ 6.1-1 6.1.1 DESIGN BASES ............................................................................ 6.1-1 6.1.2 SYSTEM DESCRIPTION AND OPERATION ................................ 6.1-5 6.1.2.1 General Description ................................................ 6.1-5 6.1.2.2 Component Design ................................................. 6.1-8 6.1.2.3 Operation ............................................................... 6.1-16 6.1.3 TESTING ...................................................................................... 6.1-20 6.1.3.1 Operational Testing .............................................. 6.1-20 6.1.3.2 Environmental Testing ......................................... 6.1-21 6.1.4 DESIGN ANALYSIS..................................................................... 6.1-21 6.2 CONTAINMENT SPRAY SYSTEM ........................................................... 6.2-1 6.2.1 DESIGN BASIS .............................................................................. 6.2-1 6.2.2 SYSTEM DESCRIPTION AND OPERATION ................................ 6.2-2 6.2.2.1 General Description ................................................ 6.2-2 6.2.2.2 Component Description ......................................... 6.2-2 6.2.2.3 System Operation ................................................... 6.2-3 6.2.3 DESIGN ANALYSIS....................................................................... 6.2-4 6.2.3.1 Margins of Safety .................................................... 6.2-4 6.2.3.2 Margins of Capacity ................................................ 6.2-4 6.2.3.3 Testing ..................................................................... 6.2-4 6.3 CONTAINMENT AIR COOLERS .............................................................. 6.3-1 6.3.1 DESIGN BASES ............................................................................ 6.3-1 6.3.2 SYSTEM DESCRIPTION AND OPERATION ................................ 6.3-1 6.3.2.1 General Description ................................................ 6.3-1 6.3.2.2 System Operation ................................................... 6.3-3 6.3.3 DESIGN ANALYSIS....................................................................... 6.3-4 6.3.4 COMPONENT TESTING................................................................ 6.3-5 6.3.4.1 Coils ......................................................................... 6.3-5 6.3.4.2 Fans.......................................................................... 6.3-6 6.3.4.3 Testing ..................................................................... 6.3-6 6.4 CONTAINMENT SUMP pH CONTROL .................................................... 6.4-1 6.4.1 DESIGN BASIS .............................................................................. 6.4-1 6.4.2.1 General Description ................................................ 6.4-1 6.4.2.2 Operation ................................................................. 6.4-1 6.4.2.3 Materials .................................................................. 6.4-2 6.4.2.4 Paint ......................................................................... 6.4-3 6.5 CONTAINMENT VENTING CHARCOAL FILTER .................................... 6.5-1 6.5.1 GENERAL ...................................................................................... 6.5-1 6.6 DELETED

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMS Revision 29 TABLE OF CONTENTS Page 2 of 3 6.7 CONTAINMENT ISOLATION SYSTEM.................................................... 6.7-1 6.7.1 DESIGN BASIS .............................................................................. 6.7-1 6.7.2 SYSTEM DESCRIPTION AND OPERATION ................................ 6.7-1 6.7.2.1 System Description................................................. 6.7-1 6.7.2.2 Component Description ......................................... 6.7-4 6.7.2.3 System Operation ................................................... 6.7-4 6.7.3 DESIGN ANALYSIS ....................................................................... 6.7-6 6.7.3.1 System Reliability - Margins of Safety ........................... 6.7-6 6.7.3.2 Provisions for Testing and Inspection........................... 6.7-6 6.8 REACTOR CAVITY FLOODING SYSTEM ............................................... 6.8-1 6.8.1 SYSTEM OPERATION .................................................................. 6.8-1 6.9 INSERVICE INSPECTION OF ASME CLASSES 1, 2 AND 3 SYSTEMS AND COMPONENTS ................................................................................ 6.9-1 6.9.1 STRUCTURAL INTEGRITY EXAMINATION ................................. 6.9-2 6.9.2 PUMP AND VALVE TESTING PROGRAM ................................... 6.9-3 6.9.2.1 Pump Testing Program........................................... 6.9-3 6.9.2.2 Valve Testing Program ........................................... 6.9-3 6.10 CONTROL ROOM HABITABILITY ........................................................ 6.10-1 6.10.1 DESIGN BASIS ............................................................................ 6.10-1 6.10.2 SYSTEM DESIGN ........................................................................ 6.10-1 6.10.3 DESIGN ANALYSIS..................................................................... 6.10-2 REFERENCES ............................................................................................................. 6-1 LIST OF TABLES 6-1 Safety Injection and Refueling Water Tank Design Parameters 6-2 Low Pressure Safety Injection Pump Data Summary 6-3 High Pressure Safety Injection Pump Data Summary 6-4 Shutdown Cooling Heat Exchanger Data Summary 6-5 Safety Injection Tank Design Parameters 6-6 Containment Spray System Component Description 6-7 Containment Air Cooler Component Description 6-8 Containment Air Coolers Performance Data for Normal Operation 6-9 Containment Air Coolers Performance Data for Post-DBA Conditions 6-10 ECCS Component Systems 6-11 Deleted 6-12 ISI Major Components and/or Systems List 6-13 Inservice Pump Test Program Summary 6-14 Technical Specification 3.6.3, Containment Isolation Valves, Applicability

FSAR CHAPTER 6 - ENGINEERED SAFEGUARDS SYSTEMS Revision 29 TABLE OF CONTENTS Page 3 of 3 LIST OF FIGURES 6-1 Sh 1 Piping & Instrument Diagram, Safety Injection Containment Spray and Shutdown Cooling System 6-1 Sh 2 Piping & Instrument Diagram, Safety Injection Containment Spray and Shutdown Cooling System 6-2 Sh 1 Piping & Instrument Diagram, Safety Injection Containment Spray and Shutdown Cooling System 6-2 Sh 1A Piping & Instrument Diagram, Safety Injection Containment Spray and Shutdown Cooling System 6-2 Sh 1B Piping & Instrument Diagram, Safety Injection Containment Spray 6-3 Containment Air Coolers Relief Panel & Condensate Drain 6-4 Containment Vent Filter 6-5 Sh 1 Containment Penetrations 6-5 Sh 2 Containment Penetrations 6-5 Sh 2A Containment Penetrations 6-5 Sh 3 Containment Penetrations 6-6 Reactor Cavity Flooding System 6-7 Capacity Curve 1713A Nozzle

FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 TABLE OF CONTENTS Page 1 of 6 SECTIONS

7.1 INTRODUCTION

....................................................................................... 7.1-1 7.2 REACTOR PROTECTIVE SYSTEM ......................................................... 7.2-1 7.2.1 GENERAL ...................................................................................... 7.2-1 7.2.2 DESIGN BASES............................................................................. 7.2-2 7.2.3 REACTOR PROTECTIVE SYSTEM ACTIONS ............................. 7.2-4 7.2.3.1 High Rate-of-Change of Power .............................. 7.2-4 7.2.3.2 Variable High Power ............................................... 7.2-5 7.2.3.3 Low Primary Coolant Flow ..................................... 7.2-6 7.2.3.4 High Pressurizer Pressure ..................................... 7.2-7 7.2.3.5 Thermal Margin/Low Pressure ............................... 7.2-8 7.2.3.6 Loss of Load ........................................................... 7.2-9 7.2.3.7 Low Steam Generator Water Level ........................ 7.2-9 7.2.3.8 Low Steam Generator Pressure ............................. 7.2-9 7.2.3.9 Containment High Pressure ................................. 7.2-10 7.2.3.10 Manual Trip ............................................................ 7.2-10 7.2.4 SIGNAL GENERATION ............................................................... 7.2-11 7.2.5 LOGIC OPERATION .................................................................... 7.2-12 7.2.5.1 Trip Logic (See Figure 7-2) .................................. 7.2-12 7.2.5.2 Trip Bypass Logic ................................................. 7.2-12 7.2.5.3 CRDM Clutch Power Circuitry (See Figure 7-1) .. 7.2-14 7.2.6 TESTING ...................................................................................... 7.2-15 7.2.7 EFFECTS OF FAILURES ............................................................ 7.2-16 7.2.8 POWER SOURCES ..................................................................... 7.2-18 7.2.9 PHYSICAL SEPARATION AND ELECTRICAL ISOLATION ....... 7.2-19 7.2.9.1 Physical Separation .............................................. 7.2-19 7.2.9.2 Electrical Isolation ................................................ 7.2-19 7.2.10 REACTOR TRIP AND PRETRIP SET POINTS ........................... 7.2-21 7.3 ENGINEERED SAFEGUARDS CONTROLS ............................................ 7.3-1 7.

3.1 INTRODUCTION

............................................................................ 7.3-1 7.3.2 SAFETY INJECTION SYSTEM CONTROL CIRCUITS AND EQUIPMENT INITIATION .............................................................. 7.3-2 7.3.2.1 Design Basis ........................................................... 7.3-2 7.3.2.2 Description and Operation ..................................... 7.3-2 7.3.2.3 Design Analysis ...................................................... 7.3-4 7.3.3 CONTAINMENT HIGH PRESSURE AND HIGH RADIATION ....... 7.3-5 7.3.3.1 Design Basis ........................................................... 7.3-5 7.3.3.2 Description and Operation ..................................... 7.3-5 7.3.3.3 Design Analysis ...................................................... 7.3-8

FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 TABLE OF CONTENTS Page 2 of 6 7.3.4 SAFETY INJECTION AND REFUELING WATER TANK LOW LEVEL .................................................................................. 7.3-9 7.3.4.1 Design Basis ........................................................... 7.3-9 7.3.4.2 Description and Operation ................................... 7.3-10 7.3.4.3 Design Analysis .................................................... 7.3-11 7.3.5 ENGINEERED SAFEGUARDS TESTING.................................... 7.3-11 7.3.5.1 Design Bases ........................................................ 7.3-11 7.3.5.2 Testing Description .............................................. 7.3-12 7.4 OTHER SAFETY RELATED PROTECTION, CONTROL AND DISPLAY SYSTEMS ................................................................................. 7.4-1 7.4.1 REACTOR SHUTDOWN CONTROLS .......................................... 7.4-1 7.4.2 PRIMARY COOLANT BOUNDARIES PROTECTION ................... 7.4-1 7.4.2.1 Primary Coolant Overpressure Protection System ..................................................................... 7.4-1 7.4.2.2 Other Primary Coolant Boundaries Protection..... 7.4-5 7.4.3 AUXILIARY FEEDWATER CONTROLS ........................................ 7.4-6 7.4.3.1 Auxiliary Feedwater Initiation ................................ 7.4-6 7.4.3.2 Auxiliary Feedwater Flow Controls and Isolation .......................................................... 7.4-12 7.4.4 CONTAINMENT HYDROGEN CONTROLS ................................ 7.4-15 7.4.4.1 Design Basis ......................................................... 7.4-15 7.4.5 VENTILATION AND EFFLUENT RELEASES CONTROLS ........ 7.4-16 7.4.5.1 Control Room ........................................................ 7.4-16 7.4.5.2 Engineered Safeguards Pump Rooms ................ 7.4-16 7.4.5.3 Radwaste Area ...................................................... 7.4-16 7.4.5.4 Fuel Handling Areas ............................................. 7.4-16 7.4.5.5 Waste Gas Decay Tank......................................... 7.4-16 7.4.6 OTHER SAFETY RELATED DISPLAY SYSTEMS...................... 7.4-17 7.4.6.1 Subcooled Margin Monitor ................................... 7.4-17 7.4.6.2 Wide-Range Containment Pressure, Temperature and Water Level .............................. 7.4-18 7.4.6.3 Reactor Vessel Level Monitoring System ........... 7.4-19 7.4.6.4 Core Exit Thermocouple (CET) System .............. 7.4-21 7.5 NONSAFETY-RELATED REGULATING CONTROLS ............................ 7.5-1 7.5.1 DESIGN BASES............................................................................. 7.5-1 7.5.1.1 Reactor Regulating ................................................. 7.5-1 7.5.1.2 Primary Pressure Regulating ................................. 7.5-2 7.5.1.3 Feedwater Regulating............................................. 7.5-2 7.5.1.4 Pressurizer Level Regulating ................................. 7.5-3 7.5.1.5 Steam Dump and Bypass ....................................... 7.5-3 7.5.1.6 Turbine Runback ..................................................... 7.5-4 7.5.1.7 Turbine Generator Controls ................................... 7.5-4

FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 TABLE OF CONTENTS Page 3 of 6 7.5.2 SYSTEM DESIGN .......................................................................... 7.5-4 7.5.2.1 Reactor Regulating ................................................. 7.5-4 7.5.2.2 Primary Pressure Regulating ................................. 7.5-7 7.5.2.3 Feedwater Regulating............................................. 7.5-8 7.5.2.4 Pressurizer Level Regulating ................................. 7.5-9 7.5.2.5 Steam Dump and Bypass ....................................... 7.5-9 7.5.2.6 Turbine Generator Controls ................................. 7.5-11 7.5.3 SYSTEM EVALUATION............................................................... 7.5-12 7.5.3.1 Rod Drive Control System .................................... 7.5-12 7.5.3.2 Primary Pressure Regulating ............................... 7.5-13 7.5.3.3 Feedwater Regulating........................................... 7.5-13 7.5.3.4 Pressurizer Level Regulating ............................... 7.5-14 7.5.3.5 Steam Dump and Bypass ..................................... 7.5-16 7.5.3.6 Turbine Generator Controls ................................. 7.5-17 7.6 NUCLEAR STEAM SUPPLY SYSTEM INSTRUMENTATION ................. 7.6-1 7.6.1 DESIGN BASES............................................................................. 7.6-1 7.6.1.1 Process Instrumentation ........................................ 7.6-1 7.6.1.2 Nuclear Instrumentation ......................................... 7.6-2 7.6.1.3 Control Rod Position Instrumentation .................. 7.6-2 7.6.1.4 Incore Instrumentation ........................................... 7.6-3 7.6.1.5 Palisades Plant Computer (PPC) ........................... 7.6-4 7.6.2 SYSTEM DESCRIPTION ............................................................... 7.6-5 7.6.2.1 Process Instrumentation ........................................ 7.6-5 7.6.2.2 Nuclear Instrumentation ....................................... 7.6-11 7.6.2.3 Control Rod Position Instrumentation ............... 7.6-15 7.6.2.4 Incore Instrumentation ......................................... 7.6-17 7.6.2.5 Palisades Plant Computer .................................... 7.6-19 7.7 OPERATING CONTROL STATIONS ....................................................... 7.7-1 7.7.1 GENERAL LAYOUT ...................................................................... 7.7-1 7.7.2 CONTROL ROOM ......................................................................... 7.7-1 7.7.3 ENGINEERED SAFEGUARDS AUXILIARY PANEL (C-33) .......... 7.7-4 7.7.4 AUXILIARY HOT SHUTDOWN CONTROL PANELS (C-150/C-150A) .............................................................................. 7.7-5 7.7.5 RADWASTE SYSTEM LOCAL CONTROL PANEL ...................... 7.7-7 7.7.6 MISCELLANEOUS LOCAL CONTROL STATIONS ..................... 7.7-7 7.7.7 FEATURES WHICH ENHANCE SAFE OPERATION .................... 7.7-7 7.7.8 IN-PLANT COMMUNICATION SYSTEM ....................................... 7.7-7 7.7.9 OUT-OF-PLANT COMMUNICATION SYSTEM ............................. 7.7-8

FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 TABLE OF CONTENTS Page 4 of 6 7.8 QUALITY CONTROL................................................................................ 7.8-1 7.8.1 SPECIFICATIONS.......................................................................... 7.8-1 7.8.2 SUPPLIER'S QUALITY CONTROL ............................................... 7.8-2 7.8.3 REACTOR PROTECTIVE SYSTEM SHOP TEST ......................... 7.8-2 7.8.4 SHIPPING AND STORAGE ........................................................... 7.8-3 7.8.5 RELIABILITY ................................................................................. 7.8-3 7.8.6 RECORDS AND CERTIFICATION ................................................ 7.8-4 7.8.7 FIELD QUALITY CONTROL .......................................................... 7.8-4 REFERENCES ............................................................................................................. 7-1 APPENDICES Appendix 7A, "Engineered Safeguard Testing Appendix 7C, "Regulatory Guide 1.97 Rev 3, Parameter Summary Table" LIST OF TABLES 7-1 Reactor Protective System Relays 7-2 Regulating Rods Withdrawal Interlocks 7-3 Source/Wide-Range Nuclear Instrument Channel Trip Unit Actions 7-4 Power-Range Safety Channel Trip Unit Actions 7-5 Control Rod Position Light Matrix LIST OF FIGURES 7-1 Reactor Protective System Block Diagram 7-2 Reactor Protective System Functional Diagram 7-3 Typical Measurement Channel Functional Diagram 7-4 Schematic Diagram, Pressurizer Pressure ATWS 7-5 Schematic Diagram, Pressurizer Pressure ATWS 7-6 Low Flow Protective System Functional Diagram 7-7 Logic for Thermal Margin Monitor 7-8 Neutron Flux Monitoring System Start-Up and Logarithmic Range Channels 7-9 Neutron Flux Monitoring System Power Range Channels 7-10 Power Rate-of-Change Trip and Pretrip Interface With RPS 7-11 Zero Power Mode Bypass 7-12 Reactor Protective System Interfaces 7-13 Logic Diagram, Safety Injection Initiation 7-14 Sh 1 Logic Diagram, Main Generator Protection 7-14 Sh 2 Logic Diagram, Turbine-Generator Trips and Fast Transfer 7-14 Sh 3 Logic Diagram, 2400 Volt Load Shed 7-14 Sh 4 Logic Diagram, Diesel Start (CPCo) 7-14 Sh 5 Logic Diagram, Diesel Engine Control, Trips and Alarms 7-14 Sh 6 Logic Diagram, Diesel Generator Breakers 7-14 Sh 7 Logic Diagram, Bus 1C and 1D Incoming Breakers 7-14 Sh 8 Logic Diagram, Power to Bus 1E, 1F and 1G Incoming Breakers

FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 TABLE OF CONTENTS Page 5 of 6 7-14 Sh 9 Logic Diagram, Bus 1A & 1B Incoming Breakers 7-14 Sh 10 Logic Diagram, Generator Breaker and M.O.D. Control 7-14 Sh 11 Logic Diagram, Start-Up XFMR. Protection 7-14 Sh 12 Logic Diagram, Safeguard Transformer 1-1 7-14 Sh 13 Logic Diagram, Circuit Breaker Operation 7-15 Schematic Diagram, Safety Injection Signal Auxiliary Circuits 7-16 Schematic Diagram, Safety Injection Signal Auxiliary Circuits 7-17 Schematic Diagram, Safety Injection and Sequence Loading Circuits 7-18 Schematic Diagram, Safety Injection and Sequence Loading Circuits 7-19 Schematic Diagram, Safety Injection and Sequence Loading Circuits 7-20 Schematic Diagram, Safety Injection and Sequence Loading Circuits 7-21 Schematic Diagram, Safety Injection and Sequence Loading Test Circuit 7-22 Schematic Diagram, Safety Injection and Sequence Loading Test Circuit 7-23 Schematic Diagram, Safety Injection and Sequence Loading Test Circuit 7-24 Logic Diagram, Containment High Pressure Signal 7-25 Logic Diagram, Containment High Radiation 7-26 Schematic Diagram, Containment High Pressure, High Radiation and SIRW Tank Low Level 7-27 Schematic Diagram, Containment High Pressure, High Radiation and SIRW Tank Low Level 7-28 Schematic Diagram, Containment Isolation on High Pressure or High Radiation 7-29 Schematic Diagram, Containment Isolation on High Pressure or High Radiation 7-30 Logic Diagram, SIS Test and RAS 7-31 Schematic Diagram, SIRW Tank and Containment Sump Valves 7-32 Schematic Diagram, SIRW Tank and Containment Sump Valves 7-33 Logic Diagram, Legend and Notes 7-34 Logic Diagram, Legend and Notes 7-35 Logic Diagram, Legend and Notes 7-36 Schematic Diagram, Steam Generator Level Instrumentation 7-37 Logic Diagram, Auxiliary Feedwater Actuation System 7-38 Logic Diagram, Motor Driven Auxiliary Feedwater Pump P-8A 7-39 Logic Diagram, Motor Driven Auxiliary Feedwater Pump P-8C 7-40 Sh 1 Logic Diagram, Turbine Driven Auxiliary Feedwater Pump P-8B 7-40 Sh 2 Logic Diagram, Turbine Driven Auxiliary Feedwater Pump P-8B 7-41 Interface Loop Diagram, Pump Low Suction Pressure Trip 7-41 Sh 1 Logic Diagram Turbine Driven Auxiliary Feedwater Pump P-8B 7-41 Sh 2 Logic Diagram Turbine Driven Auxiliary Feedwater Pump P-8B 7-42 Logic Diagram, Auxiliary Feedwater Pumps Low Suction Pressure Trip 7-43 Interface Loop Diagram, Flow Control 7-44 Interface Loop Diagram, Flow Control 7-45 Interface Loop Diagram, Flow and Pressure Indication 7-46 Logic Diagram, Aux Feedwater Flow Control and Pump Test Logic 7-47 Logic Diagram, Auxiliary Feedwater Flow Control and Pump Test Logic 7-48 Logic Diagram, Auxiliary Feedwater Actuation System 7-49 Logic Diagram, Auxiliary Feedwater - Steam Generator Isolation Valves

FSAR CHAPTER 7 - INSTRUMENTATION AND CONTROLS Revision 30 TABLE OF CONTENTS Page 6 of 6 7-50 Logic Diagram, Auxiliary Feedwater - Steam Generator Isolation Valves 7-51 Logic Diagram, AFAS-FOGG Remote Display and Annunciator Assignment 7-52 Logic Diagram, AFAS-FOGG Remote Display and Annunciator Assignment 7-53 Reactor Shutdown Controls 7-54 Reactor Regulating System Block Diagram 7-55 Rod Drive Control System Schematic Diagram 7-56 Rod Position Set Points 7-57 Pressure Control Program 7-58 Block Diagram, Steam Dump and Bypass System 7-59 Pressurizer Level Control System Failures Study - Mode "A" Failure 7-60 Piping Drawing, Nuclear Detector Wells 7-61 Block Diagram, Critical Functions Monitor System

FSAR CHAPTER 8 - ELECTRICAL SYSTEMS Revision 27 TABLE OF CONTENTS Page 1 of 5 SECTIONS

8.1 INTRODUCTION

....................................................................................... 8.1-1 8.1.1 DESIGN BASIS .............................................................................. 8.1-1 8.

1.2 DESCRIPTION

AND OPERATION................................................. 8.1-3 8.1.3 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT ...................................................... 8.1-4 8.1.4 SEISMIC QUALIFICATION OF ELECTRICAL EQUIPMENT ......... 8.1-6 8.1.5 STATION BLACKOUT ...................................................................8.1-6 8.2 NETWORK INTERCONNECTION ............................................................ 8.2-1 8.2.1 DESIGN BASIS .............................................................................. 8.2-1 8.

2.2 DESCRIPTION

AND OPERATION................................................. 8.2-1 8.2.3 DESIGN ANALYSIS ....................................................................... 8.2-3 8.2.4 TRANSMISSION SYSTEM OWNERSHIP ...................................... 8.2-5 8.3 STATION DISTRIBUTION ........................................................................ 8.3-1 8.3.1 4,160 VOLT SYSTEM .................................................................... 8.3-1 8.3.1.1 Design Basis ............................................................ 8.3-1 8.3.1.2 Description and Operation ..................................... 8.3-1 8.3.1.3 Design Analysis ....................................................... 8.3-3 8.3.2 2,400 VOLT SYSTEM .................................................................... 8.3-3 8.3.2.1 Design Basis ............................................................ 8.3-3 8.3.2.2 Description and Operation ..................................... 8.3-3 8.3.2.3 Design Analysis ....................................................... 8.3-7 8.3.3 480 VOLT SYSTEM ....................................................................... 8.3-7 8.3.3.1 Design Basis ............................................................ 8.3-7 8.3.3.2 Description and Operation ..................................... 8.3-8 8.3.3.3 Design Analysis ..................................................... 8.3-10 8.3.4 CONTROL ROD DRIVE POWER ................................................. 8.3-10 8.3.4.1 Design Basis .......................................................... 8.3-10 8.3.4.2 Description and Operation ................................... 8.3-11 8.3.4.3 Design Analysis ..................................................... 8.3-11

FSAR CHAPTER 8 - ELECTRICAL SYSTEMS Revision 27 TABLE OF CONTENTS Page 2 of 5 8.3.5 DC AND PREFERRED AC SYSTEMS ......................................... 8.3-11 8.3.5.1 Design Basis .......................................................... 8.3-11 8.3.5.2 Description and Operation ................................... 8.3-11 8.3.5.3 Design Analysis ..................................................... 8.3-17 8.3.6 INSTRUMENT AC SYSTEM.........................................................8.3-18 8.3.6.1 Design Basis .......................................................... 8.3-18 8.3.6.2 Description and Operation ................................... 8.3-18 8.3.6.3 Design Analysis ..................................................... 8.3-18 8.4 EMERGENCY POWER SOURCES........................................................... 8.4-1 8.4.1 EMERGENCY GENERATORS ....................................................... 8.4-1 8.4.1.1 Design Basis ............................................................ 8.4-1 8.4.1.2 Description and Operation ..................................... 8.4-1 8.4.1.3 Design Analysis ....................................................... 8.4-4 8.4.2 STATION BATTERIES ...................................................................8.4-7 8.4.2.1 Design Basis ............................................................ 8.4-7 8.4.2.2 Description and Operation ..................................... 8.4-8 8.4.2.3 Design Analysis ....................................................... 8.4-9 8.4.3 TURBINE GENERATOR COASTDOWN ....................................... 8.4-9 8.4.3.1 Design Basis ............................................................ 8.4-9 8.4.3.2 Description and Operation ................................... 8.4-10 8.4.4 EMERGENCY POWER SUPPLY FOR PRESSURIZER HEATERS ............................................................................... 8.4-10 8.4.4.1 Design Basis .......................................................... 8.4-10 8.4.4.2 Description and Operation ................................... 8.4-10 8.4.5 SUPPLEMENTAL 2400 VOLT POWER SUPPLY ....................... 8.4-11 8.4.5.1 Design Basis .......................................................... 8.4-11 8.4.5.2 Description and Operation ................................... 8.4-11

