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  • / E-Mail : hajd@kocen.comTel. : (031) 777-8526

    12 2007. 4. 5 - 4. 6

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  • 1968 2 14 ( 3371)

    1970 11 15 (WEICO)

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    1971 11 15 1

    1978 4 29 1

    2007 20 , 6

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  • - 1

    10 CFR 50 (Domestic Licensing of Production and Utilization Facilities)

    Appendix B (Quality Assurance Criteria for Nuclear Power Plants and Fuel

    Reprocessing Plants),

    ANSI N45.2 (Quality Assurance Requirements for Nuclear Facilities)

    ASME NQA-1 (Quality Assurance Requirements for Nuclear Facilities

    Applications) .

    - 1995 (KEPIC ,

    Korea Electric Power Industry Code) (QAP)

    .

    - KEPIC QAP 1995 ASME NQA-1-1994 edition 1995 addenda

    .

    ,

    .

    1

    4

  • - Westinghouse 1

    ,

    10 CFR 50 Appendix B (Quality Assurance Criteria for Nuclear Power

    Plants and Fuel Reprocessing Plants) .

    - 1

    CSA Z299 Series .

    - 2,3,4 1,2

    Westinghouse 10CFR50 Appendix B

    .

    - 1,2 10CFR50 Appendix B .

    - 3,4 ,

    ABB-CE 10CFR50 Appendix B .

    - 2,3,4 , 10CFR50 Appendix B .

    2

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  • 10 CFR 50 Appendix B Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

    -

    , , , 18 .

    I. Organization

    II. Quality Assurance Program

    III. Design Control

    IV. Procurement Document Control

    V. Instructions, Procedures and Drawings

    VI. Document Control

    VII. Control of Purchased Material, Equipment and Services

    2

    6

  • VIII. Identification and Control of Materials, Parts and Components

    IX. Control of Special Processes

    X. Inspection

    XI. Test Control

    XII. Control of Measuring and Test Equipment

    XIII. Handling, Storage and Shipping

    XIV. Inspection, Test and Operating Status

    XV. Nonconforming Materials, or Components

    XVI. Corrective Action

    XVII. Quality Assurance Records

    XVIII. Audits

    2

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  • ASME NQA-1 Quality Assurance Requirements for Nuclear Facilities Applications

    - (Applicant)

    10 CFR 50 Appendix B , ,

    .

    - ANSI ASME 1979 NQA-1 .

    - NQA-1 , NQA-1 .

    - Basic Requirements ( ), Supplementary Requirements ( ), Appendices () 3 , KEPIC QAP .

    2

    8

  • -

    , 1958311 483 .

    - 4 11 .

    - 7 4 .

    1.

    2.

    3.

    2

    9

  • 4.

    5. ,

    6.

    7.

    8.

    9.

    10.

    11.

    12.

    13.

    14.

    15.

    16.

    17.

    18.

    2

    10

  • - 7 4

    2000-17(2000.12.29) ,

    2001-47 (2001.12.27) .

    - 3

    2000-17 (KEPIC) (QAP) .

    2

    11

  • KEPIC QAP

    -

    ASME Boiler and Pressure Vessel Code Section III ASME NQA-1 (1994 Edition 1995 Addenda) , , , , , , (QAP-1) , , , , , (QAP-2) .

    - KEPIC 2005 KEPIC QAP

    . (Bilingual) , ISO/IEC 21 (Adoption of International Standard as Regional or National Standards ; ) , ( IDT : , MOD : , NEQ : ) . QAP-1 , QAP-2 .

    2

    12

  • 4 .

    (1) AEC > ERDA > DOE (Standards and Directives)

    1950 AEC

    (2) AEC > NRC (Regulations and Regulatory Guides)

    1960

    1970 , AEC

    (3) ANSI N45.2 > ASME NQA-1 (Related Standards)

    1970 ASME

    (4) ASME Section III Boiler and Pressure Vessel Code

    1970 Performance-Based Approach

    3

    13

  • - NQA , . NQA .

    - Task Proposal Notice (TPN) ASME NQA Main Committee 20044 1954 2005 50 Continuing Evolution of U.S Nuclear Quality Assurance Principles, Practice and Requirement - Part I, II 2005 8 .

    - 2 .

    - , . .

    - Hyman G. Rickover 1962 3 .

    3

    14

    2006 KEPIC-Week

  • , ,

    (More effective management and engineering attention must be given to routine and

    conventional aspects of nuclear power.)

    , , , ,

    (Specification must be clearly understood, respected and enforced by manufacturers as well

    as customers.)

    , . (More effective use must be made of quality

    assurance program requirements.)

