ML17212A041

Final Safety Analysis Report, Rev. 35, Frontmatter

ML17212A041
Person / Time
Site:	Millstone
Issue date:	06/29/2017
From:	Dominion Nuclear Connecticut
To:	Office of Nuclear Reactor Regulation
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MILLSTONE POWER STATION UNIT 2 FINAL SAFETY ANALYSIS REPORT 1 of 2 Revision Summary of Change Revision 34 (2016 - 2017 Reporting Period)

Revision Revision Release Date Change ActivityDocument Elements Affected (Sections, Tables, Figures)

Summary Description of Changes 344/5/16 AdministrativeAs identified in the 2016 N RC Submittal List of Changed Pages and submitted Summary of Change.Administrative (FSAR content not affected). Change indicator(s) and page change identi fication(s) present in the 2016 NRC Submittal were removed in preparation for the 2017 Annual Re port. This forms the base line for changes incorporated under the Revision 34 series. Revision level of the authoring files are unchanged. This supports Revision/Change traceability.34.19/29/16 AdministrativeVariousReflects administrative (FSAR content not affected) markup to identify sensitive non-safeguards unclassified information where applicable. 34.19/29/16MP2-UCR-2016-004Table 11.2-1Correct typo identified by CR1017686.34.19/29/16MP2-UCR-2016-006Section 14.8.2.2.4Millstone 2 NRC License Amendment 32 6, "Millstone Power Station Unit2 - Issuance of Amendment to Revise Technical Specifications forContainment Leak Rate Testing (CAC No. MF5838)," March 31, 2016(ADAMS Accession Number ML16068A312).34.19/29/16MP2-UCR-2016-007Chapter 1 section 1.A; Chapter 8 List of Figures; Chapter 8section 8.1.1.4, 8.1.2.1; 8.1.2.2; 8.1.2.3 and Figure 8.1-1A;8.1-1BUnit 2 SLOD Removal (LBDCR 15-MP2-006)34.212/22/16MP2-UCR-2013-017Table 6.7-1, Table 9.9-11 Reflects correction of technical value in the respective tables.34.212/22/16MP2-UCR-2015-0071.2.10.4, 1.A, 9.8.2.1.1, 9.8.2.1.2, 9.8.2.2.2, Figure 9.8-7, Figure 9.8-8A, Figure 9.8-8B, Figure 9.8-8C, 14.7.4.1Reflects changes associated with LBDCR 12-MP2-008.34.212/22/16MP2-UCR-2016-0039.3.2.3Update Subsection 9.3.2.3 to reflect changes made by DCN DM2-00-0166-07 that eliminated the packing leak-off lines on M22-SI-306.

2 of 234.212/22/16MP2-UCR-2016-00911.E.1RM-8123 and RM-8262 are described incorrectly in the FSAR. This change removes the reference to a gamma geiger muller detector chamber type and replace it with the correct beta scintillator type detector.34.212/22/16MP2-UCR-2016-010 15.2.1.2Cancellation of Millstone 2 Boraflex Monitoring Program.34.212/22/16MP2-UCR-2016-012 15.2.1.21MP3 HVK Chiller Service Water Thermal Performance Testing Elimination.34.212/22/16MP2-UCR-2016-01614.6.5.2, 14.6.5.2.5, 14.6.5.2.5

.1, 14.6.5.2.5.2 , 14.6.5.2.5.3, 14.6.5.2.5.4, 14.6.5.2.5.5, 14.6.5.2.5.8, 14.6.5.2.5.9, 14.6.5.2.6, 14.6.5.2.7, 14.6.5.2.8, Figures 14.6.5.2-1, 14.6.5.2-2, 14.6.5.2-3, 14.6.5.2-4, 14.6.5.2-5, 14.6.5.2-6, 14.6.5.2-7, 14.6.5.2-8, 14.6.5.2-9, 14.6.5.2-10, 14.6.5.2-11, 14.6.5.2-12, 14.6.5.2-13, 14.6.5.2-14, 14.6.5.2-15, 14.6.5.2-16, 14.6.5.2-17, 14.6.5.2-18, 14.6.5.2-19, 14.6.5.2-20, 14.6.5.2-21, 14.6.5.2-22, Tables 14.6.5.2-3, 14.6.5.2-4, 14.6.5.2-5, 14.6.5.2-6, 14.6.5.2-7This SAR change request updates the Small Break Loss of Coolant Accident (SBLOCA) analysis presented in FSAR Section 14.6.5.2.34.303/30/17MP2-UCR-2016-0089.5.1.1, 9.5.2.1, 9.5.3.1The NRC requested additional inform ation be provided in the FSAR to describe the procedural controls in place to maintain the Millstone 2 Spent Fuel Pool temperature below 150°F. LAR 15-571 3506/29/17MP2-UCR-2015-02514.0.11, 14.6.1.1, 14.6.1.6Confirmatory Order EA-13-188, AREVA analysis ANP-3406, Rev. 0 -

Remove credit for charging from the long-term portion of the inadvertent opening of the PORV (IOPORV) event.

3506/29/17MP2-UCR-2017-00410.3.4.2, Table 10.3-1LA3022214 - Modify FSAR Section 10.3.4.2 Tests and Inspection to read

"See Section 5.2.7.4.1-" in lieu of 5.2.8.4.2.

Revision 34 (2016 - 2017 Reporting Period)

Revision Revision Release Date Change ActivityDocument Elements Affected (Sections, Tables, Figures)

Summary Description of Changes MPS2 UFSAR LOA 1 of 3 LIST OF ABBREVIATIONS Abbreviation ADH Aerated Drain HeaderAEASAuxiliary Exhaust Actuation Signal AESAuxiliary Exhaust SystemATWSAnticipated Transient Without Scram

BOLBeginning of Life BWRBoiling Water Reactor CEAControl Element AssemblyCEDMControl Element Drive Mechanism CEDSControl Element Drive System

CFRCode of Federal Regulations CIAS Containment Isolation Actuation Signal CRFSControl Room Filtration SystemCSASContainment Spray Actuation Signal

CSSContainment Spray SystemCVCSChemical and Volume Control System

CVHContainment Vent Header DBADesign Basis Accident DBEDesign Basis Earthquake DNB Departure from Nucleate BoilingDNBRDeparture from Nucleate Boiling Ratio

DRLDivision of Reactor Licensing EB Enclosure Building EBFR Enclosure Building Filtration Region EBFS Enclosure Building Filtration System MPS2 UFSAR (CONTINUED)

Abbreviation LOA 2 of 3ECCSEmergency Core Cooling SystemEOLEnd of Life ESCSEngineered Safety Features Control System FDegrees Fahrenheit FPSFire Protection System FTFuel Transfer FWFeed Water HMPHigh Mechanical Performance HPSIHigh Pressure Safety Injection HTPHigh Thermal Performance IAInstrument Air IDInside Diameter LOCALoss of Coolant Accident LPSILow Pressure Safety Injection MPCMaximum Permissible Concentration MSLMean Sea Level MSSMain Steam System MTUMetric Tons Uranium MWDMegawatt Days NDTNon-Destructive Testing NDTTNil Ductility Transition TemperatureNSNitrogen SupplyNSSSNuclear Steam Supply System OBEOperating Basis Earthquake MPS2 UFSAR (CONTINUED)

Abbreviation LOA 3 of 3ODOutside DiameterPAPurge Air PDHPrimary Drain Header PDTPrimary Drain Tank PPMParts Per Million PVMPPreoperational Vibr ation Monitoring ProgramPWRPressurized Water Reactor RBCCWReactor Building Closed Cooling Water RBCCWSReactor Building Closed Cooling Water System RCSReactor Coolant System RWSRadioactive Waste System RWSTRefueling Water Storage Tank SAStation Air SGBSSteam Generator Blowdown System SIASSafety Injection Actuation Signal SISSafety Injection System SRASSump Recirculation Actuation Signal SRSTSpent Resin Storage Tank SSSampling System TBCCWSTurbine Building Closed Cooling Water SystemWGHWaste Gas HeaderWRECWestinghouse Rector Evaluation CenterWTRWestinghouse Test Reactor MPS2 UFSARLOES 1of8LIST OF EFFECTIVE SECTIONSChapter 1- INTRODUCTION AND

SUMMARY

Table of Contents List of Tables List of Figures

1.1 INTRODUCTION

1.2

SUMMARY

DESCRIPTION1.3 COMPARISON WITH OTHER PLANTS1.4 PRINCIPAL ARCHITECTURAL AND ENGINEERING CRITERIA FOR DESIGN1.5 RESEARCH AND DEV ELOPMENT REQUIREMENTS

1.6 IDENTIFICATION

OF CONTRACTORS

1.7 GENERAL

DESIGN CHANGES SINCE ISSUANCE OF PRELIMINARY SAFETY ANALYSIS REPORT1.8 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.]1.9 TOPICAL REPORTS1.10 MATERIAL INCORPORATED BY REFERENCE1.A AEC GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTSChapter 2 - SITE AND ENVIRONMENT Table of Contents List of Tables

List of Figures2.1 GENERAL DESCRIPTION2.2 POPULATION, LAND USE AND WATER USE2.3 METEOROLOGY2.4 GEOLOGY2.5 HYDROLOGY

2.5 HYDROLOGY

MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 2of82.6 SEISMOLOGY2.7 SUBSURFACE AND FOUNDATIONS2.8 ENVIRONMENTAL MONITORING PROGRAM2.9 ENVIRONMENTAL RADIATION MONITORING PROGRAMChapter 3- REACTOR Table of Contents List of Tables

List of Figures3.1

SUMMARY

DESCRIPTION3.2 DESIGN BASES

3.3 MECHANICAL

DESIGN3.4 NUCLEAR DESIGN AND EVALUATION3.5 THERMAL-HYDRAULIC DESIGN 3.A ANALYSIS OF REACTOR VESSEL INTERNALSChapter 4- REACTOR COOLANT SYSTEM Table of Contents List of Tables

List of Figures4.1 GENERAL SYSTEM DESCRIPTION4.2 DESIGN BASIS

4.3 SYSTEM

COMPONENT DESIGN4.4 MATERIALS COMPATIBILITY4.5 SYSTEM DESIGN EVALUATION

4.6 TESTS

AND INSPECTIONS4.A SEISMIC ANALYSIS OF REACTOR COOLANT SYSTEM MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 3of8Chapter 5- STRUCTURES Table of Contents List of Tables

List of Figures5.1 GENERAL5.2 CONTAINMENT GENERAL DESCRIPTION

5.3 ENCLOSURE

BUILDING5.4 AUXILIARY BUILDING5.5 TURBINE BUILDING

5.6 INTAKE

STRUCTURE5.7 EXTERNAL CLASS I TANKS5.8 SEISMIC DESIGN

5.9 CONSTRUCTION

PRACTICE AND QUALITY ASSURANCE5.A DESCRIPTION OF FINITE ELEMEN T METHOD USED IN CONTAINMENT ANALYSIS5.B JUSTIFICATION FOR LOAD FACT ORS AND LOAD COMBINATIONS USED IN DESIGN EQUATIONS OF CONTAINMENT5.C JUSTIFICATION FOR CAPACITY REDUCTION FACTORS () USED IN DETERMINING CAPACITY OF CONTAINMENT5.D EXPANDED SPECTRUM OF TORNADO MISSILES5.E COMPUTER PROGRAM LIST AND DESCRIPTIONS 5.E.1 COMPUTER PROGRAM APPLICABILITY AND VALIDATION5.E.2 COMPUTER PROGRAM TEST PROBLEM SOLUTIONS5.E.3 COMPUTER PROGRAM TEST PROBLEM SIMILARITIES 5.F CONTAINMENT WATER INTRUSION INTO TENDON GALLERY DURING CONSTRUCTION (1)

MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 4of8Chapter 6- ENGINEERED SA FETY FEATURES SYSTEMS Table of Contents List of Tables

List of Figures6.1 GENERAL6.2 REFUELING WATER STORAGE TANK AND CONTAINMENT SUMP6.3 SAFETY INJECTION SYSTEM6.4 CONTAINMENT SPRAY SYSTEM6.5 CONTAINMENT AIR RECIRCULATION AND COOLING SYSTEM

6.6 CONTAINMENT

POST-ACCIDENT HYDROGEN CONTROL SYSTEM6.7 ENCLOSURE BUILDING FILTRATION SYSTEMChapter 7- INSTRUMENTATION AND CONTROL Table of Contents List of Tables

List of Figures

7.1 INTRODUCTION

7.2 REACTOR

PROTECTIVE SYSTEM7.3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM7.4 REGULATING SYSTEMS

7.5 INSTRUMENTATION

SYSTEM7.6 OPERATING CONTROL STATIONS7.7 CONTROL ROOM ANNUNCIATION

7.8 COMMUNICATION

SYSTEMS7.9 ANTICIPATED TRANSIENTS WITHOUT SCRAM CIRCUITRY7.10 AUXILIARY STEAM LINE BREAK DETECTION/ISOLATION SYSTEM7.11 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 5of8Chapter 8- ELECTRICAL SYSTEMS Table of Contents List of Tables

List of Figures8.0 ELECTRICAL DRAWINGS SU BMITTED TO AEC FOR REVIEW8.1 ELECTRIC POWER8.2 4160-VOLT AND 6900-VOLT SYSTEMS8.3 EMERGENCY GENERATORS8.4 480 VOLT SYSTEM

8.5 BATTERY

SYSTEM8.6 ALTERNATING CURRENT INSTRUMENTATION AND CONTROL8.7 WIRE, CABLE AND RACEWAY FACILITIESChapter 9- AUXILIARY SYSTEMS Table of Contents List of Tables

List of Figures9.1 GENERAL9.2 CHEMICAL AND VOLUME CONTROL SYSTEM9.3 SHUTDOWN COOLING SYSTEM

9.4 REACTOR

BUILDING CLOSED COOLING WATER SYSTEM9.5 SPENT FUEL POOL COOLING SYSTEM9.6 SAMPLING SYSTEM

9.7 COOLING

WATER SYSTEMS9.8 FUEL AND REACTOR COMPONENT HANDLING EQUIPMENT9.9 PLANT VENTILATION SYSTEMS9.10 FIRE PROTECTION SYSTEM9.11 COMPRESSED AIR SYSTEM 9.12 WATER TREATMENT SYSTEM MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 6of89.13 AUXILIARY STEAM SYSTEMChapter 10- STEAM AND POWER CONVERSION SYSTEM Table of Contents List of Tables

List of Figures10.1

SUMMARY

DESCRIPTION10.2 TURBINE GENERATOR 10.3 MAIN STEAM SUPPLY SYSTEM10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEMChapter 11- RADIOACTIVE WASTE PROCESSING AND RADIATION PROTECTION SYSTEMS Table of Contents List of Tables

List of Figures11.1 RADIOACTIVE WASTE PROCESSING SYSTEMS11.2 RADIATION PROTECTION11.A SOURCE TERMS FOR RADIOA CTIVE WASTE PROCESSING AND RELEASES TO THE ENVIRONMENT11.B RADIOACTIVE WASTE PROCESSING OF RELEASES TO ENVIRONMENT11.C DOSES FROM RADIOACTIVE RELE ASES AND COST-BENEFIT ANALYSIS11.D EXPECTED ANNUAL INHALATI ON DOSES AND ESTIMATED AIR CONCENTRATIONS OF RADIOACTIV E ISOTOPES FOR MP2 FACILITIES11.E AIRBORNE ACTIVITY SAMPLING SYSTEM FOR CONTAINMENT, SPENT FUEL AND RADWASTE ATMOSPHERESChapter 12- CONDUCT OF OPERATIONS Table of Contents12.1 ORGANIZATIONAL STRUCTURE 12.2 TRAINING PROGRAM12.3 EMERGENCY PLANNING MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 7of812.4 REVIEW AND AUDIT12.5 PLANT PROCEDURES12.6 RECORDS12.7 PHYSICAL SECURITY PLANS12.8 QUALITY ASSURANCE PROGRAM12.9 DELETED BY PKG FSC MP2-UCR-2011-014Chapter 13- INITIAL TESTS AND OPERATION Table of Contents List of Tables

List of Figures

13.1 DESCRIPTION

OF TH E STARTUP TEST PROGRAM13.2 STARTUP TEST PROGRAM ORGA NIZATION AND RESPONSIBILITIES13.3 ADMINISTRATIVE CONDUCT OF THE STARTUP TEST PROGRAM13.4 MILLSTONE STARTUP GROUP TRAINING PROGRAM13.5 INITIAL INSPECTION AND COMPONENT TESTING PHASE13.6 PREOPERATIO NAL AND A CCEPTANCE TEST PROGRAM13.7 HOT FUNCTIO NAL TEST PROGRAM 13.8 INITIAL FUEL LOADING13.9 INITIAL CRITICALITY 13.10 LOW POWER PHYSICS TESTING13.11 POWER ASCENSION TESTING13.12 PIPING OPERATIONAL TESTING 13.13 ACTIVE VALVES OPERATIONAL TESTING13.A PREOPERATIONAL TEST DESCRIPTIONS MPS2 UFSARLIST OF EFFECTIVE SECTIONS (CONTINUED)LOES 8of8Chapter 14- SAFETY ANALYSIS Table of Contents List of Tables

