The Requirements and the Standards for a Verification and Survey ASME NQA-1 2008 for SQA V&V

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  • The Requirements and the Standards for a Verification and Validation of a Nuclear Reactor

    Analyzer Software for NRC License

    (KEPCO NUCLEAR FUEL)

    (Bongsik Park)

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    Contents

    Background & Objectives

    NRC Regulatory Guides Structure for SQA

    Analyze SRP 0800 Chapter 4.3 and BTP 7-14 for SQA

    V&V requirements of the Software for NRC License

    Software Verification and Validation

    Survey ASME NQA-1 2008 for SQA V&V

    Suggestions to ASME V&V 30 Committee

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    Background(1/5)

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    Background(2/5)

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    Background(3/5)

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    Background(4/5)

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    What is the V&V requirements of the Software

    for NRC License?

    What is the V&V processes of the Software for

    NRC License?

    The Software is a Nuclear Reactor Analyzer

    Software.

    Background & Objectives(5/5)

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    NRC Regulatory Guides Structure for SQA of General Design Software(1/5)

    Appendix B, P50

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    NRC Regulatory Guides Structure for SQA of General Design Software(2/5)

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    NRC Regulatory Guides Structure for SQA of General Design Software(3/5)

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    Regulatory Guide Periodic Review[ April 2015]

    Regulatory Guide Number: 1.28, Revision 4Title: QUALITY ASSURANCE PROGRAM CRITERIA(DESIGN AND CONSTRUCTION)

    1. What are the known technical or regulatory issues with the current version of theRegulatory Guide (RG)? The NRC issued RG 1.28, Revision 4, in June 2010. The methods described inRevision 4 are generally equivalent to the methods described in Revision 3, whichendorsed NQA-1-1983 through the NQA-1a-1983 Addenda. Revision 4 extends thescope of the NRCs endorsement to include NQA-1, Part II. Part II containsamplifying QA requirements for certain specific work activities that occur at variousstages of a facilitys life. []The NRC staff performed a review and identified that differences exist between thepreviously endorsed guidance (NQA-1-2008 and NQA-1a-2009 addenda) and themost recently issued guidance from the American Society of Mechanical Engineers(NQA-1b-2011, NQA-1-2012 and NQA-1-2015). Additional time and resources arerequired to understand the impact of these changes. The NRC staff continues toendorse the previous guidance and is not aware of any issues that would precludeits use.

    NRC Regulatory Guides Structure for SQA of General Design Software(4/5)

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    NRC Regulatory Guides Structure for SQA of General Design Software(5/5)

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    Analyze SRP 0800 Chapter 4.3 and BTP 7-14 for SQA(1/3)

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    Analyze SRP 0800 Chapter 4.3 and BTP 7-14 for SQA(2/3)

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    Analyze SRP 0800 Chapter 4.3 and BTP 7-14 for SQA(3/3)

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    The Part I and Part II requirements included in NQA-1-2008 and the NQA-1a-2009 Addenda, Quality Assurance Requirements for Nuclear Facility Applications (Ref. 7, 8), for the implementation of a QA program during the design and construction phases of nuclear power plants and fuel reprocessing plants are acceptable to the NRC staff and provide an adequate basis for complying with the requirements of Appendix B to 10 CFR Part 50.

    [REGULATORY GUIDE 1.28]

    V&V requirements of the Software for NRC License(1/3)

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    The computer codes used in the nuclear design are described in sufficient detail to enable the reviewer to establish that the theoretical bases, assumptions, and numerical approximations for a given code reflect the current state of the art.

    Verification of the database, computer codes, and analysis procedures has been made by comparing calculated results with measurements obtained from critical experiments and operating reactors.

