ML23193A882
Text
MILLSTONE POWER STATION UNIT 2 FINAL SAFETY ANALYSIS REPORT Revision 4106/29/23
Revision 4106/29/23 MPS-2 FSAR LOA 1 of 3
LIST OF ABBREVIATIONS
Abbreviation
ADH Aerated Drain Header
AEAS Auxiliary Exhaust Actuation Signal
AES Auxiliary Exhaust System
ATWS Anticipated Transient Without Scram
BOL Beginning of Life
BWR Boiling Water Reactor
CEA Control Element Assembly
CEDM Control Element Drive Mechanism
CEDS Control Element Drive System
CFR Code of Federal Regulations
CIAS Containment Isolation Actuation Signal
CRFS Control Room Filtration System
CSAS Containment Spray Actuation Signal
CSS Containment Spray System
CVCS Chemical and Volume Control System
CVH Containment Vent Header
DBA Design Basis Accident
DNB Departure from Nucleate Boiling
DNBR Departure from Nucleate Boiling Ratio
DRL Division of Reactor Licensing
EB Enclosure Building
EBFR Enclosure Building Filtration Region
EBFS Enclosure Building Filtration System Revision 4106/29/23 MPS-2 FSAR LOA 2 of 3
List of Abbreviations (Continued)
Abbreviation
ECCS Emergency Core Cooling System
EOL End of Life
ESCS Engineered Safety Features Control System
F Degrees Fahrenheit
FPS Fire Protection System
FT Fuel Transfer
FW Feed Water
HMP High Mechanical Performance
HPSI High Pressure Safety Injection
HTP High Thermal Performance
IA Instrument Air
ID Inside Diameter
LOCA Loss of Coolant Accident
LPSI Low Pressure Safety Injection
MPC Maximum Permissible Concentration
MSL Mean Sea Level
MSS Main Steam System
MWD Megawatt Days
NDT Non-Destructive Testing
NDTT Nil Ductility Transition Temperature
NS Nitrogen Supply
NSSS Nuclear Steam Supply System
OBE Operating Basis Earthquake Revision 4106/29/23 MPS-2 FSAR LOA 3 of 3
List of Abbreviations (Continued)
Abbreviation
OD Outside Diameter
PA Purge Air
PDH Primary Drain Header
PDT Primary Drain Tank
PPM Parts Per Million
PVMP Preoperational Vibration Monitoring Program
PWR Pressurized Water Reactor
RBCCW Reactor Building Closed Cooling Water
RBCCWS Reactor Building Closed Cooling Water System
RWS Radioactive Waste System
RWST Refueling Water Storage Tank
SA Station Air
SGBS Steam Generator Blowdown System
SIAS Safety Injection Actuation Signal
SIS Safety Injection System
SRAS Sump Recirculation Actuation Signal
SRST Spent Resin Storage Tank
SS Sampling System
TBCCWS Turbine Building Closed Cooling Water System
WGH Waste Gas Header
WREC Westinghouse Rector Evaluation Center
WTR Westinghouse Test Reactor Revision 4106/29/23 MPS-2 FSAR TOC 1 of 9
TABLE OF CONTENTS Section Title Page
CHAPTER 1: INTRODUCTION AND
SUMMARY
Table of Contents
List of Tables
List of Figures
1.1 Introduction....................................................................................................... 1.1-1
1.2 Summary Description....................................................................................... 1.2-1
1.3 Comparison with Other Plants.......................................................................... 1.3-1
1.4 Principal Architectural And Engineering Criteria for Design.......................... 1.4-1
1.5 Research and Development Requirements....................................................... 1.5-1
1.6 Identification of Contractors............................................................................. 1.6-1
1.7 General Design Changes Since Issuance of Preliminary Safety Analysis Report.....
1.7-1
1.8 Advisory Committee on Reactor Safeguards Special Interest Items [This Section Provides Historical Information Provided to the ACRS at the Time of Initial Licensing and Was Not Intended to Be Updated.]........................................... 1.8-1
1.9 Topical Reports................................................................................................. 1.9-1
1.10 Material Incorporated by Reference............................................................... 1.10-1
1.A AEC General Design Criteria for Nuclear Power Plants................................. 1.A-1
CHAPTER 2: SITE AND ENVIRONMENT
Table of Contents
List of Tables
List of Figures
2.1 General Description.......................................................................................... 2.1-1
2.2 Population, Land Use and Water Use............................................................... 2.2-1
2.3 Meteorology...................................................................................................... 2.3-1
2.4 Geology............................................................................................................. 2.4-1
2.5 Hydrology......................................................................................................... 2.5-1 Revision 4106/29/23 MPS-2 FSAR TOC 2 of 9
Table of Contents (Continued)
Section Title Page
2.6 Seismology........................................................................................................ 2.6-1
2.7 Subsurface and Foundations............................................................................. 2.7-1
2.8 Environmental Monitoring Program................................................................. 2.8-1
2.9 Environmental Radiation Monitoring Program................................................ 2.9-1
CHAPTER 3: REACTOR
Table of Contents
List of Tables
List of Figures
3.1 Summary Description....................................................................................... 3.1-1
3.2 Design Bases..................................................................................................... 3.2-1
3.3 Mechanical Design........................................................................................... 3.3-1
3.4 Nuclear Design and Evaluation........................................................................ 3.4-1
3.5 Thermal-Hydraulic Design............................................................................... 3.5-1
3.A Analysis of Reactor Vessel Internals............................................................... 3.A-1
CHAPTER 4: REACTOR COOLANT SYSTEM
Table of Contents
List of Tables
List of Figures