List of Figures14.0 GENERAL14.1 INCREASE IN HEAT REMOVA L BY THE SECONDARY SYSTEM14.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM14.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW14.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES 14.5 INCREASES IN REACTOR COOLANT SYSTEM INVENTORY14.6 DECREASES IN REACTOR COOLANT INVENTORY14.7 RADIOACTIVE RELEASES FROM A SUBSYSTEM OR COMPONENT14.8 MILLSTONE UNIT 2 FSAR EVENTS NOT CONTAINED IN THE STANDARD REVIEW PLAN Chapter 15- LICENSE RENEWAL Table of Contents List of Tables

15.0 INTRODUCTION

15.1 OVERVIEW OF AGING MANAGEMENT PROGRAMS15.2 PROGRAMS THAT MANAGE THE EFFECTS OF AGING ON STRUCTURES AND COMPONENTS WITHIN THE SCOPE OF LICENSE RENEWAL15.3 TIME-LIMITED AGING ANALYSIS 15.4 TLAA SUPPORT PROGRAMS15.5 EXEMPTIONS 15.6 LICENSE RENEWAL COMMITMENTS MPS2 UFSAR LOET 1 of 15LIST OF EFFECTIVE TABLES Number TitleTable1.1-1 Licensing HistoryTable1.2-1 Summary of Codes and Standard s for Components of Water-Cooled Nuclear Power Units (1)Table1.3-1 Comparison with Other Plants Table1.4-1 Seismic Class I Systems and ComponentsTable1.8-1 Comparison of Preoperational Vibration Monitoring Program Design ParametersTable1.9-1 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 Su rge and Waves on Unit Number 2 StructuresTable 2.5-2 Design Wave ConditionsTable 2.5-3 Roof Surface Area and Number and Size of Roof DrainsTable 2.5-4 All Catch Basins for Elevation Ar ea Draining Into and Runoff Flowing In and Out of a Catch BasinTable3.2-1 Stress Limits for Reactor Vessel Internal StructuresTable3.3-1 Mechanical Design Parameters

• Table3.3-2 Pressurized Water Reactor Prim ary Coolant Water Chemistry Recommended SpecificationsTable3.4-1 Fuel Characteristics for a Representative Reload CoreTable3.4-2 Neutronics Characteristic s for a Representative Reload CoreTable3.4-3 Representative S hutdown Margin RequirementsTable3.5-1 Nominal Reactor and Fuel Design Parameters Table3.5-2 Design Operating Hydr aulic Loads on Vessel InternalsTable3.5-3 Uncertainty Sources fo r DNBR Calculations (DELETED)Table3.A-1 Natural Frequencies for Vertical Seismic Analysis Mathematical Model Table3.A-2 Seismic Stresses in Critical Reactor Internals Components for the Design Basis EarthquakeTable 4.1-1 Reactor Cool ant System VolumesTable4.2-1 Principal Design Parame ters of Reactor Coolant SystemTable4.2-2A Table of Loading Combinations and Primary Stress Limits MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 2 of 15Table4.2-2B Table of Loading Combinations and Primary Stress Limits for the Replacement Reactor Vessel Head and Replacement pressurizerTable4.2-3 Reactor Coolant System Code RequirementsTable4.2-4 Comparison with Safety Guide 26Table4.3-1 Reactor Vessel ParametersTable4.3-2 Steam Generator ParametersTable4.3-3 Main Steam Sa fety Valve ParametersTable4.3-4 Tech Pub Review PKG for T4.3-4Reactor Coolant Pump Parameters Table4.3-5 Reactor Cool ant Piping ParametersTable4.3-6 Pressurizer ParametersTable4.3-7 Quench Tank ParameterTable4.3-8 Pressurizer Spray (R C-100E, RC-100F) Valve ParametersTable4.3-9 Power-Operated Relief Valve Isolation Valve Para meters (RC-403, RC-405)Table4.3-10 Pressurizer Power-Operated Relief Valve Parameters (RC-402, RC-404)Table4.3-11 Pressurizer Safety Valve Parameters (RC-200, RC-201)Table4.3-12 Active and Inactive Valves in the React or Coolant System BoundaryTable4.4-1 Materials Exposed to Coolant Table4.4-2 Reactor Coolant ChemistryTable4.5-1 Reactor Coolant System Component Nozzles, Nozzle Sizes and Nozzle MaterialsTable4.5-2 Reactor Coolant Syst em Heatup and Cooldown LimitsTable4.6-1 RTNDT Determination for Reactor Vessel Base Metal Millstone Unit Number 2Table4.6-2 Charpy V-notch and Drop Weight Test Values - Pressurizer Millstone Unit Number 2Table4.6-3 Charpy V-notch and Drop Weight Test Values - Steam GeneratorTable4.6-4 Charpy V-not ch Values - PipingTable4.6-5 Plate and Weld Metal Chemical AnalysisTable4.6-6 Beltline Mechanical Test Properties - Reactor Ve ssel Surveillance MaterialsTable4.6-7 Tensile Test Properties - Reactor Vessel Surveillance MaterialsTable4.6-8 Summary of Specimens Provided for Each Exposure Location MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 3 of 15Table4.6-9 Capsule Removal ScheduleTable4.6-10 Inspection of Reactor Coolant System Components During Fabrication and ConstructionTable4.6-11 Reactor Coolant Syst em Inspection C-E Requirements Table4.6-12 RT PTS Values at 54 EFPYTable4.6-13 Adjusted Reference Temperatures (ART) ProjectionsTable4.A-1 Natural Frequencies and Dominant Degrees of FreedomTable4.A-2 Seismic Loads on Reactor Coolant System Components for Operational Basis EarthquakeTable5.2-1 Containment Stru cture Analysis SummaryTable5.2-2 Containment Structur e Analysis Summary - Dead Load, Initial Prestress and Live Load (D+KF+L)Table5.2-3 Containment Structur e Analysis Summary - Dead Load, Initial Prestress and Live Load (D+F+L+1.15P)Table5.2-4 Containment Structur e Analysis Summary - Dead Load, Initial Prestress and Live Load, Operating Temperature and OBE (D+F+L+T 0+E) Table5.2-5 Containment Structur e Analysis Summary - Dead Lo ad, Prestress, Live Load, 100% Accident Pressure and Acci dent Temperature (D+F+L+1.0P+T 1)Table5.2-6 Containment Structur e Analysis Summary - Dead Load, Prestress, Operating Temperature, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+T 0+H+R+E 1)Table5.2-6A Deleted by FSARCR 04-MP2-016Table5.2-7 Containment Struct ure Analysis Summary - D ead Load, Prestress, 100%

Accident Pressure, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+1.0P+H+T 1+E 1) Table5.2-8 Containment Struct ure Analysis Summary - D ead Load, Prestress, 125%

Accident Pressure, 125% Thermal Expa nsion Forces of Pipes, Accident Temperature and 125% DBE (D+F+1.25P+1.25H+T 1+1.25E)Table5.2-9 Containment Struct ure Analysis Summary - D ead Load, Prestress, 150%

Accident Pressure, and Acci dent Temperature (D+F+1.5P+T 1)Table5.2-10 Spectrum of Potential Mi ssiles From Inside the ContainmentTable5.2-11 Containment Structur e Isolation Valve InformationTable5.2-12 Containmen t Penetration Piping MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 4 of 15Table5.2-13 Major (1) Containment Isolation ValvesTable5.2-14 Typical Leak Rate M easurement System InstrumentationTable5.2-15 Typical Containment Resistance Temperature Detectors and Dewcell Sensor Volume Weight FractionsTable5.5-1 Maximum Actual Stresses - Turbine Building Table5.8-1 Material Damping Values Table5.9-1 Aggregate TestsTable5.9-2 Cement TestsTable5.9-3 Fly Ash Tests Table5.9-4 Typical Chemical Analysis of Fly Ash UsedTable5.9-5 Allowable Void Limits for Cadwelding Table5.D-1 Impactive Ve locities (fps) of Mi ssiles of Different C dA/W Factors as Picked from the Ground by the Design TornadoTable5.D-2 Kinetic Energy per Ft 2 of Impact AreaTable5.D-3 Radius vs. Velocity FPS/MPH (D=0.882 psi/V 1 = 27 mph)Table5.D-4 Radius vs. Velocity FPS/MPH (D=3 psi/V 1 = 60 mph)Table5.D-5 Velocities of Various Missiles Table5.D-6 Test Data Summary Table 5.D.A-1A Relative Conserva tism in Steps A, B, and CTable 5.D.A-2A Table 5.D.A-3A Table6.1-1 Pipe Rupture Protection RequirementsTable6.1-2 OmittedTable6.1-3 Design Non-Seismic Category I Components Locate d Inside Containment and Enclosure BuildingTable6.1-4 Pipe Rupture Criteria Applicability (Outside Containm ent) Based on Normal Operating Plant ConditionsTable6.2-1 Refueling Water Storage Tank and Containment Sump Table6.3-1 Omitted Table6.3-2 Principal Design Parameters of the Safety Injection System MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 5 of 15Table6.3-3 Shutdown Cooli ng Heat Exchanger DataTable6.3-4 OmittedTable6.3-5 Internal Dimensi ons of Containment Sump Re circulation Piping and ValvesTable6.3-6 Safety Injection System Failure M ode Analysis High Pressure Safety InjectionTable6.3-7 Administrative Error Analys is-Safety Injection System ValvesTable6.3-8 Failure Modes and Effects An alysis for Boron Precipitation ControlTable6.4-1 Containment Spray System Component Design ParametersTable6.4-2 Containment Spray Sy stem Failure Mode AnalysisTable6.5-1 Containment Air Recirculation a nd Cooling Units Materials of ConstructionTable6.5-2 Containment Air Recirculati on and Cooling Units Performance DatadnTable6.5-3 Containment Air Reci rculation and Cooling SystemTable6.6-1 Containment Post Accident Hydr ogen Control Systems Component DescriptionTable6.6-2 Deleted by FSARCR 04-MP2-018 Table6.6-3 OmittedTable6.6-4 Post-Incident Recirculation System Failure Mode Analysis Table6.7-1 Enclosure Building Filtra tion System Component DescriptionTable6.7-2 Enclosure Building Filtra tion System Failure Mode AnalysisTable7.2-1 Reactor Trip and Pretrip Set PointsTable 7.2.1.1-I Parameters Aff ecting Fuel Design LimitTable 7.2.1.1-II Pertinent NSSS parame ters and Monitored VariablesTable 7.2.1.1-III Trip Functions Table 7.2.1.1-IV Trip Variable MonitoredTable 7.3.2.2-1 ESAS Failure Mode Analysis for Containment Pressure ChannelsTable7.4-1 Prohibits on CEAs Table7.5-1 Major Process InstrumentationTable7.5-2 OmittedTable7.5-3 Regulatory Guide 1.97 (Rev. 2)

Accident Monitoring InstrumentationTable7.5-4 Area Radiation Monitors Table7.5-5 Liquid Process/Ef fluent Radiation Monitors MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 6 of 15Table7.5-6 Airborne Process/Effluent Radiation MonitorsTable7.5-6A Process Radi ation Monitors (Steam)Table7.5-7 CEA Position Light MatrixTable7.6-1 Major Equipment Norm ally Used for Hot ShutdownTable7.6-2 Major Equipment Normally Used for Cold Shutdown Table8.3-1 Diesel Fuel Oi l System Mode AnalysisTable8.3-2 "A" Emergency Di esel Generator LoadingTable8.3-3 "B" Emergency Di esel Generator LoadingTable8.5-1 Battery Service Prof ile for Batteries 201A and 201BTable8.7-1 Cable CharacteristicsTable8.7-2 Omitted Table8.7-3 Omitted Table8.7-4 Facility IdentificationTable9.2-1 Chemical and Volume Control System ParametersTable9.2-2 Reactor C oolant and Demineraliz ed Water ChemistryTable9.2-3 Regenerative Heat ExchangerTable9.2-4 Letdown Control ValvesTable9.2-5 Letdown Heat Exchanger Table9.2-6 Ion ExchangersTable9.2-7 Letdown FiltersTable9.2-8 Volume Control Tank Table9.2-9 Charging PumpsTable9.2-10 Concentrated Boric Acid Preparation and StorageTable9.2-11 Boric Acid Pumps and StrainersTable9.3-12 Shutdown Cooling Heat Exchangers Design Basis ParametersTable9.3-13 Shutdown Cooling System Design Parameters Table9.4-1 Reactor Buil ding Closed Cooling Water System ComponentsTable9.4-2 Reactor Building Closed Cooling Water System Failure Mode AnalysisTable9.4-3 Minimum Required RBCCW Flow to Essential Safety-Related Loads LOCA MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 7 of 15 Injection and Recirculation OperationsTable9.5-4 Spent Fuel Pool Monitoring EquipmentTable9.5-5 Components of Spen t Fuel Pool Cooling SystemTable9.7-1 Circulating Water System ComponentsTable9.7-2 Service Water System ComponentsTable9.7-3 Turbine Building Closed Cooling Water Sy stem ComponentsTable9.7-4 Service Water Cooling SystemTable9.8-1 Transfer Tube Isolation ValveTable9.8-2 Spent Fuel Pool Platform Crane Table9.8-3 Spent Fuel Cask CraneTable9.8-4 Failure Mode AnalysisTable9.8-5 Radiation Levels from Heated Junction Thermocouple (R/Hr)