FSAR CHAPTER 8 - ELECTRICAL SYSTEMS Revision 27 TABLE OF CONTENTS Page 3 of 5 8.5 RACEWAY AND CABLING SYSTEM ....................................................... 8.5-1 8.5.1 DESIGN BASIS .............................................................................. 8.5-1 8.5.1.1 Fire Protection Features ......................................... 8.5-1 8.5.1.2 Electrical Penetrations of Reactor Containment .. 8.5-1 8.5.2 DESIGN DESCRIPTION .................................................................8.5-1 8.5.3 DESIGN EVALUATION ..................................................................8.5-3 8.5.3.1 Compliance With Regulatory Guide 1.75 .............. 8.5-3 8.5.3.2 Raceway and Cabling Separation Criteria ............ 8.5-4 8.5.3.3 Raceway and Cabling Fire Barriers ....................... 8.5-7 8.5.3.4 Cable Spreading Room Protection Design ........... 8.5-7 8.5.3.5 Cable Penetration Rooms Protection Design ....... 8.5-8 8.5.3.6 Raceway Runs Protection Design ......................... 8.5-9 8.5.3.7 Safety-Related Cabling Routing Via Nonsafety-Related Areas ........................................ 8.5-9 8.5.3.8 Containment Building Routing Protection .......... 8.5-10 8.5.3.9 Other Areas Routing Protection ...........................8.5-10 8.6 AUTOMATIC TRANSFER, VOLTAGE PROTECTION AND LOAD SHEDDING CONTROLS .............................................................................................. 8.6-1 8.6.1 DESIGN BASIS .............................................................................. 8.6-1 8.

6.2 DESCRIPTION

AND OPERATION................................................. 8.6-2 8.6.3 DESIGN ANALYSIS ....................................................................... 8.6-5 8.6.3.1 Automatic Transfer System .................................... 8.6-5 8.6.3.2 Voltage Protection and Load Shedding Systems. 8.6-6

FSAR CHAPTER 8 - ELECTRICAL SYSTEMS Revision 27 TABLE OF CONTENTS Page 4 of 5 8.7 PHYSICAL SEPARATION, ELECTRICAL ISOLATION AND SUPPORT SYSTEMS ............................................................................... 8.7-1 8.7.1 ELECTRICAL ISOLATION (SEE FIGURE 8-1)..............................8.7-1 8.7.2 PHYSICAL SEPARATION..............................................................8.7-2 8.7.2.1 General .....................................................................8.7-2 8.7.2.2 Transformers ........................................................... 8.7-3 8.7.2.3 Protection Against Water Damage......................... 8.7-3 8.7.2.4 Smoke Control ......................................................... 8.7-4 8.7.2.5 Switchgear Rooms Protection ............................... 8.7-4 8.7.2.6 Emergency Generators Rooms Protection ........... 8.7-5 8.7.2.7 Battery Rooms Protection ......................................8.7-6 8.7.3 SUPPORT SYSTEMS .................................................................... 8.7-7 8.7.3.1 Ventilation ................................................................ 8.7-7 8.8 MOTOR OPERATED VALVES ................................................................. 8.8-1 8.9 LIGHTING SYSTEMS ............................................................................... 8.9-1 8.10 QUALITY CONTROL .............................................................................. 8.10-1 REFERENCES ............................................................................................................. 8-1 LIST OF TABLES 8-1 Switchyard System Ratings and Construction of Components 8-2 4,160 Volt System Ratings and Construction of Components 8-3 2,400 Volt System Ratings and Construction of Components 8-4 480 Volt System Ratings and Construction of Components 8-5 DC and Preferred AC Systems Ratings and Construction of Components 8-6 Diesel 1-1 Sequence Start 8-7 Diesel 1-2 Sequence Start

FSAR CHAPTER 8 - ELECTRICAL SYSTEMS Revision 27 TABLE OF CONTENTS Page 5 of 5 LIST OF FIGURES 8-1 Sh 1 Single Line Meter & Relay Diagram, 480 Volt Motor Control Center - Warehouse 8-1 Sh 2 Plant Single Line Diagram 8-1 Sh 3 Plant Single Line Diagram 8-2 Substation 8-3 Sh 1 Single Line Meter & Relay Diagram, Generator & 4160 V System 8-3 Sh 2 Single Line Meter & Relay Diagram, Cooling Tower Systems 8-4 Single Line Meter & Relay Diagram, 2400 Volt System 8-5 Sh 1 Single Line Meter & Relay Diagram, 480 Volt Load Centers 8-5 Sh 2 Single Line Meter & Relay Diagram, 480 Volt Load Centers 8-5 Sh 3 Single Line Meter & Relay Diagram, Cooling Tower Systems 8-6 Sh 1 Single Line Meter & Relay Diagram, 480 Volt Motor Control Centers 8-6 Sh 2 Single Line Meter & Relay Diagram, 480 Volt Motor Control Centers 8-6 Sh 3 Single Line Meter & Relay Diagram, 480 Volt Motor Control Centers 8-6 Sh 4 Single Line Meter & Relay Diagram, Radwaste System 8-7 Sh 1 Single Line Meter & Relay Diagram, 125V DC, 120V Instrument &

Preferred AC System 8-7 Sh 2 Single Line Meter & Relay Diagram, 125V DC, 120V Instrument &

Preferred AC System 8-8 125V DC System, Auxiliary Shutdown Layout 8-9 Substation 120/240V AC & 125V DC Power Distribution Center 8-10 Voltage Protection Sensors Location 8-11 Piping & Instrument Diagram, Lube Oil, Fuel Oil and Diesel Generator Systems

FSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 31 TABLE OF CONTENTS Page 1 of 6 SECTIONS 9.1 SERVICE WATER SYSTEM ..................................................................... 9.1-1 9.1.1 DESIGN BASIS .............................................................................. 9.1-1 9.1.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.1-1 9.1.2.1 System Description................................................. 9.1-1 9.1.2.2 Component Description ......................................... 9.1-2 9.1.2.3 System Operation ................................................... 9.1-3 9.1.3 DESIGN ANALYSIS ....................................................................... 9.1-5 9.1.3.1 Margins of Safety .................................................... 9.1-5 9.1.3.2 Provisions for Testing and Inspection .................. 9.1-6 9.1.3.3 Discharge Line Rupture Analysis .......................... 9.1-6 9.1.3.4 Generic Letter 96-06 Waterhammer Analysis ....... 9.1-8 9.2 REACTOR PRIMARY SHIELD COOLING SYSTEM ................................ 9.2-1 9.2.1 DESIGN BASIS .............................................................................. 9.2-1 9.2.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.2-1 9.2.2.1 System Description................................................. 9.2-1 9.2.2.2 Component Description ......................................... 9.2-1 9.2.2.3 System Operation ................................................... 9.2-2 9.2.3 DESIGN ANALYSIS ....................................................................... 9.2-3 9.2.3.1 Margins of Safety .................................................... 9.2-3 9.3 COMPONENT COOLING SYSTEM.......................................................... 9.3-1 9.3.1 DESIGN BASIS .............................................................................. 9.3-1 9.3.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.3-1 9.3.2.1 System Description................................................. 9.3-1 9.3.2.2 Component Description ......................................... 9.3-2 9.3.2.3 System Operation ................................................... 9.3-2 9.3.3 DESIGN ANALYSIS ....................................................................... 9.3-6 9.3.3.1 Margins of Safety .................................................... 9.3-6 9.3.3.2 Provisions for Testing and Inspection .................. 9.3-7 9.4 SPENT FUEL POOL COOLING SYSTEM ............................................... 9.4-1 9.4.1 DESIGN BASIS .............................................................................. 9.4-1 9.4.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.4-1 9.4.2.1 System Description................................................. 9.4-1 9.4.2.2 Component Description ......................................... 9.4-2 9.4.2.3 System Operation ................................................... 9.4-2 9.4.3 DESIGN ANALYSIS ....................................................................... 9.4-3 9.4.3.1 Margins of Safety .................................................... 9.4-3 9.4.3.2 Provisions for Testing. ........................................... 9.4-4

FSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 31 TABLE OF CONTENTS Page 2 of 6 9.5 COMPRESSED AIR SYSTEMS ................................................................ 9.5-1 9.5.1 INSTRUMENT AIR SYSTEM ......................................................... 9.5-1 9.5.1.1 Design Basis ........................................................... 9.5-1 9.5.1.2 System Description................................................. 9.5-1 9.5.1.3 Component Description ......................................... 9.5-1 9.5.1.4 System Operation ................................................... 9.5-2 9.5.1.5 Design Analysis ...................................................... 9.5-3 9.5.2 HIGH PRESSURE AIR SYSTEM ................................................... 9.5-4 9.5.2.1 Design Basis ........................................................... 9.5-4 9.5.2.2 System Description................................................. 9.5-4 9.5.2.3 Component Description ......................................... 9.5-4 9.5.2.4 System Operation ................................................... 9.5-5 9.5.2.5 Design Analysis ...................................................... 9.5-5 9.5.3 BACKUP SYSTEMS ...................................................................... 9.5-6 9.5.3.1 Design Basis ........................................................... 9.5-6 9.5.3.2 System Description................................................. 9.5-7 9.5.3.3 Component Description ......................................... 9.5-7 9.5.3.4 System Operation ................................................... 9.5-7 9.5.3.5 Design Analysis ...................................................... 9.5-8 9.5.4 FEEDWATER PURITY AIR SYSTEM ............................................ 9.5-8 9.5.4.1 Design Basis ........................................................... 9.5-8 9.5.4.2 System Description................................................. 9.5-8 9.5.4.3 Component Description ......................................... 9.5-8 9.5.4.4 System Operation ................................................... 9.5-8 9.5.5 RADWASTE AREA COMPRESSOR ............................................. 9.5-9 9.6 FIRE PROTECTION ................................................................................. 9.6-1 9.6.1 DESIGN BASIS .............................................................................. 9.6-1 9.6.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.6-2 9.6.2.1 System Description................................................. 9.6-2 9.6.2.2 Component Description ......................................... 9.6-3 9.6.2.3 System Operation ................................................... 9.6-4 9.6.3 DESIGN ANALYSIS ....................................................................... 9.6-5 9.6.4 FIRE PROTECTION PROGRAM..9.6-5 9.7 AUXILIARY FEEDWATER SYSTEM ........................................................ 9.7-1 9.7.1 DESIGN BASIS .............................................................................. 9.7-1 9.7.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.7-1 9.7.2.1 System Description................................................. 9.7-1 9.7.2.2 Component Description ......................................... 9.7-2 9.7.2.3 System Operation ................................................... 9.7-2 9.7.3 DESIGN ANALYSIS ....................................................................... 9.7-4 9.7.4 SYSTEM RELIABILITY .................................................................. 9.7-5 9.7.5 TESTS AND INSPECTION ............................................................ 9.7-5

FSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 31 TABLE OF CONTENTS Page 3 of 6 9.8 HEATING, VENTILATION AND AIR-CONDITIONING SYSTEM ............. 9.8-1 9.8.1 DESIGN BASIS .............................................................................. 9.8-1 9.8.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.8-2 9.8.2.1 System Description................................................. 9.8-2 9.8.2.2 Component Description ......................................... 9.8-4 9.8.2.3 Codes ....................................................................... 9.8-6 9.8.2.4 Operation ................................................................. 9.8-7 9.8.3 TESTS AND INSPECTIONS ........................................................ 9.8-22 9.8.4 LOSS OF INSTRUMENT AIR TO VENTILATION DAMPERS..... 9.8-23 9.8.5 SAFETY EVALUATION ............................................................... 9.8-24 9.8.5.1 Introduction ........................................................... 9.8-24 9.8.5.2 Evaluation .............................................................. 9.8-24 9.9 SAMPLING SYSTEM ................................................................................ 9.9-1 9.9.1 DESIGN BASIS .............................................................................. 9.9-1 9.9.2 SYSTEM DESCRIPTION AND OPERATION................................. 9.9-1 9.9.3 SYSTEM EVALUATION................................................................. 9.9-2 9.10 CHEMICAL AND VOLUME CONTROL SYSTEM .................................. 9.10-1 9.10.1 DESIGN BASIS ............................................................................ 9.10-1 9.10.2 SYSTEM DESCRIPTION AND OPERATION............................... 9.10-1 9.10.2.1 General................................................................... 9.10-1 9.10.2.2 Volume Control ..................................................... 9.10-2 9.10.2.3 Chemical Control .................................................. 9.10-3 9.10.2.4 Reactivity Control ................................................. 9.10-4 9.10.2.5 Pressure-Leakage Test System ........................... 9.10-5 9.10.2.6 Component Functional Description .................... 9.10-5 9.10.3 OPERATIONS .............................................................................. 9.10-8 9.10.3.1 Start-Up .................................................................. 9.10-8 9.10.3.2 Normal Operations ................................................ 9.10-9 9.10.3.3 Shutdown ............................................................. 9.10-10 9.10.3.4 Emergency Operations ....................................... 9.10-11 9.10.4 DESIGN ANALYSIS ................................................................... 9.10-11 9.10.5 TESTING AND INSPECTION .................................................... 9.10-12 9.10.6 REGENERATIVE HEAT EXCHANGER ..................................... 9.10-12 9.11 FUEL HANDLING AND STORAGE SYSTEMS ...................................... 9.11-1 9.