4.1 General System Description............................................................................. 4.1-1
4.2 Design Basis..................................................................................................... 4.2-1
4.3 System Component Design............................................................................... 4.3-1
4.4 Materials Compatibility.................................................................................... 4.4-1
4.5 System Design Evaluation................................................................................ 4.5-1
4.6 Tests and Inspections........................................................................................ 4.6-1 Revision 4106/29/23 MPS-2 FSAR TOC 3 of 9
Table of Contents (Continued)
Section Title Page
4.A Seismic Analysis of Reactor Coolant System.................................................. 4.A-1
CHAPTER 5: STRUCTURES
Table of Contents
List of Tables
List of Figures
5.1 General.............................................................................................................. 5.1-1
5.2 Containment General Description.................................................................... 5.2-1
5.3 Enclosure Building........................................................................................... 5.3-1
5.4 Auxiliary Building............................................................................................ 5.4-1
5.5 Turbine Building............................................................................................... 5.5-1
5.6 Intake Structure................................................................................................. 5.6-1
5.7 External Class I Tanks...................................................................................... 5.7-1
5.8 Seismic Design................................................................................................. 5.8-1
5.9 Construction Practice and Quality Assurance.................................................. 5.9-1
5.A Description of Finite Element Method Used in Containment Analysis.......... 5.A-1
5.B Justification For Load Factors and Load Combinations Used in Design Equations of Containment.................................................................................................5.B-1
5.C Justification For Capacity Reduction Factors () Used in Determining Capacity of Containment......................................................................................................5.C-1
5.D Expanded Spectrum of Tornado Missiles........................................................ 5.D-1
5.E Computer Program List and Descriptions........................................................ 5.E-1
5.E.1 Computer Program Applicability and Validation.......................................... 5.E.1-1
5.E.2 Computer Program Test Problem Solutions.................................................. 5.E.2-1
5.E.3 Computer Program Test Problem Similarities............................................... 5.E.3-1
5.F Containment Water Intrusion Into Tendon Gallery During Construction (1)... 5.F-1 Revision 4106/29/23 MPS-2 FSAR TOC 4 of 9
Table of Contents (Continued)
Section Title Page
CHAPTER 6: ENGINEERED SAFETY FEATURES SYSTEMS
Table of Contents
List of Tables
List of Figures
6.1 General.............................................................................................................. 6.1-1
6.2 Refueling Water Storage Tank and Containment Sump................................... 6.2-1
6.3 Safety Injection System.................................................................................... 6.3-1
6.4 Containment Spray System............................................................................... 6.4-1
6.5 Containment Air Recirculation and Cooling System....................................... 6.5-1
6.6 Containment Post-Accident Hydrogen Control System................................... 6.6-1
6.7 Enclosure Building Filtration System............................................................... 6.7-1
CHAPTER 7: INSTRUMENTATION AND CONTROL
Table of Contents
List of Tables
List of Figures
7.1 Introduction....................................................................................................... 7.1-1
7.2 Reactor Protective System................................................................................ 7.2-1
7.3 Engineered Safety Features Actuation System................................................. 7.3-1
7.4 Regulating Systems........................................................................................... 7.4-1
7.5 Instrumentation System.................................................................................... 7.5-1
7.6 Operating Control Stations............................................................................... 7.6-1
7.7 Control Room Annunciation............................................................................. 7.7-1
7.8 Communication Systems.................................................................................. 7.8-1
7.9 Anticipated Transients Without Scram Circuitry............................................. 7.9-1 Revision 4106/29/23 MPS-2 FSAR TOC 5 of 9
Table of Contents (Continued)
Section Title Page
7.10 Auxiliary Steam Line Break Detection/isolation System............................... 7.10-1
7.11 Environmental Qualification of Electrical Equipment Important to Safety... 7.11-1
CHAPTER 8: ELECTRICAL SYSTEMS
Table of Contents
List of Tables
List of Figures
8.0 Electrical Drawings Submitted to AEC for Review......................................... 8.0-1
8.1 Electric Power................................................................................................... 8.1-1
8.2 4160-Volt and 6900-Volt Systems................................................................... 8.2-1
8.3 Emergency Generators...................................................................................... 8.3-1
8.4 480 Volt System................................................................................................ 8.4-1