Table9.9-6 Control Element Dr ive Mechanism Cooling SystemTable9.9-7 Containment and En closure Building Purge SystemTable9.9-8 Containment Auxi liary Circulation SystemTable9.9-9 Containment Penetration Cooling SystemTable9.9-10 Penetration Air Cooling RequirementsTable9.9-11 Radwaste Ventilation System Table9.9-12 Nonradioac tive Ventilation SystemTable9.9-13 Engineered Safety Feat ures Room Air Re circulation SystemTable9.9-14 Fuel Handl ing Ventilation SystemTable9.9-15 Main Exhaust SystemTable9.9-16 Control Room Air Conditioning SystemTable9.9-17 Diesel Generator Ventilation Systems Table9.9-18 Turbine Building Ventilation SystemTable9.9-19 Access Control Area Air Conditioning SystemTable9.9-20 Balance of Unit Ventilation System Table9.9-21 Engineered Safety Features Room Air Recirc. System Failure Mode AnalysisTable9.9-22 Control Room Air Conditioning System Failure Mode Analysis MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 8 of 15Table9.9-23 Diesel Generator Ventil ation System Failure Mode AnalysisTable9.9-24 Vital Switchgear Ventilation System Component DescriptionTable9.9-25 Auxiliary Chilled Wate r System Component DescriptionTable9.9-26 Vital Chilled Water System Component DescriptionTable9.9-27 Indoor Design Temperat ures for Significant Plant AreasTable9.11-1 Compressed Air Sy stem Component DescriptionTable9.11-2 Gas Receiver Tanks Safety EvaluationTable9.12-3 Water Treatm ent System ComponentsTable10.1-1 DELETEDTable10.2-1 Turbine Generator Component DescriptionTable10.3-2 Major Component s of Main Steam SystemTable10.3-3 Omitted Table10.3-4 Operating Details for Valve Sy stems Protecting Steam Generations of OverpressureTable10.4-5 Major Components of th e Condensate and Feedwater SystemTable10.4-6 Failure Analysis of Steam Generator Blowdown System ComponentsTable11.1-1 Radioactive Waste Processi ng System Component Description Table11.1-2 Sources and Expect ed Volumes of Solid WastesTable11.1-3 Radioactivity levels of solid wastes (See Note)Table11.1-4 Curie Inventory of Solid Waste Sh ipped from Millstone Unit 2 (See Note)Table11.1-5 Assumptions for Waste Gas Decay Tank AccidentTable11.2-6 Source Terms for Shielding DesignTable11.A-7 Design-Basis and Expected Primary Coolant Activity ConcentrationsTable11.A-8 Calculated Reactor Core ActivitiesTable11.A-9 Expected Annual Effluent Releas es (Curies Per Year), by Radionuclide, from Each Release PointTable11.A-10 Expected Annual Liquid Effluent Activity Releases (Curies/Year), by Radionuclide, from Each Waste StreamTable11.A-11 Expected Annual Liquid Effluent Concentrations (Diluted and Undiluted), by Radionuclide, from Each Waste System MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 9 of 15Table11.A-12 Design Basis Radionuc lide Concentrations in Liquid Effluent, in Fractions of 10CFRPart 20 Concentration LimitsTable11.A-13 Design-Basis Radionuclide Airborne Concentrat ions at the Site Boundary From All Gaseous Effluent Release Points Combined, in Fractions of 10CFRPart 20 Concentration LimitsTable11.A-14 Total Annual Design-Basis and Expected Releases of Radioactive Liquid Waste to the Environment From All Sources Combined, in Curies Per YearTable11.A-15 Total Annual Design Basis and Exp ected Releases of Airborne Radioactive Waste to the Environment From All Release Points Combined, in Curies Per YearTable11.A-16 Basis for Reactor Coolant System Activity NUREG-0017 gale Code InputTable11.B-17 Inputs to PWR-GALE CodeTable11.C-18 Comparison of Calculated Annual Maximum Indivi dual Doses with 10CFRPart 50 AppendixI Design ObjectivesTable11.C-19 Annual Total Body a nd Thyroid Doses to the Populat ion Within 50 Miles of the Millstone Site, In Man-Rem, From Ex pected Liquid and Airborne Effluent ReleasesTable11.D-20 Containment Buil ding Airborne ConcentrationsTable11.D-21 Auxiliary Buildi ng Airborne ConcentrationsTable11.D-22 Turbine Building Airborne ConcentrationsTable13.12-1 Seismic Category I-ASME SectionIII Classes 1 and 2 Piping SystemsTable14.0-1 Reactor Operating Modes For Millstone Unit 2Table14.0-2 Disposition of Events SummaryTable14.0.1-1 Accident Category Us ed For Each Analyzed EventTable14.0.2-1 Plant Operating ConditionsTable14.0.2-2 Nominal Fuel Design ParametersTable14.0.3-1 Core Power Di stribution (TABLE DELETED)Table14.0.3-1 Range of Key Initia l Condition Operating ParametersTable14.0.5-1 Reactivity Pa rameters (TABLE DELETED)Table14.0.7-1 Analytical Trip SetpointsTable14.0.7-2 Uncertainties Applied at HFP Condition in Local Po wer Density Limiting Safety System Settings Calculations MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 10 of 15Table14.0.7-3Uncertainties Applied at HFP Condition in the Thermal Margin/Low Pressure Limiting Safety System Settings CalculationsTable14.0.7-4 Uncertainties Applied at HFP C ondition in the Local Power Density Limiting Condition for Operation CalculationsTable14.0.7-5 Uncertainties Applied in Departur e from Nucleate Boil ing Limiting Condition for Operation CalculationsTable14.0.8-1 Component Capa cities and SetpointsTable14.0.9-1 Overview of Plant Systems a nd Equipment Available for Transient and Accident ConditionsTable14.0.12-1 Nomenclature Us ed in Plotted ResultsTable14.1.1-1 Available Reactor Pr otection for the Decrease in Feedwater Temperature EventTable14.1.1-2 Disposition of Events for the Decrease in Feedwater Temperature EventTable14.1.2-1 Available Reactor Protection for the Increase in Feedwater Flow EventTable14.1.2-2 Disposition of Events for the Increase in Feedwater Flow EventTable14.1.3-1 Available Reactor Protection for the Increase in Steam Flow Event Table14.1.3-2 Disposition of Events fo r the Increase in Steam Flow EventTable14.1.3-3 Initial Conditions for th e Increase in Steam Flow EventTable14.1.3-4 Event Summary for the Increase in Steam Flow Event Table14.1.3-5 Peak Reactor Power Levels for Increase in Steam Flow EventTable14.1.4-1 Available Reactor Pr otection for the Inadvertent Op ening of a Steam Generator Relief or Safety ValvesTable14.1.4-2 Disposition of Events for the Ina dvertent Opening of a Steam Generator Relief or Safety Valve EventTable14.1.5.1-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of ContainmentTable14.1.5.1-2 Disposition of Even ts for Steam System Piping Failures Inside and Outside ContainmentTable14.1.5.1-3 S-RELAP5 Thermal-Hydraulic Input (Pre-Scram Steam Line Break)Table14.1.5.1-4 Actuation Signals and Dela ys (Pre-Scram Steam Line Break)Table14.1.5.1-5 S-RELAP5 Neutronics Input and Assumptions (Pre-Scram Steam Line Break)Table14.1.5.1-6 MDNBR and Peak Reactor Power Level Summary (Pre-Scram Steam Line Break)

MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 11 of 15Table14.1.5.1-7 LHGR-Limiting Pre-Scram Steam Line Break Se quence of Events: HFP 0.20ft 2 Asymmetric Break Inside Containment with Offsite Power AvailableTable14.1.5.1-8 MDNBR-Limiting Pr e-Scram Steam Line Break Sequence of Events: HFP 3.51ft 2 Asymmetric Break Inside Contai nment with Loss of Offsite PowerTable14.1.5.2-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment, Post-Scram AnalysisTable14.1.5.2-2 Disposition of Events for Steam System Piping Failures Inside and Outside of Containment, Post-Scram AnalysisTable14.1.5.2-3 SRELAP5 -Thermal-Hydraulic Input (Post-Scram Steam Line Break)Table14.1.5.2-4 Actuation Signals and Dela ys (Post-Scram Steam Line Break)Table14.1.5.2-5 S-RELAP5 Neutroni cs Input and Assumptions (P ost-Scram Steam Line Break)Table14.1.5.2-6 Post-Scram Steam Li ne Break Analysis SummaryTable14.1.5.2-7 LHGR-Limiting Sequence of Events - HZP Offsite Power AvailableTable14.1.5.2-8 MDNBR-Limiting Post-Scram Steam Line Break Analysis SummaryTable14.1.5.3-1 Assumptions Used in Main Steam Line Break AnalysisTable14.1.5.3-2 Summary of Millst one 2 MSLB Accident DosesTable14.1.5.3-3 Deleted by FS ARCR PKG FSC 07-MP2-006Table14.2.1-1 Available Reactor for th e Loss of External Load EventTable14.2.1-2 Disposition of Events for the Loss of External Load EventTable14.2.1-3 Event Summary for the Loss of External Load Event (Primary Overpressurization Case)Table14.2.1-4 Event Summary for the Loss of External Load Event (Secondary Overpressurization Case)Table14.2.1-5 Event Summary for the Loss of Exte rnal Load Event (Min imum Departure from Nucleate Boiling Ratio Case)Table14.2.2-1 Available Reactor Protection for the Turbine Trip EventTable14.2.2-2 Disposition of Events for the Turbine Trip EventTable14.2.4-1 Available Reactor Protection for the Closure of the Main Steam Isolation Valves EventsTable14.2.4-2 Disposition of Events for the Closur e of the Main Steam Is olation Valves EventsTable14.2.4-3 Event Summary for the Main Stea m Isolation Valve Closure Event (Lower Steam Flow Case)

MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 12 of 15Table14.2.7-1 Available Reactor Protection for the Loss of No rmal Feedwater Flow EventTable14.2.7-2 Disposition of Events for the Loss of Normal Feedwater Flow EventTable14.2.7-3 Sequence of Events for Minimum Steam Generator Invent ory Case: One Motor-Driven AFW Pump Fails to Start with Offsite Power and Steam DumpsTable14.2.7-4 Sequence of Events for Maximum Pressurizer Level Case

Loss of Offsite Power, One Motor-Driven AFW Pump Fails to StartTable14.3.1-1 Available Reactor Protection for the Loss of Fo rced Reactor Coolant Flow EventTable14.3.1-2 Disposition of Events for the Loss of Forced Reactor Coolant Flow Event Table14.3.1-3 Event Summary for the Loss of Forced Reactor Coolant FlowTable14.3.3-1 Available Reactor Protection for th e Reactor Coolant Pump Rotor Seizure EventTable14.3.3-2 Disposition of Events for the Reactor Coolant Pump Rotor Seizure Event Table14.3.3-3 Event Summary for the R eactor Coolant Pump Rotor SeizureTable14.4.1-1 Available Reactor Protection for the Uncont rolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition EventTable14.4.1-2 Disposition of Even ts for the Uncontrolled Cont rol Rod/Bank Wi thdrawal from a Subcritical or Low-Powe r Startup Condition EventTable14.4.1-3 Event Summary for the Uncontrolled Bank Withdrawal from Low-Power Event Table14.4.2-1 Available Reactor Protection for the Uncont rolled Control Rod/Bank Withdrawal at Power EventTable14.4.2-2 Disposition of Events for the Un controlled Control R od/Bank Withdrawal at Power EventTable14.4.2-3 Event Summary for the Uncontroll ed Rod/Bank Withdr awal Event for the Limiting 100% Power CaseTable14.4.3.1-1 Available Reactor Protection for the Dropped Control Rod/Bank EventTable14.4.3.1-2 Disposition of Events fo r the Dropped Control Rod/Bank EventTable14.4.3.1-3 Event Summary for the Li miting Dropped Control Rod/Bank Case Table14.4.3.5-1 Available Reactor Protection for the Single Control Rod Withdrawal EventTable14.4.3.5-2 Disposition of Events for th e Single Control Rod Withdrawal Event Table14.4.4-1 Available Reactor ProtectionTable14.4.4-2 Disposition of Events for th e Startup of an Inactive Loop EventTable14.4.6-1 Available Reactor Protection for Chemical a nd Volume Control System MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 13 of 15Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant EventTable14.4.6-2 Disposition of Events for th e Chemical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor

Coolant EventTable14.4.6-3 Summary of Results for the Boro n Dilution Event Asymme tric Dilution Front ModelTable14.4.6-4 Summary of Results for the Boro n Dilution Event Instantaneous Mixing ModeTable14.4.8-1 Available Reactor Protection for the Spectrum of Control Rod Ejection AccidentsTable14.4.8-2 Disposition of Events for the Spectrum of Control Rod Ejection AccidentsTable14.4.8-3 Event Summary for a Control Ro d Ejection (Maximum Pressurization Case)Table14.4.8-4 Event Summary for a Control Rod Ejection Minimu m Departure from Nucleate Boiling Ratio CaseTable14.4.8-5 dnBounding Beginning of Cycle/End of Cycle Ejected Rod Analysis Table14.4.8-6 CREA Radiologica l Analysis AssumptionsTable14.4.8-7 Radiological C onsequences of a CREATable14.6.1-1 Available Reactor Protection for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pr essure Relief Valve EventTable14.6.1-2 Disposition of Events for the In advertent Opening of a Pressurized Water Reactor Pressurizer Relief Valve EventTable14.6.1-3 Event Summary for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief ValveTable14.6.3-1 Available Reactor Protection for the Radiological Consequences of Steam Generator Tube Rupture EventTable14.6.3-2 Disposition of Events for the Radiological Consequences of Steam Generator Tube Rupture EventTable14.6.3-3 Sequence of Events for the Steam Generator Tube Rupture EventTable14.6.3-4 Mass Releases for the Steam Generator Tube Rupture AccidentTable14.6.3-5 Assumptions for th e Radiological Eval uation for the Steam Generator Tube Rupture EventTable14.6.3-6 Summary - Radiological Consequenc es of the Steam Generator Tube Rupture Event MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 14 of 15Table14.6.5.1-1 Available Reactor Protection for the Large Brea k Loss of Coolant AccidentTable14.6.5.1-2 Disposition of Events for th e Large Break Loss of Coolant AccidentTable14.6.5.1-3 Millstone Unit 2 Syst em Analysis Parameters (Large Break Loss of Coolant Accident Analysis)Table14.6.5.1-4 Millston e Unit 2 Large Break Loss of Coolant Accident AnalysisTable14.6.5.1-5 Millston e Unit 2 Large Break LOCA AnalysisTable14.6.5.1-6 Millston e Unit 2 Large Break LOCA AnalysisTable14.6.5.1-7 Peak Clad Temperature Including All Penalties and Bene fits - Large Break LOCATable14.6.5.2-1 Available Reactor Protection for the Small Break Loss of Coolant AccidentTable14.6.5.2-2 Disposition of Events for th e Small Break Loss of Coolant Accident Table14.6.5.2-3 Millstone Un it 2 Small Break Loss of Coolan t Accident System Analysis ParametersTable14.6.5.2-4 Deleted by FSCR MPS-UCR-2016-016 Table14.6.5.2-5 Calculated Event Times for Small Break Loss-of-Coolant AccidentTable14.6.5.2-6 Analysis Results for Small Break Loss-of-Coolant AccidentTable14.6.5.2-7 Peak Clad Temperature Including All Penalties and Bene fits - Small Break LOCATable14.6.5.3-1 Core and System Parame ters Used in the LTC AnalysisTable14.7.1-1 Deleted by FS ARCR PKG FSC 07-MP2-006Table14.7.4-1 Assumption for Fuel Handling Accident in the Spent Fuel PoolTable14.7.4-2 Assumption for Fuel Ha ndling Accident in ContainmentTable14.7.4-3 Deleted by FSARCR 02-MP2-015 Table14.7.5-1 Assumptions for Spent Fuel Cask Tip Accident Table14.8.2-1 Containment Design ParametersTable14.8.2-2 Initial Conditions for Pressure AnalysesTable14.8.2-3 Minimum Containment Heat Sink Data Table14.8.2-4 Sequence of Events, MP2-MSLB: Loss of Offsite Power and the Failure of Vital Bus VA-10 or VA-20 from 102% PowerTable14.8.2-5 Engineered Safety Features Performance for MSLB Containment Analysis Table14.8.4-1 Loss of Coolant A ccident (Off site Assumptions)

MPS2 UFSAR LIST OF EFFECTIVE TABLES (CONTINUED)

Table Title LOET 15 of 15Table14.8.4-2 Summary of Doses for Loss of Coolant AccidentTable14.8.4-3 Loss of Coolant Acci dent (Control Room Assumptions)Table14.8.4-4 Atmospheric Dispersion Data for Millstone Unit 2 Control RoomTable14.8.4-5 Dose to Millstone Un it 2 Control Room Operators Table15.3-1 Containment Tendon PrestressTable 15.6-1 License Re newal Commitments MPS2 UFSARLOEF 1 of 49LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET 1.2-1FIGURE 1.2-1Site Layout N/A 1.2-2FIGURE 1.2-2Plot Plan 25203-10003 (a)1.2-3FIGURE 1.2-3General Arrangement, Turbine Building Pl an at Operating Floor Elevation 54 Feet 6 Inches25203-27011 (a)1.2-4FIGURE 1.2-4General Arrangement, Turbine Building Pl an at Mezzanine Floor Elevation 31 Feet 6 Inches 25203-27012 (a)1.2-5FIGURE 1.2-5General Arrangement, Turbine Building Plan at Ground Floor Elevation 14 Feet 6 Inches 25203-27013 (a)1.2-6FIGURE 1.2-6General Arrangement Containm ent Plan at Floor Elevation 14 feet 6 inches and Elevation 36 feet 6 inches 25203-27014 (a)1.2-7FIGURE 1.2-7General Arrangement Auxiliary Building Plan at Elevation 36 feet 6 inches and Elevation 38 feet 6 inches 25203-27015 (a)1.2-8FIGURE 1.2-8General Arrangement Auxilia ry Building Sections "G-G" and "H-H" 25203-27016 (a)1.2-9FIGURE 1.2-9General Arrangement Auxiliary Building Ground Floor Elevati on 14 feet 6 inches and Cable Vault Elevation 25 feet 6 inches 25203-27017 (a)1.2-10FIGURE 1.2-10General Arrangement Containmen t and Auxiliary Building Plan at Elevati on (-)5 feet 0 inches and Elevation (-

)3 feet 6 inches 25203-27018 (a)1.2-11FIGURE 1.2-11General Arrangement Containment and Auxiliary Building Plan at Elevation (-)25 feet 6 inches and Elevation (-)22 feet 6 inches 25203-27019 (a)1.2-12FIGURE 1.2-12General Arrangement Cont ainment and Auxiliary Building Plan at Elevation (-)45 feet 6 inches 25203-27020 (a)1.2-13FIGURE 1.2-13General Arrangement Containment and Auxiliary Building Section"A-A" 25203-27021 (a)1.2-14FIGURE 1.2-14General Arrangement Containment and Auxiliary Building Section"B-B" 25203-27022 (a)1.2-15FIGURE 1.2-15General Arrangement Turbine Building Sections "C-C" and "E-E" 25203-27023 (a)

