ML23193A882

1 to Updated Final Safety Analysis Report, Frontmatter

ML23193A882
Person / Time
Site:	Millstone
Issue date:	06/28/2023
From:	Dominion Energy Nuclear Connecticut
To:	Office of Nuclear Reactor Regulation
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References
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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

DBE Design Basis Earthquake

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

MTU Metric Tons Uranium

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

RCS Reactor Coolant 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