11.1 INTRODUCTION

.......................................................................... 9.11-1 9.11.2 NEW FUEL STORAGE ................................................................ 9.11-1 9.11.3 SPENT FUEL STORAGE ............................................................ 9.11-2 9.11.3.1 Original Design ..................................................... 9.11-2 9.11.3.2 Modified Spent Fuel Storage ............................... 9.11-3 9.11.3.3 Structural Analysis................................................ 9.11-5

FSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 31 TABLE OF CONTENTS Page 4 of 6 9.11.3.4 Prevention of Criticality During Transfer and Storage ........................................................... 9.11-6 9.11.3.5 Radiological Considerations ............................. 9.11-10 9.11.3.5.1 Radiation Shielding .................................. 9.11-10 9.11.3.5.2 Pool Surface Dose.................................... 9.11-10 9.11.3.5.3 Airborne Doses ......................................... 9.11-11 9.11.3.5.4 General Area Doses ................................. 9.11-12 9.11.3.5.5 Protection Against Radioactivity Release...................................................... 9.11-12 9.11.4 FUEL HANDLING SYSTEM....................................................... 9.11-13 9.11.4.1 General................................................................. 9.11-14 9.11.4.2 Fuel Handling Structures ................................... 9.11-15 9.11.4.3 Major Fuel Handling Equipment ........................ 9.11-15 9.11.4.4 System Evaluation .............................................. 9.11-28 9.11.4.5 Test Program ....................................................... 9.11-29 9.11.5 SPENT FUEL STORAGE AT AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION ............................... 9.11-30 9.11.5.1 Description Of 10CFR72 License Items Which Interface With The 10CFR50 License..... 9.11-31 9.11.5.1.1 Multi-Assembly Sealed Basket And Transfer Cask ........................................... 9.11-31 9.11.5.1.2 Transnuclear 32PT-S125 DSC, 24 PTH-S125 DSC and OS-197 Transfer Cask .............. 9.11-32 9.11.5.1.3 Impact Limiting Pads ............................... 9.11-32 9.11.5.1.4 Security For The Independent Spent Fuel Storage Installation.......................... 9.11-33 9.11.5.1.5 Lifting Equipment ..................................... 9.11-33 9.11.5.1.6 Spent Fuel Pool Boron And Temperature Limits .................................. 9.11-33 9.12 ULTIMATE HEAT SINK .......................................................................... 9.12-1 9.12.1 DESIGN BASIS ............................................................................ 9.12-1 9.12.2 SYSTEM DESCRIPTION AND OPERATION............................... 9.12-1 9.12.2.1 System Description............................................... 9.12-1 9.12.2.2 System Operation ................................................. 9.12-3 9.12.3 DESIGN ANALYSIS ..................................................................... 9.12-3 9.12.3.1 Margin of Safety .................................................... 9.12-3 9.12.3.2 Provisions for Testing and Inspection ................ 9.12-4 9.12.3.3 Heat Sink At Hot Shutdown Conditions .............. 9.12-4 REFERENCES ............................................................................................................. 9-1

FSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 31 TABLE OF CONTENTS Page 5 of 6 LIST OF TABLES 9-1 Service Water System Flow Requirements 9-2 Service Water System Design Ratings and Construction of Components 9-3 Reactor Primary Shield Cooling System Design Ratings and Construction of Components 9-4 Component Cooling System Heat Loads 9-5 Component Cooling Water System Design Ratings and Construction of Components 9-6 Component Cooling System Required Flow Rates 9-7 Spent Fuel Pool Cooling System Design Ratings and Construction of Components 9-8 Instrument Air System Design Ratings and Construction of Components 9-9 Effect of Loss of Air to Air-Operated Valves 9-10 Fire Detection Instrumentation 9-11 Fire Protection System Design Ratings and Construction of Components 9-12 Auxiliary Feedwater System Design Ratings and Construction of Components 9-13 Design Basis Ambient Conditions 9-14 Control Room HVAC System Major Component Design Data 9-15 Ventilation Dampers: Functions and Positions for Various Modes of Plant Operation 9-16 Sampling Stations 9-17 Sample Point Summary 9-18 Chemical and Volume Control System Design Parameters 9-19 Fuel Handling Data 9-20 Fuel Building Crane

FSAR CHAPTER 9 - AUXILIARY SYSTEMS Revision 31 TABLE OF CONTENTS Page 6 of 6 LIST OF FIGURES 9-1 Sh 1 System Diagram, Service Water System 9-1 Sh 1A P&ID, Service Water System 9-1 Sh 1B P&ID, Service Water System 9-1 Sh 2 P&ID, Service Water Screen Structure, and Chlorinator 9-2 P&ID, Shield Cooling System 9-3 Nominal Operating Conditions Cooling Coil Centerline 9-4 Nominal Operating Conditions Mid-Span of Two Cooling Coils 9-5 Bounding Design Cooling Coil Centerline 9-6 Bounding Design Conditions and Mid-Span of Two Cooling Coils 9-7 Sh 1 P&ID, Component Cooling System 9-7 Sh 2 P&ID, Component Cooling System 9-7 Sh 3 P&ID, Component Cooling System 9-8 P&ID, Spent Fuel Pool Cooling System 9-9 Sh 1 P&ID, Service and Instrument Air Systems 9-9 Sh 2 P&ID, Miscellaneous Gas Supply Systems 9-10 Sh 1 P&ID, High Pressure Air Operated Valves 9-10 Sh 1A P&ID High Pressure Air Operated Valves 9-10 Sh 2 P&ID, High Pressure Air Operated Valves 9-11 Sh 1 P&ID, Fire Protection System 9-11 Sh 2 P&ID, Fire Protection System 9-11 Sh 3 P&ID, Fire Protection System 9-12 P&ID, Auxiliary Feedwater System 9-13 P&ID, Auxiliary Feedwater Steam Supply 9-14 Sh 1 P&ID, Heating, Ventilation and Air Conditioning, Switchgear and Cable Spreading Rooms 9-14 Sh 2 P&ID, Heating, Ventilation and Air Conditioning, Containment Building 9-14 Sh 3 P&ID, Heating, Ventilation and Air Conditioning, Radwaste Area 9-14 Sh 4 P&ID, Heating, Ventilation and Air Conditioning, Miscellaneous Buildings 9-14 Sh 5 P&ID, Heating, Ventilation and Air Conditioning, Control Room 9-14 Sh 6 P&ID, Heating, Ventilation and Air Conditioning, Control Room 9-14 Sh 7 P&ID, Heating, Ventilation and Air Conditioning, Control Room 9-14 Sh 8 Heating and Ventilation Air Flow Diagram 9-14 Sh 9 P&ID, Heating, Ventilating and Cooling Auxiliary Building Addition 9-15 P&ID, Fluid System Diagram Post Accident Sample Monitor System 9-16 P&ID, Gas Analyzing Systems (Containment Hydrogen) 9-17 Monitoring and Sampling Systems (Radwaste Addition) 9-18 Sh 1 P&ID, Chemical and Volume Control System 9-18 Sh 1A P&ID, Chemical and Volume Control System 9-18 Sh 1B P&ID, Chemical and Volume Control System 9-19 Boron Concentration vs Core Lifetime 9-20 Palisades Plant Spent Fuel Storage Rack Arrangement

FSAR CHAPTER 10 - STEAM AND POWER CONVERSION SYSTEM Revision 30 TABLE OF CONTENTS Page 1 of 1 SECTIONS 10.1 DESIGN BASIS ................................................................................... 10.1-1 10.2 SYSTEM DESCRIPTION AND OPERATION ......................................... 10.2-1 10.2.1 SYSTEM GENERAL DESCRIPTION........................................... 10.2-1 10.2.2 SYSTEM TURBINE ...................................................................... 10.2-5 10.2.2.1 High-Pressure Turbine ............................................. 10.2-5 10.2.2.2 Low-Pressure Turbine .............................................. 10.2-6 10.2.2.3 Electrical Generator10.2-8 10.2.2.4 Exciter....10.2-8 10.2.3 CONDENSATE AND FEEDWATER.10.2-9 10.2.3.1 Condensate System..10.2-9 10.2.3.2 Condensate Demineralizer System....10.2-10 10.2.3.3 Feedwater Regulating System.10.2-11 10.2.4 CIRCULATING WATER SYSTEM......10.2-13 10.2.4.1 Cooling Towers....10.2-13 10.2.4.2 Makeup and Blowdown......10.2-14 10.2.4.3 Dilution...10.2-14 10.2.5 CODES AND STANDARDS..10.2-14 10.3 SYSTEM ANALYSIS..10.3-1 10.3.1 REACTOR AND/OR TURBINE TRIP......10.3-1 10.4 TESTS AND INSPECTIONS....10.4-1 10.4.1 PIPE WALL THINNING INSPECTION PROGRAM..10.4-1 REFERENCES..None LIST OF TABLES 10-1 Turbine Casing Properties 10-2 Stud Mechanical Properties 10-3 Signal System Operating Conditions 10-4 Cooling Tower Design Summary 10-5 Cooling Tower Pumps LIST OF FIGURES 10-1 System Diagram, Main Steam, Main and Auxiliary Turbine Systems 10-2 System Diagram, Extractions, Heaters Vents and Drain Systems 10-3 Sh 1 Piping and Instrument Diagram, Steam Generator Blowdown Modification 10-3 Sh 2 Piping and Instrument Diagram, Steam Generator Blowdown Modification 10-3 Sh 3 Piping and Instrument Diagram, Steam Generator Blowdown Modification 10-4 System Diagram, Feedwater and Condensate System 10-5 General Assembly Electrical Generator 10-6 System Diagram, Cooling Tower System

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND Revision 28 RADIATION PROTECTION Page 1 of 4 TABLE OF CONTENTS SECTIONS 11.1 SOURCE TERMS ................................................................................... 11.1-1 11.2 LIQUID RADIOACTIVE WASTE SYSTEM ............................................. 11.2-1 11.2.1 DESIGN BASES........................................................................... 11.2-1 11.2.1.1 Design Objective ................................................... 11.2-1 11.2.1.2 Design Criteria ...................................................... 11.2-1 11.2.1.3 Codes ..................................................................... 11.2-1 11.2.2 SYSTEM DESCRIPTION ............................................................. 11.2-2 11.2.2.1 Clean Waste Section ............................................. 11.2-2 11.2.2.2 Dirty Waste Section .............................................. 11.2-4 11.2.2.3 Laundry Waste Section ........................................ 11.2-4 11.2.3 RADIOACTIVE RELEASES ......................................................... 11.2-5 11.2.3.1 Clean Waste Section ............................................. 11.2-5 11.2.3.2 Dirty Waste Section .............................................. 11.2-8 11.2.3.3 Laundry Waste Section ........................................ 11.2-8 11.2.4 BALANCE OF PLANT (BOP) INTERFACE................................. 11.2-8 11.2.4.1 Clean Waste Section ............................................. 11.2-8 11.2.4.2 Dirty Waste Section .............................................. 11.2-8 11.2.4.3 Laundry Waste Section ........................................ 11.2-9 11.2.4.4 Alternate Radwaste Processing System...11.2-9 11.2.5 SYSTEM EVALUATION ......................................................................... 11.2-9 11.3 GASEOUS RADIOACTIVE WASTE SYSTEM ....................................... 11.3-1 11.3.1 DESIGN BASIS ............................................................................ 11.3-1 11.3.2 SYSTEM DESCRIPTION ............................................................. 11.3-1 11.3.2.1 Gas Collection Header.......................................... 11.3-1 11.3.2.2 Waste Gas Processing System............................ 11.3-2 11.3.3 RADIOACTIVE RELEASES ......................................................... 11.3-2 11.3.4 BOP INTERFACE ........................................................................ 11.3-3 11.3.5 SYSTEM EVALUATION............................................................... 11.3-3 11.4 SOLID WASTE MANAGEMENT SYSTEM ............................................. 11.4-1 11.4.1 DESIGN BASIS ............................................................................ 11.4-1 11.4.2 SYSTEM DESCRIPTION ............................................................. 11.4-2 11.4.2.1 System Modifications ........................................... 11.4-2 11.4.2.2 Radioactive Waste Storage Facilities ................. 11.4-3 11.4.2.3 Alternate Radwaste Processing Standard Dewatering System ................................................................... 11.4-8 11.4.3 RADIOACTIVE RELEASES ......................................................... 11.4-8 11.4.4 BOP INTERFACE ........................................................................ 11.4-9 11.4.5 SYSTEM EVALUATION............................................................... 11.4-9 11.4.6 REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 ..................................................................... 11.4-9