MPS2 UFSARLOEF 2 of 491.2-16FIGURE 1.2-16General Arrangement Turbine Building Sections"D-D" and "F-F" 25203-27024 (a)1.2-17FIGURE 1.2-17General Arrangement Intake Structure Auxiliary Steam Boiler Room Plan and Section 25203-27025 (a)2.4-1FIGURE 2.4-1Geological Features N/A2.4-2aFIGURE 2.4-2aBoring Plan N/A2.4-2bFIGURE 2.4-2bTest Borings N/A2.4-2cFIGURE 2.4-2cBoring Logs N/A2.4-2dFIGURE 2.4-2dBoring Logs N/A2.4-3FIGURE 2.4-3Seismic Line Location Map N/A2.4-4FIGURE 2.4-4Seismic Profiles N/A2.5-1FIGURE 2.5-1Topography in the Vicinity of Millstone Point N/A2.5-2FIGURE 2.5-2Bore Hole and Test Pit Locations N/A2.5-3FIGURE 2.5-3Test Pit Number1 N/A2.5-4FIGURE 2.5-4Test Pit Number2 N/A2.5-5FIGURE 2.5-5Relationship Between Hurricane Wind Direction and Plant LayoutN/A2.5-6FIGURE 2.5-6Section Through Plant N/A2.5-7FIGURE 2.5-7Profiles of Plant N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 3 of 492.5-8FIGURE 2.5-8Surge Hydrograph for PMH N/A2.5-9FIGURE 2.5-9Bottom Profile for Surge Traverse Line N/A2.5-10FIGURE 2.5-10Storm Tracker for Probable Maximum Hurricane N/A2.5-11FIGURE 2.5-11Location of the Center of the Storm Within the Critical AreaN/A2.5-12FIGURE 2.5-12Shore Protection N/A2.5-13FIGURE 2.5-13Shore Protection N/A2.5-14FIGURE 2.5-14Wave Force Diagrams For The Three Zones And Their Corresponding Bottom Profiles Near The WallsN/A 2.5-15FIGURE 2.5-15Typical Anchorage Detail N/A 2.5-16FIGURE 2.5-16Filter System and the Gr adation of the Filter MaterialsN/A 2.5-17FIGURE 2.5-17Scour Protection N/A 2.5-18FIGURE 2.5-18Flood Protection N/A 2.5-19FIGURE 2.5-19General Roof Plan N/A 2.5-20FIGURE 2.5-20Drainage Plan N/A 2.5-21FIGURE 2.5-21Turbine and Auxiliary Building Plans at Elevation 14Feet 6InchesN/A 2.5-22FIGURE 2.5-22Auxiliary Building Basement Plans N/A 2.5-23FIGURE 2.5-23Intake Structure N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 4 of 492.5-24FIGURE 2.5-24Louver Protection - Intake Structure N/A2.7-1FIGURE 2.7-1Excavation Plan N/A2.7-2FIGURE 2.7-2Backfill and Compaction Requirements N/A3.1-1FIGURE 3.1-1Reactor Vertical Arrangement N/A3.1-2FIGURE 3.1-2Reactor Core Cross Section N/A3.3-1FIGURE 3.3-1Fuel Rod Assembly N/A3.3-2AFIGURE 3.3-2AAREVA - Reload Fuel Assembly Batch "S" and PriorN/A3.3-2BFIGURE 3.3-2BAREVA - Reload Fuel Assembly Batch "T" and LaterN/A 3.3-3AFIGURE 3.3-3AAREVA - Reload Fuel Assembly Components Batch "S" and PriorN/A3.3-3BFIGURE 3.3-3BAREVA - Reload Fuel Assembly Components Batch "T" and LaterN/A3.3-4AFIGURE 3.3-4ABi-Metallic Fuel Spacer Assembly N/A3.3-4BFIGURE 3.3-4BHTP Fuel Space Assembly N/A3.3-5FIGURE 3.3-5Fuel Assembly Hold Down Device N/A3.3-6FIGURE 3.3-6Control Element Assembly N/A3.3-7FIGURE 3.3-7Control Elem ent Assembly Materials N/A3.3-8FIGURE 3.3-8Control Element Assemblies Group and Number DesignationN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 5 of 493.3-9FIGURE 3.3-9Core Orientation N/A3.3-11FIGURE 3.3-11Reactor Internals Assembly N/A3.3-12FIGURE 3.3-12Pressure Vessel-Core Support Barrel Snubber AssemblyN/A3.3-13FIGURE 3.3-13Core Shroud Assembly N/A3.3-14FIGURE 3.3-14Upper Guide Structure Assembly N/A3.3-15FIGURE 3.3-15Control Element Drive Mechanism (Magnetic Jack)N/A 3.3-16FIGURE 3.3-16(Left Blank Intentionally)

N/A 3.3-17FIGURE 3.3-17Heated Junction Thermocouple Probe Pressure Boundary Installation N/A 3.3-18FIGURE 3.3-18Typical Heated Junction Ther mocouple Probe Assembly Installation N/A 3.3-19FIGURE 3.3-19Placement of Natural Uranium Re placement Fuel Rods and Fuel Assembly Orientation Relative to the Core Baffle for Cycle19N/A 3.4-1FIGURE 3.4-1Representative Full Core Loading Pattern N/A 3.4-2FIGURE 3.4-2Representative Quarter Core Loading Pattern N/A 3.4-3FIGURE 3.4-3Representative BOC and EOC Exposure DistributionN/A 3.4-4FIGURE 3.4-4Representative Boron Letdown, HFP, ARO N/A 3.4-5FIGURE 3.4-5Representative Normalized Power Distributions, Hot Full Power, Equilibrium Xenon, 150MWD/MTU N/A 3.4-6FIGURE 3.4-6Representative Normalized Power Distribution, Hot Full Power, Equilibrium Xenon, 18,020 MWD/MTUN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 6 of 493.A-1FIGURE 3.A-1Representative Node Locations - Horizontal Mathematical ModelN/A3.A-2FIGURE 3.A-2Mathematical Mode l - Horizontal Seismic Analysis N/A3.A-3FIGURE 3.A-3Mathematical Model - Vertical Seismic Analysis N/A3.A-4FIGURE 3.A-4Core Support Barrel Upper Flange - Finite Element ModelN/A3.A-5FIGURE 3.A-5Core Support Barrel Lower Flange - Finite Element ModelN/A 3.A-6FIGURE 3.A-6Lateral Seismic Model - Mode 1, 3.065 CPS N/A 3.A-7FIGURE 3.A-7Lateral Seismic Model - Mode 2, 5.118 CPS N/A 3.A-8FIGURE 3.A-8Lateral Seismic Model - Mode 2, 5.118 CPS N/A 3.A-9FIGURE 3.A-9Reactor Vessel Flange Ve rtical Response Spectrum (1% Damping)

N/A 3.A-10FIGURE 3.A-10ASHSD Finite Element Model of th e Core Support Barrel/Thermal Shield System N/A3.A-11FIGURE 3.A-11Vertical Shock Model N/A 3.A-12FIGURE 3.A-12Lateral Shock Mode N/A 3.A-13FIGURE 3.A-13SAMMSOR DYNASOR Finite Element Model of Co re Support Barrel N/A 4.1-1FIGURE 4.1-1P&ID for Reactor Coolant System & Pump (Sheet 1) 25203-26014 (a)Sheet 1 of 34.1-1FIGURE 4.1-1P&ID for Reactor Coolant System & Pump (Sheet 2) 25203-26014 (a)Sheet 2 of 34.1-1FIGURE 4.1-1P&ID for Reactor Coolant System & Pump (Sheets 3) 25203-26014 (a)Sheet 3 of 3LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 7 of 494.1-2FIGURE 4.1-2Reactor Coolant System Arrangement-Elevation N/A4.1-3FIGURE 4.1-3Reactor Coolan t System Arrangement-Plan N/A4.3-1FIGURE 4.3-1Reactor Vessel N/A4.3-2FIGURE 4.3-2Steam Generator N/A4.3-3FIGURE 4.3-3Reactor Coolant Pump N/A4.3-4FIGURE 4.3-4P&ID Reactor Coolant Pump 25203-26014 (a)Sheet 3 of 34.3-5FIGURE 4.3-5Reactor Coolant Pump Seal Area N/A4.3-6FIGURE 4.3-6Reactor Coolant Pump Predicted Performance N/A4.3-7FIGURE 4.3-7Pressurizer N/A4.3-8FIGURE 4.3-8Temperature Control Program N/A4.3-9FIGURE 4.3-9Pressurizer Level Setpoint Program N/A4.3-10FIGURE 4.3-10Pressurizer Level Control Program N/A4.3-11FIGURE 4.3-11Quench Tank N/A4.3-12FIGURE 4.3-12Permanent Reactor Cavity Seal Plate N/A4.5-1FIGURE 4.5-1Reactor Coolant System Pressure Te mperature Limitations for 7 Full Power YearsN/A4.5-2FIGURE 4.5-2Reactor Coolant System Pressure - Temp Limitations During Plant Heatup/Cooldown After 7 Years Integrated Neutron FluxN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 8 of 494.5-3FIGURE 4.5-3Reactor Coolant System Pressure Temperature Limitations For 0 to 2 Years of Full PowerN/A4.5-4FIGURE 4.5-4Reactor Coolant System Heatup Limitations for 54 EFPYN/A4.5-5FIGURE 4.5-5Reactor Coolant System Cooldown Limitations for 54EFPY N/A 4.6-1FIGURE 4.6-1Location of Surv eillance Capsule Assemblies N/A 4.6-2FIGURE 4.6-2Typical Surveillance Capsule Assembly N/A 4.6-3FIGURE 4.6-3Typical Charpy Impact Compartment Assembly N/A 4.6-4FIGURE 4.6-4Typical Tensile-Monitor Compartment Assembly N/A 4.6-5FIGURE 4.6-5Base Metal - WR (Transverse) Plate C-506-1 Impact Energy vs TemperatureN/A 4.6-6FIGURE 4.6-6Base Metal - WR (T ransverse) Plate C-506-1 Lateral Expansion versus TemperatureN/A 4.6-7FIGURE 4.6-7Base Metal - RW (Longitudinal) Plate C-506-1 Impact Energy versus TemperatureN/A 4.6-8FIGURE 4.6-8Base Metal - RW (Longitudinal) Plate C-506-1 Lateral Expansion vs TemperatureN/A 4.6-9FIGURE 4.6-9WELD Metal PLATE C-506-2/C-506-3 IMPACT ENERGY vs TemperatureN/A 4.6-10FIGURE 4.6-10Weld Metal, Plate C-506-2/C-506-3 Lateral Expansion vs TemperatureN/A4.6-11FIGURE 4.6-11HAZ Metal, Plate C-506-1 Impact Energy versus TemperatureN/A 4.6-12FIGURE 4.6-12HAZ Metal, Plate C-506-1 La teral Expansion versus TemperatureN/A 4.6-13FIGURE 4.6-13SRM (HSST Plate 01MY - Longitudinal) Impact Energy versus TemperatureN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 9 of 494.6-14FIGURE 4.6-14SRM (HSST Plate 01MY - Longitudina l) Lateral Expansion versus TemperatureN/A 4.A-1FIGURE 4.A-1Reactor Coolant Syst em Seismic Analysis Model MS2N/A 4.A-1AFIGURE 4.A-1AReactor Coolant System - Seismic Analysis Model MS2 and RV14 N/A 4.A-2FIGURE 4.A-2RV14 Reactor and Internals Seismic Analysis ModelN/A 4.A-3FIGURE 4.A-3Pressurizer Seismic Analysis Model N/A 4.A-4FIGURE 4.A-4Surge Line Seismic Analysis Model N/A 5.2-1FIGURE 5.2-1Containment Structure Details N/A 5.2-2FIGURE 5.2-2Containment Structure Details N/A 5.2-3FIGURE 5.2-3Design Thermal Gradient N/A 5.2-4FIGURE 5.2-4Equipment Hatch Details N/A 5.2-5FIGURE 5.2-5Personnel Lock Details N/A 5.2-6FIGURE 5.2-6Liner Plate N/A 5.2-7FIGURE 5.2-7Leak Chase Channels N/A 5.2-8FIGURE 5.2-8Typical Penetrations N/A 5.2-9FIGURE 5.2-9Bracket Details N/A 5.2-10FIGURE 5.2-10Liner Plate Details N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 10 of 495.2-11FIGURE 5.2-11Reactor Vessel Support Details N/A 5.2-12FIGURE 5.2-12Lower Steam Generator Support Details N/A 5.2-13FIGURE 5.2-13Upper Steam Generator Support Details N/A 5.2-14FIGURE 5.2-14Primary and Secondary Shield Wall N/A 5.2-15FIGURE 5.2-15Detail - Seismic Restraint N/A 5.2-16FIGURE 5.2-16Finite Element Mesh of Bottom of Containment ShellN/A 5.2-17FIGURE 5.2-17Finite Element Mesh of Top of Containment Shell N/A 5.2-18FIGURE 5.2-18Finite Element Mesh of Containment Shell for Stressing SequenceN/A 5.2-19FIGURE 5.2-19Containment Structure Stress Analysis Summary, Dead Load and Initia l Prestress, Live Load N/A 5.2-20FIGURE 5.2-20Containment Structure Stress Analysis Summary, Dead Load, Live Load, Prestress and Test Pressure N/A 5.2-21FIGURE 5.2-21Containment Structure Stress Analysis Summary, De ad Load, Live Load, Prestress, Operating Temperature and DB EN/A 5.2-22FIGURE 5.2-22Containment Structure Stress Analysis Summary, De ad Load, Live Load, Prestress, 100% Accident Pressure and Accident Temperature N/A 5.2-23FIGURE 5.2-23Containment Structure Stress Analysis Summary, Dead Load, Prestress, Operating Temperature, Thermal Expansio n Forces of Pipes, Pipe Rupture Forces and DBE N/A 5.2-24FIGURE 5.2-24Containment Structure Stress Analysis Summary, Dead Load, Prestress, 100% Accide nt Pressure, Thermal Expansi on Forces of Pipes, Accident Te mperature and DBE N/A 5.2-25FIGURE 5.2-25Containment Structure Stress Analysis Summary, Dead Load, Prestress, 125% Acci dent Pressure, 125% Thermal Ex pansion Forces of Pipes, Accident Temperature and 125% OBE N/A 5.2-26FIGURE 5.2-26Containment and Structure Stress Analysis Summary, Dead Load, Prestres s, 150% Accident Pressure and Accident TemperatureN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 11 of 495.2-27FIGURE 5.2-27Isolation Valve Arrangements N/A5.2-28FIGURE 5.2-28Isolation Valve Arrangements N/A5.2-29FIGURE 5.2-29Isolation Valve Arrangements N/A5.2-30FIGURE 5.2-30Isolation Valve Arrangements N/A5.2-31FIGURE 5.2-31Isolation Valve Arrangements N/A5.2-32FIGURE 5.2-32Isolation Valve Arrangements N/A5.2-33FIGURE 5.2-33Isolation Valve Arrangements N/A5.2-34FIGURE 5.2-34Isolation Valve Arrangements N/A5.2-35FIGURE 5.2-35Reactor Coolant System Plan N/A5.2-36FIGURE 5.2-36Reactor Coolant System Elevation N/A 5.2-37FIGURE 5.2-37Deleted by FSARCR 04-MP2-016 N/A 5.3-1FIGURE 5.3-1Enclosure Building N/A 5.3-2FIGURE 5.3-2Enclosure Building Layout N/A 5.3-3FIGURE 5.3-3Waterproof Membrane Details N/A 5.3-4FIGURE 5.3-4Waterproof Membrane Details N/A 5.3-5FIGURE 5.3-5Spent Fuel Cask Travel Limits N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 12 of 495.4-1FIGURE 5.4-1Probable Missile Trajectories Inside Auxiliary BuildingN/A5.4-2FIGURE 5.4-2Missile Resistant Siding Detail N/A5.4-3FIGURE 5.4-3Location of Missile Resistant Siding N/A5.5-1FIGURE 5.5-1Joint Detail at Turbine Pedestal N/A5.5-2FIGURE 5.5-2Joint Detail at Col. Line E N/A5.6-1FIGURE 5.6-1Intake Structure Layout N/A5.6-2FIGURE 5.6-2C. W. System - Plan N/A5.8-1FIGURE 5.8-1Recommended Damped Response Spectra 9%g Acceleration, Operating Basis EarthquakeN/A5.8-2FIGURE 5.8-2Recommended Damped Response Spectra 17%g Acceleration, Design Basis EarthquakeN/A5.8-3FIGURE 5.8-3Recommended Damped Response Spectra 9%g Acce leration, Operating Basis Earthquake (Soil Surface)N/A5.8-4FIGURE 5.8-4Recommended Damped Response Spectra, 17%g Acceleration, Design Basis Earthquake (Soil Surface)N/A5.8-5FIGURE 5.8-5Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Cri tical Damping = 0.5%)

N/A5.8-6FIGURE 5.8-6Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Cri tical Damping = 1%)

N/A5.8-7FIGURE 5.8-7Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Cri tical Damping = 2%)

N/A5.8-8FIGURE 5.8-8Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Cri tical Damping = 5%)

N/A5.8-9FIGURE 5.8-9Response Spectra from the Time History Design Earthquake with Various Frequency IntervalsN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 13 of 495.8-10FIGURE 5.8-10Comparison of Response Spectra with 1952 Taft and 1940 El Centro Earthquake N/A5.8-11FIGURE 5.8-11Foundation Outline N/A 5.8-12FIGURE 5.8-12Sections A-A & B-B N/A 5.8-13FIGURE 5.8-13Auxiliary Bay of Turbine Building N/A 5.8-14FIGURE 5.8-14Containment Mass Model N/A 5.8-15FIGURE 5.8-15Mode Shapes for the Containment Building N/A 5.8-16FIGURE 5.8-16Containment Building Design Earthquake 9% Ground Acceleration N/A 5.8-17FIGURE 5.8-17Containment Building Desi gn Earthquake 17% Ground Acceleration N/A 5.8-18FIGURE 5.8-18Containment Structur e Elevation 53 feet 0 inches N/A 5.8-19FIGURE 5.8-19Containment Structur e Elevation 97 feet 0 inches N/A 5.8-20FIGURE 5.8-20Containment Structur e Elevation 152 feet 6 inches N/A 5.8-21FIGURE 5.8-21Containment Internals Model N/A 5.8-22FIGURE 5.8-22Mode Shapes & Frequencies Containment Internals - North-SouthN/A 5.8-23FIGURE 5.8-23Mode Shapes & Frequencies Containment Internals - North-South OBE (DBE)N/A 5.8-24FIGURE 5.8-24Mode Shapes & Frequencies Containment Internals - East-WestN/A 5.8-25FIGURE 5.8-25Containment Internals - East-West OBE (DBE)

