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  • Boiling Water Reactor GE BWR/4 Technology

    Technology Manual

    Chapter 4.0

    Containment Systems

  • TABLE OF CONTENTS

    4.0 CONTAINMENT SYSTEMS ............................................................................. 1

    4.0.1 Primary Containment System .................................................................. 1

    4.0.2 Secondary Containment System ................................................................. 1

    4.0.3 Reactor Building Standby Ventilation System ............................................... 1

    4.0.4 Nuclear Steam Supply Shutoff System ........................................................ 1

    4.0.5 Control Room Ventilation System ............................................................. 1

    LIST OF FIGURES

    4.0-1 Mark II Containment System ....................................................................... 3

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    USNRC Technical Training Center

    G.E. Technology Systems Manual Containment Systems

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  • G.E. Technology Systems Manual Containment Systems

    4.0 CONTAINMENT SYSTEMS

    The containment systems, shown in Figure 4.0 1, provide a multibarrier pressure suppression type of containment. The containment systems provide two distinct fission product barriers (the primary containment and the secondary containment) in addition to the other fission product barriers that already exist (fuel cladding and reactor coolant pressure boundary). The term "pressure suppression" comes from the fact that

    steam generated as a result of a loss of coolant accident is channeled to a suppression pool, where it is condensed. This suppresses the peak pressure that otherwise would be realized in the primary containment.

    4.0.1 Primary Containment System (Section 4.1)

    The Primary Containment System contains fission products released from a loss of coolant accident (LOCA) so that off site radiation dose limits specified in 10 CFR 100 are not exceeded; provides a heat sink for certain safety related equipment; and provides a source of water for Emergency Core Cooling Systems and the Reactor Core Isolation Cooling System.

    4.0.2 Secondary Containment System (Section 4.2)

    The Secondary Containment System minimizes the ground level release of radioactive material following an accident and provides the contain ment boundary when the primary containment is not intact.

    4.0.3 Reactor Building Standby Ventilation System (Section 4.3)

    The Reactor Building Standby Ventilation System processes the secondary containment atmosphere prior to release under accident conditions; provides a means of venting the primary containment; and performs leak tests of the secondary containment.

    4.0.4 Nuclear Steam Supply Shutoff System (Section 4.4)

    The Nuclear Steam Supply Shutoff System (NSSSS) isolates the primary and secondary

    containments during accident conditions to limit the release of radioactive materials to within 10 CFR 100 limits.

    4.0.5 Control Room Ventilation System (Section 4.5)

    The Control Room Ventilation System ensures that control room operators can remain in the control room and take actions to operate and maintain the plant in a safe condition under all accident conditions.

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    Secondary Containment

    Primary Containment

    Pressure Suppression

    Chamber

    Figrue 4.0-1 Mark II Containment System

    4.0-3

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  • Boiling Water Reactor GE BWR/4 Technology

    Technology Manual

    Chapter 4.1

    Primary Containment System

  • G.E., Technology Systems Manual 'Primary Containment System

    TABLE OF CONTENTS

    4.1 PRIMARY CONTAINMENT SYSTEM ................................................................. 1

    4.1.1 Introduction ........................................................................................ 1

    4.1.2 Component Description ......................................................................... 2

    4.1.2.1 Drywell ................................................................................. 2

    4.1.2.2 Suppression Chamber ....................................... 3

    4.1.2.3 Interconnecting Vent System ............................... 3

    4.1.2.4 Primary Containment Auxiliary Systems ............................................. 4

    4.1.3 System Features and Interfaces ................................................................. 6

    4.1.3.1 Primary Containment Integrity ......................................................... 6

    4.1.3.2 Normal Operation ........................................................................ 7

    4.1.3.3 Containment Heat Removal ............................................................ 7

    4.1.3.4 Containment Response to a LOCA ................................................... 7

    4.1.3.5 Suppression Pool Temperature Monitoring ........................................... 9

    4.1.3.6 System Isolation .......................................................................... 9

    4.1.3.7 System Interfaces ....................................................................... 9

    4.1.4 BWR Differences ............................................................................... 10

    4.1.5 PRA Insights .................................................................................... 10

    4.1.6 Summary ....................................................................................... 11

    LIST OF TABLES

    4.1-1 Primary Containment Design Summary ........................................................... 13

    4.1-2 Primary Containment Design Summary ........................................................... 15

    4.1-3 LOCA Chronology ..................................................................................... 17

    USNRC Technical Training Center 4.1-i Rev 0197-• USNRC Technical Training Center I 4.1-i Rev 0197

  • I -__________

    G.E. Technology Systems Manual Primary Containment System

    LIST OF FIGURES

    4.1-1 Primary Containment (Drywell) .................................................................. 19 4.1-2 Drywell Head ....................................................................................... 21 4.1-3 Drywell Access Penetrations ...................................................................... 23 4.1-4 Drywell Pipe Penetrations ......................................................................... 25 4.1-5 Primary Containment Auxiliary Systems ........................................................ 27 4.1-6 Primary Containment Instrumentation & Atmosphere Monitoring System ..................... 29

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  • G.E. Technology Systems Manual Primary Containment System

    4.1 PRIMARY CONTAINMENT SYSTEM

    Lesson Objectives:

    1. State the system's purposes. 2. Explain how the system accomplishes its

    purposes. -3. -Explain the general arrangement and purpose

    of the following major system components: -a. Drywell b. Vertical downcomers (vents) c. Suppression chamber d. Suppression pool e. Suppression chamber to drywell vacuum

    breakers f.- Primary Containment Purge System

    4. Explain the multibarrier, pressure suppres sion concept as applied to the Mark II Containment design.

    5. Describe what constitutes the primary containment fission product barrier.

    -6. Explain the primary containment response to a major loss of coolant accident.

    7. Explain how POST-LOCA hydrogen gas concentration is controlled.

    8. Define primary containment integrity. 9. Describe the interfaces between this system

    and the following: - a., Main Steam System

    b. Reactor Core Isolation Cooling System c., Secondary Containment System d. Reactor-Building Standby Ventilation

    -System e. -Nuclear Steam 'Supply Shutoff System f. High Pressure Coolant Injection System g. Core Spray System • h. Residual Heat Removal System

    4.1.1 Introduction

    The purposes of the Primary Containment System are to contain fission products released

    - from a loss of coolant accident (LOCA) so that off site radiation dose limits specified in 10 CFR 100 are not exceeded, condense steam, provide a

    -. heat sink for certain safety related equipment, and to provide a source of water for Emergency Core Cooling Systems and the Reactor Core Isolation

    2Cooling System....

    The functional classification-'of ,the Primary Containment System is that of a safety related system. Its' regulatory classification is that of an engineered safety feature (ESF) system.

    The Primary Containment System consists of several major components, many of which can be seen in Figure 4.1-1. These major components include the drywell, which surrounds the reactor vessel' and recirculation loops; a suppression chamber, which stores a large body of water (the suppression pool); and an interconnecting vent network between the drywell and suppression chamber. Additionally,- there are numerous auxiliary systems for the Primary C

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