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{{#Wiki_filter:PNPS-FSAR
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==SUMMARY==
==SUMMARY==
TABLE OF CONTENTS Summ T of C-i Rev. 30  Nov. 2015 Section Title Volume Section 1 Introduction and Summary 1
TABLE OF CONTENTS Section   Title                                               Volume Section 1 Introduction and Summary                               1 1.1       Project Identification                                 1 1.2       Definitions                                           1 1.3       Methods of Technical Presentation                     1 1.4       Classification of BWR Systems, Criteria,               1 and Requirements for Safety Evaluation 1.5       Principal Design Criteria                             1 1.6       Station Description                                   1 1.7       Comparison of Principal Design Characteristics                                       1 1.8       Summary of Radiation Effects                           1 1.9       Station Management                                     1 1.10     Quality Assurance Program                             1 1.11     Station Research, Development, and Further Information Requirements and Resolutions Summary       1 Section 2 Station Site and Environs                             1 2.1       Introduction                                           1 2.2       Site Description                                       1 2.3       Meteorology                                           1 2.4       Hydrology                                             1 2.5       Geology and Seismology                                 1 2.6       Environs Radiation Surveillance Program               1 Section 3 Reactor                                               1 3.1       Summary Description                                   1 3.2       Fuel Mechanical Design                                 1 3.3       Reactor Vessel Internals Mechanical Design             1 3.4       Reactivity Control Mechanical Design                   1 3.5       Control Rod Drive Housing Supports                     1 3.6       Nuclear Design                                         1 3.7       Thermal and Hydraulic Design                           1 3.8       Standby Liquid Control System                         1 3.9       Recirculation Pump Trip, Alternate Rod Insertion, and Feedwater Pump Trip Systems                       1 Section 4 Reactor Coolant System                                 2 4.1       Summary Description                                   2 4.2       Reactor Vessel and Appurtenances Mechanical Design                                                 2 4.3       Recirculation System                                   2 4.4       Nuclear System Pressure Relief System                 2 4.5       Main Steam Line Flow Restrictor                       2 Summ T of C-i        Rev. 30 - Nov. 2015
1.1 Project Identification 1 1.2 Definitions 1 1.3 Methods of Technical Presentation 1 1.4 Classification of BWR Systems, Criteria, 1 and Requirements for Safety Evaluation 1.5 Principal Design Criteria 1 1.6 Station Description 1 1.7 Comparison of Principal Design Characteristics 1 1.8 Summary of Radiation Effects 1 1.9 Station Management 1 1.10 Quality Assurance Program 1 1.11 Station Research, Development, and Further Information Requirements and Resolutions Summary 1 Section 2 Station Site and Environs 1
 
2.1 Introduction 1 2.2 Site Description 1 2.3 Meteorology 1 2.4 Hydrology 1 2.5 Geology and Seismology 1 2.6 Environs Radiation Surveillance Program 1
PNPS-FSAR
Section 3 Reactor 1 3.1 Summary Description 1 3.2 Fuel Mechanical Design 1 3.3 Reactor Vessel Internals Mechanical Design 1 3.4 Reactivity Control Mechanical Design 1 3.5 Control Rod Drive Housing Supports 1 3.6 Nuclear Design 1 3.7 Thermal and Hydraulic Design 1 3.8 Standby Liquid Control System 1 3.9 Recirculation Pump Trip, Alternate Rod Insertion, and Feedwater Pump Trip Systems 1
Section 4 Reactor Coolant System 2
4.1 Summary Description 2 4.2 Reactor Vessel and Appurtenances Mechanical Design 2 4.3 Recirculation System 2 4.4 Nuclear System Pressure Relief System 2 4.5 Main Steam Line Flow Restrictor 2
PNPS-FSAR


==SUMMARY==
==SUMMARY==
TABLE OF CONTENTS (Cont)
TABLE OF CONTENTS (Cont)
Summ T of C-ii Rev. 30  Nov. 201 5Section Title                         Volume 4.6 Main Steam Line Isolation Valves 2 4.7 Reactor Core Isolation Cooling System 2 4.8 Residual Heat Removal System 2 4.9 Reactor Water Cleanup System 2 4.10 Nuclear System Leakage Rate Limits 2 4.11 Main Steam Lines and Feedwater Piping 2
Section  Title                                           Volume 4.6       Main Steam Line Isolation Valves                 2 4.7       Reactor Core Isolation Cooling System             2 4.8       Residual Heat Removal System                     2 4.9       Reactor Water Cleanup System                     2 4.10     Nuclear System Leakage Rate Limits               2 4.11     Main Steam Lines and Feedwater Piping             2 Section 5 Containment                                       2 5.1       Summary Descriptions                             2 5.2       Primary Containment System                       2 5.3       Secondary Containment System                     2 5.4       Control of Combustible Gas Concentrations in Containment                                   2 Section 6 Core Standby Cooling Systems                     2 6.1       Safety Objective                                 2 6.2       Safety Design Bases                               2 6.3       Summary Description - Core Standby Cooling Systems                                           2 6.4       Description                                       2 6.5       Safety Evaluation                                 2 6.6       Inspection and Testing                           2 6.7       The Nuclear Safety Requirements for Plant Operation                               2 6.8       Current Technical Specifications                 2 Section 7 Control and Instrumentation                       3 7.1       Summary Description                               3 7.2       Reactor Protection System                         3 7.3       Primary Containment and Reactor Vessel Isolation Control System                         3 7.4       Core Standby Cooling Systems Control and Instrumentation                               3 7.5       Neutron Monitoring System                         3 7.6       Refueling Interlocks                             3 7.7       Reactor Manual Control System                     3 7.8       Reactor Vessel Instrumentation                   3 7.9       Recirculation Flow Control System                 3 7.10     Feedwater Control System                         3 7.11     Turbine Generator Control System                 3 7.12     Process Radiation Monitoring                     3 7.13     Area Radiation Monitoring System                 3 7.14     Environs Radiation Monitors                       3 7.15     Health Physics and Laboratory Analysis Radiation Monitors                               3 Summ T of C-ii        Rev. 30 - Nov. 2015
Section 5 Containment 2 5.1 Summary Descriptions 2 5.2 Primary Containment System 2 5.3 Secondary Containment System 2 5.4 Control of Combustible Gas Concentrations in Containment 2 Section 6 Core Standby Cooling Systems 2 6.1 Safety Objective 2 6.2 Safety Design Bases 2 6.3 Summary Description - Core Standby Cooling Systems 2 6.4 Description 2 6.5 S afety Evaluation 2 6.6 Inspection and Testing 2 6.7 The Nuclear Safety Requirements for Plant Operation 2 6.8 Current Technical Specifications 2 Section 7 Control and Instrumentation 3 7.1 Summary Description 3 7.2 Reactor Protection System 3 7.3 Primary Containment and Reactor Vessel Isolation Control System 3 7.4 Core Standby Cooling Systems Control and Instrumentation 3 7.5 Neutron Monitoring System 3 7.6 Refueling Interlocks 3 7.7 Reactor Manual Control System 3 7.8 Reactor Vessel Instrumentation 3 7.9 Recirculation Flow Control System 3 7.10 Feedwater Control System 3 7.11 Turbine Generator Control System 3 7.12 Process Radiation Monitoring 3 7.13 Area Radiation Monitoring System 3 7.14 Environs Radiation Monitors 3 7.15 Health Physics and Laboratory Analysis Radiation Monitors 3
PNPS-FSAR 