N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 14 of 495.8-26FIGURE 5.8-26Containment Internals Elevation 0 feet 0 inches - OBE (North-South) Reactor Vessel SupportN/A5.8-27FIGURE 5.8-27Containment Internals Elevation 0 feet 0 inches - OBE (East-West) Reactor Vessel SupportN/A5.8-28FIGURE 5.8-28Containment Internals Elevation 14 feet 6 inches - OBE (North-South) Pressurizer SupportN/A5.8-29FIGURE 5.8-29Containment Internals Elevation 14 feet 6 inches - OBE (East-West) Pressurizer SupportN/A5.8-30FIGURE 5.8-30Containment Internals Elevation 38 feet 6 inches - OBE (North-South) Safety Injection Tank SupportN/A5.8-31FIGURE 5.8-31Containment Internals Elevation 38 feet 6 inches - OBE (East-West) Safety Injection Tank SupportN/A5.8-32FIGURE 5.8-32Containment Internals Elevation 43 feet 0 inches - OBE (North-South) Steam Generator Upper Support (Snubbers)N/A 5.8-33FIGURE 5.8-33Containment Internals Elevation 43 feet 0 inches - OBE (East-West) Steam Ge nerator Upper Support (Snubbers)

N/A 5.8-34FIGURE 5.8-34Containment Internals Elevation 50 feet 0 inches - OBE (North-South) Steam Ge nerator Upper Support (Shear Ke ys)N/A 5.8-35FIGURE 5.8-35Containment Internals Elevation 50 feet 0 inches - OBE (East-West) Steam Generator Upper Support (Shear Keys)N/A 5.8-36FIGURE 5.8-36Containment Internals Elevation0 feet 0 inches - OBE (North-South) Steam Generator Lower SupportN/A 5.8-37FIGURE 5.8-37Containment Internals Elevation 0 feet 0 inches - OBE (East-West) Stea m Generator Lower SupportN/A 5.8-38FIGURE 5.8-38Auxiliary Building Model N/A 5.8-39FIGURE 5.8-39Mode Shapes & Frequencie s Auxiliary Building - North-SouthN/A 5.8-40FIGURE 5.8-40Auxiliary Buildi ng - North-South OBE (DBE)

N/A 5.8-41FIGURE 5.8-41Mode Shapes & Frequencies Auxiliary Building - East-WestN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 15 of 495.8-42FIGURE 5.8-42Auxiliary Building - East-West OBE (DBE)

N/A5.8-43FIGURE 5.8-43Auxiliary Buildi ng Elevation 14 feet 6 inches N/A5.8-44FIGURE 5.8-44Auxiliary Buildi ng Elevation 38 feet 6 inches N/A5.8-45FIGURE 5.8-45Auxiliary Buildi ng Elevation 71 feet 6 inches N/A5.8-46FIGURE 5.8-46Warehouse Model N/A5.8-47FIGURE 5.8-47Mode Shapes & Frequencies Warehouse Bldg. - East-WestN/A5.8-48FIGURE 5.8-48Mode Shapes & Frequencies Warehouse Bldg. - North-SouthN/A5.8-49FIGURE 5.8-49Warehouse Bldg. - OBE (DBE)

N/A5.8-50FIGURE 5.8-50Warehouse Elevation 38 feet 6 inches N/A5.8-51FIGURE 5.8-51Turbine Building Model N/A5.8-52FIGURE 5.8-52Mode Shapes & Frequencies Turbine Bldg. - North-SouthN/A5.8-53FIGURE 5.8-53Turbine Bldg. OBE (DBE) East-West N/A5.8-54FIGURE 5.8-54Mode Shapes & Frequencies Turbine Bldg. - East-WestN/A5.8-55FIGURE 5.8-55Turbine Bldg. OBE (DBE) North-South N/A5.8-56FIGURE 5.8-56Turbine Building Elevation 31 feet 6 inches N/A5.8-57FIGURE 5.8-57Turbine Building Crane - OBE N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 16 of 495.8-58FIGURE 5.8-58Intake Structure Model N/A5.8-59FIGURE 5.8-59Intake Structure OBE (DBE)

N/A5.8-60FIGURE 5.8-60Mode Shapes & Frequencies Intake Structure N/A5.8-61FIGURE 5.8-61Intake Structure El evation 14 feet 0 inches OBE N/A5.A-1FIGURE 5.A-1Thick Walled Cylinder With Internal Pressure N/A5.D-1FIGURE 5.D-1Tangential Velocities as Derived from Hoecker's Pressure - Time ProfileN/A 5.D-2FIGURE 5.D-2Monthly Weather Review - Hoecker N/A 5.D-3FIGURE 5.D-3Test Data Summary N/A 5.D-1AFIGURE 5.D-1APlan of Spent Fuel Area N/A 5.D-2AFIGURE 5.D-2ASpent Fuel Pool Section View N/A 5.D-3AFIGURE 5.D-3AMissile Strike Angle to Missile Proof Siding N/A 6.1-1FIGURE 6.1-1Safety Injection P&ID (Sheet 1) 25203-26015 (a)Sheet 1 of 36.1-1FIGURE 6.1-1Safety Injection P&ID (Sheet 2) 25203-26015 (a)Sheet 2 of 36.1-1FIGURE 6.1-1Safety Injection P&ID (Sheet 3) 25203-26015 (a)Sheet 3 of 36.1-2FIGURE 6.1-2Main Steam Pipe Whip Restraint N/A6.1-3FIGURE 6.1-3Pipe Restraint Design N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 17 of 496.1-4FIGURE 6.1-4Fluid Jet Expansion Model N/A6.3-1FIGURE 6.3-1Safety Injection and Containment Spray Pumps Suction Piping N/A 6.3-2FIGURE 6.3-2High Pressure Safety Injection Pump Performance N/A 6.3-3FIGURE 6.3-3Low Pressure Safety Injection Pump Performance N/A 6.4-1FIGURE 6.4-1Area 5 Piping Containment Spray and Hydrogen PurgeN/A 6.4-2FIGURE 6.4-2Containment Spray Nozzles Spray Pa tterns (1713A Nozzle Spraying Horizontally)N/A 6.4-3FIGURE 6.4-3Containment Spray No zzles Spray Patterns (1713A Nozzle Spraying Downward on 45°)N/A 6.4-4FIGURE 6.4-4Containment Spray Nozz les Spray Patterns (1713A Nozzle Spraying Vertically Downward)N/A 6.4-4AFIGURE 6.4-4ATypical Spray Coverage Patterns N/A 6.4-5FIGURE 6.4-5Not Used N/A 6.4-6FIGURE 6.4-6Not Used N/A 6.4-7FIGURE 6.4-7Containment Spray Nozz le Performance Characteristics N/A 6.4-8FIGURE 6.4-8Containment Spray Pump Performance Char acteristics.

N/A 6.4-9FIGURE 6.4-9Containment Heat Removal Systems Sink SchematicN/A 6.5-1FIGURE 6.5-1Containment Air Recirculation and Cooling Un it Fan Performance CurveN/A 6.5-2FIGURE 6.5-2Containment Air Recirculation and Co oling Unit Coil Perfor mance CharacteristicsN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 18 of 496.6-1FIGURE 6.6-1Post-Incident Recirculation Fan Perfor mance Characteristics N/A 6.7-3FIGURE 6.7-3Enclosure Building Filtra tion System Fan Performance CurveN/A 7.2-1FIGURE 7.2-1Reactor Protecti ve System Block Diagram 7.2-2FIGURE 7.2-2Reactor Protective System Functional Diagram 25203-29193 (a)Sheet 1 7.2-3FIGURE 7.2-3Nuclear Instrumentat ion System Functional Diagram7.2-4FIGURE 7.2-4Low Flow Protective System Functional Diagram7.2-5FIGURE 7.2-5Low Steam Generator Pressure Reactor Trip Bypass Functional Diagram7.2-6FIGURE 7.2-6Block Diagram Core Protection Trips 7.2-7FIGURE 7.2-7Neutron Flux Monitoring System Logarithmic Range Channels7.2-8FIGURE 7.2-8Neutron Flux Monitori ng System Power Range Channels7.2-9FIGURE 7.2-9Not Used 7.2-10FIGURE 7.2-10Reactor Coolant Pump Underspeed Block Diagram 7.2-11FIGURE 7.2-11Variable High Power Trip Operation 7.2-12FIGURE 7.2-12Thermal Margin Trip 7.2-13FIGURE 7.2-13T Power Calculation7.2-14FIGURE 7.2-14Local Power Density TripLIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 19 of 497.3-1FIGURE 7.3-1Engineered Safety Logic 25203-28150 (a)Sheet 1 7.3-2AFIGURE 7.3-2AEngineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)Sheet 2A 7.3-2BFIGURE 7.3-2BEngineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)Sheet 2B 7.3-2CFIGURE 7.3-2CEngineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)Sheet 2C 7.3-2DFIGURE 7.3-2DEngineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)Sheet 2D 7.3-3FIGURE 7.3-3Engineered Safety Logic Sequencer & Channel 5 Output 25203-28150 (a)Sheet 3 7.3-4FIGURE 7.3-4Engineered Safety Logic 25203-28150 (a)Sheet 4 7.4-1FIGURE 7.4-1Deleted by FSARCR 05-MP2-026 N/A7.4-2FIGURE 7.4-2CEA Position Setpoints N/A7.4-3FIGURE 7.4-3CEDS Functional Block Diagram 25203-29155 (a)Sheet 9 7.4-4FIGURE 7.4-4Pressure Control Program N/A7.4-5FIGURE 7.4-5Steam Dump to Condensers and Turbine Bypass SystemN/A7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 1) 25203-39220 (a)Sheet 7A 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 2) 25203-39220 (a)Sheet 7B 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 3) 25203-39220 (a)Sheet 8A 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 4) 25203-39220 (a)Sheet 8B LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 20 of 497.4-6FIGURE 7.4-6Feedwater Control System (Sheet 5) 25203-39220 (a)Sheet 9A 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 6) 25203-39220 (a)Sheet 9B 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 7) 25203-39220 (a)Sheet 10A 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 8) 25203-39220 (a)Sheet 10B 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 9) 25203-39220 (a)Sheet 11A 7.4-6FIGURE 7.4-6Feedwater Control System (Sheet 10) 25203-39220 (a)Sheet 11B 7.4-7FIGURE 7.4-7Feedwater Regulating System Block Power DistributionN/A 7.4-8FIGURE 7.4-8Reactivity Control System N/A 7.4-9FIGURE 7.4-9Motion Inhibit Circuit In terconnection Simplified DiagramN/A 7.5-1FIGURE 7.5-1Pressurizer Pressure Meas urement Channel Functional DiagramN/A 7.5-2FIGURE 7.5-2Out-Of-Core Nu clear Detector Location N/A 7.5-3FIGURE 7.5-3In-Core Nuclear Detector Assembly N/A 7.5-4FIGURE 7.5-4In-Core Detector/Core Exit Thermocouple and RVLM Sensor Locations N/A 7.5-5FIGURE 7.5-5Process Radiation Monitor Schematic N/A 7.5-6FIGURE 7.5-6Heated Junction Thermocouple Probe Assembly N/A 7.5-7FIGURE 7.5-7ICCMS Functional Block Diagram N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 21 of 497.5-8FIGURE 7.5-8ICCMS Data Processing N/A7.5-9FIGURE 7.5-9ICCMS Display Hierarchy N/A 7.6-1FIGURE 7.6-1General Arrangement Control Room Plan Elevation 35 feet 6 inches 25203-27027 (a)7.6-2FIGURE 7.6-2C01, CRP, Front View Arra ngement Safeguards Section (Sheet 1) 25203-30208 (a)Sheet 1 of 4 7.6-2FIGURE 7.6-2C01, CRP, Front View Arra ngement Safeguards Section (Sheet 2) 25203-30208 (a)Sheet 2 of 4 7.6-2FIGURE 7.6-2C01, CRP, Front View Arra ngement Safeguards Section (Sheet 3) 25203-30208 (a)Sheet 3 of 4 7.6-2FIGURE 7.6-2C01, CRP, Front View Arra ngement Safeguards Section (Sheet 4) 25203-30208 (a)Sheet 4 of 4 7.6-3FIGURE 7.6-3CRP Front View Arrangements (Sheet 1) 25203-30209 (a)Sheet 1 of 2 7.6-3FIGURE 7.6-3CRP Front View Arrangements (Sheet 2) 25203-30209 (a)Sheet 2 of 2 7.6-3FIGURE 7.6-3CRP Front View Arrangements (Sheet 3) 25203-30210 (a)Sheet 1 of 2 7.6-3FIGURE 7.6-3CRP Front View Arrangements (Sheet 4) 25203-30210 (a)Sheet 2 of 2 7.6-4FIGURE 7.6-4C04 CRP, Front View Arrangement Reactivity Control System (Sheet 1)25203-30211 (a)Sheet 1 7.6-4FIGURE 7.6-4C04 CRP, Front View Arrangement Reactivity Control System (Sheet 2)25203-30211 (a)Sheet 2 7.6-4FIGURE 7.6-4C04 CRP, Front View Arrangement Reactivity Control System (Sheet 3)25203-30211 (a)Sheet 3 7.6-4FIGURE 7.6-4C04 CRP, Front View Arrangement Reactivity Control System (Sheet 4)25203-30211 (a)Sheet 4 7.6-5FIGURE 7.6-5C05, CRP, Front View Arrangement Steam Generator

& Feedwater Control (Sheets 1) 25203-30212 (a)Sheet 1 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 22 of 497.6-5FIGURE 7.6-5C05, CRP, Front View Arrangement Steam Generator

& Feedwater Control (Sheet 2) 25203-30212 (a)Sheet 2 7.6-5FIGURE 7.6-5C05, CRP, Front View Arrangement Steam Generator

& Feedwater Control (Sheet 3) 25203-30212 (a)Sheet 3 7.6-5FIGURE 7.6-5C05, CRP, Front View Arrangement Steam Generator