8.5 Battery System.................................................................................................. 8.5-1
8.6 Alternating Current Instrumentation and Control............................................. 8.6-1
8.7 Wire, Cable and Raceway Facilities................................................................. 8.7-1
CHAPTER 9: AUXILIARY SYSTEMS
Table of Contents
List of Tables
List of Figures
9.1 General.............................................................................................................. 9.1-1
9.2 Chemical and Volume Control System............................................................ 9.2-1
9.3 Shutdown Cooling System................................................................................ 9.3-1
9.4 Reactor Building Closed Cooling Water System............................................. 9.4-1
9.5 Spent Fuel Pool Cooling System...................................................................... 9.5-1
9.6 Sampling System.............................................................................................. 9.6-1 Revision 4106/29/23 MPS-2 FSAR TOC 6 of 9
Table of Contents (Continued)
Section Title Page
9.7 Cooling Water Systems.................................................................................... 9.7-1
9.8 Fuel and Reactor Component Handling Equipment......................................... 9.8-1
9.9 Plant Ventilation Systems................................................................................. 9.9-1
9.10 Fire Protection System.................................................................................... 9.10-1
9.11 Compressed Air System.................................................................................. 9.11-1
9.12 Water Treatment System................................................................................ 9.12-1
9.13 Auxiliary SteamSystem................................................................................. 9.13-1
CHAPTER 10: STEAM AND POWER CONVERSION SYSTEM
Table of Contents
List of Tables
List of Figures
10.1 Summary Description..................................................................................... 10.1-1
10.2 Turbine Generator........................................................................................... 10.2-1
10.3 Main Steam Supply Syst em........................................................................... 10.3-1
10.4 Other Features of Steam and Power Conversion System............................... 10.4-1
CHAPTER 11: RADIOACTIVE WASTE PROCESSING AND RADIATION PROTECTION SYSTEMS
Table of Contents
List of Tables
List of Figures
11.1 Radioactive Waste Processing Systems.......................................................... 11.1-1
11.2 Radiation Protection....................................................................................... 11.2-1
11.A Source Terms for Radioactive Waste Processing and Releases to the Environment 11.A-1
11.B Radioactive Waste Processing of Releases to Environment...............................................................................................11.B-1 Revision 4106/29/23 MPS-2 FSAR TOC 7 of 9
Table of Contents (Continued)
Section Title Page
11.C Doses From Radioactive Releases and Cost-Benefit Analysis..........................................................................................................11.C-1
11.D Expected Annual Inhalation Doses and Estimated Air Concentrations of Radioactive Isotopes for MP2 Facilities.......................... 11.D-1
11.E Airborne Activity Sampling System for Containment, Spent Fuel and Radwaste Atmospheres................................................................................................... 11.E-1
CHAPTER 12: CONDUCT OF OPERATIONS
Table of Contents
12.1 Organizational Structure................................................................................. 12.1-1
12.2 Training Program............................................................................................ 12.2-1
12.3 Emergency Planning....................................................................................... 12.3-1
12.4 Review and Audit........................................................................................... 12.4-1
12.5 Plant Procedures............................................................................................. 12.5-1
12.6 Records........................................................................................................... 12.6-1
12.7 Physical Security Plans................................................................................... 12.7-1
12.8 Quality Assurance Program............................................................................ 12.8-1
12.9 Deleted by Pkg FSC MP2-UCR-2011-014..................................................... 12.9-1
CHAPTER 13: INITIAL TESTS AND OPERATION
Table of Contents
List of Tables
List of Figures
13.1 Description of the Startup Test Program........................................................ 13.1-1
13.2 Startup Test Program Organization and Responsibilities............................................................................................... 13.2-1
13.3 Administrative Conduct of the Startup Test Program.................................... 13.3-1
13.4 Millstone Startup Group Training Program.................................................... 13.4-1 Revision 4106/29/23 MPS-2 FSAR TOC 8 of 9
Table of Contents (Continued)
Section Title Page
13.5 Initial Inspection and Component Testing Phase........................................... 13.5-1
13.6 Preoperational and Acceptance Test Program................................................ 13.6-1
13.7 Hot Functional Test Program.......................................................................... 13.7-1
13.8 Initial Fuel Loading........................................................................................ 13.8-1
13.9 Initial Criticality.............................................................................................. 13.9-1