==SUMMARY==
PNPS-FSAR
TABLE OF CONTENTS (Cont)    Summ T of C
-iii Rev. 30  Nov. 2015 Section Title                            Volume  7.16 Process Computer System  3 7.17 Nuclear System Stability Analysis for Initial Core 3 7.18 Reactor Building Isolation and Control System 3 7.19 RHR Service Water System (SSW, RBCCW) 3 7.20 Equipment Area Cooling System  3 7.21 Meteorological Instrumentation  3  Section 8 Electrical Power System  4  8.1 Summary Description 4 8.2 Unit and Preferred AC Power Sources 4 8.3 Secondary AC Power Source  4 8.4 Auxiliary Power Distribution System 4 8.5 Standby AC Power Source  4 8.6 125 and 250 Volt DC Power Systems 4 8.7 24 Volt DC Power System  4 8.8 120 Volt AC Power Systems  4 8.9 Cable Installation Criteria  4 8.10 Blackout AC Power Source  4 Section 9 Radioactive Waste Systems  4 9.1 Summary Description 4 9.2 Liquid Radwaste System 4 9.3 Solid Radwaste System 4 9.4 Gaseous Radwaste System  4 9.5 Trash Compaction and Decontamination Facilities 4 Section 10 Auxiliary Systems 4
10.1 Summary Description 4 10.2 New Fuel Storage 4 10.3 Spent Fuel Storage 4 10.4 Fuel Pool Cooling and Cleanup System 4 10.5 Reactor Building Closed Cooling Water System 4 10.6 Turbine Building Closed Cooling Water System 4 10.7 Salt Service Water System  4 10.8 Fire Protection System 4 10.9 H VAC Systems 4 10.10 Makeup Water Treatment System  4 10.11 Instrument and Service Air Systems 4 10.12 Potable and Sanitary Water System 4 10.13 Equipment and Floor Drainage Systems 4 10.14 Process Sampling Systems  4 10.15 Communications Systems 4 10.16 Station Lighting System  4 10.17 Main Control Room Environmental Control System 4 10.18 Equipment Area Cooling System  4 10.19 Post Accident Sampling System  4 PNPS-FSAR


==SUMMARY==
==SUMMARY==
TABLE OF CONTENTS (Cont)
TABLE OF CONTENTS (Cont)
Summ T of C
Section   Title                                           Volume 7.16      Process Computer System                            3 7.17      Nuclear System Stability Analysis for Initial Core                                      3 7.18      Reactor Building Isolation and Control System                                     3 7.19      RHR Service Water System (SSW, RBCCW)              3 7.20      Equipment Area Cooling System                     3 7.21      Meteorological Instrumentation                    3 Section 8  Electrical Power System                            4 8.1       Summary Description                               4 8.2       Unit and Preferred AC Power Sources                4 8.3       Secondary AC Power Source                          4 8.4       Auxiliary Power Distribution System                4 8.5       Standby AC Power Source                            4 8.6       125 and 250 Volt DC Power Systems                  4 8.7       24 Volt DC Power System                           4 8.8       120 Volt AC Power Systems                          4 8.9       Cable Installation Criteria                        4 8.10      Blackout AC Power Source                          4 Section 9 Radioactive Waste Systems                          4 9.1       Summary Description                               4 9.2       Liquid Radwaste System                            4 9.3       Solid Radwaste System                              4 9.4       Gaseous Radwaste System                            4 9.5        Trash Compaction and Decontamination Facilities    4 Section 10 Auxiliary Systems                                  4 10.1       Summary Description                                4 10.2       New Fuel Storage                                  4 10.3       Spent Fuel Storage                                4 10.4       Fuel Pool Cooling and Cleanup System              4 10.5       Reactor Building Closed Cooling Water System      4 10.6       Turbine Building Closed Cooling Water System      4 10.7       Salt Service Water System                          4 10.8       Fire Protection System                            4 10.9      HVAC Systems                                      4 10.10      Makeup Water Treatment System                      4 10.11      Instrument and Service Air Systems                4 10.12      Potable and Sanitary Water System                  4 10.13      Equipment and Floor Drainage Systems              4 10.14     Process Sampling Systems                          4 10.15      Communications Systems                            4 10.16      Station Lighting System                            4 10.17      Main Control Room Environmental Control System    4 10.18      Equipment Area Cooling System                      4 10.19      Post Accident Sampling System                      4 Summ T of C-iii      Rev. 30 - Nov. 2015
-iv Rev. 30  Nov. 201 5  Section Title   Volume 10.20 Crack Arrest Verification System 4 10.21 Hydrogen Water Chemistry Extended Test System 4 10.22 Electrolytic Hydrogen Water Chemistry System 4 10.23 Mitigation Monitoring System 4
Section 11 Power Conversion Systems 4 11.1 Summary Description 4 11.2 Turbine-Generator 4 11.3 Main Condenser 4 1 1.4 Main Condenser Gas Removal and Turbine Sealing Systems 4 11.5 Turbine Bypass System 4 11.6 Circulating Water System 4 11.7 Condensate Demineralizer System 4 11.8 Condensate and Feedwater System 4 11.9 Condensate Storage System Section 12 Structures and Shielding 4
12.1 Summary Description 4 12.2 Structural Design 4 12.3 Shielding and Radiation Protection 4 12.4 Radioactive Materials Safety 4
Section 13 Conduct of Operations 5
13.1 Introduction and Summary 5 13.2 Organization and Responsibilities 5 13.3 Training 5 13.4 Preoperational Test Program 5 13.5 Reactor Startup and Power Test Program 5 13.6 Station Procedures 5 13.7 Records 5 13.8 Operational Review and Audits 5
Section 14 Station Safety Analysis 5
14.1 Introduction 5 14.2 Reactor Limits 5 14.3 Method of Approach 5 14.4 Abnormal Operational Transients 5 14.5 Postulated Design Basis Accidents 5 14.6 Special Events 5 14.7 References 5
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==SUMMARY==
PNPS-FSAR
TABLE OF CONTENTS (Cont)    Summ T of C-v Rev. 30  Nov. 2015  Section Title  Volume  Appendix A Pressure Integrity of Piping and Equipment Pressure Parts 5
A.1 Scope  5 A.2 Classification of Piping and Equipment Pressure Parts 5 A.3 Design Requirements 5 A.4 Materials  5 A.5 Fabrication and Installation Requirements 5 A.6 Testing and Inspection Requirements 5 A.7 Final Cleaning and Protection  5 A.8 F1, F2, F3, and F4 Fabrication and Erection Schedule 5 A.9 M1, M2, and M3 Material Schedules  5 A.10 T1, T2, T3, T4, and T5 Inspection and Testing Schedules 5
Appendix B Technical Specifications 5
B.1 Technical Specifications 5 B.2 Technical Specifications Relocated to the FSAR 5 B.3 Relocated Technical Specifications and Related 5  Bases  5 B.4 References 5
Appendix C Structural Loading Criteria  5 C.1 Scope  5 C.2 Concrete and Steel Structures  5 C.3 Components 5
Appendix D Quality Assurance Program  5  D.1 General  5 D.2 Program Organization and Responsibility 5 D.3 Quality Surveillance and Auditing  5 D.4 Quality Controls and Assurance Measures 5 D.5 QC-QA Documentation and Records  5 D.6 Project Communications 5  Attachment D.I  General Electric Quality  System for BWR Nuclear Steam Supply Projects 5  Attachment D.II  Bechtel Quality Assurance Program,  Pilgrim Nuclear Power Station 5  Attachment D.III Site Handling and Storage of Nuclear Steam Supply System Equipment, Pilgrim Nuclear Power Station 5
PNPS-FSAR