& Feedwater Control (Sheet 4) 25203-30212 (a)Sheet 47.6-6FIGURE 7.6-6C06, CRP. Front View A rrangement Plant Auxiliary (Sheet 1) 25203-30213 (a)Sheet 1 of 2 7.6-6FIGURE 7.6-6C06, CRP. Front View A rrangement Plant Auxiliary (Sheet 2) 25203-30213 (a)Sheet 2 of 2 7.6-7FIGURE 7.6-7C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 1) 25203-30214 (a)Sheet 1 of 4 7.6-7FIGURE 7.6-7C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 2) 25203-30214 (a)Sheet 2 of 4 7.6-7FIGURE 7.6-7C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 3) 25203-30214 (a)Sheet 3 of 4 7.6-7FIGURE 7.6-7C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 4) 25203-30214 (a)Sheet 4 of 4 7.6-8FIGURE 7.6-8C08, CRP Front View Arrangement Station Service Electric (Sheet 1) 25203-30215 (a)Sheet 1 of 4 7.6-8FIGURE 7.6-8C08, CRP Front View Arrangement Station Service Electric (Sheet 2) 25203-30215 (a)Sheet 2 of 4 7.6-8FIGURE 7.6-8C08, CRP Front View Arrangement Station Service Electric (Sheet 3) 25203-30215 (a)Sheet 3 of 4 7.6-8FIGURE 7.6-8C08, CRP Front View Arrangement Station Service Electric (Sheet 4) 25203-30215 (a)Sheet 4 of 4 7.6-9FIGURE 7.6-9Local Control Panels (C60) & (C61) 25203-28006 (a)Sheet 1 of 3 7.6-10FIGURE 7.6-10Local Control Panels (C63) & (C21) 25203-28006 (a)Sheet 2 of 3 7.6-11FIGURE 7.6-11Engineered Safety Equipment Status Panel Layout (C01X) 25203-30071 (a) LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 23 of 497.6-12FIGURE 7.6-12Condensate Demineralizer Waste Treating Panel CDXN/A7.6-13FIGURE 7.6-13Condensate Demineralizer Waste Treating Panel CDXN/A7.6-14FIGURE 7.6-14Condensate Demineralizer Waste Treating Panel CDXN/A7.6-15FIGURE 7.6-15Condensate Demineralizer Waste Treating Panel CDXN/A7.9-1FIGURE 7.9-1Logic Diagram - Anticipated Transient Without Scram 25203-28105 (a)Sheet 36 7.9-2FIGURE 7.9-2Block Diagram Diverse SCRAM System (ATWS) 25203-37005 (a)Sheet 105 7.9-3FIGURE 7.9-3Schematic Diagram Diverse SCRAM System ATWS 25203-32012 (a)Sheet 48 7.10-1FIGURE 7.10-1Piping and Instrumentation Diagram Auxiliary Steam and Condensate 25203-26026 (a)Sheet 2 of 5 8.1-1AFIGURE 8.1-1ADeleted by FSARCR MP2-UCR-2016-007 N/A8.1-1BFIGURE 8.1-1BHunts Brook Junction N/A8.1-1CFIGURE 8.1-1C345 kV Transmission Map of Connecticut and Western MassachusettsN/A8.1-1DFIGURE 8.1-1D345 kV Switchyard N/A8.2-1FIGURE 8.2-1Main Single Line Diagram 25203-30001 (a)8.3-1FIGURE 8.3-1Logic Diagrams Di esel Generators (Sheet A) 25203-30034 (a)Sheet 1 8.3-1FIGURE 8.3-1Logic Diagrams Diesel Generators (Sheet B) 25203-30034 (a)Sheet 2 8.3-2FIGURE 8.3-2Diesel Generator Related (Sheet 0A) 25203-32041 (a)Sheet A LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 24 of 498.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 1) 25203-32041 (a)Sheet 1 8.3-2FIGURE 8.3-2Diesel Generator Related (Sheet 1A) 25203-32041 (a)Sheet 1A8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 2) 25203-32041 (a)Sheet 28.3-2FIGURE 8.3-2Diesel Generator Related (Sheet 2A) 25203-32041 (a)Sheet 2A 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 3) 25203-32041 (a)Sheet 3 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 4) 25203-32041 (a)Sheet 4 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 5) 25203-32041 (a)Sheet 5 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 6) 25203-32041 (a)Sheet 6 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 7) 25203-32041 (a)Sheet 7 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 8) 25203-32041 (a)Sheet 8 8.3-2FIGURE 8.3-2Diesel Gene rator Related (Sheet 9) 25203-32041 (a)Sheet 9 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 10) 25203-32041 (a)Sheet 10 8.3-2FIGURE 8.3-2Diesel Generator Related (Sheet 11) 25203-32041 (a)Sheet 11 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 12) 25203-32041 (a)Sheet 12 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 13) 25203-32041 (a)Sheet 13 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 14) 25203-32041 (a)Sheet 14 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 25 of 498.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 15) 25203-32041 (a)Sheet 15 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 16) 25203-32041 (a)Sheet 16 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 17) 25203-32041 (a)Sheet 17 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 18) 25203-32041 (a)Sheet 18 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 19) 25203-32041 (a)Sheet 19 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 20) 25203-32041 (a)Sheet 20 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 21) 25203-32041 (a)Sheet 21 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 22) 25203-32041 (a)Sheet 22 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 23) 25203-32041 (a)Sheet 23 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 24) 25203-32041 (a)Sheet 24 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 25) 25203-32041 (a)Sheet 25 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 26) 25203-32041 (a)Sheet 26 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 27) 25203-32041 (a)Sheet 27 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 28) 25203-32041 (a)Sheet 28 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 29) 25203-32041 (a)Sheet 29 8.3-2FIGURE 8.3-2Diesel Genera tor Related (Sheet 30) 25203-32041 (a)Sheet 30 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 26 of 498.3-3FIGURE 8.3-3Not Used8.3-4FIGURE 8.3-4Diesel Generator Fuel Oil System/Auxiliary Steam Condensate and Heater Index (Sheets 1) 25203-26010 (a)Sheet 1 of 1 8.3-4FIGURE 8.3-4Diesel Generator Fuel Oil System/Auxiliary Steam Condensate and Heater Index (Sheet 2) 25203-26026 (a)Sheet 3 of 5 8.3-4FIGURE 8.3-4Diesel Generator Fuel Oil System/Auxiliary Steam Condensate and Heater Index (Sheet 3) 25203-26026 (a)Sheet 4 of 5 8.3-5FIGURE 8.3-5Diesel Generators' Ancillary Systems (Sheet 1A) 25203-26018 (a)Sheet 4 of 5 8.3-5FIGURE 8.3-5Diesel Generators' Ancillary Systems (Sheet 1B) 25203-26018 (a)Sheet 5 of 5 8.3-5FIGURE 8.3-5Diesel Generators

' Ancillary Systems (Sheet 2) 25203-26018 (a)Sheet 2 of 5 8.3-5FIGURE 8.3-5Diesel Generators

' Ancillary Systems (Sheet 3) 25203-26018 (a)Sheet 3 of 5 8.4-1FIGURE 8.4-1Charging Pump -

Power Supply Crossover P18B 25203-32009 (a)Sheet 42 8.4-2FIGURE 8.4-2Service Water Strainer ML1B Power Supply Crossover Scheme 25203-32013 (a)Sheet 39 8.5-1FIGURE 8.5-1Single Line Diagram 125 VDC / VAC Systems (Sheet 1) 25203-30024 (a)8.5-1FIGURE 8.5-1Single Line Diagram 125 VDC / VAC Systems (Sheet 2) 25203-30023 (a)8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 1) 25203-32045 (a)Sheet 1 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 2) 25203-32045 (a)Sheet 2 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 3) 25203-32045 (a)Sheet 3 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 4) 25203-32045 (a)Sheet 4 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 27 of 498.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 5) 25203-32045 (a)Sheet 5 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 6) 25203-32045 (a)Sheet 6 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 7) 25203-32045 (a)Sheet 7 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 8) 25203-32045 (a)Sheet 8 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 9) 25203-32045 (a)Sheet 9 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 10A) 25203-32045 (a)Sheet 10A 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 10B) 25203-32045 (a)Sheet 10B 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 10C) 25203-32045 (a)Sheet 10C 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 10D) 25203-32045 (a)Sheet 10D 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 11) 25203-32045 (a)Sheet 11 8.5-2FIGURE 8.5-2Reactor Trip Switchgear Circ uit Breaker Control Circuitry (Sheet 12) 25203-32045 (a)Sheet 12 8.7-1FIGURE 8.7-1Raceway Plans (Sheet 1) 25203-34060 (a)8.7-1FIGURE 8.7-1Raceway Plan Cable Vault Area

-6, Elevation 25 Feet 6 Inches (Sheet 2) 25203-34031 (a)8.7-1FIGURE 8.7-1Raceway Plan Cable Vault Area

-7, Elevation 25 Feet 6 Inches (Sheet 3) 25203-34032 (a)8.7-1FIGURE 8.7-1Raceway Plan Containment Ar ea Elevation 14 Feet 6 Inches (Sheets 4) 25203-34042 (a)9.0-1FIGURE 9.0-1P&ID Legend 25203-26001 (a)Sheet 1 of 3 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 28 of 499.0-2FIGURE 9.0-2P&ID Legend 25203-26001 (a)Sheet 2 of 3 9.0-3FIGURE 9.0-3General Legend Notes N/A9.2-1FIGURE 9.2-1Chemical and Volu me Control System Flow Schematic (Normal Operation)N/A9.2-2FIGURE 9.2-2P&IDs: Charging; Deborating; Pu rification; Boric Acid Systems (Sheet 1) 25203-26017 (a)Sheet 1 of 3 9.2-2FIGURE 9.2-2P&IDs: Charging; Deborating; Pu rification; Boric Acid Systems (Sheet 2) 25203-26017 (a)Sheet 2 of 3 9.2-2FIGURE 9.2-2P&IDs: Charging; Deborating; Pu rification; Boric Acid Systems (Sheet 3) 25203-26017 (a)Sheet 3 of 3 9.3-1FIGURE 9.3-1Shutdown Cooling Flow Diagram N/A9.4-1FIGURE 9.4-1P&ID RBCCW System RBCCW Pumps and Heat Exchangers 25203-26022 (a)Sheet 1 of 6 9.4-2FIGURE 9.4-2RBCCW System Spent Fuel Pool and Shutdown Heat Exchangers 25203-26022 (a)Sheet 2 of 6 9.4-3FIGURE 9.4-3P&ID RBCCW. System Containment Spray Pump and Safety Injection Pump Seal Coolers 25203-26022 (a)Sheet 3 of 6 9.4-4FIGURE 9.4-4P&ID RBCCW. System Reactor Coolant Pump, Thermal Barriers and Lube Oil Coolers 25203-26022 (a)Sheet 4 of 6 9.4-5FIGURE 9.4-5P&ID RBCCW. System Containment Air Recirculation and Coolant Unit 25203-26022 (a)Sheet 5 of 6 9.4-6FIGURE 9.4-6P&ID Diagram RBCCW. System Reactor Vessel Support Concrete Cooling Coils 25203-26022 (a)Sheet 6 of 6 9.4-7FIGURE 9.4-7Reactor Building Closed Cooling Water Pump Performance CurveN/A 9.5-1FIGURE 9.5-1P&ID Spent Fuel Pool Cleaning and Cleanup System (Sheet 1) 25203-26023 (a)Sheet 1 of 2 9.5-1FIGURE 9.5-1P&ID Spent Fuel Pool Cleaning and Cleanup System (Sheet 2) 25203-26023 (a)Sheet 2 of 2 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET 15-19 MPS2 UFSARLOEF 29 of 499.5-2FIGURE 9.5-2Spent Fuel Pool Pump Performance Curve N/A9.6-1FIGURE 9.6-1P&ID Diagram Sampling System 25203-26025 (a)Sheet 1 of 4 9.6-2FIGURE 9.6-2P&ID Diagram Sampling System 25203-26025 (a)Sheet 2 of 4 9.6-3FIGURE 9.6-3P&ID Diagram Sampling System 25203-26025 (a)Sheet 3 of 4 9.6-4FIGURE 9.6-4P&ID Post Accident Sa mpling System Reactor Coolant Sample 25203-26074 (a)Sheet 1 of 2 9.6-5FIGURE 9.6-5P&ID Post Accident Sa mpling System Containment Air Sample 25203-26074 (a)Sheet 2 of 2 9.7-1FIGURE 9.7-1P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 1) 25203-26008 (a)Sheet 1 of 4 9.7-1FIGURE 9.7-1P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 2) 25203-26008 (a)Sheet 2 of 4 9.7-1FIGURE 9.7-1P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 3) 25203-26008 (a)Sheet 3 of 4 9.7-1FIGURE 9.7-1P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 4) 25203-26008 (a)Sheet 4 of 4 9.7-2FIGURE 9.7-2P&ID TBCCW System (Sheet 1) 25203-26007 (a)Sheet 1 of 3 9.7-2FIGURE 9.7-2P&ID TBCCW System (Sheet 2) 25203-26007 (a)Sheet 2 of 3 9.7-2FIGURE 9.7-2P&ID TBCCW System (Sheet 3) 25203-26007 (a)Sheet 3 of 3 9.7-3FIGURE 9.7-3Typical Service Water Pump Certified Test Curve N/A9.7-4FIGURE 9.7-4Deleted by FSARCR 03-MP2-011 N/A9.8-1FIGURE 9.8-1Plan of New Fuel Storage Racks N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 30 of 499.8-2FIGURE 9.8-2New Fuel Storage Racks - Section "A-A" N/A9.8-3FIGURE 9.8-3New Fuel Storage Rack Assembly (8 Rack Module) 25203-13013 (a)Sheet 14 9.8-4FIGURE 9.8-4New Fuel Storage Rack Assembly (4 Rack Module) 25203-13013 (a)Sheet 19 9.8-5FIGURE 9.8-5Storage Rack N/A9.8-6FIGURE 9.8-6Closure Bar New Fuel Storage Racks 25203-13013 (a)Sheet 10 9.8-7FIGURE 9.8-7Fuel Pool Arrangement - Four Region N/A9.8-8AFIGURE 9.8-8ATypical Spent Fuel Rack Module/Poison Box - Regions 1 and 2N/A9.8-8BFIGURE 9.8-8BTypical Spent Fuel Rack Module/Regions 3 and 4 N/A 9.8-8CFIGURE 9.8-8CPoison Box (Boraf lex poison no longer credited)

N/A 9.8-8DFIGURE 9.8-8DAdjustable Foot N/A 9.8-9FIGURE 9.8-9Collector Leak Channel Plan at Base of Walls N/A 9.8-10FIGURE 9.8-10Refueling Equipment Arrangement N/A9.8-11FIGURE 9.8-11Refueling Machine N/A 9.8-12FIGURE 9.8-12Deleted by PKG FSC MP2-UCR-2009-006 N/A 9.8-13FIGURE 9.8-13Reactor Vess el Head Lifting Rig N/A 9.8-14FIGURE 9.8-14Core Support Barrel Lifting Rig N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 31 of 499.8-15FIGURE 9.8-15Upper Guide Structure Lifting Rig N/A9.8-16FIGURE 9.8-16Surveillance Capsule Retrieval Tool N/A9.8-17FIGURE 9.8-17Spent Fuel Pool Platform Crane N/A9.8-18FIGURE 9.8-18Spent Fuel Pool Platform Crane Travel Limits N/A9.8-19FIGURE 9.8-19Spent Fuel Cask Crane 25203-29022 (a)169 9.8-20FIGURE 9.8-20Heated Junction Thermocouple Handling Canister N/A9.9-1FIGURE 9.9-1P&ID Containment and Enclosure Building Ventilation 25203-26028 (a)Sheet 1 of 6 9.9-2FIGURE 9.9-2Ventilation P&IDs (Sheet 1) 25203-26028 (a)Sheet 2 of 6 9.9-2FIGURE 9.9-2Ventilation P&IDs (Sheet 2) 25203-26028 (a)Sheet 3 of 6 9.9-2FIGURE 9.9-2Ventilation P&IDs (Sheet 3) 25203-26028 (a)Sheet 4 of 6 9.9-2FIGURE 9.9-2Ventilation P&IDs (Sheet 4) 25203-26028 (a)Sheet 5 of 6 9.9-3FIGURE 9.9-3P&ID Auxiliary Building Ventilation System (Sheet 1) 25203-26029 (a)Sheet 1 of 7 9.9-3FIGURE 9.9-3P&ID Auxiliary Building Ventilation System (Sheet 2) 25203-26029 (a)Sheet 2 of 7 9.9-3FIGURE 9.9-3P&ID Auxiliary Building Ventilation System (Sheet 3) 25203-26029 (a)Sheet 3 of 7 9.9-4FIGURE 9.9-4P&ID HVAC System Turbine Building, Intake Structure, Warehouse a nd Diesel Generator Rooms 25203-26027 (a)Sheet 19.9-4AFIGURE 9.9-4AP&ID Control Room Air Conditioning System 25203-26027 (a)Sheet 3 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 32 of 499.9-5FIGURE 9.9-5Control Element Drive Mechanism (CEDM) Fan Performance CurveN/A 9.9-6FIGURE 9.9-6Containment Purge Fan Performance Curve N/A 9.9-7FIGURE 9.9-7Containment Auxiliary Ci rculation Fan Performance CurveN/A 9.9-8FIGURE 9.9-8Containment Penetrati on Cooling Fan Performance CurveN/A 9.9-9FIGURE 9.9-9Radwaste Ventil ation Fan Performance Curve N/A 9.9-10FIGURE 9.9-10Logic Diagram Radwaste Area Supply Fan 25203-28129 (a)Sheet 22 9.9-11FIGURE 9.9-11Non-Radioactive Supply Fan Performance Curve N/A9.9-12FIGURE 9.9-12Non-Radioactive Exhaust Fan Performance Curve N/A9.9-13FIGURE 9.9-13Battery Room E xhaust Fan Performance Curve N/A9.9-14FIGURE 9.9-14Cable Vault Tran sfer Fan Performance Curve N/A9.9-15FIGURE 9.9-15Engineered Safety Features Room Fan Performance CurveN/A9.9-16FIGURE 9.9-16Fuel Handling S upply Fan Performance Curve N/A9.9-17FIGURE 9.9-17Deleted N/A9.9-18FIGURE 9.9-18Main Exhaust Fan Performance Curve N/A9.9-19FIGURE 9.9-19Control Room Air Conditioning Fan Performance CurveN/A9.9-20FIGURE 9.9-20Air Cooled Conde nser Fan Performance Curve N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 33 of 499.9-21FIGURE 9.9-21Control Room Exhaust Fan Performance Curve N/A9.9-22FIGURE 9.9-22Control Room Filtration System Fan Performance CurveN/A 9.9-23FIGURE 9.9-23Diesel Generator Room Supply Fan Performance CurveN/A 9.9-24FIGURE 9.9-24Diesel Genera tor Fan Performance Curve N/A 9.9-25FIGURE 9.9-25Turbine Building Supply Fan Performance Curve N/A 9.9-26FIGURE 9.9-26Turbine Building Exhaust Fan Performance Curve N/A 9.9-27FIGURE 9.9-27Electrical Room Supply Fan Performance Curve N/A 9.9-28FIGURE 9.9-28Access Control Area Air Conditioning Fan Performance CurveN/A 9.9-29FIGURE 9.9-29Deleted N/A 9.9-30FIGURE 9.9-30Deleted N/A 9.9-31FIGURE 9.9-31P&ID Turbine Building, Intake Structure, Warehouse and Diesel Generator Room Chilled Water System 25203-26027 (a)Sheet 2 9.10-1FIGURE 9.10-1Deleted N/A9.10-2FIGURE 9.10-2P&ID Domestic Water (Sheet 1)25203-26011 (a)Sheet 1 of 7 9.10-2FIGURE 9.10-2P&ID Domestic Water (Sheet 2)25203-26011 (a)Sheet 2 of 7 9.11-1FIGURE 9.11-1P&ID Instrument Ai r System Compressors F-3E and F-3F 25203-26009 (a)Sheet 1 9.11-2FIGURE 9.11-2P&ID Instrument Air System Compressors F-3D 25203-26009 (a)Sheet 9 of 10 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 34 of 499.12-1FIGURE 9.12-1P&ID Diagram Water Treatment System 25203-26030 (a)Sheet 1 of 1 9.13-1FIGURE 9.13-1P&ID Auxiliary Steam and Condensate (Sheet 1) 25203-26026 (a)Sheet 1 of 5 9.13-1FIGURE 9.13-1P&ID Auxiliary Steam and Condensate (Sheet 2) 25203-26026 (a)Sheet 2 of 5 9.13-1FIGURE 9.13-1P&ID Auxiliary Steam and Condensate (Sheet 3) 25203-26026 (a)Sheet 3 of 5 9.13-1FIGURE 9.13-1P&ID Auxiliary Steam and Condensate (Sheet 4) 25203-26026 (a)Sheet 4 of 5 10.1-1FIGURE 10.1-1Deleted by FSARCR 03-MP2-007]

