Control System Architecture for a Modern Nuclear Power Plant PowerPoint PPT Presentation

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Title: Control System Architecture for a Modern Nuclear Power Plant


1
Control System Architecture for a Modern Nuclear
Power Plant
  • Presented by J. Harber
  • P. Foster, A. Xing
  • Atomic Energy of Canada Limited
  • IAEA Tech Meeting, Beijing China
  • Nov 3-6, 2008

Unrestricted
2
Presentation Outline
  • Modern IC Design Concepts
  • Safety Categorization of Functions
  • IC Platforms System Architecture
  • Summary

CANDU, ACR-1000 and ACR are registered
trade-marks of Atomic Energy of Canada Limited
3
Modern IC Design Concepts
  • IEC Standards for development of Programmable
    Electronic Systems (PESs)
  • Concepts of system development based on safety
    significance of the functions being provided by
    programmable devices
  • IEC 61226, IEC 61513, IEC 62138, IEC 60880, (IEC
    61508)
  • Better understanding of human performance design
  • Improved information presentation
  • Alarm processing and prioritization
  • Initial implementations in recent builds
  • Increased emphasis on documenting the safety case
    for the design

4
Safety Categorization of Functions
  • Based on principles of IEC 61226, safety
    functions in all systems are categorized and
    their importance to safety is identified
  • Safety functions performed by each system are
    identified
  • Safety functions are based on principles of IAEA
    NS-R-1
  • Probabilistic safety assessments provide design
    assist and ensure that safety goals are met by
    the design (along with deterministic analysis).

5
ACR-1000 IC Design Features
  • Safety Related systems across the station are
    divided into two functional groups
  • Implementing 2 of 4 logic in ACR-1000 IC where
    reliable signals are required
  • Limited sharing of measurement signals as
    permitted by Canadian regulations

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Distributed Control System for Monitoring and
Control Functions
  • Distributed Control System (DCS) consists of two
    subsystems
  • Essential Control Subsystem (ECSS)
  • Largely Category B functions
  • Five safety systems are independent of the DCS
  • Plant Control Subsystem (PCSS)
  • Normal Process Control Functions
  • Allocation of functions to DCS subsystems based
    on safety category

7
Operator Displays Control Interface Systems
  • Safety System Monitoring Computers (SSMC)
  • Displays for Category A and B functions
  • Plant Display System (PDS)
  • Displays and control interface for Category C
    (and non-safety) functions

8
ACR-1000 IC Platforms
  • Trip computers used in two fully independent
    shutdown systems
  • Combination of hardwired and qualified digital
    controllers used for Category A B safety
    functions
  • Distributed control system (DCS) used for
    monitoring and control functions
  • Safety System Monitoring Computers Plant
    Display System used for monitoring operator
    interface functions

9
Category A and B Functions
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Category C and Non-safety
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Overview of the Instrumentation and Control
Systems of the ACR-1000
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Overview of ACR-1000 Monitoring and Control
Platforms
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Field Control Equipment Rooms
  • Distribution of monitoring and control functions

For shutdown and long term heatsink monitoring
when MCR unavailable
14
Summary
  • Categorization of functions
  • Supports IC system development, operator
    interface design, and Probabilistic Safety
    Assessment (PSA) studies
  • Enhanced monitoring and control systems
  • IC system development in accordance with safety
    significance
  • Improved operator interface maintenance
    diagnostics
  • Safety System Monitoring Computers
  • Plant Display System
  • Improved documentation to develop monitoring and
    control functions

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