==SUMMARY==
==SUMMARY==
TABLE OF CONTENTS (Cont)
TABLE OF CONTENTS (Cont)
Summ T of C
Section    Title                                              Volume 10.20      Crack Arrest Verification System                      4 10.21      Hydrogen Water Chemistry Extended Test System        4 10.22      Electrolytic Hydrogen Water Chemistry System          4 10.23      Mitigation Monitoring System                          4 Section 11 Power Conversion Systems                              4 11.1       Summary Description                                  4 11.2       Turbine-Generator                                    4 11.3       Main Condenser                                        4 11.4       Main Condenser Gas Removal and Turbine Sealing Systems                                      4 11.5       Turbine Bypass System                                4 11.6       Circulating Water System                              4 11.7      Condensate Demineralizer System                      4 11.8      Condensate and Feedwater System                      4 11.9      Condensate Storage System                            4 Section 12 Structures and Shielding                              4 12.1       Summary Description                                   4 12.2       Structural Design                                    4 12.3      Shielding and Radiation Protection                    4 12.4      Radioactive Materials Safety                         4 Section 13 Conduct of Operations                                5 13.1       Introduction and Summary                              5 13.2       Organization and Responsibilities                    5 13.3       Training                                              5 13.4       Preoperational Test Program                          5 13.5       Reactor Startup and Power Test Program                5 13.6       Station Procedures                                    5 13.7      Records                                              5 13.8      Operational Review and Audits                        5 Section 14 Station Safety Analysis                              5 14.1       Introduction                                         5 14.2       Reactor Limits                                        5 14.3       Method of Approach                                    5 14.4       Abnormal Operational Transients                      5 14.5       Postulated Design Basis Accidents                    5 14.6       Special Events                                        5 14.7       References                                            5 Summ T of C-iv        Rev. 30 - Nov. 2015
-vi Rev. 30  Nov. 201 5 Section Title  Volume  Appendix E Stack Release Limit Calculations for Pilgrim Station Site 5
E.1 Analytical Model 5 E.2 Verification of Analytical Model  5 E.3 Stack Release Limit Calculations for Pilgrim Station Site 5 E.4 Building Exhaust Vent Release  5 E.5 Summary  5 E.6 References 5
Appendix F Comparison of Pilgrim Nuclear Power Station with the Proposed General Design Criteria Published by the AEC for Public Comment in The Federal Register July 11, 1967  6 F.1 Summary Description 6 F.2 Criteria Conformance 6  Appendix G Station Nuclear Safety Operation Analysis Supporting Nuclear Safety Requirements for Plant Operation  6  G.1 Analytical Objective 6 G.2 Bases for Selecting Operation Requirements for Plant Operation 6 G.3 Bases for Selecting Surveillance Test Frequencies for Nuclear Safety Systems and Engineered Safeguards for Plant Operation 6 G.4 Method of Analysis 6 G.5 Analysis and Results 6 G.6 Conclusion 6
Appendix H Tornado Criteria for Nuclear Power Plants 6 H.0 Foreword  6 H.1 Introduction 6 H.2 Characteristics of Tornadoes  6 H.3 Tornado Probability 6 H.4 Wind Loading 6 H.5 Pressure Differential 6 H.6 Water Loss 6 H.7 Tornado Missiles 6 H.8 References 6
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==SUMMARY==
PNPS-FSAR
TABLE OF CONTENTS (Cont)    Summ T of C
-vii Rev. 30  Nov. 2015 Appendix I Site Investigation of the Seabreezes 6  I.1 Introduction 6 I.2 Results and Conclusions 6  Section Title  Volume I.3 Discussion 6 I.4 Data and Calculations 6 I.5 References 6  Appendix J Station Research, Development, and    Further Information Requirements and Resolution 6  J.1 Resolution of ACRS Concerns  6 J.2 Areas Specified in the ACRS Construction Permit Letter for Pilgrim Nuclear Power Station  6 J.3 Areas Specified in the AEC Staff    Construction Permit - Safety Evaluation Report for Pilgrim Nuclear Power Station 6 J.4 Areas Specified in Recent, Related ACRS Construction and Operating Permit Letters 6 J.5 Summary Conclusions 6 J.6 References 6
Appendix K Inservice Inspection Program  6 K.1 General  6 K.2 Inspection Program Development  6 K.3 Inspection Program Implementation  6 K.4 Reference Base Examinations  6 K.5 Documentation and Records  6 Appendix L Containment Report 7
L.1 Introduction and Summary 7 L.2 Basis for Containment Design  7 L.3 Containment System Design  7 L.4 Initial Overload and Leakage Rate Test 7 L.5 Manufacturer's Data Report for Nuclear Vessels  7 Appendix M Reactor Pressure Vessel Design Report 7
M.1 Introduction to the Report  7 M.2 Summary  7  Appendix N Emergency Plan 7
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==SUMMARY==
==SUMMARY==
TABLE OF CONTENTS (Cont)
TABLE OF CONTENTS (Cont)
Summ T of C
Section   Title                                           Volume Appendix A Pressure Integrity of Piping and Equipment Pressure Parts                                    5 A.1       Scope                                              5 A.2       Classification of Piping and Equipment Pressure Parts                                    5 A.3       Design Requirements                                5 A.4       Materials                                          5 A.5       Fabrication and Installation Requirements          5 A.6       Testing and Inspection Requirements                5 A.7       Final Cleaning and Protection                      5 A.8        F1, F2, F3, and F4 Fabrication and Erection Schedule                                          5 A.9        M1, M2, and M3 Material Schedules                  5 A.10      T1, T2, T3, T4, and T5 Inspection and Testing Schedules                                  5 Appendix B Technical Specifications                          5 B.1        Technical Specifications                          5 B.2        Technical Specifications Relocated to the FSAR    5 B.3        Relocated Technical Specifications and Related    5 Bases                                              5 B.4        References                                        5 Appendix C Structural Loading Criteria                        5 C.1       Scope                                              5 C.2        Concrete and Steel Structures                      5 C.3        Components                                        5 Appendix D Quality Assurance Program                          5 D.1       General                                            5 D.2       Program Organization and Responsibility            5 D.3       Quality Surveillance and Auditing                  5 D.4       Quality Controls and Assurance Measures            5 D.5       QC-QA Documentation and Records                    5 D.6       Project Communications                            5 Attachment D.I   General Electric Quality System for BWR Nuclear Steam Supply Projects      5 Attachment D.II Bechtel Quality Assurance Program, Pilgrim Nuclear Power Station                      5 Attachment D.III Site Handling and Storage of Nuclear Steam Supply System Equipment, Pilgrim Nuclear Power Station                              5 Summ T of C-v        Rev. 30 - Nov. 2015
-viii Rev. 30  Nov. 2015 Section Title Volume Appendix O Analysis of the Consequences of  High Energy Piping Failures Outside The Primary Containment  7 O.1 Introduction 7 O.2 Analysis Assumptions 7 O.3 Analysis Approach 7 O.4 Structural Loading Analytical Technique 7 O.5 Jet and Fluid Forces Analytical Techniques 7 O.6 Detailed System Analyses  7 O.7 Environmental Qualification of Electrical  Equipment  7 Appendix P Deleted  7 Appendix Q Supplemental Reload Submittal  7 Q.1 Introduction 7
Appendix R Initial Core Station Safety Analysis 7  R.1 Introduction 7 R.2 Analyses of Abnormal Operational Transients (Initial Core)  7 R.3 Analysis of Design Basis Accidents (Initial Core) 7 R.4 Special Events (Initial Core)  7 R.5 Analytical Methods (Initial Core) 7 R.6 Evaluation Using Standard NRC Approach (Initial Core)   7  Appendix S License Renewal Commitments  7 S.1 Supplement for Renewed Operating License 7 S.2 Aging Management programs and Activities 7  Transients (Initial Core)  7 S.3 Evaluation of Time
-Limited Aging Analyses  7 S.4 References 7
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-vi.........................................30 Summ T of C
-vii........................................30 Summ T of C
-viii.......................................30


