Nuclear Safety

Appendix 9: IAEA Criteria

Safety of nuclear power plant: Design Requirements Safety Standards Series No. NS-R-1, ISBN 92-0-101900-9).

This appendix comprises the list of contents for the above IAEA document and is included to show an example of the contents of a modern set of Design Safety Criteria for Nuclear Plants. The complete document can be obtained from the IAEA or viewed at http://www.iaea.org.

CONTENTS

  1. INTRODUCTION

    • Background (1.1)

    • Objective (1.2 1.4)

    • Scope (1.5 1.7)

    • Structure (1.8)

  2. SAFETY OBJECTIVES AND CONCEPTS

    • Safety objectives (2.1 2.8)

    • The concept of Defense in Depth (2.9 2.11)

  3. REQUIREMENTS FOR MANAGEMENT OF SAFETY

    • Responsibilities in management (3.1)

    • Management of design (3.2 3.5)

    • Proven engineering practices (3.6 3.8)

    • Operational experience and safety research (3.9)

    • Safety assessment (3.10 3.12)

    • Independent verification of the safety assessment (3.13)

    • Quality assurance (3.14 3.16)

  4. PRINCIPAL TECHNICAL REQUIREMENT

    • Requirements for Defense in Depth (4.1 4.4)

    • Safety functions (4.5 4.7)

    • Accident prevention and plant safety characteristics (4.8)

    • Radiation protection and acceptance criteria (4.9 4.13)

  5. REQUIREMENTS FOR PLANT DESIGN

    • Safety classification (5.1 5.3)

    • General design basis (5.4 5.31)

    • Design for reliability of structures, systems and components (5.32 5.42)

    • Provision for in-service testing, maintenance, repair, inspection and monitoring (5.43 5.44)

    • Equipment qualification (5.45 5.46)

    • Ageing (5.47)

    • Human factors (5.48 5.56)

    • Other design considerations (5.57 5.68)

    • Safety analysis (5.69 5.73)

  6. REQUIREMENTS FOR DESIGN OF PLANT SYSTEMS

    • Reactor core and associated features (6.1 6.20)

    • Reactor coolant system (6.21 6.42)

    • Containment system (6.43 6.67)

    • Instrumentation and control (6.68 6.86)

    • Emergency control centre (6.87)

    • Emergency power supply (6.88 6.89)

    • Waste treatment and control systems (6.90 6.95)

    • Fuel handling and storage systems (6.96 6.98)

    • Radiation protection (6.99 6.106)

APPENDIX I: POSTULATED INITIATING

EVENTS APPENDIX II: REDUNDANCY, DIVERSITY

AND INDEPENDENCE...

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