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND Revision 28 RADIATION PROTECTION Page 2 of 4 TABLE OF CONTENTS 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEM .............................................................................. 11.5-1 11.5.1 DESIGN BASIS ............................................................................ 11.5-1 11.5.2 SYSTEM DESCRIPTION ............................................................. 11.5-1 11.5.3 EFFLUENT MONITORING AND SAMPLING .............................. 11.5-2 11.5.4 SYSTEM EVALUATION............................................................... 11.5-3 11.6 RADIATION PROTECTION .................................................................... 11.6-1 11.6.1 GENERAL .................................................................................... 11.6-1 11.6.1.1 Radiation Exposure of Personnel........................ 11.6-1 11.6.1.2 Radiation Exposure of Materials and Components ................................................... 11.6-1 11.6.2 RADIATION ZONING AND ACCESS CONTROL ........................ 11.6-2 11.6.3 GENERAL DESIGN CONSIDERATIONS .................................... 11.6-3 11.6.3.1 Specific Design Values ......................................... 11.6-3 11.6.3.2 Reactor Core Data................................................. 11.6-3 11.6.4 SHIELDING DESIGN ................................................................... 11.6-4 11.6.4.1 Containment Building Shell ................................. 11.6-4 11.6.4.2 Containment Building Interior.............................. 11.6-4 11.6.4.3 Auxiliary Building (Including Radwaste Building Addition) ................................................. 11.6-5 11.6.4.4 Turbine Building ................................................... 11.6-7 11.6.4.5 General Plant Yard Areas ..................................... 11.6-7 11.6.4.6 Other Buildings ..................................................... 11.6-7 11.6.5 AREA RADIATION MONITORING SYSTEMS............................. 11.6-8 11.6.5.1 Design Basis ......................................................... 11.6-8 11.6.5.2 System Description............................................... 11.6-8 11.6.5.3 Testing and Maintenance ..................................... 11.6-9 11.6.6 HEALTH PHYSICS ...................................................................... 11.6-9 11.6.6.1 Facilities ................................................................ 11.6-9 11.6.6.2 Tool and Equipment Decontamination Facility 11.6-10 11.6.6.3 Calibration Facility .............................................. 11.6-11 11.6.6.4 Radiation Control ................................................ 11.6-11 11.6.6.5 Shielding .............................................................. 11.6-11 11.6.6.6 Access Control .................................................... 11.6-11 11.6.6.7 Facility Contamination Control .......................... 11.6-13 11.6.6.8 Personnel Contamination Control ..................... 11.6-14 11.6.6.9 Airborne Contamination Control ....................... 11.6-15 11.6.6.9.1 Respiratory Protection Program ............. 11.6-15 11.6.6.10 External Radiation Dose Determination............ 11.6-17 11.6.6.11 Internal Radiation Dose Determination ............. 11.6-17

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND Revision 28 RADIATION PROTECTION Page 3 of 4 TABLE OF CONTENTS 11.6.7 RADIATION PROTECTION INSTRUMENTATION .................... 11.6-18 11.6.7.1 Counting Room Instrumentation ....................... 11.6-18 11.6.7.2 Portable Radiation Detecting Instrumentation . 11.6-18 11.6.7.3 Air Sampling Instrumentation ............................ 11.6-18 11.6.7.4 Personal Monitoring Instrumentation................ 11.6-19 11.6.7.5 Emergency Instrumentation ............................... 11.6-19 11.6.8 TESTS AND INSPECTIONS ...................................................... 11.6-19 11.6.8.1 Shielding .............................................................. 11.6-19 11.6.8.2 Area and Process Radiation Monitors .............. 11.6-20 11.6.8.3 Continuous Air Monitors .................................... 11.6-20 11.6.8.4 Radiation Protection Instrumentation ............... 11.6-20 11.6.9 CONTROL OF BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL (SNM) SOURCES ........................................ 11.6-21 11.6.10 RADIOACTIVE MATERIAL STORAGE FACILITIES .......... 11.6-22 REFERENCES ........................................................................................................... 11-1 LIST OF TABLES 11-1 Primary Coolant Fission and Corrosion Product Activities 11-2 Radioactive Waste Quantities of Significant Activity 11-3 Equipment Ratings and Construction Codes - Original Equipment 11-4 Equipment Ratings and Construction Codes - Additional Equipment Installed 1971-1973 11-5 Primary System Drain Tank 11-6 Equipment Drain Tank 11-7 Dirty Waste Drain Tank 11-8 Liquid Radwaste 11-9 Maximum Calculated Tritium Release Due to Evaporation From Refueling Cavity and Spent Fuel Pool 11-10 LADTAP Input Data and Results Maximum Individual Dose Calculations 11-11 Activity in Coolant and Gaseous Waste 11-12 Special Location GASPAR Input Data 11-13 Dose Results for Special Locations, Maximum Individual Doses by Age Group and Organ 11-14 Deleted 11-15 Process Radiation Service and Equipment 11-16 Area Radiation Detectors 11-17 Primary Coolant Fission and Corrosion Product Activities for AST Dose Analyses

FSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT AND Revision 28 RADIATION PROTECTION Page 4 of 4 TABLE OF CONTENTS LIST OF FIGURES 11-1 Sh 1 P&ID Radioactive Waste Treatment System Clean 11-1 Sh 1A P&ID Radioactive Waste Treatment System Clean 11-1 Sh 1B P&ID Radioactive Waste Treatment System Clean 11-1 Sh 1C P&ID Radioactive Waste Treatment System Clean 11-1 Sh 2 P&ID Radioactive Waste Treatment System Clean 11-1 Sh 3 P&ID Radwaste Evaporator System Clean Wastes 11-2 Sh 1 P&ID Dirty Waste & Gaseous Waste 11-2 Sh 2 P&ID Radwaste Evaporator System Miscellaneous Waste 11-2 Sh 2A P&ID Radwaste Evaporator System Miscellaneous Waste 11-2 Sh 2B P&ID Radwaste Evaporator System Miscellaneous Waste 11-3 Sh 1 P&ID Radioactive Waste Treatment System Gaseous Waste 11-3 Sh 2 P&ID Radioactive Waste Treatment System Gaseous Waste 11-4 Sh 1 Spent Resin Storage and Radwaste Packaging System 11-4 Sh 2 P&ID Radwaste Solidification System 11-4 Sh 3 P&ID Liquid Volume Reduction System 11-5 Sh 1 P&ID Radiation Monitoring and Sampling Systems 11-5 Sh 1A P&ID Radiation Monitoring and Sampling Systems 11-5 Sh 1B P&ID Radiation Monitoring and Sampling Systems 11-5 Sh 2 P&ID Radiation Monitoring and Sampling Systems 11-6 Gaseous Effluent Monitoring System 11-7 Architectural Access Control and Radiation Zoning (Plant in Operation) 11-8 Architectural Access Control and Radiation Zoning (Plant in Operation) 11-9 Architectural Access Control and Radiation Zoning (Plant in Operation)

FSAR CHAPTER 12 - CONDUCT OF OPERATIONS Revision 30 TABLE OF CONTENTS Page 1 of 1 SECTIONS 12.1 ORGANIZATION AND RESPONSIBILITY ............................................. 12.1-1 12.1.1 MANAGEMENT AND TECHICAL SUPPORT ORGANIZATIONS .................................................................. 12.1-1 12.2 TRAINING .................................................................................... 12.2-1 12.2.1 PLANT STAFF TRAINING PROGRAM .................................. 12.2-1 12.2.1.1 Plant Access Training............................................... 12.2-1 12.2.1.2 Radiation Worker Training (RWT) ............................ 12.2-1 12.2.1.3 Licensed and Nonlicensed Operator Training Program .................................................. 12.2-2 12.2.1.4 Instrumentation and Controls (I&C) Technician Training Programs ................................................ 12.2-2 12.2.1.5 Mechanical and Electrical Maintenance Personnel Training Program .................................................. 12.2-3 12.2.1.6 Radiological Protection Technician Training Program .................................................. 12.2-3 12.2.1.7 Chemistry Technician Training Program ................ 12.2-3 12.2.1.8 Engineering Support Personnel Training Program .................................................. 12.2-3 12.2.1.9 Fire Protection Training............................................ 12.2-4 12.2.2 TRAINING EFFECTIVENESS EVALUATION ........................ 12.2-4 12.3 PLANT PROCEDURES .......................................................................... 12.3-1 12.3.1 PROCEDURE CONTROL REQUIREMENTS ......................... 12.3-1 12.3.2 UPGRADE AND MAINTENANCE OF EMERGENCY OPERATING PROCEDURES ........................................... 12.3-2 12.3.3 OPERATING REQUIREMENTS MANUAL (ORM) ................. 12.3-2 12.4 REVIEW AND ASSESMENT .................................................................. 12.4-1 12.5 EMERGENCY PLANNING ..................................................................... 12.5-1 12.6 INDUSTRIAL SECURITY ....................................................................... 12.6-1 REFERENCES .......................................................................................................... None TABLES .................................................................................................................... None LIST OF FIGURES 12-1 Entergy Nuclear Site Leadership 12-2 Plant Specific Titles for Generic Titles Located in the Technical Specifications 12-3 Deleted

FSAR CHAPTER 13 - INITIAL TESTS AND OPERATIONS Revision 30 TABLE OF CONTENTS Page 1 of 1 SECTIONS 13.1 TESTS PRIOR TO REACTOR FUELING ............................................... 13.1-1 13.2 REACTOR FUELING AND PHYSICS TESTS ........................................ 13.2-1 13.2.1 CORE LOADING ......................................................................... 13.2-1 13.2.2 POST-LOADING TESTS ............................................................. 13.2-2 13.2.3 INITIAL CRITICALITY.................................................................. 13.2-2 13.3 POST CRITICALITY AND POWER ESCALATION13.3-1 13.3.1 ZERO POWER TESTING13.3-1 13.3.2 POWER ESCALATION13.3-1 13.3.3 ESCALATION TO 2,650 MWt....13.3-2 13.4 OPERATION RESTRICTIONS.....13.4-1 13.4.1 SAFETY PRECAUTIONS....13.4-1 13.4.2

SUMMARY

.13.4-1 REFERENCES..None TABLES.None FIGURESNone

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 1 of 15 SECTIONS

14.1 INTRODUCTION

..................................................................................... 14.1-1 14.

1.1 BACKGROUND

...................................................................... 14.1-1 14.1.2 ANALYSES AT NOMINAL POWER LEVEL OF 2,650 MWt .. 14.1-5 14.1.3 ANALYSES PERFORMED AT 2,580.6 MWt INCLUDING UNCERTAINTY ...................................................................... 14.1-5 14.2 UNCONTROLLED CONTROL ROD WITHDRAWAL ............................ 14.2-1 14.2.1 UNCONTROLLED CONTROL ROD BANK WITHDRAWAL FROM A SUBCRITICAL OR LOW POWER START-UP CONDITION ................................. 14.2-1 14.2.1.1 Event Description.................................................. 14.2-1 14.2.1.2 Thermal-Hydraulic Analysis ................................. 14.2-2 14.2.1.2.1 Analysis Method ......................................... 14.2-2 14.2.1.2.2 Bounding Event Input ................................ 14.2-2 14.2.1.2.3 Analysis of Results .................................... 14.2-3 14.2.1.3 Radiological Consequences ................................ 14.2-3 14.2.1.4 Conclusions .......................................................... 14.2-3 14.2.2 UNCONTROLLED CONTROL ROD BANK WITHDRAWAL AT POWER ................................................... 14.2-4 14.2.2.1 Event Description.................................................. 14.2-4 14.2.2.2 Thermal-Hydraulic Analysis ................................. 14.2-4 14.2.2.2.1 Analysis Method ......................................... 14.2-4 14.2.2.2.2 Bounding Event Input ................................ 14.2-5 14.2.2.2.3 Analysis of Results .................................... 14.2-5 14.2.2.3 Radiological Consequences ................................ 14.2-6 14.2.2.4 Conclusions .......................................................... 14.2-6 14.2.3 SINGLE CONTROL ROD WITHDRAWAL ............................. 14.2-6 14.2.3.1 Event Description.................................................. 14.2-6 14.2.3.2 Thermal-Hydraulics Analysis ............................... 14.2-7 14.2.3.2.1 Analysis Method ......................................... 14.2-7 14.2.3.2.2 Bounding Event Input ................................ 14.2-7 14.2.3.2.3 Analysis of Results .................................... 14.2-8 14.2.3.3 Radiological Consequences ................................ 14.2-8 14.2.3.4 Conclusions .......................................................... 14.2-8

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 2 of 15 14.3 BORON DILUTION ................................................................................. 14.3-1 14.3.1 EVENT DESCRIPTION ........................................................... 14.3-1 14.3.2 THERMAL-HYDRAULIC ANALYSIS ...................................... 14.3-2 14.3.2.1 Analysis Method .................................................... 14.3-2 14.3.2.2 Bounding Event Input ........................................... 14.3-3 14.3.2.3 Analysis of Results ............................................... 14.3-3 14.3.2.3.1 Dilution During Refueling (Mode 6) .......... 14.3-3 14.3.2.3.2 Dilution During Cold Shutdown (Mode 5) 14.3-4 14.3.2.3.3 Dilution During Hot Shutdown (Mode 4) .. 14.3-6 14.3.2.3.4 Dilution During Hot Standby (Mode 3)...... 14.3-7 14.3.2.3.5 Dilution During Power Operation and Startup (Modes 1 and 2)............................. 14.3-8 14.3.2.3.6 Failure to Add Boron to Compensate for Reactivity Changes After Shutdown ......... 14.3-8 14.3.3 RADIOLOGICAL CONSEQUENCES ..................................... 14.3-9 14.