List of Effective Pages Vol. 7 (1 thru 10).............30 APPENDIX L
==SUMMARY==
TABLE OF CONTENTS (Cont)
Section    Title                                          Volume Appendix E Stack Release Limit Calculations for Pilgrim Station Site                                      5 E.1        Analytical Model                                  5 E.2        Verification of Analytical Model                  5 E.3        Stack Release Limit Calculations for Pilgrim Station Site                                      5 E.4        Building Exhaust Vent Release                    5 E.5        Summary                                          5 E.6        References                                        5 Appendix F Comparison of Pilgrim Nuclear Power Station with the Proposed General Design Criteria Published by the AEC for Public Comment in The Federal Register July 11, 1967                6 F.1        Summary Description                              6 F.2        Criteria Conformance                              6 Appendix G Station Nuclear Safety Operation Analysis Supporting Nuclear Safety Requirements for Plant Operation                                        6 G.1       Analytical Objective                              6 G.2        Bases for Selecting Operation Requirements for Plant Operation                                  6 G.3        Bases for Selecting Surveillance Test Frequencies for Nuclear Safety Systems and Engineered Safeguards for Plant Operation    6 G.4        Method of Analysis                                6 G.5        Analysis and Results                              6 G.6        Conclusion                                        6 Appendix H Tornado Criteria for Nuclear Power Plants        6 H.0        Foreword                                          6 H.1        Introduction                                      6 H.2        Characteristics of Tornadoes                      6 H.3        Tornado Probability                              6 H.4        Wind Loading                                      6 H.5        Pressure Differential                            6 H.6        Water Loss                                        6 H.7        Tornado Missiles                                  6 H.8        References                                        6 Summ T of C-vi        Rev. 30 - Nov. 2015