13.10 Low Power Physics Testing.......................................................................... 13.10-1
13.11 Power Ascension Testing.............................................................................. 13.11-1
13.12 Piping Operational Testing........................................................................... 13.12-1
13.13 Active Valves Operational Testing............................................................... 13.13-1
13.A Preoperational Test Descriptions................................................................... 13.A-1
CHAPTER 14: SAFETY ANALYSIS
Table of Contents
List of Tables
List of Figures
14.0 General............................................................................................................ 14.0-1
14.1 Increase in Heat Removal By the Secondary System..................................... 14.1-1
14.2 Decrease in Heat Removal by the Secondary System.................................... 14.2-1
14.3 Decrease in Reactor Coolant System Flow..................................................... 14.3-1
14.4 Reactivity and Power Distribution Anomalies............................................... 14.4-1
14.5 Increases in Reactor Coolant System Inventory............................................. 14.5-1
14.6 Decreases in Reactor Coolant Inventory........................................................ 14.6-1
14.7 Radioactive Releases From a Subsystem or Component................................ 14.7-1
14.8 Millstone Unit 2 FSAR Events Not Contained in the Standard Review Plan 14.8-1 Revision 4106/29/23 MPS-2 FSAR TOC 9 of 9
Table of Contents (Continued)
Section Title Page
CHAPTER 15: LICENSE RENEWAL
Table of Contents
List of Tables
15.0 Introduction..................................................................................................... 15.0-1
15.1 Overview of Aging Management Programs................................................... 15.1-1
15.2 Programs That Manage The Effects of Aging on Structures and Components Within the Scope of License Renewal................................ 15.2-1
15.3 Time-Limited Aging Analysis........................................................................ 15.3-1
15.4 TLAA Support Programs................................................................................ 15.4-1
15.5 Exemptions..................................................................................................... 15.5-1
15.6 License Renewal Commitments..................................................................... 15.6-1 Revision 4106/29/23 MPS-2 FSAR LOT 1 of 19 LIST OF TABLES Number Title
Table 1.1-1 Licensing History
Table 1.2-1 Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units (1)
Table 1.3-1 Comparison with Other Plants
Table 1.4-1 Seismic Class I Systems and Components
Table 1.8-1 Comparison of Preoperational Vi bration Monitoring Program Design Parameters
Table 1.9-1 Topical Reports
Table 2.3-1 Distances from Release Point to Receptors
Table 2.3-2 (Deleted)
Table 2.5-1 Effect of Hurricane Generated Surge and Waves on Unit Number 2 Structures
Table 2.5-2 Design Wave Conditions
Table 2.5-3 Roof Surface Area and Number and Size of Roof Drains
Table 2.5-4 All Catch Basins for Elevation Area Draining Into and Runoff Flowing In and Out of a Catch Basin
Table 3.2-1 Stress Limits for Reacto r Vessel Internal Structures
Table 3.3-1 Mechanical Design Parameters
- Table 3.3-2 Pressurized Water Reactor Pr imary Coolant Water Chemistry Recommended Specifications
Table 3.4-1 Fuel Characteristics for a Representative Reload Core
Table 3.4-2 Neutronics Characteristics fo r a Representative Reload Core
Table 3.4-3 Representative Shutdown Margin Requirements
Table 3.5-1 Nominal Reactor and Fuel Design Parameters
Table 3.5-2 Design Operating Hydraulic Loads on Vessel Internals
Table 3.5-3 Uncertainty Sources for DN BR Calculations (Deleted)
Revision 4106/29/23 MPS-2 FSAR LOT 2 of 19
List of Tables (Continued)
Number Title
Table 3.A-1 Natural Frequencies fo r Vertical Seismic Analysis Mathematical Model
Table 3.A-2 Seismic Stresses in Critical Reactor Internals Components for the Design Basis Earthquake
Table 4.1-1 Reactor Coolant System Volumes
Table 4.2-1 Principal Design Parameters of Reactor Coolant System
Table 4.2-2A Table of Loading Combinations and Primary Stress Limits
Table 4.2-2B Table of Loading Combinations and Primary Stress Limits for the Replace-ment Reactor Vessel Head and Replacement pressurizer
Table 4.2-3 Reactor Coolant System Code Requirements
Table 4.2-4 Comparison with Safety Guide 26
Table 4.3-1 Reactor Vessel Parameters
Table 4.3-2 Steam Generator Parameters
Table 4.3-3 Main Steam Safety Valve Parameters
Table 4.3-4 Tech Pub Review PKG for T4.3-4R eactor Coolant Pump Parameters
Table 4.3-5 Reactor Coolant Piping Parameters
Table 4.3-6 Pressurizer Parameters
Table 4.3-7 Quench Tank Parameter
Table 4.3-8 Pressurizer Spray (RC-100E, RC-100F) Valve Parameters
Table 4.3-9 Power-Operated Relief Valve Isolation Valve Parameters (RC-403, RC-405)
Table 4.3-10 Pressurizer Power-Operated Reli ef Valve Parameters (RC-402, RC-404)
Table 4.3-11 Pressurizer Safety Valve Parameters (RC-200, RC-201)
Table 4.3-12 Active and Inactive Valves in the Reactor Coolant System Boundary
Table 4.4-1 Materials Exposed to Coolant Revision 4106/29/23 MPS-2 FSAR LOT 3 of 19
List of Tables (Continued)
Number Title
Table 4.4-2 Reactor Coolant Chemistry
Table 4.5-1 Reactor Coolant System Component Nozzles, Nozzle Sizes and Nozzle Materials
Table 4.5-2 Reactor Coolant System Heatup and Cooldown Limits
Table 4.6-1 RT NDT Determination for Reactor Vessel Base Metal Millstone Unit Number 2
Table 4.6-2 Charpy V-Notch and Drop Weight Test Values - Pressurizer Millstone Unit Number 2
Table 4.6-3 Charpy V-notch and Drop Weight Test Values - Steam Generator
Table 4.6-4 Charpy V-notch Values - Piping
Table 4.6-5 Plate and Weld Meta l Chemical Analysis
Table 4.6-6 Beltline Mechanical Test Properties - Reactor Vessel Surveillance Materials
Table 4.6-7 Tensile Test Properties - Reac tor Vessel Surveillance Materials
Table 4.6-8 Summary of Specimens Provided for Each Exposure Location
