Periodic Safety Review of Nuclear Power Plants

0,39

MB

62

stron

4687

ID

International Atomic Energy Agency

2003

rok

CONTENTS

1. INTRODUCTION . 1

Background (1.1–1.2) . 1

Objective (1.3) . 1

Scope (1.4–1.5) . 1

Structure (1.6) . 2

2. RATIONALE FOR AND OBJECTIVE OF PERIODIC SAFETY REVIEW 2

Rationale for a PSR (2.1–2.7) 2

Objective of a PSR (2.8) . 4

3. REVIEW STRATEGY (3.1–3.9) . 4

4. SAFETY FACTORS IN A PERIODIC SAFETY REVIEW . 6

Introduction (4.1–4.9) . 6

Plant design (4.10–4.13) . 9

Actual condition of systems,

structures and components (4.14–4.16) . 10

Equipment qualification (4.17–4.20) . 11

Ageing (4.21–4.25) 12

Deterministic safety analysis (4.26–4.28) . 13

Probabilistic safety assessment (4.29–4.32) . 14

Hazard analysis (4.33–4.35) 15

Safety performance (4.36–4.38) . 16

Use of experience from other plants and research findings (4.39–4.40) 17

Organization and administration (4.41–4.42) 18

Procedures (4.43–4.44) 19

Human factors (4.45–4.46) . 20

Emergency planning (4.47–4.48) 20

Radiological impact on the environment (4.49–4.50) . 21

Global assessment (4.51–4.52) 22

5. ROLES AND RESPONSIBILITIES (5.1–5.4) 22

6. REVIEW PROCEDURE . 23

Introduction (6.1–6.2) . 23

Activities of the plant operating organization (6.3–6.17) 29

Activities of the regulatory body (6.18–6.24) 32

7. BASIS FOR ACCEPTABILITY OF CONTINUED PLANT OPERATION (7.1–7.3) . 33

8. POST-REVIEW ACTIVITIES (8.1–8.4) . 35

APPENDIX: ELEMENTS OF THE REVIEW . 36

REFERENCES . 43

GLOSSARY . 46

CONTRIBUTORS TO DRAFTING AND REVIEW 49

BODIES FOR THE ENDORSEMENT OF SAFETY STANDARDS 50