L-i....................................................28 L-ii...................................................28 L-iii..................................................28 L-iv...................................................28 L-v....................................................28
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==SUMMARY==
-8 ...............................17
TABLE OF CONTENTS (Cont)
Appendix I Site Investigation of the Seabreezes              6 I.1       Introduction                                      6 I.2        Results and Conclusions                            6 Section    Title                                            Volume I.3        Discussion                                        6 I.4        Data and Calculations                              6 I.5        References                                        6 Appendix J Station Research, Development, and Further Information Requirements and Resolution                                        6 J.1        Resolution of ACRS Concerns                        6 J.2        Areas Specified in the ACRS Construction Permit Letter for Pilgrim Nuclear Power Station                                            6 J.3        Areas Specified in the AEC Staff Construction Permit - Safety Evaluation Report for Pilgrim Nuclear Power Station          6 J.4        Areas Specified in Recent, Related ACRS Construction and Operating Permit Letters          6 J.5        Summary Conclusions                                6 J.6        References                                        6 Appendix K Inservice Inspection Program                      6 K.1        General                                            6 K.2        Inspection Program Development                    6 K.3        Inspection Program Implementation                  6 K.4        Reference Base Examinations                        6 K.5        Documentation and Records                          6 Appendix L Containment Report                                7 L.1        Introduction and Summary                          7 L.2        Basis for Containment Design                      7 L.3        Containment System Design                          7 L.4        Initial Overload and Leakage Rate Test            7 L.5        Manufacturer's Data Report for Nuclear Vessels                                            7 Appendix M Reactor Pressure Vessel Design Report              7 M.1       Introduction to the Report                        7 M.2        Summary                                            7 Appendix N Emergency Plan                                    7 Summ T of C-vii      Rev. 30 - Nov. 2015


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==SUMMARY==
-11 ..............................17 FL.2-2 Refer to C1A 3
TABLE OF CONTENTS (Cont)
-5 ...............................17 FL.2-3 Refer to C1A 4
Section    Title                                        Volume Appendix O Analysis of the Consequences of High Energy Piping Failures Outside The Primary Containment                          7 O.1       Introduction                                    7 O.2       Analysis Assumptions                            7 O.3        Analysis Approach                                7 O.4        Structural Loading Analytical Technique          7 O.5        Jet and Fluid Forces Analytical Techniques      7 O.6        Detailed System Analyses                        7 O.7        Environmental Qualification of Electrical Equipment                                        7 Appendix P Deleted                                          7 Appendix Q Supplemental Reload Submittal                    7 Q.1        Introduction                                    7 Appendix R Initial Core Station Safety Analysis            7 R.1        Introduction                                    7 R.2       Analyses of Abnormal Operational Transients (Initial Core)                        7 R.3       Analysis of Design Basis Accidents (Initial Core)                                  7 R.4       Special Events (Initial Core)                    7 R.5       Analytical Methods (Initial Core)                7 R.6       Evaluation Using Standard NRC Approach (Initial Core)                          7 Appendix S License Renewal Commitments                      7 S.1        Supplement for Renewed Operating License        7 S.2       Aging Management programs and Activities        7 Transients (Initial Core)                        7 S.3        Evaluation of Time-Limited Aging Analyses        7 S.4       References                                      7 Summ T of C-viii    Rev. 30 - Nov. 2015
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Page, Table (T), or Revision     Figure (F)     Number   EP7 - 2 of 10 Rev. 30 - Nov. 2015 FL-2-12 Refer to C1A 14
Page, Table (T), or                                   Revision Figure (F)                                       Number FL-2-12 Refer to C1A 14-4 .............................17 FL.2-13 Refer to C1A 15-6 .............................17 FL.2-14 Refer to C1A 16-4 .............................17 FL.2-15 Refer to C1A 17-5 .............................17 FL.2-16 Refer to C1A 19-10 ............................17 FL.2-17 Refer to C1A 20-7 .............................17 FL.2-18 Refer to C1A 21-5 .............................17 FL.2-19 Refer to C1A 50-5 .............................17 FL.2-20 Refer to C1A 51-7 .............................17 FL.2-21 Refer to C1A 52-5 .............................17 FL.2-22 Refer to C1A 58-4 .............................17 FL.2-23 Refer to C1A 62-4 .............................17 FL.2-24 Refer to C1A 100-3 ............................17 FL.2-25 Refer to C1A 185 ..............................17 L.3-1 Pages (1-13).....................................28 TL.3-1 (1 of 1)........................................28 TL.3-2 (1 of 1).........................................9 TL.3-3 (1 of 2)........................................11 TL.3-3 (2 of 2)........................................11 TL.3-4 (1 of 1).........................................5 TL.3-5 (1 of 1).........................................0 TL.3-6 (1 of 1).........................................0 TL.3-7 (1 of 1).........................................0 TL.3-8 (1 of 2).........................................1 TL.3-8 (2 of 2).........................................1 TL.3-9 (1 of 1).........................................2 TL.3-10 (1 of 1)........................................0 TL.3-11 (1 of 1).......................................21 TL.3-12 (1 of 1).......................................21 FL.3-1 (1 of 1).........................................0 FL.3-2 (1 of 1).........................................0 L.4-1...................................................0 L.5-1 (Form N-1)........................................0 L.5-2 (Form N-1)........................................0 L.5-3 (Form N-2)........................................0 L.5-4 (Form N-2)........................................0 EP7 - 2 of 10            Rev. 30 - Nov. 2015
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Page, Table (T), or Revision     Figure (F)     Number   EP7 - 3 of 10 Rev. 30 - Nov. 2015 APPENDIX M
Page, Table (T), or                                   Revision Figure (F)                                       Number APPENDIX M M-i....................................................29 M-ii...................................................29 M.1-1..................................................29 M.1-2..................................................29 FM.1-1 Refer to 1979-216-6 (C.E.)......................17 FM.1-2 Refer to 1979-185-3 (C.E.)......................17 M.2-1..................................................25 M.2-2..................................................25 APPENDIX N N.1-1...................................................9 APPENDIX O O-i....................................................11 O-ii...................................................11 O-iii...................................................9 O-iv....................................................5 O-v.....................................................5 O-vi....................................................5 O.1-1..................................................15 O.2-1..................................................15 O.2-1a.................................................15 O.2-2...................................................5 O.2-3...................................................5 TO.2-1 (1 of 1).........................................5 FO.2-1 (1 of 1).........................................5 FO.2-2 (1 of 1).........................................5 O.3-1...................................................9 EP7 - 3 of 10            Rev. 30 - Nov. 2015
 