Table 4.6-9 Capsule Removal Schedule
Table 4.6-10 Inspection of Reactor Coolant System Component s During Fabrication and Construction
Table 4.6-11 Reactor Coolant System Inspection C-E Requirements
Table 4.6-12 Reactor Coolant System Insp ection C-E Requirements (Continued)
Table 4.6-13 RT PTS Values at 54 EFPY
Table 4.6-14 Adjusted Reference Temperatures (ART) Projections
Table 4.A-1 Natural Frequencies and Dominant Degrees of Freedom
Table 4.A-2 Seismic Loads on Reactor Coolant System Components for Operational Basis Earthquake
Table 5.2-1 Containment Structure Analysis Summary Revision 4106/29/23 MPS-2 FSAR LOT 4 of 19
List of Tables (Continued)
Number Title
Table 5.2-2 Containment Structure Analysis Summ ary - Dead Load, Initial Prestress and Live Load (D+KF+L)
Table 5.2-3 Containment Structure Analysis Summ ary - Dead Load, Initial Prestress and Live Load (D+F+L+1.15P)
Table 5.2-4 Containment Structure Analysis Summ ary - Dead Load, Initial Prestress and Live Load, Operating Temperature and OBE (D+F+L+T0+E)
Table 5.2-5 Containment Structure Analysis Summ ary - Dead Load, Prestress, Live Load, 100% Accident Pressure and Accident Temperature (D+F+L+1.0P+T1)
Table 5.2-6 Containment Structure Analysis Summary - Dead Load, Prestress, Operating Temperature, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+T0+H+R+E1)
Table 5.2-6A Deleted by FSARCR 04-MP2-016
Table 5.2-7 Containment Structure Analysis Summary - Dead Load, Prestress, 100%
Accident Pressure, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+1.0P+H+T1+E1)
Table 5.2-8 Containment Structure Analysis Summary - Dead Load, Prestress, 125%
Accident Pressure, 125% Thermal Expansion Forces of Pipes, Accident Temperature and 125% DBE (D+F+1.25P+1.25H+T1+1.25E)
Table 5.2-9 Containment Structure Analysis Summary - Dead Load, Prestress, 150%
Accident Pressure, and Accident Temperature (D+F+1.5P+T1)
Table 5.2-10 Spectrum of Potential Missil es From Inside the Containment
Table 5.2-11 Containment Structure Isolation Valve Information
Table 5.2-12 Containment Penetration Piping
Table 5.2-13 Major (1) Containment Isolation Valves
Table 5.2-14 Typical Leak Rate Measur ement System Instrumentation Revision 4106/29/23 MPS-2 FSAR LOT 5 of 19
List of Tables (Continued)
Number Title
Table 5.2-15 Typical Containment Resistance Temperature Detectors and Dewcell Sensor Volume Weight Fractions
Table 5.5-1 Maximum Actual Stresses - Turbine Building
Table 5.8-1 Material Damping Values
Table 5.9-1 Aggregate Tests
Table 5.9-2 Cement Tests
Table 5.9-3 Fly Ash Tests
Table 5.9-4 Typical Chemical Anal ysis of Fly Ash Used
Table 5.9-5 Allowable Void Limits for Cadwelding
Table 5.D-1 Impactive Velocities (fps ) of Missiles of Different CdA/W Factors as Picked from the Ground by the Design Tornado
Table 5.D-2 Kinetic Energy per Ft 2 of Impact Area
Table 5.D-3 Radius vs. Velocity FPS/MPH (D=0.882 psi/V 1 = 27 mph)
Table 5.D-4 Radius vs. Velocity FPS/MPH (D=3 psi/V 1 = 60 mph)
Table 5.D-5 Velocities of Various Missiles
Table 5.D-6 Test Data Summary
Table 5.D.A-1A Relative Conservatism in Steps A, B, and C
Table 5.D.A-2A
Table 5.D.A-3A
Table 6.1-1 Pipe Rupture Prot ection Requirements
Table 6.1-2 Omitted
Table 6.1-3 Design Non-Seismic Category I Components Located Inside Containment and Enclosure Building Revision 4106/29/23 MPS-2 FSAR LOT 6 of 19
List of Tables (Continued)
Number Title
Table 6.1-4 Pipe Rupture Criteria Applicabi lity (Outside Containment) Based on Normal Operating Plant Conditions
Table 6.2-1 Refueling Water Storage Tank and Containment Sump
Table 6.3-1 Omitted
Table 6.3-2 Principal Design Parameters of the Safety Injection System
Table 6.3-3 Shutdown Cooling Heat Exchanger Data
Table 6.3-4 Omitted
Table 6.3-5 Internal Dimensions of Containmen t Sump Recirculation Piping and Valves
Table 6.3-6 Safety Injection System Failure Mode Analysis High Pressure Safety Injection
Table 6.3-7 Administrative Error Analysis-Safety Injection System Valves
Table 6.3-8 Failure Modes and Effects Analys is for Boron Precipitation Control
Table 6.4-1 Containment Spray System Component Design Parameters
Table 6.4-2 Containment Spray System Failure Mode Analysis
Table 6.5-1 Containment Air Recirculation and Cooling Units Materials of Construction
Table 6.5-2 Containment Air Recirculation a nd Cooling Units Performance Data
Table 6.5-3 Containment Air Recirculation and Cooling System
Table 6.6-1 Containment Post Accident Hydr ogen Control Systems Component Description
Table 6.6-2 Deleted by FSARCR 04-MP2-018
Table 6.6-3 Omitted
Table 6.6-4 Post-Incident Recirculation System Failure Mode Analysis
Table 6.7-1 Enclosure Building Filtration System Component Description
Table 6.7-2 Enclosure Building Filtration System Failure Mode Analysis Revision 4106/29/23 MPS-2 FSAR LOT 7 of 19
List of Tables (Continued)
Number Title
Table 7.2-1 Reactor Trip and Pretrip Set Points
Table 7.2.1.1-I Parameters Affecting Fuel Design Limit
Table 7.2.1.1-II Pertinent NSSS parameters and Monitored Variables
Table 7.2.1.1-III Trip Functions
Table 7.2.1.1-IV Trip Variable Monitored
Table 7.3.2.2-1 ESAS Failure Mode Analysis for Containment Pressure Channels
Table 7.4-1 Prohibits on CEAs
Table 7.5-1 Major Process Instrumentation
Table 7.5-2 Omitted
Table 7.5-3 Regulatory Guide 1.97 (Rev. 2) Accident Monitoring Instrumentation
Table 7.5-4 Area Radiation Monitors
Table 7.5-5 Liquid Process/Efflue nt Radiation Monitors
Table 7.5-6 Airborne Process/Effl uent Radiation Monitors
Table 7.5-6A Process Radiation Monitors (Steam)
Table 7.5-7 CEA Position Light Matrix
Table 7.6-1 Major Equipment Normal ly Used for Hot Shutdown
Table 7.6-2 Major Equipment Normally Used for Cold Shutdown
Table 8.3-1 Diesel Fuel Oil System Mode Analysis
Table 8.3-2 A Emergency Diesel Generator Loading
Table 8.3-3 B Emergency Diesel Generator Loading
Table 8.5-1 Battery Service Profile for Batteries 201A and 201B
Table 8.7-1 Cable Characteristics
Table 8.7-2 Omitted Revision 4106/29/23 MPS-2 FSAR LOT 8 of 19
List of Tables (Continued)
Number Title
Table 8.7-3 Omitted