3.4 CONCLUSION

S ...................................................................... 14.3-9 14.4 CONTROL ROD DROP .......................................................................... 14.4-1 14.4.1 DROPPED ROD EVENT......................................................... 14.4-1 14.4.1.1 Event Description.................................................. 14.4-1 14.4.1.2 Thermal-Hydraulic Analysis ................................. 14.4-2 14.4.1.2.1 Analysis Methods ....................................... 14.4-2 14.4.1.2.2 Bounding Event Input ................................ 14.4-2 14.4.1.2.3 Analysis of Results .................................... 14.4-2 14.4.1.3 Radiological Consequences ................................ 14.4-3 14.4.1.4 Conclusions .......................................................... 14.4-3 14.4.2 DROPPED BANK EVENT ...................................................... 14.4-3 14.4.2.1 Event Description.................................................. 14.4-3 14.4.2.2 Thermal-Hydraulic Analysis ................................. 14.4-3 14.4.2.2.1 Analysis Methods ....................................... 14.4-3 14.4.2.2.2 Bounding Event Input ................................ 14.4-4 14.4.2.2.3 Analysis of Results .................................... 14.4-4 14.4.2.3 Radiological Consequences ................................ 14.4-4 14.4.2.4 Conclusions .......................................................... 14.4-5 14.5 CORE BARREL FAILURE...................................................................... 14.5-1 14.5.1 EVENT DESCRIPTION ........................................................... 14.5-1 14.5.2 THERMAL-HYDRAULIC ANALYSIS ...................................... 14.5-1 14.5.3 RADIOLOGICAL CONSEQUENCES ..................................... 14.5-1 14.

5.4 CONCLUSION

S ...................................................................... 14.5-1

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 3 of 15 14.6 CONTROL ROD MISOPERATION ......................................................... 14.6-1 14.6.1 MALPOSITION OF THE PART-LENGTH CONTROL ROD GROUP .......................................................................... 14.6-1 14.6.1.1 Event Description.................................................. 14.6-1 14.6.1.2 Thermal-Hydraulic Analysis ................................. 14.6-1 14.6.1.3 Radiological Consequences ................................ 14.6-1 14.6.1.4 Conclusions .......................................................... 14.6-1 14.6.2 STATICALLY MISALIGNED CONTROL ROD/BANK ............ 14.6-1 14.6.2.1 Event Description.................................................. 14.6-1 14.6.2.2 Thermal-Hydraulics Analysis ............................... 14.6-2 14.6.2.2.1 Analysis Method ......................................... 14.6-2 14.6.2.2.2 Bounding Event Input ................................ 14.6-2 14.6.2.2.3 Analysis of Results .................................... 14.6-3 14.6.2.3 Radiological Consequences ................................ 14.6-3 14.6.2.4 Conclusion ............................................................ 14.6-3 14.7 DECREASED REACTOR COOLANT FLOW ......................................... 14.7-1 14.7.1 LOSS OF FORCED REACTOR COOLANT FLOW ............... 14.7-1 14.7.1.1 Event Description.................................................. 14.7-1 14.7.1.2 Thermal-Hydraulic Analysis ................................. 14.7-2 14.7.1.2.1 Analysis Method ......................................... 14.7-2 14.7.1.2.2 Bounding Event Input ................................ 14.7-2 14.7.1.2.3 Analysis of Results .................................... 14.7-2 14.7.1.3 Radiological Consequences ................................ 14.7-3 14.7.1.4 Conclusions .......................................................... 14.7-3 14.7.2 REACTOR COOLANT PUMP ROTOR SEIZURE .................. 14.7-3 14.7.2.1 Event Description.................................................. 14.7-3 14.7.2.2 Thermal-Hydraulic Analysis ................................. 14.7-4 14.7.2.2.1 Analysis Method ......................................... 14.7-4 14.7.2.3 Bounding Event Input ........................................... 14.7-4 14.7.2.4 Analysis of Results ............................................... 14.7-4 14.7.2.5 Radiological Consequences ................................ 14.7-4 14.7.2.6 Conclusions .......................................................... 14.7-5 14.8 START-UP OF AN INACTIVE LOOP ..................................................... 14.8-1 14.8.1 EVENT DESCRIPTION ........................................................... 14.8-1 14.9 EXCESSIVE FEEDWATER INCIDENT ................................................... 14.9-1 14.10 INCREASE IN STEAM FLOW (EXCESS LOAD) ................................. 14.10-1 14.10.1 EVENT DESCRIPTION ......................................................... 14.10-1 14.10.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.10-2 14.10.2.1 Analysis Method .................................................. 14.10-2 14.10.2.2 Bounding Event Input ......................................... 14.10-2 14.10.2.3 Analysis of Results ............................................. 14.10-3 14.10.3 RADIOLOGICAL CONSEQUENCES ................................... 14.10-3 14.

10.4 CONCLUSION

S .................................................................... 14.10-4

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 4 of 15 14.11 POSTULATED CASK DROP ACCIDENTS .......................................... 14.11-1 14.11.1 EVENT DESCRIPTION ......................................................... 14.11-1 14.11.2 STRUCTURAL ANALYSIS ................................................... 14.11-2 14.11.2.1 Analysis Method .................................................. 14.11-3 14.11.2.1.1 Analysis of Cask Drop Scenarios ........... 14.11-3 14.11.2.1.2 Cask Overturn Due to Seismic Event .............................................. 14.11-3 14.11.2.2 Bounding Event Input ......................................... 14.11-4 14.11.2.2.1 Analysis of Cask Drop Scenarios .......... 14.11-4 14.11.2.2.2 Cask Overturn Due to Seismic Event ................................................... 14.11-4 14.11.2.3 Analysis Results ................................................. 14.11-5 14.11.2.3.1 Analysis of Cask Drop Scenarios ........... 14.11-5 14.11.2.3.2 Cask Overturn Due to Seismic Event ................................................... 14.11-6 14.11.3 RADIOLOGICAL CONSEQUENCES ................................... 14.11-6 14.11.3.1 Analysis Method .................................................. 14.11-6 14.11.3.1.1 Radiological Consequences of a Cask Drop in the Spent Fuel Pool. ... 14.11-6 14.11.3.1.2 Impact on MTC/MSB Due to Postulated Drop on the VCC in the Track Alley. ........................................ 14.11-7 14.11.3.2 Bounding Event Input ......................................... 14.11-8 14.11.3.2.1 Radiological Consequences of a Cask Drop in the Spent Fuel Pool. ... 14.11-8 14.11.3.3 Analysis Results ................................................. 14.11-8 14.11.3.3.1 Radiological Consequences of a Cask Drop in the Spent Fuel Pool. ... 14.11-8 14.11.3.3.2 Drop of the Loaded MTC on to the VCC in the Track Alley ...................... 14.11-8 14.

11.4 CONCLUSION

S .................................................................... 14.11-8 14.12 LOSS OF EXTERNAL LOAD ............................................................... 14.12-1 14.12.1 EVENT DESCRIPTION ......................................................... 14.12-1 14.12.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.12-1 14.12.2.1 Analysis Method .................................................. 14.12-1 14.12.2.2 Bounding Event Input ......................................... 14.12-2 14.12.2.3 Analysis of Results ............................................. 14.12-3 14.12.3 RADIOLOGICAL CONSEQUENCES ................................... 14.12-3 14.

12.4 CONCLUSION

S .................................................................... 14.12-4

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 5 of 15 14.13 LOSS OF NORMAL FEEDWATER ...................................................... 14.13-1 14.13.1 EVENT DESCRIPTION ......................................................... 14.13-1 14.13.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.13-3 14.13.2.1 Analysis Method .................................................. 14.13-3 14.13.2.2 Bounding Event Input ......................................... 14.13-3 14.13.2.3 Analysis of Results ............................................. 14.13-5 14.13.3 RADIOLOGICAL CONSEQUENCES ................................. 14.13-10 14.

13.4 CONCLUSION

S .................................................................. 14.13-10 14.14 STEAM LINE RUPTURE INCIDENT .................................................... 14.14-1 14.14.1 EVENT DESCRIPTION ......................................................... 14.14-1 14.14.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.14-2 14.14.2.1 Analysis Method .................................................. 14.14-2 14.14.2.2 Bounding Event Input ......................................... 14.14-3 14.14.2.3 Analysis of Results ............................................. 14.14-4 14.14.3 RADIOLOGICAL CONSEQUENCES ................................... 14.14-7 14.14.3.1 Analysis Method .................................................. 14.14-7 14.14.3.2 Bounding Event Input ......................................... 14.14-7 14.14.3.3 Analysis of Results ............................................. 14.14-8 14.

14.4 CONCLUSION

S .................................................................... 14.14-9 14.15 STEAM GENERATOR TUBE RUPTURE WITH A LOSS OF OFFSITE POWER .......................................................................... 14.15-1 14.15.1 EVENT DESCRIPTION ......................................................... 14.15-1 14.15.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.15-2 14.15.2.1 Analysis Method .................................................. 14.15-2 14.15.2.2 Bounding Event Input ......................................... 14.15-2 14.15.2.3 Analysis of Results ............................................. 14.15-4 14.15.3 RADIOLOGICAL ANALYSIS ................................................ 14.15-6 14.15.3.1 Analysis Method .................................................. 14.15-6 14.15.3.2 Bounding Event Input ......................................... 14.15-7 14.15.3.3 Analysis of Results ............................................. 14.15-8 14.

15.4 CONCLUSION

S .................................................................... 14.15-9

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 6 of 15 14.16 CONTROL ROD EJECTION ................................................................ 14.16-1 14.16.1 EVENT DESCRIPTION ......................................................... 14.16-1 14.16.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.16-1 14.16.2.1 Analysis Method .................................................. 14.16-1 14.16.2.2 Bounding Event Input ......................................... 14.16-2 14.16.2.3 Analysis of Results ............................................. 14.16-2 14.16.3 RADIOLOGICAL CONSEQUENCES ................................... 14.16-3 14.16.3.1 Induced LOCA ..................................................... 14.16-3 14.16.3.1.1 Analysis Method ....................................... 14.16-3 14.16.3.1.2 Bounding Event Input .............................. 14.16-4 14.16.3.1.3 Analysis of Results .................................. 14.16-4 14.16.3.2 Steam Generator Release................................... 14.16-4 14.16.3.2.1 Analysis Method ....................................... 14.16-4 14.16.3.2.2 Bounding Event Input .............................. 14.16-5 14.16.3.2.3 Analysis of Results .................................. 14.16-5 14.