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-216-6 (C.E.)......................17 FM.1-2 Refer to 1979
-185-3 (C.E.)......................17 M.2-1..................................................25 M.2-2..................................................25 APPENDIX N
 
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Latest revision as of 22:37, 30 October 2019

Redacted - Updated Final Safety Analysis Report (UFSAR) Part 5 - November 2015
ML16083A469
Person / Time
Site: Pilgrim
Issue date: 11/30/2015
From:
Entergy Nuclear Operations
To: Booma Venkataraman
Plant Licensing Branch 1
Ventkataraman V, DORL/LPLI-I, 415-2934
Shared Package
ML16083A494 List:
References
CAC MF7229
Download: ML16083A469 (381)


Text

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS Section Title Volume Section 1 Introduction and Summary 1 1.1 Project Identification 1 1.2 Definitions 1 1.3 Methods of Technical Presentation 1 1.4 Classification of BWR Systems, Criteria, 1 and Requirements for Safety Evaluation 1.5 Principal Design Criteria 1 1.6 Station Description 1 1.7 Comparison of Principal Design Characteristics 1 1.8 Summary of Radiation Effects 1 1.9 Station Management 1 1.10 Quality Assurance Program 1 1.11 Station Research, Development, and Further Information Requirements and Resolutions Summary 1 Section 2 Station Site and Environs 1 2.1 Introduction 1 2.2 Site Description 1 2.3 Meteorology 1 2.4 Hydrology 1 2.5 Geology and Seismology 1 2.6 Environs Radiation Surveillance Program 1 Section 3 Reactor 1 3.1 Summary Description 1 3.2 Fuel Mechanical Design 1 3.3 Reactor Vessel Internals Mechanical Design 1 3.4 Reactivity Control Mechanical Design 1 3.5 Control Rod Drive Housing Supports 1 3.6 Nuclear Design 1 3.7 Thermal and Hydraulic Design 1 3.8 Standby Liquid Control System 1 3.9 Recirculation Pump Trip, Alternate Rod Insertion, and Feedwater Pump Trip Systems 1 Section 4 Reactor Coolant System 2 4.1 Summary Description 2 4.2 Reactor Vessel and Appurtenances Mechanical Design 2 4.3 Recirculation System 2 4.4 Nuclear System Pressure Relief System 2 4.5 Main Steam Line Flow Restrictor 2 Summ T of C-i Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Section Title Volume 4.6 Main Steam Line Isolation Valves 2 4.7 Reactor Core Isolation Cooling System 2 4.8 Residual Heat Removal System 2 4.9 Reactor Water Cleanup System 2 4.10 Nuclear System Leakage Rate Limits 2 4.11 Main Steam Lines and Feedwater Piping 2 Section 5 Containment 2 5.1 Summary Descriptions 2 5.2 Primary Containment System 2 5.3 Secondary Containment System 2 5.4 Control of Combustible Gas Concentrations in Containment 2 Section 6 Core Standby Cooling Systems 2 6.1 Safety Objective 2 6.2 Safety Design Bases 2 6.3 Summary Description - Core Standby Cooling Systems 2 6.4 Description 2 6.5 Safety Evaluation 2 6.6 Inspection and Testing 2 6.7 The Nuclear Safety Requirements for Plant Operation 2 6.8 Current Technical Specifications 2 Section 7 Control and Instrumentation 3 7.1 Summary Description 3 7.2 Reactor Protection System 3 7.3 Primary Containment and Reactor Vessel Isolation Control System 3 7.4 Core Standby Cooling Systems Control and Instrumentation 3 7.5 Neutron Monitoring System 3 7.6 Refueling Interlocks 3 7.7 Reactor Manual Control System 3 7.8 Reactor Vessel Instrumentation 3 7.9 Recirculation Flow Control System 3 7.10 Feedwater Control System 3 7.11 Turbine Generator Control System 3 7.12 Process Radiation Monitoring 3 7.13 Area Radiation Monitoring System 3 7.14 Environs Radiation Monitors 3 7.15 Health Physics and Laboratory Analysis Radiation Monitors 3 Summ T of C-ii Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Section Title Volume 7.16 Process Computer System 3 7.17 Nuclear System Stability Analysis for Initial Core 3 7.18 Reactor Building Isolation and Control System 3 7.19 RHR Service Water System (SSW, RBCCW) 3 7.20 Equipment Area Cooling System 3 7.21 Meteorological Instrumentation 3 Section 8 Electrical Power System 4 8.1 Summary Description 4 8.2 Unit and Preferred AC Power Sources 4 8.3 Secondary AC Power Source 4 8.4 Auxiliary Power Distribution System 4 8.5 Standby AC Power Source 4 8.6 125 and 250 Volt DC Power Systems 4 8.7 24 Volt DC Power System 4 8.8 120 Volt AC Power Systems 4 8.9 Cable Installation Criteria 4 8.10 Blackout AC Power Source 4 Section 9 Radioactive Waste Systems 4 9.1 Summary Description 4 9.2 Liquid Radwaste System 4 9.3 Solid Radwaste System 4 9.4 Gaseous Radwaste System 4 9.5 Trash Compaction and Decontamination Facilities 4 Section 10 Auxiliary Systems 4 10.1 Summary Description 4 10.2 New Fuel Storage 4 10.3 Spent Fuel Storage 4 10.4 Fuel Pool Cooling and Cleanup System 4 10.5 Reactor Building Closed Cooling Water System 4 10.6 Turbine Building Closed Cooling Water System 4 10.7 Salt Service Water System 4 10.8 Fire Protection System 4 10.9 HVAC Systems 4 10.10 Makeup Water Treatment System 4 10.11 Instrument and Service Air Systems 4 10.12 Potable and Sanitary Water System 4 10.13 Equipment and Floor Drainage Systems 4 10.14 Process Sampling Systems 4 10.15 Communications Systems 4 10.16 Station Lighting System 4 10.17 Main Control Room Environmental Control System 4 10.18 Equipment Area Cooling System 4 10.19 Post Accident Sampling System 