Table 8.7-4 Facility Identification
Table 9.2-1 Chemical and Volume Control System Parameters
Table 9.2-2 Reactor Coolant and Demi neralized Water Chemistry
Table 9.2-3 Regenerative Heat Exchanger
Table 9.2-4 Letdown Control Valves
Table 9.2-5 Letdown Heat Exchanger
Table 9.2-6 Ion Exchangers
Table 9.2-7 Letdown Filters
Table 9.2-8 Volume Control Tank
Table 9.2-9 Charging Pumps
Table 9.2-10 Concentrated Boric Acid Preparation and Storage
Table 9.2-11 Boric Acid Pumps and Strainers
Table 9.3-1 Shutdown Cooling Heat Excha ngers Design Basis Parameters
Table 9.3-2 Shutdown Cooling System Design Parameters
Table 9.4-1 Reactor Building Closed Cool ing Water System Components
Table 9.4-2 Reactor Building Closed Cooling Wa ter System Failure Mode Analysis
Table 9.4-3 Minimum Required RBCCW Flow to Essential Safety-Related Loads LOCA Injection and Recirculation Operations
Table 9.5-1 Spent Fuel Pool Monitoring Equipment
Table 9.5-2 Components of Spent Fuel Pool Cooling System
Table 9.7-1 Circulating Water System Components
Table 9.7-2 Service Water System Components Revision 4106/29/23 MPS-2 FSAR LOT 9 of 19
List of Tables (Continued)
Number Title
Table 9.7-3 Turbine Building Closed C ooling Water System Components
Table 9.7-4 Service Water Cooling System
Table 9.8-1 Transfer Tube Isolation Valve
Table 9.8-2 Spent Fuel Pool Platform Crane
Table 9.8-3 Spent Fuel Cask Crane
Table 9.8-4 Failure Mode Analysis
Table 9.8-5 Radiation Levels from Heated Junction Thermocouple (R/Hr)
Table 9.9-1 Control Element Drive Mechanism Cooling System
Table 9.9-2 Containment and Enclosure Building Purge System
Table 9.9-3 Containment Auxiliary Circulation System
Table 9.9-4 Containment Penetr ation Cooling System
Table 9.9-5 Penetration Air Cooling Requirements
Table 9.9-6 Radwaste Ventilation System
Table 9.9-7 Nonradioactive Ventilation System
Table 9.9-8 Engineered Safety Features Room Air Recirculation System
Table 9.9-9 Fuel Handling Ventilation System
Table 9.9-10 Main Exhaust System
Table 9.9-11 Control Room Air Conditioning System
Table 9.9-12 Diesel Generator Ventilation Systems
Table 9.9-13 Turbine Building Ventilation System
Table 9.9-14 Access Control Area Air Conditioning System
Table 9.9-15 Balance of Unit Ventilation System Revision 4106/29/23 MPS-2 FSAR LOT 10 of 19
List of Tables (Continued)
Number Title
Table 9.9-16 Engineered Safety Features Room Air Recirc. System Failure Mode Analysis
Table 9.9-17 Control Room Air Conditioning System Failure Mode Analysis
Table 9.9-18 Diesel Generator Ventilation System Failure Mode Analysis
Table 9.9-19 Vital Switchgear Ventilati on System Component Description
Table 9.9-20 Auxiliary Chilled Water Sy stem Component Description
Table 9.9-21 Vital Chilled Water Syst em Component Description
Table 9.9-22 Indoor Design Temperatures for Significant Plant Areas
Table 9.11-1 Compressed Air System Component Description
Table 9.11-2 Gas Receiver Tanks Safety Evaluation
Table 9.12-1 Water Treatment System Components
Table 10.1-1 Deleted
Table 10.2-1 Turbine Generator Component Description
Table 10.3-1 Major Components of Main Steam System
Table 10.3-2 Omitted
Table 10.3-3 Operating Details for Valve System s Protecting Steam Generations of Overpressure
Table 10.4-1 Major Components of the C ondensate and Feedwater System
Table 10.4-2 Failure Analysis of Steam Generator Blowdown System Components
Table 11.1-1 Radioactive Waste Processing System Component Description
Table 11.1-2 Sources and Expected Volumes of Solid Wastes
Table 11.1-3 Radioactivity levels of solid wastes (See Note)
Table 11.1-4 Curie Inventory of Solid Waste Shi pped from Millstone Unit 2 (See Note)
Revision 4106/29/23 MPS-2 FSAR LOT 11 of 19
List of Tables (Continued)
Number Title
Table 11.1-5 Assumptions for Waste Gas Decay Tank Accident
Table 11.2-1 Source Terms for Shielding Design
Table 11.A-1 Design-Basis and Expected Primar y Coolant Activity Concentrations
Table 11.A-2 Calculated Reacto r Core Activities
Table 11.A-3 Expected Annual Effluent Releases (Curies Per Year), by Radionuclide, from Each Release Point
Table 11.A-4 Expected Annual Li quid Effluent Activity Releases (Curies/Year), by Radionuclide, from Each Waste Stream
Table 11.A-5 Expected Annual Liquid Effluent Conc entrations (Diluted and Undiluted),
by Radionuclide, from Each Waste System
Table 11.A-6 Design Basis Radionuclide Concentrations in Liquid Effluent, in Fractions of 10CFR Part 20 Concentration Limits
Table 11.A-7 Design-Basis Radionuclide Airborne Concentrations at the Site Boundary From All Gaseous Effluent Release Points Combined, in Fractions of 10CFR Part 20 Concentration Limits
Table 11.A-8 Total Annual Design-Basis and Expect ed Releases of Radioactive Liquid Waste to the Environment From All Sources Combined, in Curies Per Year
Table 11.A-9 Total Annual Design Basi s and Expected Releases of Airborne Radioactive Waste to the Environment From All Release Points Combined, in Curies Per Year
Table 11.A-10 Basis for Reactor Coolant System Activity NUREG-0017 gale Code Input
Table 11.B-1 Inputs to PWR-GALE Code
Table 11.C-1 Comparison of Calculated Annua l Maximum Individual Doses with 10CFR Part 50 Appendix I Design Objectives
Table 11.C-2 Annual Total Body and Thyroid Doses to the Population Within 50 Miles of the Millstone Site, In Man-Rem, From Expected Liquid and Airborne Effluent Releases Revision 4106/29/23 MPS-2 FSAR LOT 12 of 19
List of Tables (Continued)
Number Title
Table 11.D-1 Containment Building Airborne Concentrations
Table 11.D-2 Auxiliary Building Airborne Concentrations
Table 11.D-3 Turbine Building Airborne Concentrations
Table 13.12-1 Seismic Category I-ASME Section III Classes 1 and 2 Piping Systems
Table 14.0-1 Reactor Operating Mode s For Millstone Unit 2
Table 14.0-2 Disposition of Events Summary
Table 14.0.1-1 Accident Category Used For Each Analyzed Event
Table 14.0.2-1 Plant Operating Conditions
Table 14.0.2-2 Nominal Fuel Design Parameters
Table 14.0.3-1 Core Power Distribution (Table Deleted)
Table 14.0.4-1 Range of Key Initial Condition Operating Parameters
Table 14.0.5-1 Reactivity Parameters (Table Deleted)