16.4 CONCLUSION

...................................................................... 14.16-5 14.17 LOSS OF COOLANT ACCIDENT ........................................................ 14.17-1 14.17.1 LARGE BREAK LOCA (LBLOCA)....................................... 14.17-1 14.17.1.1 Event Description................................................ 14.17-1 14.17.1.2 Thermal Hydraulics Analysis ............................. 14.17-3 14.17.1.2.1 Analysis Method ....................................... 14.17-3 14.17.1.2.2 Bounding Event Input .............................. 14.17-5 14.17.1.2.3 Analysis of Results .................................. 14.17-6 14.17.1.3 Radiological Consequences .............................. 14.17-7 14.17.1.4 Conclusions ........................................................ 14.17-7 14.17.2 SMALL BREAK LOCA ......................................................... 14.17-8 14.17.2.1 Event Description................................................ 14.17-8 14.17.2.2 Thermal-Hydraulic Analysis ............................... 14.17-8 14.17.2.2.1 Analysis Models ....................................... 14.17-8 14.17.2.2.2 Plant Description and Summary of Analysis Parameters ......................... 14.17-9 14.17.2.2.3 Analytical Results .................................. 14.17-10 14.17.2.3 Radiological Consequences ............................ 14.17-12 14.17.2.4 Conclusion ........................................................ 14.17-12 14.17.3 REACTOR INTERNALS STRUCTURAL BEHAVIOR FOLLOWING A LOCA ....................................................... 14.17-13 14.17.3.1 Event Description.............................................. 14.17-13 14.17.3.2 Thermal-Hydraulic Analysis ............................. 14.17-14 14.17.3.2.1 Analysis Method ..................................... 14.17-14 14.17.3.2.2 Bounding Event Input ............................ 14.17-14 14.17.3.2.3 Analysis of Results ................................ 14.17-14 14.17.3.3 Radiological Consequences ............................ 14.17-14 14.17.3.4 Conclusions ...................................................... 14.17-14

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 7 of 15 14.18 CONTAINMENT PRESSURE AND TEMPERATURE ANALYSIS........ 14.18-1 14.18.1 LOCA ANALYSIS ................................................................. 14.18-1 14.18.1.1 Event Description................................................ 14.18-1 14.18.1.2 Description of GOTHIC ....................................... 14.18-1 14.18.1.3 Thermal-Hydraulic Analysis ............................... 14.18-3 14.18.1.3.1 Analysis Method ....................................... 14.18-3 14.18.1.3.2 Bounding Event Input .............................. 14.18-6 14.18.1.3.3 Analysis of Results .................................. 14.18-7 14.18.1.4 Radiological Consequences .............................. 14.18-7 14.18.1.5 Conclusion .......................................................... 14.18-8 14.18.2 MSLB INSIDE CONTAINMENT ............................................ 14.18-8 14.18.2.1 Event Description................................................ 14.18-8 14.18.2.2 Thermal-Hydraulic Analysis ............................... 14.18-9 14.18.2.2.1 Analysis Method ....................................... 14.18-9 14.18.2.2.2 Bounding Event Input ............................ 14.18-12 14.18.2.2.3 Analysis of Results ................................ 14.18-13 14.18.2.3 Radiological Consequences ............................ 14.18-14 14.18.2.4 Conclusion ........................................................ 14.18-14 14.18.3 CONTAINMENT INTERNAL STRUCTURE EVALUATION 14.18-14 14.18.3.1 Event Description.............................................. 14.18-14 14.18.3.2 Thermal Hydraulic Analysis ............................. 14.18-14 14.18.3.2.1 Analysis Method ..................................... 14.18-14 14.18.3.2.2 Bounding Event Input ............................ 14.18-15 14.18.3.2.3 Analysis of Results ................................ 14.18-17 14.18.3.3 Radiological Consequences ............................ 14.18-18 14.18.3.4 Conclusion ........................................................ 14.18-18 14.19 FUEL HANDLING INCIDENT ............................................................... 14.19-1 14.19.1 EVENT DESCRIPTION ......................................................... 14.19-1 14.19.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.19-3 14.19.3 RADIOLOGICAL CONSEQUENCES ................................... 14.19-3 14.19.3.1 Analysis Method .................................................. 14.19-3 14.19.3.2 Bounding Event Input ......................................... 14.19-4 14.19.3.3 Analysis of Results ............................................. 14.19-4 14.

19.4 CONCLUSION

S .................................................................... 14.19-5 14.20 LIQUID WASTE INCIDENT .................................................................. 14.20-1 14.20.1 EVENT DESCRIPTION ......................................................... 14.20-1 14.20.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.20-1 14.20.3 RADIOLOGICAL CONSEQUENCES ................................... 14.20-1 14.20.3.1 Analysis Method .................................................. 14.20-1 14.20.3.2 Bounding Event Input ......................................... 14.20-2 14.20.3.3 Analysis of Results ............................................. 14.20-2 14.

20.4 CONCLUSION

S .................................................................... 14.20-3

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 8 of 15 14.21 WASTE GAS INCIDENT ....................................................................... 14.21-1 14.21.1 GAS DECAY TANK RUPTURE ............................................ 14.21-1 14.21.1.1 Event Description................................................ 14.21-1 14.21.1.2 Thermal-Hydraulic Analysis ............................... 14.21-1 14.21.1.3 Radiological Consequences .............................. 14.21-1 14.21.1.3.1 Analysis Method ....................................... 14.21-1 14.21.1.3.2 Bounding Event Input .............................. 14.21-2 14.21.1.3.3 Analysis of Results .................................. 14.21-2 14.21.2 VOLUME CONTROL TANK RUPTURE ............................... 14.21-2 14.21.2.1 Event Description................................................ 14.21-2 14.21.2.2 Thermal-Hydraulic Analysis ............................... 14.21-3 14.21.2.3 Radiological Consequences .............................. 14.21-3 14.21.2.3.1 Analysis Method ....................................... 14.21-3 14.21.2.3.2 Bounding Event Input .............................. 14.21-4 14.21.2.3.3 Analysis of Results .................................. 14.21-4 14.

21.3 CONCLUSION

S .................................................................... 14.21-4 14.22 MAXIMUM HYPOTHETICAL ACCIDENT ............................................. 14.22-1 14.22.1 EVENT DESCRIPTION ......................................................... 14.22-1 14.22.2 RADIOLOGICAL CONSEQUENCES ................................... 14.22-1 14.22.2.1 Analysis Method .................................................. 14.22-1 14.22.2.2 Bounding Event Input ......................................... 14.22-2 14.22.2.3 Analysis of Results ............................................. 14.22-2 14.

22.3 CONCLUSION

...................................................................... 14.22-2 14.23 RADIOLOGICAL CONSEQUENCES OF FAILURE OF SMALL LINES CARRYING PRIMARY COOLANT OUTSIDE CONTAINMENT ........... 14.23-1 14.23.1 EVENT DESCRIPTION ......................................................... 14.23-1 14.23.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.23-1 14.23.3 RADIOLOGICAL CONSEQUENCES ................................... 14.23-1 14.23.3.1 Analysis Method .................................................. 14.23-1 14.23.3.2 Bounding Event Input ......................................... 14.23-1 14.23.3.3 Analysis of Results ............................................. 14.23-2 14.

23.4 CONCLUSION

S .................................................................... 14.23-2 14.24 CONTROL ROOM RADIOLOGICAL HABITABILITY .......................... 14.24-1 14.24.1 EVENT DESCRIPTION ......................................................... 14.24-1 14.24.2 THERMAL-HYDRAULIC ANALYSIS .................................... 14.24-1 14.24.3 RADIOLOGICAL CONSEQUENCES ................................... 14.24-1 14.24.3.1 Analysis Method .................................................. 14.24-1 14.24.3.2 Bounding Event Input ......................................... 14.24-3 14.24.3.3 Analysis of Results ............................................. 14.24-3 14.

24.4 CONCLUSION

...................................................................... 14.24-3

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 9 of 15 LIST OF TABLES 14.1-1 Specified Acceptable Fuel Design Limits 14.1-3 Trip Setpoints for Analysis of Palisades Reactor at 2,530 MWt 14.1-4 Disposition of Events Summary for Palisades Cycle 21 14.1-5 Cycle 21 Summary of Results for Standard Review Plan Chapter 15 Events 14.1-6 Summary of Radiological Consequences of the Chapter 14 Events 14.2.1-1 Event Summary For The Uncontrolled Bank Withdrawal From A Low Power Event 14.2.2-1 Event Summary For The Uncontrolled Rod Bank Withdrawal Event From Power 14.7.1-1 Event Summary For The Loss of Forced Reactor Coolant Flow 14.7.2-1 Event Summary For The Reactor Coolant Pump Rotor Seizure 14.10-1 Sequence of Events for Excess Load Limiting MDNBR Case 14.11-1 Postulated Cask Drop Accidents 14.11-2 Spent Fuel Cask Drop Radiological Analysis - Source Terms 14.11-3 Spent Fuel Cask Drop Radiological Analysis - Inputs and Assumptions 14.12-1 Event Summary For Loss of Load 14.13-1 Initial Conditions for the Loss of Normal Feedwater Analysis 14.13-2 Sequence of Events for Loss of Normal Feedwater Flow Analysis with Offsite Power Available and Steam Dump System Disabled 14.13-3 Sequence of Events for Loss of Normal Feedwater Flow Analysis with Offsite Power Available and Steam Dump System Available 14.13-4 Sequence of Events for Loss of Normal Feedwater Flow Analysis without Offsite Power Available and Steam Dump System Disabled 14.13-5 Results Summary for Loss of Normal Feedwater 14.14-1 Main Steam Line Break Input Parameters and Assumptions 14.14-2 Steam Line Break Sequence of Events During LHR-Limiting Transient (HZP, Offsite Power Available) 14.14-3 Overall Core Conditions at Time of Peak LHR 14.14-4 Steam Line Break Sequence of Events During DNBR-Limiting Transient (HZP, Loss of Offsite Power) 14.14-5 Overall Core Conditions at Time of MDNBR 14.14-6 Main Steam Line Break (MSLB) Radiological Analysis - Inputs and Assumptions 14.14-7 Main Steam Line Break (MSLB) Radiological Analysis - Intact SG Steam Release Rate 14.15-1 Initial Conditions For The Steam Generator Tube Rupture With A Loss Of Offsite Power 14.15-2 Setpoints For The Steam Generator Tube Rupture With A Loss Of Offsite Power 14.15-3 Sequence Of Events For The Steam Generator Tube Rupture With A Loss Of Offsite Power 14.15-4 Integrated Parameters For The Steam Generator Tube Rupture With A Loss Of Offsite Power

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 10 of 15 14.15-5 Steam Generator Tube Rupture (SGTR) Radiological Analysis - Inputs and Assumptions 14.15-6 SGTR Radiological Analysis - Integrated Mass Releases 14.15-7 SGTR Radiological Analysis - Flashing Fraction for Flow From Broken Tube 14.18-8 SGTR Radiological Analysis - 40 µCi/gm D.E. I-131 Activities 14.15.9 SGTR Radiological Analysis - Iodine Equilibrium Appearance Assumptions 14.15-10 SGTR Radiological Analysis - Concurrent (335 x) Iodine Spike Appearance Rate 14.15-11 SGTR Radiological Analysis - Affected Steam Generator Water Level and Decontamination Factors for Flashed Flow 14.16-1 Event Summary For The EOC HZP Control Rod Ejection 14.16-2 Control Rod Ejection Radiological Analysis - Inputs and Assumptions 14.16-3 Control Rod Ejection Radiological Analysis - Steam Release 14.17.1-1 Sampled LBLOCA Parameters 14.17.1-2 Plant Operating Range Supported by the LOCA Analysis 14.17.1-3 Statistical Distributions Used for Process Parameters 14.17.1-4 Summary of Major Parameters for the Limiting PCT Case 14.17.1-5 Summary of Hot Rod Limiting PCT Results 14.17.1-6 Calculated Event Times for the Limiting PCT Case 14.17.1-7 Containment Heat Sink Data 14.17.1-8 Containment Initial and Boundary Conditions 14.17.2-1 System Parameters and Initial Conditions Used in the Palisades SBLOCA Analysis 14.17.2-2 PCT Results of the Palisades SBLOCA Analysis 14.17.2-3 Sequence of Events for the Palisades SBLOCA Event 14.17.2-4 SBLOCA Analysis Calculation Results 14.17.3-1 Maximum Stresses, Pressures and Deflections in Critical Reactor Internals Following a Major Loss of Coolant Accident 14.17.3-2 Asymmetric Loads Analysis - Reactor Vessel Internal Component Stress Margins 14.18.1-1 LOCA Analysis Containment Building Heat Sinks/Sources 14.18.1-2 LOCA Analysis Engineered Safeguards Equipment Alignment 14.18.1-3 LOCA Initial Conditions 14.18.1-4 Containment Building Response to LOCA Double Ended Guillotine Break in a Hot Leg 14.18.1-5 LOCA Analysis Parameter Assumptions 14.18.2-1 Initial Conditions For The MSLB Containment Analysis 14.18.2-2 Initial Conditions For The MSLB Containment Analysis 14.18.2-3 MSLB Containment Analysis Results 14.18.2-4 MSLB Analysis Containment Building Heat Sinks/Sources 14.18.3-1 Reactor Cavity Geometric Factors 14.18.3-2 Geometry and Peak Pressures in Steam Generator Compartments 14.18.3-3 Differential Pressures at Various Locations 14.19-1 Fuel Handling Accident (FHA) Radiological Analysis - Inputs and Assumptions

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 11 of 15 14.19-2 Fuel Handling Accident Radiological Analysis - Source Term 14.22-1 MHA Sequence of Events for the Dose Consequence Analysis 14.22-2 Maximum Hypothetical Accident / Loss of Coolant Accident (MHA/LOCA)

Radiological Analysis - Inputs and Assumptions 14.22-3 MHA/LOCA Source Term 14.22-4 MHA/LOCA Release Phases 14.22-5 MHA/LOCA Time Dependent SIRWT pH 14.22-6 MHA/LOCA Time Dependent SIRWT Total Iodine Concentration 14.22-7 MHA/LOCA Time Dependent SIRWT Liquid Temperature 14.22-8 MHA/LOCA Time Dependent SIRWT Elemental Iodine Fraction 14.22-9 MHA/LOCA Time Dependent SIRWT Partition Coefficient 14.22-10 MHA/LOCA Adjusted Release Rate from SIRWT 14.23-1 Small Line Break Outside of Containment Radiological Analysis - Inputs and Assumptions 14.23-2 Small Line Break Outside of Containment Radiological Analysis -