N/A10.1-2FIGURE 10.1-2Deleted by FSARCR 03-MP2-007 N/A10.3-1FIGURE 10.3-1P&ID Main Steam fr om Generators (25203-26002 Sheet 1) 25203-26002 (a)Sheet 1 of 5 10.3-1FIGURE 10.3-1P&ID Main Steam Genera tor Blowdown System (25203-26002 Sheet 2) 25203-26002 (a)Sheet 2 of 5 10.3-1FIGURE 10.3-1P&ID Main Steam Turbine and Reheater 1A (25203-26002 Sheet 3) 25203-26002 (a)Sheet 3 of 5 10.3-1FIGURE 10.3-1P&ID Main Steam Turbine (25203-26002 Sheet 4) 25203-26002 (a)Sheet 4 of 5 10.4-1FIGURE 10.4-1P&ID Condenser Air Removal Water Box Priming and Turbine Building Sump (25203-26012) 25203-26012 (a) 10.4-2FIGURE 10.4-2P&ID Condensate System (25203-26005 Sheet 2) 25203-26005 (a)Sheet 1 of 4 10.4-2FIGURE 10.4-2P&ID Condensate Storage and Auxiliary Feed (25203-26005 Sheet 3) 25203-26005 (a)Sheet 2 of 4 10.4-2FIGURE 10.4-2P&ID Condensate Storage and Auxiliary Feed (25203-26005 Sheet 4) 25203-26005 (a)Sheet 3 of 4 10.4-2FIGURE 10.4-2P&ID Condensate System (25203-26005 Sheet 1) 25203-26005 (a)Sheet 4 of 4 LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 35 of 4911.1-1FIGURE 11.1-1P&ID Cl ean Liquid Radwaste System 25203-26020 (a)Sheet 1 of 5 11.1-2FIGURE 11.1-2P&ID Cl ean Liquid Radwaste System 25203-26020 (a)Sheet 2 of 5 11.1-3FIGURE 11.1-3P&ID Drains (Containment & Auxiliary Building and Auxiliary Yard Sump) (Sheet 1) 25203-26024 (a)Sheet 1 11.1-3FIGURE 11.1-3P&ID Drains (Containment & Auxiliary Building and Auxiliary Yard Sump) (Sheet 2) 25203-26024 (a)Sheet 2 11.1-3FIGURE 11.1-3P&ID Drains (Containment & Auxiliary Building and Auxiliary Yard Sump) (Sheet 3) 25203-26024 (a)Sheet 311.1-4FIGURE 11.1-4P&ID Aera ted Liquid Radwaste System 25203-26021 (a)Sheet 1 of 3 11.1-5FIGURE 11.1-5P&ID Diag ram Gaseous Radwaste System 25203-26021 (a)Sheet 2 of 3 11.1-6FIGURE 11.1-6Degasifier Performance Curve N/A11.1-7FIGURE 11.1-7P&ID Spent Resin Radwaste System 25203-26021 (a)Sheet 3 of 3 11.2-1FIGURE 11.2-1P&ID, Radiation Zones and Access Control Normal Operation With 1.0%

Failed Fuel Containment and Auxiliary Bu ilding - Elevation (-) 45 Feet 6 Inches 25203-17001 (a)11.2-2FIGURE 11.2-2P&ID, Radiation Zones and Access Control Normal Operation With 1.0%

Failed Fuel Containment and Auxiliary Bu ilding - Elevation (-) 29 Feet 6 Inches 25203-17002 (a)11.2-3FIGURE 11.2-3P&ID, Radiation Zones and Access Control Normal Operation With 1.0%

Failed Fuel Containment and Auxiliary Bu ilding - Elevation (-) 5 Feet 0 Inches 25203-17003 (a)11.2-4FIGURE 11.2-4P&ID, Radiation Zones a nd Access Control Normal Operation With 1.0%

Failed Fuel Containment Building - Eleva tion 14 Feet 6 Inches and 38 Feet 6 Inches 25203-17004 (a)11.2-5FIGURE 11.2-5P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Auxiliary Building - Elevation 14 Feet 6 Inches and 25 Feet 6 Inches 25203-17005 (a)11.2-6FIGURE 11.2-6P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Turbine Building - Elevation 14 Feet 6 Inches 25203-17006 (a)11.2-7FIGURE 11.2-7P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Auxiliary Building - Elevation 36 Feet 6 Inches 25203-17007 (a)LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 36 of 4911.2-8FIGURE 11.2-8P&ID, Radiation Zones and Access Control Normal Operation With 1.0%

Failed Fuel Containment and Auxiliary Bu ilding - SectionA-A 25203-17008 (a)11.2-9FIGURE 11.2-9P&ID, Radiation Zones and Access Control Normal Operation With 1.0%

Failed Fuel Containment and Auxiliary Bu ilding - SectionB-B 25203-17009 (a)11.2-10FIGURE 11.2-10P&ID, Radiation Zones and Access Control Normal Operation With 1.0%

Failed Fuel Containment and Auxiliary 25203-17010 (a)11.2-11FIGURE 11.2-11Neutron Shield Segment N/A11.2-12FIGURE 11.2-12Neutron Shielding - Sectional View N/A11.2-13FIGURE 11.2-13Not Used N/A11.2-14FIGURE 11.2-14Not Used N/A11.2-15FIGURE 11.2-15Neutron Shield - Thermal Loadings (Typical Annular Section)

N/A11.2-16FIGURE 11.2-16Neutron Shield - Ther mal Loadings (Plug Shield Section)

N/A11.B-1FIGURE 11.B-1NUREG-0017 Gale Code Input Diagram - Liquid Waste System N/A11.B-2FIGURE 11.B-2NUREG-0017 Gale Code Input Diagram - Airborne N/A 13.2-1FIGURE 13.2-1Millstone Nuclear Power Station Organization Diagram During Initial StartupN/A 13.2-2FIGURE 13.2-2Startup Group Organization N/A14.0.4-1FIGURE 14.0.4-1RCS Cold Leg Temperature as a Function of Power N/A14.0.4-2FIGURE 14.0.4-2Not Used N/A14.0.4-3FIGURE 14.0.4-3Not Used N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 37 of 4914.0.4-4FIGURE 14.0.4-4Not Used N/A14.0.4-5FIGURE 14.0.4-5Not Used N/A14.0.4-6FIGURE 14.0.4-6Not Used N/A14.0.4-7FIGURE 14.0.4-7Linear Heat Rate Limiting Condition for Operation used in Local Power Density Limiti ng Condition for Operation VerificationN/A14.0.7-1FIGURE 14.0.7-1Verification of Local Power Density Limiting Safety System SettingN/A14.0.7-2FIGURE 14.0.7-2Thermal Margin/Low Pressure Trip Function A1 N/A14.0.7-3FIGURE 14.0.7-3Thermal Margin/Low Pressure Trip Function QR1 N/A14.0.7-4FIGURE 14.0.7-4Not Used N/A14.0.7-5FIGURE 14.0.7-5Verification of the Departure from Nucleate Boiling Limiting Condition for OperationN/A14.0.7-6FIGURE 14.0.7-6Verification of Local Power Density Limiting Condition for OperationN/A14.0.7-7FIGURE 14.0.7-7Linear Heat Rate Limiting Condition of Operation Used in Local Power Density Limiting Condition of Operation VerificationN/A14.1.3-1FIGURE 14.1.3-1Normalized Power and Heat Flux for the Increase in Steam Flow EventN/A14.1.3-2FIGURE 14.1.3-2Reactivity Feedback for the Increase in Steam Flow EventN/A14.1.3-3FIGURE 14.1.3-3Reactor Coolant Temperatures for Increase in Steam Flow EventN/A14.1.3-4FIGURE 14.1.3-4Core Inlet Mass Flow Rate for the Increase in Steam Flow EventN/A14.1.3-5FIGURE 14.1.3-5Pressurizer Pressure for the Increase in Steam Flow EventN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 38 of 4914.1.3-6FIGURE 14.1.3-6Steam Generator Pressures for the Increase in Steam Flow EventN/A14.1.3-7FIGURE 14.1.3-7Steam Mass Flow Rates for the Increase in Steam Flow EventN/A14.1.3-8FIGURE 14.1.3-8Main Feedwater Flow for the Increase in Steam Flow EventN/A14.1.3-9FIGURE 14.1.3-9Main Feedwater Temperature for the Increase in Steam Flow EventN/A14.1.5.1-1FIGURE 14.1.5.1-1Normalized Core Power (0.20 ft 2 Asymmetric Break Inside Containment)

N/A14.1.5.1-2FIGURE 14.1.5.1-2Core Inlet Temperatures (0.20 ft 2 Asymmetric Break Inside Containment)

N/A14.1.5.1-3FIGURE 14.1.5.1-3Reactivit y Feedback (0.20 ft 2 Asymmetric Break Inside Containment)

N/A14.1.5.1-4FIGURE 14.1.5.1-4Pressurizer Pressure (0.20 ft 2 Asymmetric Break Inside Containment)

N/A14.1.5.1-5FIGURE 14.1.5.1-5Steam Generator Pressures (0.20 ft 2 Asymmetric Break Inside Containment)

N/A14.1.5.1-6FIGURE 14.1.5.1-6Steam Mass Flow Rates (0.20 ft 2 Asymmetric Break Inside Containment)

N/A14.1.5.1-7FIGURE 14.1.5.1-7Normalized Power and Heat Flux (Asymmetric 3.51 ft 2 Break Inside Containment with Loss of Offsite Power)

N/A14.1.5.1-8FIGURE 14.1.5.1-8Reactor Coolant Te mperatures (Asymmetric 3.51 ft 2 Break Inside Containment with Loss of Offsite Power)

N/A14.1.5.1-9FIGURE 14.1.5.1-9Normalized Reactor Coolant System Flow Rate (Asymmetric 3.51 ft 2 Break Inside Containment with Loss of Offsite Power)

N/A14.1.5.1-10FIGURE 14.1.5.1-10Pressurizer Pr essure (Asymmetric 3.51 ft 2 Break Inside Containment with Loss of Offsite Power)

N/A14.1.5.1-11FIGURE 14.1.5.1-11Steam Generator Pressures (Asymmetric 3.51 ft 2 Break Inside Containment with Loss of Offsite Power)

N/A14.1.5.2-1FIGURE 14.1.5.2-1One Pump High Pressure Safety Injection System Delivery vs. Primary Pressure (Post-Scram Steam Line Break)N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 39 of 4914.1.5.2-2FIGURE 14.1.5.2-2Steam Generator Break Flow (HZP Post-Scram St eam Line Outside Containment Break with Offsite Power Available)N/A14.1.5.2-3FIGURE 14.1.5.2-3Steam Generators' Secondary Pressures (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)N/A14.1.5.2-4FIGURE 14.1.5.2-4Core Inlet Temperatures (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Avai lable)N/A14.1.5.2-5FIGURE 14.1.5.2-5Pressurizer Pressure (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Availab le)N/A14.1.5.2-6FIGURE 14.1.5.2-6Pressurizer Level (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)

N/A14.1.5.2-7FIGURE 14.1.5.2-7Steam Generators' Secondary Mass (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)N/A14.1.5.2-8FIGURE 14.1.5.2-8Reactivity Components (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Availa ble)N/A14.1.5.2-9FIGURE 14.1.5.2-9Reactor Power (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)

N/A14.1.5.2-10FIGURE 14.1.5.2-10Steam Generator Break Flow (HZP Post-Scram St eam Line Outside Containment Break with Loss of Offsite Power)N/A14.1.5.2-11FIGURE 14.1.5.2-11Steam Generators' Secondary Pressures (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)N/A14.1.5.2-12FIGURE 14.1.5.2-12Core Inlet Temperatures (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)N/A14.1.5.2-13FIGURE 14.1.5.2-13Pressurizer Pressure (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Pow er)N/A14.1.5.2-14FIGURE 14.1.5.2-14Pressurizer Level (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)

N/A14.1.5.2-15FIGURE 14.1.5.2-15Reactivity Components (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Po wer)N/A14.1.5.2-16FIGURE 14.1.5.2-16Reactor Power (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)