Table 14.0.7-1 Analytical Trip Setpoints
Table 14.0.7-2 Uncertainties Applied at HFP Condition in Local Power Density Limiting Safety System Settings Calculations
Table 14.0.7-3 Uncertainties Applied at HFP Condition in the Thermal Margin/Low Pressure Limiting Safety System Settings Calculations
Table 14.0.7-4 Uncertainties Applied at HFP C ondition in the Local Power Density Limiting Condition for Operation Calculations
Table 14.0.7-5 Uncertainties Applied in Depart ure from Nucleate Boiling Limiting Condition for Operation Calculations
Table 14.0.8-1 Component Capacities and Setpoints
Table 14.0.9-1 Overview of Plant Systems and E quipment Available for Transient and Accident Conditions
Table 14.0.12-1 Nomenclature Used in Plotted Results Revision 4106/29/23 MPS-2 FSAR LOT 13 of 19
List of Tables (Continued)
Number Title
Table 14.1.1-1 Available Reactor Protection for the Decrease in Feedwater Temperature Event
Table 14.1.1-2 Disposition of Events for the Decr ease in Feedwater Temperature Event
Table 14.1.2-1 Available Reactor Protection for the Increase in Feedwater Flow Event
Table 14.1.2-2 Disposition of Events for the Increase in Feedwater Flow Event
Table 14.1.3-1 Available Reactor Protection for the Increase in Steam Flow Event
Table 14.1.3-2 Disposition of Events for the Increase in Steam Flow Event
Table 14.1.3-3 Initial Conditions for the Increase in Steam Flow Event
Table 14.1.3-4 Event Summary for the Increase in Steam Flow Event
Table 14.1.3-5 Peak Reactor Power Levels for Increase in Steam Flow Event
Table 14.1.4-1 Available Reactor Protection for the Inadvertent Opening of a Steam Generator Relief or Safety Valves
Table 14.1.4-2 Disposition of Events for the Ina dvertent Opening of a Steam Generator Relief or Safety Valve Event
Table 14.1.5.1-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment
Table 14.1.5.1-2 Disposition of Events for Steam Syst em Piping Failures Inside and Outside Containment
Table 14.1.5.1-3 S-RELAP5 Thermal-Hydraulic Input (Pre-Scram Steam Line Break)
Table 14.1.5.1-4 Actuation Signals and Delays (Pre-Scram Steam Line Break)
Table 14.1.5.1-5 S-RELAP5 Neutronics Input and As sumptions (Pre-Scram Steam Line Break)
Table 14.1.5.1-6 MDNBR and Peak Reactor Power Leve l Summary (Pre-Scram Steam Line Break)
Table 14.1.5.1-7 LHGR-Limiting Pr e-Scram Steam Line Break Sequence of Events: HFP 0.20ft2 Asymmetric Break Inside Containment with Offsite Power Available Revision 4106/29/23 MPS-2 FSAR LOT 14 of 19
List of Tables (Continued)
Number Title
Table 14.1.5.1-8 MDNBR-Limiting Pr e-Scram Steam Line Break Sequence of Events: HFP 3.51ft2 Asymmetric Break Inside Containment with Loss of Offsite Power
Table 14.1.5.2-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment, Post-Scram Analysis
Table 14.1.5.2-2 Disposition of Events for Steam Syst em Piping Failures Inside and Outside of Containment, Post-Scram Analysis
Table 14.1.5.2-3 SRELAP5 -Thermal-Hydraulic Input (Post-Scram Steam Line Break)
Table 14.1.5.2-4 Actuation Signals and Delays (Post-Scram Steam Line Break)
Table 14.1.5.2-5 S-RELAP5 Neutronics Input and Assumptions (Post-Scram Steam Line Break)
Table 14.1.5.2-6 Post-Scram Steam Line Break Analysis Summary
Table 14.1.5.2-7 LHGR-Limiting Sequence of Events - HZP Offsite Power Available
Table 14.1.5.2-8 MDNBR-Limiting Post-Scram Stea m Line Break Analysis Summary
Table 14.1.5.3-1 Assumptions Used in Main Steam Line Break Analysis
Table 14.1.5.3-2 Summary of Millstone 2 MSLB Accident Doses
Table 14.1.5.3-3 Deleted by FSARCR PKG FSC 07-MP2-006
Table 14.2.1-1 Available Reactor for the Loss of External Load Event
Table 14.2.1-2 Disposition of Events for the Loss of External Load Event
Table 14.2.1-3 Event Summary for the Loss of External Load Event (Primary Overpressurization Case)
Table 14.2.1-4 Event Summary for the Loss of External Load Event (Secondary Overpressurization Case)
Table 14.2.1-5 Event Summary for the Loss of External Load Event (Minimum Departure from Nucleate Boiling Ratio Case)
Table 14.2.2-1 Available Reactor Protection for the Turbine Trip Event
Table 14.2.2-2 Disposition of Events for the Turbine Trip Event Revision 4106/29/23 MPS-2 FSAR LOT 15 of 19
List of Tables (Continued)
Number Title
Table 14.2.4-1 Available Reactor Protection for the Closure of the Main Steam Isolation Valves Events
Table 14.2.4-2 Disposition of Events for the Closur e of the Main Steam Isolation Valves Events
Table 14.2.4-3 Event Summary for the Main Steam Isolation Valve Closure Event (Lower Steam Flow Case)
Table 14.2.7-1 Available Reactor Protection for the Loss of Normal Feedwater Flow Event
Table 14.2.7-2 Disposition of Events for the Loss of Normal Feedwater Flow Event
Table 14.2.7-3 Sequence of Events for Minimum Steam Generator Inventory Case: One Motor-Driven AFW Pump Fails to Start with Offsite Power and Steam Dumps
Table 14.2.7-4 Sequence of Events for Maximum Pres surizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start
Table 14.3.1-1 Available Reactor Protection for the Loss of Forced Reactor Coolant Flow Event
Table 14.3.1-2 Disposition of Events for the Loss of Forced Reactor Coolant Flow Event
Table 14.3.1-3 Event Summary for the Loss of Forced Reactor Coolant Flow
Table 14.3.3-1 Available Reactor Protection for th e Reactor Coolant Pump Rotor Seizure Event
Table 14.3.3-2 Disposition of Events for the Reac tor Coolant Pump Rotor Seizure Event
Table 14.3.3-3 Event Summary for the Reacto r Coolant Pump Rotor Seizure
Table 14.4.1-1 Available Reactor Protection for the Uncontrolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition Event
Table 14.4.1-2 Disposition of Events for the Uncontrolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition Event
Table 14.4.1-3 Event Summary for the Uncontrolled Bank Withdrawal from Low-Power Event Revision 4106/29/23 MPS-2 FSAR LOT 16 of 19
List of Tables (Continued)
Number Title
Table 14.4.2-1 Available Reactor Protection for the Uncontrolled Control Rod/Bank Withdrawal at Power Event
Table 14.4.2-2 Disposition of Events for the Uncontrolled Control Rod/Bank Withdrawal at Power Event
