ML18018A801

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 1 - Table of Contents

ML18018A801
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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BFN-26 1.0-i

1.0 INTRODUCTION

AND

SUMMARY

TABLE OF CONTENTS 1.1 Project Identification.................................................................................................................. 1.1-1 1.1.1 Identification and Qualification of Contractors............................................................ 1.1-1 1.1.2 Licensing Basis Documents....................................................................................... 1.1-3 1.2 Definitions.................................................................................................................................. 1.2-1 1.3 Methods of Technical Presentation........................................................................................... 1.3-1 1.3.1 Purpose..................................................................................................................... 1.3-1 1.3.2 Radioactive Material Barrier Concept........................................................................ 1.3-1 1.3.3 Organization of Contents........................................................................................... 1.3-1 1.3.4 Format Organization of Sections................................................................................ 1.3-2 1.3.5 Power Level Basis for Analysis of Abnormal Operational Transients and Accidents............................................................................................................ 1.3-3 1.4 Classification of BWR Systems, Criteria, and Requirements for Safety Evaluation................... 1.4-1 1.4.1 Introduction................................................................................................................ 1.4-1 1.4.2 Classification Basis.................................................................................................... 1.4-1 1.4.3 Use of the Classification Plan.................................................................................... 1.4-2 1.5 Principal Design Criteria............................................................................................................ 1.5-1 1.5.1 Principal Design Criteria Classification-by-Classification........................................... 1.5-1 1.5.2 Principal Design Criteria, System-By-System............................................................ 1.5-7 1.6 Plant Description....................................................................................................................... 1.6-1 1.6.1 General...................................................................................................................... 1.6-1 1.6.2 Nuclear Safety Systems and Engineered Safeguards............................................... 1.6-9 1.6.3 Special Safety Systems............................................................................................. 1.6-15 1.6.4 Process Control and Instrumentation......................................................................... 1.6-15 1.6.5 Auxiliary Systems....................................................................................................... 1.6-19 1.6.6 Shielding.................................................................................................................... 1.6-22 1.6.7 Implementation of Loading Criteria............................................................................ 1.6-22 1.7 Comparison of Principal Design Characteristics........................................................................ 1.7-1 1.7.1 Nuclear System Design Characteristics..................................................................... 1.7-1 1.7.2 Power Conversion Systems Design Characteristics.................................................. 1.7-1 1.7.3 Electrical Power Systems Design Characteristics...................................................... 1.7-1 1.7.4 Containment Design Characteristics.......................................................................... 1.7-1 1.7.5 Structural Design Characteristics............................................................................... 1.7-2 1.7.6 Discussion of Core Design Improvement................................................................... 1.7-2

BFN-26 1.0-ii

1.0 INTRODUCTION

AND

SUMMARY

TABLE OF CONTENTS (Cont'd) 1.8 Summary of Radiation Effects................................................................................................... 1.8-1 1.8.1 Normal Operation....................................................................................................... 1.8-1 1.8.2 Abnormal Operational Transients.............................................................................. 1.8-1 1.8.3 Accidents................................................................................................................... 1.8-1 1.9 Plant Management.................................................................................................................... 1.9-1 1.10 Quality Assurance Program....................................................................................................... 1.10-1 1.11 Identification-Resolution of Construction Permit Concern - Summary....................................... 1.11-1 1.11.1 General...................................................................................................................... 1.11-1 1.12 General Conclusions................................................................................................................. 1.12-1

BFN-26 1.0-iii INTRODUCTION AND

SUMMARY

LIST OF TABLES Table Title 1.3-1 List of FSAR Engineering Drawings 1.3-2 Engineering Drawings Cross-Reference List 1.4-1 BWR Safety Engineering Concept for Classification of BWR Systems, Criteria, and Requirements for Safety Evaluation 1.4-2A Classification of BWR Systems, Criteria, and Requirements for Safety Evaluation 1.4-2B Classification of BWR Systems, Criteria, and Requirements for Safety Evaluation 1.7-1 Comparison of Nuclear System Design Characteristics 1.7-2 Comparison of Power Conversion Systems Design Characteristics 1.7-3 Comparison of Electrical Power System Design Characteristics 1.7-4 Comparison of Containment Design Characteristics 1.7-5 Comparison of Containment Design Characteristics 1.11-1 Browns Ferry Nuclear Plant Topical Reports Submitted to the AEC in Support of Docket 1.11-2 Browns Ferry Nuclear Plant AEC-ACRS Concerns - Resolutions 1.11-3 Browns Ferry Nuclear Plant AEC-Staff Concerns - Resolutions Units 1 and 2 1.11-4 AEC-Staff Concerns - Resolutions Unit 3 1.11-5 AEC-ACRS Concerns On Other Dockets - Resolutions 1.11-6 AEC-ACRS Concerns On Other Dockets - Capability for Resolution

BFN-26 1.0-iv INTRODUCTION AND

SUMMARY

LIST OF ILLUSTRATIONS Figure Title 1.2-1 Relationship Between Safety Action and Protective Action 1.2-2 Relationship Between Protective Functions and Protective Actions 1.2-3 Relationships Between Different Types of Systems, Actions, and Objectives 1.3-1 Piping and Instrument Symbols 1.3-2 General Symbols Flow Diagram 1.6-1

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BFN-26 1.0-v INTRODUCTION AND

SUMMARY

LIST OF ILLUSTRATIONS (Cont'd)

Figure Title 1.6-25

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1.6-26

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1.6-27

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1.6-28 Reactor Heat Balance - Pre-uprated Power 1.6-28a Reactor Heat Balance - Uprated Power 1.6-29 sht 1 Turbine-Generator Heat Balance - Rated Power (Unit 2) 1.6-29 sht 2 Turbine-Generator Heat Balance - Rated Power (Unit 3) 1.6-29 sht 3 Turbine-Generator Heat Balance - Rated Power (Unit 1) 1.6-30 General Plant Systems Flow Diagram