4 Summ T of C-iii Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Section Title Volume 10.20 Crack Arrest Verification System 4 10.21 Hydrogen Water Chemistry Extended Test System 4 10.22 Electrolytic Hydrogen Water Chemistry System 4 10.23 Mitigation Monitoring System 4 Section 11 Power Conversion Systems 4 11.1 Summary Description 4 11.2 Turbine-Generator 4 11.3 Main Condenser 4 11.4 Main Condenser Gas Removal and Turbine Sealing Systems 4 11.5 Turbine Bypass System 4 11.6 Circulating Water System 4 11.7 Condensate Demineralizer System 4 11.8 Condensate and Feedwater System 4 11.9 Condensate Storage System 4 Section 12 Structures and Shielding 4 12.1 Summary Description 4 12.2 Structural Design 4 12.3 Shielding and Radiation Protection 4 12.4 Radioactive Materials Safety 4 Section 13 Conduct of Operations 5 13.1 Introduction and Summary 5 13.2 Organization and Responsibilities 5 13.3 Training 5 13.4 Preoperational Test Program 5 13.5 Reactor Startup and Power Test Program 5 13.6 Station Procedures 5 13.7 Records 5 13.8 Operational Review and Audits 5 Section 14 Station Safety Analysis 5 14.1 Introduction 5 14.2 Reactor Limits 5 14.3 Method of Approach 5 14.4 Abnormal Operational Transients 5 14.5 Postulated Design Basis Accidents 5 14.6 Special Events 5 14.7 References 5 Summ T of C-iv Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Section Title Volume Appendix A Pressure Integrity of Piping and Equipment Pressure Parts 5 A.1 Scope 5 A.2 Classification of Piping and Equipment Pressure Parts 5 A.3 Design Requirements 5 A.4 Materials 5 A.5 Fabrication and Installation Requirements 5 A.6 Testing and Inspection Requirements 5 A.7 Final Cleaning and Protection 5 A.8 F1, F2, F3, and F4 Fabrication and Erection Schedule 5 A.9 M1, M2, and M3 Material Schedules 5 A.10 T1, T2, T3, T4, and T5 Inspection and Testing Schedules 5 Appendix B Technical Specifications 5 B.1 Technical Specifications 5 B.2 Technical Specifications Relocated to the FSAR 5 B.3 Relocated Technical Specifications and Related 5 Bases 5 B.4 References 5 Appendix C Structural Loading Criteria 5 C.1 Scope 5 C.2 Concrete and Steel Structures 5 C.3 Components 5 Appendix D Quality Assurance Program 5 D.1 General 5 D.2 Program Organization and Responsibility 5 D.3 Quality Surveillance and Auditing 5 D.4 Quality Controls and Assurance Measures 5 D.5 QC-QA Documentation and Records 5 D.6 Project Communications 5 Attachment D.I General Electric Quality System for BWR Nuclear Steam Supply Projects 5 Attachment D.II Bechtel Quality Assurance Program, Pilgrim Nuclear Power Station 5 Attachment D.III Site Handling and Storage of Nuclear Steam Supply System Equipment, Pilgrim Nuclear Power Station 5 Summ T of C-v Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Section Title Volume Appendix E Stack Release Limit Calculations for Pilgrim Station Site 5 E.1 Analytical Model 5 E.2 Verification of Analytical Model 5 E.3 Stack Release Limit Calculations for Pilgrim Station Site 5 E.4 Building Exhaust Vent Release 5 E.5 Summary 5 E.6 References 5 Appendix F Comparison of Pilgrim Nuclear Power Station with the Proposed General Design Criteria Published by the AEC for Public Comment in The Federal Register July 11, 1967 6 F.1 Summary Description 6 F.2 Criteria Conformance 6 Appendix G Station Nuclear Safety Operation Analysis Supporting Nuclear Safety Requirements for Plant Operation 6 G.1 Analytical Objective 6 G.2 Bases for Selecting Operation Requirements for Plant Operation 6 G.3 Bases for Selecting Surveillance Test Frequencies for Nuclear Safety Systems and Engineered Safeguards for Plant Operation 6 G.4 Method of Analysis 6 G.5 Analysis and Results 6 G.6 Conclusion 6 Appendix H Tornado Criteria for Nuclear Power Plants 6 H.0 Foreword 6 H.1 Introduction 6 H.2 Characteristics of Tornadoes 6 H.3 Tornado Probability 6 H.4 Wind Loading 6 H.5 Pressure Differential 6 H.6 Water Loss 6 H.7 Tornado Missiles 6 H.8 References 6 Summ T of C-vi Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Appendix I Site Investigation of the Seabreezes 6 I.1 Introduction 6 I.2 Results and Conclusions 6 Section Title Volume I.3 Discussion 6 I.4 Data and Calculations 6 I.5 References 6 Appendix J Station Research, Development, and Further Information Requirements and Resolution 6 J.1 Resolution of ACRS Concerns 6 J.2 Areas Specified in the ACRS Construction Permit Letter for Pilgrim Nuclear Power Station 6 J.3 Areas Specified in the AEC Staff Construction Permit - Safety Evaluation Report for Pilgrim Nuclear Power Station 6 J.4 Areas Specified in Recent, Related ACRS Construction and Operating Permit Letters 6 J.5 Summary Conclusions 6 J.6 References 6 Appendix K Inservice Inspection Program 6 K.1 General 6 K.2 Inspection Program Development 6 K.3 Inspection Program Implementation 6 K.4 Reference Base Examinations 6 K.5 Documentation and Records 6 Appendix L Containment Report 7 L.1 Introduction and Summary 7 L.2 Basis for Containment Design 7 L.3 Containment System Design 7 L.4 Initial Overload and Leakage Rate Test 7 L.5 Manufacturer's Data Report for Nuclear Vessels 7 Appendix M Reactor Pressure Vessel Design Report 7 M.1 Introduction to the Report 7 M.2 Summary 7 Appendix N Emergency Plan 7 Summ T of C-vii Rev. 30 - Nov. 2015