Concurrent (500 x) Iodine Spike Appearance Rate 14.24-1 Time Dependent Control Room Parameters 14.24-2 Control Room Atmospheric Dispersion (X/Q) Factors for AST Analysis Events 14.24-3 Release-Receptor Point Pairs Assumed for AST Analysis Events LIST OF FIGURES 14.1-3 Palisades Scram Curve 14.2.1-1 Control Rod Withdrawal Incident HZP Reactivity Insertion Curve 14.2.1-2 Control Rod Withdrawal Incident HZP Reactivity Feedbacks 14.2.1-3 Control Rod Withdrawal Incident HZP Total Reactivity 14.2.1-4 Control Rod Withdrawal Incident HZP Power and Heat Flux 14.2.1-5 Control Rod Withdrawal Incident HZP System Pressure 14.2.1-6 Control Rod Withdrawal Incident HZP Inlet Enthalpy 14.2.2-1 Reactivities For Uncontrolled bank Withdrawal At Full Power 14.2.2-2 Reactor Power Level For Uncontrolled Bank Withdrawal Full Power 14.2.2-3 Core Average Heat Flux For Uncontrolled Bank Withdrawal At Full Power 14.2.2-4 Pressurizer Pressure For Uncontrolled Bank Withdrawal At Full Power 14.2.2-5 Pressurizer Liquid Level For Uncontrolled Bank Withdrawal At Full Power 14.2.2-6 PCS Mass Flow Rate For Uncontrolled Bank Withdrawal At Full Power 14.2.2-7 PCS Temperatures For Uncontrolled Bank Withdrawal At Full Power 14.2.2-8 Secondary Pressure For Uncontrolled Bank Withdrawal At Full Power 14.2.2-9 S/G Liquid Level For Uncontrolled Bank Withdrawal At Full Power 14.7.1-1 Primary Coolant System Mass Flow Rate For Loss Of Forced Flow 14.7.1-2 Reactor Power Level For Loss Of Forced Flow 14.7.1-3 Core Average Heat Flux For Loss Of Forced Flow 14.7.1-4 Pressurizer Pressure For Loss Of Forced Flow 14.7.1-5 Primary Coolant System Temperatures For Loss Of Forced Flow 14.7.2-1 Primary Coolant System Mass Flow Rate For Reactor Coolant Pump Rotor Seizure 14.7.2-2 Reactor Power Level For Reactor Coolant Pump Rotor Seizure

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 12 of 15 14.7.2-3 Core Average Heat Flux For Reactor Coolant Pump Rotor Seizure 14.7.2-4 Pressurizer Pressure For Reactor Coolant Pump Rotor Seizure 14.7.2-5 Primary Coolant System Temperatures For Reactor Coolant Pump Rotor Seizure 14.10-1 Power Comparisons - Excess Load 14.10-2 Primary Coolant System Temperatures - Excess Load 14.10-3 Pressurizer Pressure - Excess Load 14.10-4 Pressurizer Collapsed Liquid Level - Excess Load 14.10-5 Components of Reactivity - Excess Load 14.11-1 Partial Operating Floor Plan EL 649'-0" 14.12-1 Reactor Power Level For Loss Of External Load Event 14.12-2 Primary Pressures For Loss Of External Load Event 14.12-3 Pressurizer Liquid Volume For Loss Of External Load Event 14.12-4 Primary Coolant System Temperatures For Loss Of External Load Event 14.12-5 Secondary Pressures For Loss Of External Load Event 14.13-1 Reactor Power, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-2 Primary Coolant System Loop Temperatures, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-3 Primary Coolant System Loop Flow, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-4 Pressurizer Pressure, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-5 Pressurizer Spray Flow, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-6 Pressurizer SRV Flow, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-7 Pressurizer Level, LNFF with Offsite Power Available and Steam Dump System Disabled 14.13-8 SG Auxiliary Feedwater Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 14.13-9 SG Dome Pressure, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 14.13-10 SG Liquid Mass Inventory, LNFF Analysis with Off-Site Power Available and Steam Dump System Disabled 14.13-11 Reactor Power, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-12 Primary Coolant System Loop Temperatures, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-13 Primary Coolant System Loop Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-14 Pressurizer Pressure, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-15 Pressurizer Spray Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-16 Pressurizer SRV Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 13 of 15 14.13-17 Pressurizer Level, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-18 SG Auxiliary Feedwater Flow, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-19 SG Dome Pressure, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-20 SG Liquid Mass Inventory, LNFF Analysis with Off-Site Power Available and Steam Dump System Available 14.13-21 Reactor Power, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-22 Primary Coolant System Loop Temperatures, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-23 Primary Coolant System Loop Flow, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-24 Pressurizer Pressure, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-25 Pressurizer Level, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-26 SG Auxiliary Feedwater Flow, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-27 SG Dome Pressure, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.13-28 SG Liquid Mass Inventory, LNFF Analysis without Off-Site Power Available and Steam Dump Systems Disabled 14.14-1 Break Flow Rates During LHR-Limiting Transient 14.14-2 Steam Generator Pressures During LHR-Limiting Transient 14.14-3 Steam Generator Heat Transfer Rates During LHR-Limiting Transient 14.14-4 Steam Generator Secondary-Side Total Fluid Inventories During LHR-Limiting Transient 14.14-5 Core Inlet Temperatures During LHR-Limiting Transient 14.14-6 Core Inlet Flow Rates During LHR-Limiting Transient 14.14-7 Pressurizer Pressure During LHR-Limiting Transient 14.14-8 Pressurizer Liquid Level During LHR-Limiting Transient 14.14-9 Total HPSI Flow Rate During LHR-Limiting Transient 14.14-10 Reactivity During LHR-Limiting Transient 14.14-11 Reactor Power During LHR-Limiting Transient 14.14-12 Break Flow Rates During DNBR-Limiting Transient 14.14-13 Steam Generator Pressures During DNBR-Limiting Transient 14.14-14 Steam Generator Heat Transfer Rates During DNBR-Limiting Transient 14.14-15 Steam Generator Secondary-Side Total Fluid Inventories During DNBR-Limiting Transient 14.14-16 Core Inlet Temperatures During DNBR-Limiting Transient 14.14-17 Core Inlet Flow Rates During DNBR-Limiting Transient 14.14-18 Pressurizer Pressure During DNBR-Limiting Transient 14.14-19 Pressurizer Liquid Level During DNBR-Limiting Transient 14.14-20 Total HPSI Flow Rate During DNBR-Limiting Transient 14.14-21 Reactivity During DNBR-Limiting Transient

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 14 of 15 14.14-22 Reactor Power During DNBR-Limiting Transient 14.15-1 SGTR With LOAC: Core Power vs Time 14.15-2 SGTR With LOAC: Core Coolant Temperatures vs Time 14.15-3 SGTR With LOAC: Primary Coolant System Pressure vs Time 14.15-4 SGTR With LOAC: Steam Generator Pressure vs Time 14.15-5 SGTR With LOAC: Tube Leak Flow Rate vs Time 14.15-6 SGTR With LOAC: Integrated Tube Leak Flow vs Time 14.15-7 SGTR With LOAC: Pressurizer Liquid Volume vs Time 14.15-8 SGTR With LOAC: Affected Steam Generator Safety Valve (MSSV) Flow Rate vs Time 14.15-9 SGTR With LOAC: Affected Steam Generator Safety Valve (MSSV)

Integrated Flow vs Time 14.15-10 SGTR With LOAC: Steam Generators Liquid Mass vs Time 14.15-11 SGTR With LOAC: Core Power vs Time 14.15-12 SGTR With LOAC: Core Coolant Temperatures vs Time 14.15-13 SGTR With LOAC: Primary Coolant System Pressure vs Time 14.15-14 SGTR With LOAC: Steam Generators Pressure vs Time 14.15-15 SGTR With LOAC: Pressurizer Liquid Volume vs Time 14.15-16 SGTR With LOAC: Tube Leak Flow Rate vs Time 14.15-17 SGTR Integrated Leak Flow vs Time 14.15-18 SGTR ADV Flow Rate vs Time 14.15-19 SGTR Integrated ADV Flow vs Time 14.15-20 SGTR PCS Subcooling vs Time 14.15-21 SGTR HPSI Flow Rate vs Time 14.16-1 Control Rod Ejection, EOC HZP Case: Core Power 14.16-2 Control Rod Ejection, EOC HZP Case: Core Average Heat-Flux-Based LHR 14.16-3 Control Rod Ejection, EOC HZP Case: Total Core Reactivity 14.17.1-1 Scatter Plot of Operational Parameters 14.17.1-2 PCT Versus PCT Time Scatter Plot From Transient Calculations 14.17.1-3 PCT Versus Break Size Scatter Plot From Transient Calculations 14.17.1-4 Total Oxidation Vs. PCT Scatter Plot from Transient Calculations 14.17.1-5 Maximum Oxidation Versus PCT Scatter Plot from Transient Calculations 14.17.1-6 Peak Cladding Temperature for the Limiting Case 14.17.1-7 Break Flow for the Limiting Case 14.17.1-8 Core Inlet Mass Flux for the Limiting Case 14.17.1-9 Core Outlet Mass Flux for the Limiting Case 14.17.1-10 Void Fraction at PCS Pumps for the Limiting Case 14.17.1-11 ECCS Flows (Includes SIT, HPSI, and LPSI) for the Limiting Case 14.17.1-12 Upper Plenum Pressure for the Limiting Case 14.17.1-13 Collapsed Liquid Level in the Downcomer for the Limiting Case 14.17.1-14 Collapsed Liquid Level in the Lower Plenum for the Limiting Case 14.17.1-15 Collapsed Liquid Level in the Core for the Limiting Case 14.17.1-16 Containment and Loop Pressures for the Limiting Case 14.17.1-17 Deleted 14.17.1-18 Deleted 14.17.1-19 Deleted

FSAR CHAPTER 14 - SAFETY ANALYSIS Revision 30 TABLE OF CONTENTS Page 15 of 15 14.17.1-20 Deleted 14.17.1-21 Deleted 14.17.2-1 Break Mass Flow Rate (Limiting Case) 14.17.2-2 Primary and Secondary Pressures (Limiting Case) 14.17.2-3 Normalized Reactor Power (Limiting Case) 14.17.2-4 Total HPSI Mass Flow Rate (Limiting Case) 14.17.2-5 Total SIT Mass Flow Rate (Limiting Case) 14.17.2-6 Loop Seal Void Fractions (Limiting Case) 14.17.2-7 Break Void Fraction (Limiting Case) 14.17.2-8 Reactor Vessel and PCS Mass Inventories (Limiting Case) 14.17.2-9 Hot Channel Collapsed Level (Limiting Case) 14.17.2-10 Fluid and Cladding Temperatures (Limiting Case) 14.17.2-11 SG Narrow Range Liquid Levels (Limiting Case) 14.17.2-12 AFW Flow Rates (Limiting Case) 14.17.2-13 Total MSSV Flow (Limiting Case) 14.18.1-1 LOCA Containment Pressure Profile 14.18.1-2 LOCA Containment Temperature Profile 14.18.2-1 MSLB Containment Response Maximum Pressure Profile 14.18.2-2 MSLB Containment Response Environmental Qualification Profile 14.22-1 Deleted 14.22-2 Deleted

FSAR CHAPTER 15 - QUALITY ASSURANCE PROGRAM Revision 29 TABLE OF CONTENTS Page 1 of 2 SECTIONS 15.1 QUALITY ASSURANCE DURING THE OPERATIONAL PHASE .......... 15.1-1 15.1.1 QUALITY ASSURANCE PROGRAM MANUAL..15.1-1 15.1.2 GENERIC QUALITY ASSURANCE REQUIREMENTS FOR AGING MANAGEMENT PROGRAMS......15.1-2 15.2 QUALITY ASSURANCE DURING ORIGINAL PLANT DESIGN AND CONSTRUCTION........................................................................... 15.2-1 15.2.1 BECHTEL CORPORATION ......................................................... 15.2-1 15.2.1.1 General................................................................... 15.2-1 15.2.1.2 Organization .......................................................... 15.2-1 15.2.2 COMBUSTION ENGINEERING, INC ........................................... 15.2-2 15.2.2.1 General................................................................... 15.2-2 15.2.2.2 Organization .......................................................... 15.2-3 15.2.2.3 Responsibilities .................................................... 15.2-4 15.2.3 CONSUMERS POWER COMPANY ............................................. 15.2-5 15.2.3.1 General................................................................... 15.2-5 15.2.3.2 Vendor Shops ........................................................ 15.2-5 15.2.3.3 Nuclear Fuel .......................................................... 15.2-7 15.2.3.4 Construction Activities ......................................... 15.2-8 REFERENCES ......................................................................................................... None TABLES ................................................................................................................... None

FSAR CHAPTER 15 - QUALITY ASSURANCE PROGRAM Revision 29 TABLE OF CONTENTS Page 2 of 2 LIST OF FIGURES 15-1 Quality Assurance Organization 15-2 Combustion Engineering Incorporated Quality Assurance Organization