N/A14.2.1-1FIGURE 14.2.1-1Reactor Power Level for Loss of Exte rnal Load (Primary Overpressurization Case)N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 40 of 4914.2.1-2FIGURE 14.2.1-2Core Average Heat Flux for Loss of Ex ternal Load (Primary Ov erpressurization Case)N/A14.2.1-3FIGURE 14.2.1-3Reactor Coolant System Temp eratures for Loss of External Load (Primary Overpressurization Case)N/A14.2.1-4FIGURE 14.2.1-4Primary System Pressures for Loss of External Load (Primary Ov erpressurization Case)N/A14.2.1-5FIGURE 14.2.1-5Total Reactivity for Loss of Extern al Load (Primary Over pressurization Case)N/A14.2.1-6FIGURE 14.2.1-6Reactor Power Level for Loss of Exte rnal Load (Secondary Overpressurization Case)N/A14.2.1-7FIGURE 14.2.1-7Core Average Hot Flux for Loss of Ex ternal Load (Secondary Overpressurization Case)N/A14.2.1-8FIGURE 14.2.1-8Reactor Coolant System Temperatures for Loss of External Load (Secondary Overpressurization Case)N/A14.2.1-9FIGURE 14.2.1-9Pressurizer Pressure for Loss of Ex ternal Load (Secondary Overpressurization Case)N/A14.2.1-10FIGURE 14.2.1-10Total Reactivity for Loss of Extern al Load (Secondary Over pressurization Case)N/A14.2.1-11FIGURE 14.2.1-11Maximum Secondary System Pressures for Loss of External Load (Secondary Overpressurization Case)N/A14.2.1-12FIGURE 14.2.1-12Reactor Power Level for Loss of External Load (MDNBR Case)N/A14.2.1-13FIGURE 14.2.1-13Normalized Heat Flux for Loss of External Load (MDNBR Case)N/A14.2.1-14FIGURE 14.2.1-14Reactor Coolant System Temperature for Loss of External Load (MDNBR Case)N/A14.2.1-15FIGURE 14.2.1-15Pressurizer Pressure for Lo ss of External Load (MDNBR Case)N/A14.2.1-16FIGURE 14.2.1-16Total Reactivity for Loss of External Load (MDNBR Case)N/A14.2.1-17FIGURE 14.2.1-17Maximum Secondary System Pressure for Loss of External Load (MDNBR Case)N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 41 of 4914.2.4-1FIGURE 14.2.4-1Reactor Power Level for MSIV Closure (Lower Steam Flow Case)N/A14.2.4-2FIGURE 14.2.4-2Reactor Coolant System Temperatures for MSIV Closure (Lower Steam Flow Case)N/A14.2.4-3FIGURE 14.2.4-3Pressurizer Pressure for MSIV Closure (Lower Steam Flow Case)N/A14.2.4-4FIGURE 14.2.4-4Isolated Steam Generator Pressure at Bottom of Boiler Region for MSIV Closure (Lower Steam Flow Case)N/A14.2.4-5FIGURE 14.2.4-5Open MSIV Steam Generator Steam Dome Pressure for MSIV Closure (Lower Steam Flow Case)N/A14.2.7-1FIGURE 14.2.7-1Reactor Coolant System Loop Temperatures for Minimum Steam Generator Inventory Case: Offsite Power Available, "B" Motor-Driven AFW Pump Fails to Start N/A14.2.7-2FIGURE 14.2.7-2Steam Generator Dome Pressure for Minimum Steam Generator Inventory Case: Offsite Power Available, "B" Motor-Driven AFW Pump Fails to Start N/A14.2.7-3FIGURE 14.2.7-3Pressurizer Level for Minimum Steam Generator Inventory Case: Offsite Power Available, "B" Motor-Driven AFW Pump Fails to Start N/A14.2.7-4FIGURE 14.2.7-4Steam Generator for Liquid Mass Inventory for Minimum Steam Generator Inventory Case: Offsite to Power A vailable, "B" Motor-Driven AFW Pump Fails to Start N/A14.2.7-5FIGURE 14.2.7-5Steam Generator Collapsed Liquid Level for Minimum Steam Generator Inventory Case: Offsite to Power Available, "B" Motor-Driven AFW Pump Fails to Start N/A14.2.7-6FIGURE 14.2.7-6Reactor Coolant System Loop Temperatures for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A14.2.7-7FIGURE 14.2.7-7Steam Generator Dome Pressure for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A14.2.7-8FIGURE 14.2.7-8Pressurizer Level for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to StartN/A14.2.7-9FIGURE 14.2.7-9Steam Generator Liquid Mass Inventory for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A14.2.7-10FIGURE 14.2.7-10Steam Generator Collapsed Liquid Level for Maxi mum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A14.3.1-1FIGURE 14.3.1-1Reactor Power Level for Loss of Forced Reactor Coolant Flow N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 42 of 4914.3.1-2FIGURE 14.3.1-2Core Average Heat Flux for Loss of Forced Reactor Coolant FlowN/A14.3.1-3FIGURE 14.3.1-3Reactor Coolant System Temperature for Loss of Forced Reactor Coolant FlowN/A14.3.1-4FIGURE 14.3.1-4Pressurizer Pressure for Loss of Forced Reactor Coolant Flow N/A14.3.1-5FIGURE 14.3.1-5Reactivities for Loss of Forced Reactor Coolant Flow N/A14.3.1-6FIGURE 14.3.1-6Primary Coolant Flow Rate for Loss of Forced Reactor Coolant Flow N/A14.3.1-7FIGURE 14.3.1-7Secondary Pressure for Lo ss of Forced Reactor Coolant Flow N/A14.3.3-1FIGURE 14.3.3-1Reactor Power Level for Reactor Coolant Pump Rotor SeizureN/A14.3.3-2FIGURE 14.3.3-2Core Average Heat Flux for Reactor Coolant Pump Rotor SeizureN/A14.3.3-3FIGURE 14.3.3-3Reactor Coolant System Temperatures for Reactor Coolant Pump Rotor SeizureN/A14.3.3-4FIGURE 14.3.3-4Pressurizer Pressure for Reactor Coolant Pump Rotor SeizureN/A14.3.3-5FIGURE 14.3.3-5Reactivities for Reactor Coolant Pump Rotor SeizureN/A14.3.3-6FIGURE 14.3.3-6Primary Coolant Flow Rate fo r Reactor Coolant Pump Rotor SeizureN/A14.3.3-7FIGURE 14.3.3-7Secondary Pressure for Re actor Coolant Pump Rotor SeizureN/A14.4.1-1FIGURE 14.4.1-1Reactor Power Level for Low Power Bank Withdrawal N/A14.4.1-2FIGURE 14.4.1-2Core Average Heat Flux for Low Power Bank Withdrawal N/A14.4.1-3FIGURE 14.4.1-3Reactor Coolant Temperatures for Low Power Bank Withdrawal N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 43 of 4914.4.1-4FIGURE 14.4.1-4Pressurizer Pressure for Low Power Bank WithdrawalN/A14.4.1-5FIGURE 14.4.1-5Reactivities for Low Power Bank Withdrawal N/A14.4.2-1FIGURE 14.4.2-1Reactor Core Power for an Uncontrolled Bank Withdrawal at PowerN/A14.4.2-2FIGURE 14.4.2-2Core Average Heat Flux for an Uncontrolled Bank Withdrawal at PowerN/A14.4.2-3FIGURE 14.4.2-3Reactor Coolant System Temperatures for an Uncontrolled Bank Withdrawal at PowerN/A14.4.2-4FIGURE 14.4.2-4Pressurizer Pressure for an Uncontrolled Bank Withdrawal at PowerN/A14.4.2-5FIGURE 14.4.2-5Reactivities for an Uncontrolled Bank Withdrawal at PowerN/A14.4.2-6FIGURE 14.4.2-6Secondary Pressure for an Uncontrolled Bank Withdrawal at PowerN/A14.4.3.1-1FIGURE 14.4.3.1-1Reactor Power Level for the Limiting Dropped Contro l Rod/Bank Case N/A14.4.3.1-2FIGURE 14.4.3.1-2Reactor Coolant System Temperatures for the Limiti ng Dropped Control Rod/Bank Case N/A14.4.3.1-3FIGURE 14.4.3.1-3Pressurizer Pressure for the Limiting Dropped Control Rod/Bank Case N/A14.4.3.1-4FIGURE 14.4.3.1-4Secondary Pressure for the Limiting Dropped Control Rod/Bank Case N/A14.4.8-1FIGURE 14.4.8-1Core Power for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)N/A14.4.8-2FIGURE 14.4.8-2Core Average Heat Flux for a CEA Ejection (M inimum Departure for Nucleate Boiling Ratio Case)N/A14.4.8-3FIGURE 14.4.8-3Reactor Coolant System Temp eratures for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Cas e)N/A14.4.8-4FIGURE 14.4.8-4Pressurizer Pressure for a CEA Ejection (M inimum Departure for Nuclea te Boiling Ratio Case)N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 44 of 4914.4.8-5FIGURE 14.4.8-5Reactivities for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)N/A14.4.8-6FIGURE 14.4.8-6Secondary Pressure for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)N/A14.4.8-7FIGURE 14.4.8-7Core Power for a CEA Ejection (Overpressure)

N/A14.4.8-8FIGURE 14.4.8-8Core Average Heat Flux for a CEA Ejection (Overpressure)N/A14.4.8-9FIGURE 14.4.8-9Primary System Temperatures for a CEA Ejection (Overpressure)N/A14.4.8-10FIGURE 14.4.8-10Pressurizer Pressure fo r a CEA Ejection (Overpressure)

N/A14.4.8-11FIGURE 14.4.8-11Reactivities for a CEA Ejection (Overpressure)

N/A14.4.8-12FIGURE 14.4.8-12Secondary Pressure fo r a CEA Ejection (Overpressure)N/A14.6.1-1FIGURE 14.6.1-1Reactor Power Level for an Inadvertent Opening of a Pressurized Water Reacto r Pressurizer Pressure Relief Valve (Rated Power)N/A14.6.1-2FIGURE 14.6.1-2Core Average Heat Flux for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)N/A14.6.1-3FIGURE 14.6.1-3Reactor Coolant System Temp eratures for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)

N/A14.6.1-4FIGURE 14.6.1-4Pressurizer Pressure for an Inadvertent Opening of a Pressurized Water Reac tor Pressurizer Pressure Relief Valve (Rated Power)N/A14.6.1-5FIGURE 14.6.1-5Reactivities for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)N/A14.6.1-6FIGURE 14.6.1-6Secondary Pressure for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)N/A14.6.3-1FIGURE 14.6.3-1Steam Generator Tube Rupture with the Loss of Offsite Power RCS Temperature Versus Time N/A14.6.3-2FIGURE 14.6.3-2Steam Generator Tube Rupture with the Loss of Offsite Power Pressurizer Level Versus Time N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 45 of 4914.6.3-3FIGURE 14.6.3-3Steam Generator Tube Rupture with the Loss of Offsite Power Pressurizer Pressure Versus TimeN/A14.6.3-4FIGURE 14.6.3-4Steam Generator Tube Rupture with the Loss of Offsite Power Steam Generator Pressure Versus TimeN/A14.6.3-5FIGURE 14.6.3-5Steam Generator Tube Rupture with the Loss of Offsite Power Total Break Flow Rate Versus TimeN/A14.6.3-6FIGURE 14.6.3-6Steam Generator Tube Rupture with the Loss of Offsite Power Flashed Break Flow Rate Versus TimeN/A14.6.3-7FIGURE 14.6.3-7Steam Generator Tube Rupture with the Loss of Offsite Power Atmospheric Dump Valve Flow Rate per Steam Generator Versus Time N/A14.6.3-8FIGURE 14.6.3-8Steam Generator Tube Rupture with the Loss of Offsite Power Main Steam Safety Valve Flow Rates per Steam Generator Versus Time N/A14.6.3-9FIGURE 14.6.3-9Steam Generator Tube Rupture with the Loss of Offsite Power Auxiliary Feedwater Flow Versus TimeN/A14.6.5.1-1FIGURE 14.6.5.1-1Normalized Power (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-2FIGURE 14.6.5.1-2Safety Injection Tank (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-3FIGURE 14.6.5.1-3High Pressure Safety Injection Flow Rates (1.0 DECLG EOC Loss-of-Diesel)

N/A14.6.5.1-4FIGURE 14.6.5.1-4Low Pressure Safety Injection Flow Rates (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-5FIGURE 14.6.5.1-5Upper Plenum Pressure During Blowdown (1.0 DECLG EOC Loss-of-Diesel)

N/A14.6.5.1-6FIGURE 14.6.5.1-6Total Break Flow Rate During Blowdown (1.0 DECLG EOC Loss-of-Diesel)

N/A14.6.5.1-7FIGURE 14.6.5.1-7Average Core Inlet Flow Rate Du ring Blowdown (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-8FIGURE 14.6.5.1-8Hot Channel Inlet Flow Rate Duri ng Blowdown (1.0 DECLG EOC Loss-of-Diesel)

N/A14.6.5.1-9FIGURE 14.6.5.1-9Peak Cladding Temperature Node Fluid Qu ality During Blowdown (1.0 DE CLG EOC Loss-of-Diesel)

N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 46 of 4914.6.5.1-10FIGURE 14.6.5.1-10Peak Cladding Temperature Node Fuel (Average), Cladding and Fluid Temperatures During Blowdown (1.0 DECLG EOC Loss-of-Diesel)

N/A14.6.5.1-11FIGURE 14.6.5.1-11Peak Cladding Temperature Node Heat Transfer Coefficient Du ring Blowdown (1.0 DE CLG EOC Loss-of-Diesel)N/A14.6.5.1-12FIGURE 14.6.5.1-12Peak Cladding Temperat ure Node Heat Flux During Blowdown (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-13FIGURE 14.6.5.1-13Containment Pressure (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-14FIGURE 14.6.5.1-14Upper Plenum Pressure (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-15FIGURE 14.6.5.1-15Downcomer Mixture Level (1.0 DECLG EOC Loss-of-Diesel)

N/A14.6.5.1-16FIGURE 14.6.5.1-16Core Effective Flooding Ra te (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-17FIGURE 14.6.5.1-17Core Mixture Level (1.0 DECLG EOC Loss-of-Diesel)N/A14.6.5.1-18FIGURE 14.6.5.1-18Core Quench Level (1.0 DECLG EOC Lo ss-of-Diesel)

N/A14.6.5.1-19FIGURE 14.6.5.1-19Peak Cladding Temperature Node and Ruptured Node Cladding Temperatures (1.0 DECLG EOC Loss-of-Dies el)N/A14.6.5.2-1FIGURE 14.6.5.2-1Peak Cladding Temperature Versus Break Size (SBLOCA Break Spectrum)N/A14.6.5.2-2FIGURE 14.6.5.2-2Reactor Power - 3.78-Inch Break N/A14.6.5.2-3FIGURE 14.6.5.2-3Primary and Secondary Sy stem Pressures - 3.78-Inch Break N/A14.6.5.2-4FIGURE 14.6.5.2-4Break Mass Flow Rate - 3.78-Inch Break N/A14.6.5.2-5FIGURE 14.6.5.2-5Break Vapor Void Fraction - 3.78-Inch Break N/A14.6.5.2-6FIGURE 14.6.5.2-6Loop Seal Void Fraction - 3.78-Inch Break N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 47 of 4914.6.5.2-7FIGURE 14.6.5.2-7Total Core Inlet Ma ss Flow Rate - 3.78-Inch Break N/A14.6.5.2-8FIGURE 14.6.5.2-8Downcomer Collapsed Liquid Level - 3.78-Inch BreakN/A14.6.5.2-9FIGURE 14.6.5.2-9Inner and Outer Core Collapsed Liquid Level - 3.78-Inch BreakN/A14.6.5.2-10FIGURE 14.6.5.2-10Reactor Vessel Mass - 3.78-Inch Break N/A14.6.5.2-11FIGURE 14.6.5.2-11RCS Loop Mass Flow Rates - 3.78-Inch Break N/A14.6.5.2-12FIGURE 14.6.5.2-12Steam Generator Main Feedwater Mass Flow Rates - 3.78-Inch BreakN/A 14.6.5.2-13FIGURE 14.6.5.2-13Steam Generator Auxiliary Feedwater Mass Flow Rates - 3.78-Inch BreakN/A14.6.5.2-14FIGURE 14.6.5.2-14Steam Generator Total Mass - 3.78-Inch Break N/A14.6.5.2-15FIGURE 14.6.5.2-15(Steam Generator Narrow Range Level % - 3.78-Inch BreakN/A14.6.5.2-16FIGURE 14.6.5.2-16(High Pressure Safety Injection Mass Flow Rates - 3.78-Inch BreakN/A14.6.5.2-17FIGURE 14.6.5.2-17(Low Pressure Safety Inje ction Mass Flow Rates - 3.78-Inch BreakN/A14.6.5.2-18FIGURE 14.6.5.2-18(Safety Injection Tank Ma ss Flow Rates - 3.78-Inch Break N/A14.6.5.2-19FIGURE 14.6.5.2-19(Integrated Break Flow And Eccs Flow - 3.78-Inch Break N/A14.6.5.2-20FIGURE 14.6.5.2-20(Hot Assembly Collapsed Liquid Level - 3.78-Inch Break N/A14.6.5.2-21FIGURE 14.6.5.2-21(Hot Assembly Mixture Level - 3.78-Inch Break N/A14.6.5.2-22FIGURE 14.6.5.2-22(Peak Cladding Temperature At Pct Location (11.02 Ft) - 3.78-Inch BreakN/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 48 of 4914.6.5.2-23FIGURE 14.6.5.2-23(DELETED by FSARCR 00-MP2-023)

N/A14.6.5.2-24FIGURE 14.6.5.2-24(DELETED by FSARCR 00-MP2-023)

N/A14.6.5.3-1FIGURE 14.6.5.3-1Long Term Cooling Plan N/A14.6.5.3-2FIGURE 14.6.5.3-2Reactor Coolant System Refill Time vs. Break AreaN/A14.6.5.3-3FIGURE 14.6.5.3-3Core Flush by Hot Side Injection for a Double-Ended Guillotine Cold Leg BreakN/A14.6.5.3-4FIGURE 14.6.5.3-4Inner Vessel Boric Acid Concentration vs. Time for a Double-Ended Guillotine Cold Leg BreakN/A14.8.2-1FIGURE 14.8.2-1Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Containment Pressure vs. Time N/A14.8.2-2FIGURE 14.8.2-2Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Containment Temperature vs. Time N/A14.8.2-3FIGURE 14.8.2-3Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Mass Flow Rate vs. Time N/A14.8.2-4FIGURE 14.8.2-4Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Energy Release Rate vs. Time N/A14.8.2-5FIGURE 14.8.2-5Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Integrated Mass Flow vs. Time N/A14.8.2-6FIGURE 14.8.2-6Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Integrated Energy Release vs. Time N/A14.8.2-7FIGURE 14.8.2-7Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Affected Steam Generator Pressure vs. Time N/A14.8.2-8FIGURE 14.8.2-8Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Unaffected Steam Generator Pressure vs. Time N/A14.8.2-9FIGURE 14.8.2-9Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Affected Steam Generator Liquid Mass vs. Time N/A14.8.3-1FIGURE 14.8.3-1Deleted by FSARCR 04-MP2-018.

N/ALIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET MPS2 UFSARLOEF 49 of 4914.8.3-2FIGURE 14.8.3-2Deleted by FSARCR 04-MP2-018.

N/A14.8.3-3FIGURE 14.8.3-3Deleted by FSARCR 04-MP2-018.

N/A14.8.3-4FIGURE 14.8.3-4Deleted by FSARCR 04-MP2-018.

N/A14.8.3-5FIGURE 14.8.3-5Deleted by FSARCR 04-MP2-018.

N/A14.8.3-6FIGURE 14.8.3-6Deleted by FSARCR 04-MP2-018.

N/Aa.Incorporated by reference this engineering controlled drawing is, coincidentally, an MPS-2 FSAR figure. Refer to the controlled plant drawing for the latest revision. LIST OF EFFECTIVE FIGURESFigure NumberFigure LabelTitle Drawing Number SHEET