PNPS-FSAR

SUMMARY

TABLE OF CONTENTS (Cont)

Section Title Volume Appendix O Analysis of the Consequences of High Energy Piping Failures Outside The Primary Containment 7 O.1 Introduction 7 O.2 Analysis Assumptions 7 O.3 Analysis Approach 7 O.4 Structural Loading Analytical Technique 7 O.5 Jet and Fluid Forces Analytical Techniques 7 O.6 Detailed System Analyses 7 O.7 Environmental Qualification of Electrical Equipment 7 Appendix P Deleted 7 Appendix Q Supplemental Reload Submittal 7 Q.1 Introduction 7 Appendix R Initial Core Station Safety Analysis 7 R.1 Introduction 7 R.2 Analyses of Abnormal Operational Transients (Initial Core) 7 R.3 Analysis of Design Basis Accidents (Initial Core) 7 R.4 Special Events (Initial Core) 7 R.5 Analytical Methods (Initial Core) 7 R.6 Evaluation Using Standard NRC Approach (Initial Core) 7 Appendix S License Renewal Commitments 7 S.1 Supplement for Renewed Operating License 7 S.2 Aging Management programs and Activities 7 Transients (Initial Core) 7 S.3 Evaluation of Time-Limited Aging Analyses 7 S.4 References 7 Summ T of C-viii Rev. 30 - Nov. 2015

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Page, Table (T), or Revision Figure (F) Number VOLUME 7 Summ T of C-i..........................................30 Summ T of C-ii.........................................30 Summ T of C-iii........................................30 Summ T of C-iv.........................................30 Summ T of C-v..........................................30 Summ T of C-vi.........................................30 Summ T of C-vii........................................30 Summ T of C-viii.......................................30 List of Effective Pages Vol. 7 (1 thru 10).............30 APPENDIX L L-i....................................................28 L-ii...................................................28 L-iii..................................................28 L-iv...................................................28 L-v....................................................28 L.1-1...................................................0 FL.1-1 Refer to C1A 1-8 ...............................17 L.2-1...................................................0 TL.2-1 (1 of 9)........................................25 TL.2-1 (2 of 9)........................................25 TL.2-1 (3 of 9)........................................25 TL.2-1 (4 of 9)........................................25 TL.2-1 (5 of 9)........................................25 TL.2-1 (6 of 9)........................................25 TL.2-1 (7 of 9)........................................25 TL.2-1 (8 of 9)........................................25 TL.2-1 (9 of 9)........................................25 FL.2-1 Refer to C1A 2-11 ..............................17 FL.2-2 Refer to C1A 3-5 ...............................17 FL.2-3 Refer to C1A 4-8 ...............................17 FL.2-4 Refer to C1A 5-11 ..............................17 FL.2-5 Refer to C1A 6-8 ...............................17 FL.2-6 Refer to C1A 7-6 ...............................17 FL.2-7 Refer to C1A 8-7 ...............................17 FL.2-8 Refer to C1A 9-7 ...............................17 FL.2-9 Refer to C1A 10-4 ..............................17 FL.2-10 Refer to C1A 12-5 .............................17 FL.2-11 Refer to C1A 13-4 .............................17 EP7 - 1 of 10 Rev. 30 - Nov. 2015

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Page, Table (T), or Revision Figure (F) Number FL-2-12 Refer to C1A 14-4 .............................17 FL.2-13 Refer to C1A 15-6 .............................17 FL.2-14 Refer to C1A 16-4 .............................17 FL.2-15 Refer to C1A 17-5 .............................17 FL.2-16 Refer to C1A 19-10 ............................17 FL.2-17 Refer to C1A 20-7 .............................17 FL.2-18 Refer to C1A 21-5 .............................17 FL.2-19 Refer to C1A 50-5 .............................17 FL.2-20 Refer to C1A 51-7 .............................17 FL.2-21 Refer to C1A 52-5 .............................17 FL.2-22 Refer to C1A 58-4 .............................17 FL.2-23 Refer to C1A 62-4 .............................17 FL.2-24 Refer to C1A 100-3 ............................17 FL.2-25 Refer to C1A 185 ..............................17 L.3-1 Pages (1-13).....................................28 TL.3-1 (1 of 1)........................................28 TL.3-2 (1 of 1).........................................9 TL.3-3 (1 of 2)........................................11 TL.3-3 (2 of 2)........................................11 TL.3-4 (1 of 1).........................................5 TL.3-5 (1 of 1).........................................0 TL.3-6 (1 of 1).........................................0 TL.3-7 (1 of 1).........................................0 TL.3-8 (1 of 2).........................................1 TL.3-8 (2 of 2).........................................1 TL.3-9 (1 of 1).........................................2 TL.3-10 (1 of 1)........................................0 TL.3-11 (1 of 1).......................................21 TL.3-12 (1 of 1).......................................21 FL.3-1 (1 of 1).........................................0 FL.3-2 (1 of 1).........................................0 L.4-1...................................................0 L.5-1 (Form N-1)........................................0 L.5-2 (Form N-1)........................................0 L.5-3 (Form N-2)........................................0 L.5-4 (Form N-2)........................................0 EP7 - 2 of 10 Rev. 30 - Nov. 2015

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Page, Table (T), or Revision Figure (F) Number APPENDIX M M-i....................................................29 M-ii...................................................29 M.1-1..................................................29 M.1-2..................................................29 FM.1-1 Refer to 1979-216-6 (C.E.)......................17 FM.1-2 Refer to 1979-185-3 (C.E.)......................17 M.2-1..................................................25 M.2-2..................................................25 APPENDIX N N.1-1...................................................9 APPENDIX O O-i....................................................11 O-ii...................................................11 O-iii...................................................9 O-iv....................................................5 O-v.....................................................5 O-vi....................................................5 O.1-1..................................................15 O.2-1..................................................15 O.2-1a.................................................15 O.2-2...................................................5 O.2-3...................................................5 TO.2-1 (1 of 1).........................................5 FO.2-1 (1 of 1).........................................5 FO.2-2 (1 of 1).........................................5 O.3-1...................................................9 EP7 - 3 of 10 Rev. 30 - Nov. 2015

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