    - 1965 AEC

    .

    AEC ,

    3

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    2006 KEPIC-Week

  • 1966 AEC Commissioner James Ramey American Nuclear Society .

    All actions necessary to provide adequate confidence that a product or facility will operate satisfactorily in service."

    - DOD . (MIL-STD-109)

    A planned and systematic pattern of all activities necessary to provide adequate confidence that the item or product conforms to established technical requirements."

    - AEC 10CFR Part 50 Appendix B .

    3

    16

  • - Appendix B American National Standards N45 Committee

    . ASME NQA Committee .

    - 50 ,

    , .

    - ,

    ASME NQA Committee

    .

    - ASME NQA Committee NQA-1 .

    3

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  • NQA

    1954 : 1946 Atomic Energy Act AEC ,

    AEC Santa Fe Operation Office QC-1, Weapons Quality Policy

    QC-1 Weapons Quality Policy Requirements

    - Specification and drawing control

    - Quality control procedures

    - Control of inspection gauging and test equipment

    - Production tooling accuracy

    - In-process inspection and records

    - Control of special process

    - SFO/DOE source inspection

    - Raw material and deviation control

    3

    18

  • 1956 : AEC Dresden 1 and Indian Point 1

    (10 CFR 50 , )

    1963 : ASME Boiler and Pressure Vessel Section III

    ( )

    1965-1967 : AEC 10CFR50 Appendix A (Criterion 1 Quality Standards,

    QA Program, Quality Records )

    1967 : ASME Section III, Appendix IX Quality Assurance 15 Criteria

    1969 : AEC 10CFR50 Appendix B Quality Assurance 18 Criteria

    AEC N45.2

    1971 : The American National Standard (ANSI) N45.2-1971

    1974 : Nuclear Regulatory Commission (NRC)

    Energy Research and Development Administration (ERDA)

    1975 : ASME Committee on Nuclear Quality Assurance (NQA)

    1977 : ASME NQA Committee ANSI/ASME N45.2-1977

    (Quality assurance program requirements for nuclear facilities)

    3

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  • 1979 : ASME NQA-1-1979

    1983 : ASME NQA-1-1983 ,7 NQA-2-1983 QA standards

    1985 : NRC ASME NQA-1-1983 (endorsed), (Regulatory Guide 1.28,

    Revision 3)

    1986 : ASME NQA-1-1986

    1989 : ASME NQA-1-1989

    1991 : NRC Standard Review Plan 17.3 ASME NQA-1 NQA-2

    (endorsed)

    1994 : ASME NQA-1-1994

    (Quality assurance requirements for nuclear facility applications)

    1997 : ASME NQA-1-1997

    2000 : ASME NQA-1-2000

    2004 : ASME NQA-1-2004

    2005 : US Department of Energy (DOE) Action Plan

    ( Devi-Besse

    )

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    2006 KEPIC-Week

  • NQA 1954-2005

    ASME NQA Main Committee 2005 8 (Continuing Evolution of U.S. Nuclear Quality Assurance Principles, Practices and Requirements 1954-2005 ) .

    . (NQA Tutorial Outline)

    (1) NQA

    - AEC > DOE Standards and Directives

    - AEC > NRC Regulations, Regulatory Guides, Standard Review Plans

    - ANSI > ASME N45.2 >NQA-1/2/3 Standards

    - NQA (ANS, IEEE, )

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    2006 KEPIC-Week

  • (2)

    - Quality : The condition achieved (or existing) when an item, service or

    process meets or exceeds the users' requirements or expectations. ( : DOE)

    - Quality Assurance : All those planned and systematic actions necessary to

    provide adequate confidence that a structure, system, or component will perform

    satisfactorily in service. ( ; 10 CFR 50 Appendix B)

    - Quality Assurance : All those actions that provide confidence that quality is

    achieved (or exists). ( : ASME NQA-1)

    (3) NQA

    - (Public concerns)

    - (Government regulations)

    - (Program needs)

    - (Experiences)

    - (Quality failures)

    - (External events)

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  • , , ,, , , . NQA-1 , , . NQA-1 . NQA-1 . (sensible graded)

    , , , , , , . NQA .

    .

    NQA-1 . NQA , .

    NQA .(strict compliance)

    , .

    QA .

    NQA

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    (4) NQA

    23

  • (5) NQA-1 (underlying)

    ( NQA-1 .)

    BR ; Basic Requirements

    BR 1.

    (Senior Management) , , , , , NQA , .

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    BR 2. QA Program

    (Management) , , .

    QA , , .

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    24

  • BR 3.

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    BR 4&7.

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    BR 5. ,

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    BR 6&17.

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