Table 14.4.2-3 Event Summary for the Uncontrolled Rod/Bank Withdrawal Event for the Limiting 100% Power Case
Table 14.4.3.1-1 Available Reactor Protection fo r the Dropped Control Rod/Bank Event
Table 14.4.3.1-2 Disposition of Events for the Dropped Control Rod/Bank Event
Table 14.4.3.1-3 Event Summary for the Limiti ng Dropped Control Rod/Bank Case
Table 14.4.3.5-1 Available Reactor Prot ection for the Single Control Rod Withdrawal Event
Table 14.4.3.5-2 Disposition of Events for the Single Control Rod Withdrawal Event
Table 14.4.4-1 Available Reactor Protection
Table 14.4.4-2 Disposition of Events for the St artup of an Inactive Loop Event
Table 14.4.6-1 Available Reactor Protection for Ch emical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Event
Table 14.4.6-2 Disposition of Events for the Ch emical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Event
Table 14.4.6-3 Summary of Results for the Boro n Dilution Event Asymmetric Dilution Front Model
Table 14.4.6-4 Summary of Results for the Boron Dilution Event Instantaneous Mixing Mode
Table 14.4.8-1 Available Reactor Protection for th e Spectrum of Control Rod Ejection Accidents
Table 14.4.8-2 Disposition of Events for the Spectr um of Control Rod Ejection Accidents
Table 14.4.8-3 Event Summary for a Control Ro d Ejection (Maximum Pressurization Case)
Revision 4106/29/23 MPS-2 FSAR LOT 17 of 19
List of Tables (Continued)
Number Title
Table 14.4.8-4 Event Summary for a Control Ro d Ejection Minimum Departure from Nucleate Boiling Ratio Case
Table 14.4.8-5 dnBounding Beginning of Cycle/End of Cycle Ejected Rod Analysis
Table 14.4.8-6 CREA Radiological Analysis Assumptions
Table 14.4.8-7 Radiological Consequences of a CREA
Table 14.6.1-1 Available Reactor Protection for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve Event
Table 14.6.1-2 Disposition of Events for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Relief Valve Event
Table 14.6.1-3 Event Summary for an Inadvertent Op ening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve
Table 14.6.3-1 Available Reactor Protection for th e Radiological Consequences of Steam Generator Tube Rupture Event
Table 14.6.3-2 Disposition of Events for the Ra diological Consequences of Steam Generator Tube Rupture Event
Table 14.6.3-3 Sequence of Events for the St eam Generator Tube Rupture Event
Table 14.6.3-4 Mass Releases for the Steam Generator Tube Rupture Accident
Table 14.6.3-5 Assumptions for the Radiological Ev aluation for the Steam Generator Tube Rupture Event
Table 14.6.3-6 Summary - Radiological Consequenc es of the Steam Generator Tube Rupture Event
Table 14.6.5.1-1 Available Reactor Protection for th e Large Break Loss of Coolant Accident
Table 14.6.5.1-2 Disposition of Events for the La rge Break Loss of Coolant Accident
Table 14.6.5.1-3 Millstone Unit 2 Realisti c Large Break Loss of Coolant Accident Analysis
- Plant Parameter Values and Ranges
Table 14.6.5.1-4 Millstone Unit 2 Large Break Lo ss of Coolant Accident Analysis -
Statistical Distribution Used for Proces s Parameters Revision 4106/29/23 MPS-2 FSAR LOT 18 of 19
List of Tables (Continued)
Number Title
Table 14.6.5.1-5 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis - Passive Heat Sinks and Material Properties In Containment Geometry
Table 14.6.5.1-6 Millstone Unit 2 Large Break Lo ss of Coolant Accident Analysis -
Compliance with 10 CFR 50.46(b)
Table 14.6.5.1-7 Millstone Unit 2 Large Break Lo ss of Coolant Accident Analysis -
Summary of Major Parameters for the Demonstration Case
Table 14.6.5.1-8 Millstone Unit 2 Large Break Lo ss of Coolant Accident Analysis -
Calculated Event Times for the Demonstration Case*
Table 14.6.5.2-1 Available Reactor Protection for the Small Break Loss of Coolant Accident
Table 14.6.5.2-2 Disposition of Events for the Sm all Break Loss of Coolant Accident
Table 14.6.5.2-3 Millstone Unit 2 Small Break Loss of Coolant Accident System Analysis Parameters
Table 14.6.5.2-4 Deleted by FSCR MPS-UCR-2016-016
Table 14.6.5.2-5 Calculated Event Times for Small Break Loss-of-Coolant Accident
Table 14.6.5.2-6 Analysis Results for Small Break Loss-of-Coolant Accident
Table 14.6.5.2-7 Peak Clad Temperature Including All Penalties and Benefits - Small Break LOCA
Table 14.6.5.3-1 Core and System Parameters Used in the LTC Analysis
Table 14.6.5.4-1 Available Reactor Protection for th e Large Break Loss of Coolant Accident
Table 14.6.5.4-2 Disposition of Events for the La rge Break Loss of Coolant Accident
Table 14.6.5.4-3 Millstone Unit 2 System Analysis Parameters (Large Break Loss of Coolant Accident Analysis)
Table 14.6.5.4-4 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis
Table 14.6.5.4-5 Millstone Unit 2 Large Break LOCA Analysis
Table 14.6.5.4-6 Millstone Unit 2 Large Break LOCA Analysis Revision 4106/29/23 MPS-2 FSAR LOT 19 of 19
List of Tables (Continued)
Number Title
Table 14.6.5.4-7 Peak Clad Temperature Including All Penalties and Benefits - Large Break LOCA
Table 14.7.1-1 Deleted by FSARCR PKG FSC 07-MP2-006
Table 14.7.4-1 Assumption for Fuel Handling Accident in the Spent Fuel Pool
Table 14.7.4-2 Assumption for Fuel Handling Accident in Containment
Table 14.7.4-3 Deleted by FSARCR 02-MP2-015
Table 14.7.5-1 Assumptions for Spent Fuel Cask Tip Accident
Table 14.8.2-1 Containment Design Parameters
Table 14.8.2-2 Initial Conditions for Pressure Analyses
Table 14.8.2-3 Minimum Containm ent Heat Sink Data
Table 14.8.2-4 Sequence of Events, MP2-MSLB: Loss of Offsite Power and the Failure of Vital Bus VA-10 or VA-20 from 102% Power
Table 14.8.2-5 Engineered Safety Features Perfor mance for MSLB Containment Analysis
Table 14.8.4-1 Loss of Coolant Accident (Off site Assumptions)
Table 14.8.4-2 Summary of Doses for Loss of Coolant Accident
Table 14.8.4-3 Loss of Coolant Accident (Control Room Assumptions)
Table 14.8.4-4 Atmospheric Dispersion Data fo r Millstone Unit 2 Control Room
Table 14.8.4-5 Dose to Millstone Unit 2 Control Room Operators
Table 15.3-1 Containment Tendon Prestress
Table 15.6-1 License Rene wal Commitments