IAEA-TECDOC-609. Assessing the effectiveness. of quality management. for nuclear power plant operation IAEA

Transcription

1 IAEA-TECDOC-609 Assessing the effectiveness of quality management for nuclear power plant operation IAEA June 1991

2 The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be obtained from INIS Clearinghouse International Atomic Energy Agency Wagramerstrasse

3 PLEASE

4 ASSESSING

5 FOREWORD Measuring the effectiveness of Quality Management is useful for providing feedback

6 superintendent

7 CONTENTS 1. INTRODUCTION...

8 APPENDIX 10: EXAMPLES OF DISPLAY OF PERFORMANCE INDICATORS APPENDIX

9 1.1. Background 1. INTRODUCTION

10 satisfactory operation

11 The methodology presented is for an operating plant only. It is not intended for application during other stages of the plant life-cycle. effectiveness of the management of organizations carrying out design or construction work The

12 Important factors

13 Data

14 cause and effect analysis, brainsterming, scatter diagrams and control charts, all of which are described in detail in published text book references. Root cause analysis

15 this and to note any aspect of quality achievement from earlier stages which could affect quality during operation. One utility's approach to such a formal statement is given in Appendix 2, 4. INDICATORS 4.1. Performance indicators Several Member States have developed sets

16 relate generally

17 4.3. Audit indicators

18 5. EVALUATION To arrive at a comprehensive understanding of the effectiveness of Quality Management, it is necessary to evaluate the data from each of the groups

19 INDICATORS EVALUATE DATA ANALYSE CAUSE CONCLUSIONS Performance Indicators of verall plan objectives Measure trends redictive Indicators Time-based quantitative data

20 Time intervals should

21 findings of audits and the effectiveness of the audit process. Analysis of trends and general audit effectiveness is a further indication of Quality Management effectiveness

22 Some organizations consider that

23 Item Ho. Note 1. Report Serial No. Date of Issue 2. Date of Last Report and Serial

24

25 APPENDICES

26 Appendix 1 QUALITY MANAGEMENT PRINCIPLES

27 Appendix

28 Commissioning and Operations

29 Appendix

30 Appendix

31 Environmental Protection

32 Appendix

33 Appendix

34 A. OVERALL PERFORMANCE INDICATORS (INPO-UNIPEDE )

35 o Description:- Available energy generation divided by maximum energy generation Available energy generation reduced

36 Unplanned energy loss factor + energy availability factor + planned energy loss factor (detailed indicator) = 100 percent of maximum energy generation 5. Indicator:- Thermal Performance o Purpose:- To monitor progress in achieving and maintaining efficient thermal operation. It provides an indication of success toward meeting design capabilities. design values A plant operating at or near

37 o Description:-

38 Includes only utility personnel permanently assigned

39 preventive maintenance items overdue indicates a station committment to the preventive maintenance program and an ability to plan, schedule, and perform preventive maintenance tasks as programs require.

40 activities.

41 Appendix 7 TYPICAL PERFORMANCE MEASURES This Appendix presents typical performance measures used in some Member States in assessing the operation quality system. (A) NPP overall performance: Lost time accidents

42 (D) Technical support: Backlog of technical work (estimated man-hours) Technical surveillance omitted

43 Appendix 8 THE UNITED STATES NUCLEAR REGULATORY COMMISSION'S PERFORMANCE INDICATOR PROGRAM

44

45 Appendix 9 FINNISH PERFORMANCE INDICATORS Possible Topics

46 Appendix

47 ^ DEFiCIENCY REPORT COMPLETIONS ; 250^.a I ^ Year

48 Appendix 11 OVERALL PLANT NON-CONFORMANCE INDICATORS

49 CLASSIFICATION Appendix 12

50

51 EVENT FEEDBACK Appendix 13

52 7.1. A release or spread of activity inside the controlled area requiring special investigation

53 Definitions of Significant Event Reports (For in-depth analysis and follow-up)

54 CRITERIA Appendix 14

55

56 INCIDENTS REQUIRING Appendix 15

57

58

59 7. Transportation of Radioactive Materials

60 Boilers ph <8.0 for more than 24 hours Silica

61 Appendix

62 Appendix

63 1. Assurance of Qt.ialj.ty. Including Management Involvement and Control (cont.) Category 1 Engineering evaluations

64 Category 5. Operational and Construction Events

65 6. Staffing (Including Management) Category 1 Category

66

67 REFERENCES [I] INTERNATIONAL ATOMIC ENERGY AGENCY, Code on the Safety of Nuclear Power Plants: Quality Assurance, Safety Series

68 [14] UNITED STATES NUCLEAR REGULATORY COMMISSION, Systematic Assessment

69 Ankrum, CONTRIBUTORS TO DRAFTING AND REVIEW

70 Consultants Meetings: April June 1989 Advisory Group Meetings: December October December

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