    [ 4.3 NUCLEAR DESIGN, NUREG-0800]

    V&V requirements of the Software for NRC License(2/3)

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    V&V requirements of the Software for NRC License(3/3)

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    review. A process or meeting during which a work product, or set of work products, is presented to project personnel, managers, users, customers, or other interested parties for comment or approval. Types include code review, design review, formal qualificationreview, requirements review, test readiness review.

    verification. (1) The process of evaluating a system or component to determine whether the products of a given development phase satisfy the conditions imposed at the start of that phase. Contrast with: validation.(2) Formal proof of program correctness.See: proof of correctness.

    verification and validation (V&V). The process of determining whether the requirements for a system or component are complete and correct, the products of each development phase fulfill the requirements or conditions imposed by the previous phase, and the final system or componentcomplies with specified requirements. See also: independent verification and validation.

    Software Verification and Validation (1/4)

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    Software Verification and Validation (2/4)

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    Software Verification and Validation (3/4)

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    Software Verification and Validation for I&C (4/4)

  • NRC:Codes, Standards, Guidance, Requirements for SW Quality Assurance

    10CFR50 APP B

    RG 1.28

    Part 1 Requirement 3 800

    ASME NQA-1

    Part 1 Requirement 4

    Part 2 Requirement 7

    Part 1 Requirement 11

    Part 1 Requirement 16

    Part 1 Requirement 17

    Part 2 Subpart 2.7

    Part 2 Subpart 2.14

    10CFR50 APP B: Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

    RG 1.28 : Quality Assurance Program Criteria (Design and Construction)

    ASME NQA-1: Quality Assurance Program Requirements for Nuclear Facilities

    R3 800: Software Design Control

    R4 : Procurement Document Control

    R6 : Document Control

    R7: Control of Purchased Items and Services

    R11: Test Control

    R16: Corrective Action

    R17: Quality Assurance Records

    SP 2.7: Quality Assurance Requirements for Computer Software for Nuclear Facility Applications

    SP 2.14: Quality Assurance Requirements for Commercial Grade Items and Services

    SP 3.2-2.14: Implementing Guidance for Part II, Requirement 2.14

    SP 4.1: Guide on Quality Assurance Requirements on Software

    Part 1 Requirement 6

    Part 3 Subpart 3.2-2.14

    Part 4 Subpart 4.1

    Guidance

    The Part I and Part II requirements included in

    NQA-1-2008 and the NQA-1a-2009 Addenda,

    are acceptable to the NRC staff and provide an

    adequate basis for complying with the

    requirements of Appendix B to 10 CFR Part 50.

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    Survey ASME NQA-1 2008 for SQA V&V

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    Survey ASME NQA-1 2008 for SQA V&V

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    Survey ASME NQA-1 2008 for SQA V&V

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    Survey ASME NQA-1 2008 for SQA V&V

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    Survey ASME NQA-1 2008 for SQA V&V

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    Survey ASME NQA-1 2008 for SQA V&V

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    Survey ASME NQA-1 2008 for SQA V&V

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    Establish a common framework for V&V processes

    Define the V&V tasks

    Identify the minimum V&V tasks corresponding to

    a classified software

    Define the content of a software V&V plan (SVVP)

    Suggestions to ASME V&V 30 Committee(1/7)

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    Suggestions to ASME V&V 30 Committee(2/7)

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    Appendix B to Part 50Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

    Suggestions to ASME V&V 30 Committee(3/7)

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    Hyung Lee, Richard Schultz, Scope and Vision of the V&V 30 Standards Committee , V&V 2017 SYMPOSIUM , The Westin Las Vegas, Las Vegas, Nevada , May 3-5, 2017

    Scope and Vision of the V&V 30 Standards Committee

    The charter of the V&V 30 committee is to provide the practices and procedures for verification and validation of software used to calculate nuclear system thermal fluids behavior. The software of interest includes system analysis and computational fluid

    dynamics (CFD) numerical models, including the coupling of this software.

    The V&V30 committee is working to achieve their objectives in accordance with the above charter by: * Clarifying and normalizing the experiment design scaling approaches. * Identifying the predominant differences and applications which distinguish the systems analysis and CFD software from one another. Additionally the widely-used historic nomenclature peculiar to the systems analysis codes will be normalized with that in common use today. * Sponsoring V&V benchmark problems to provide a baseline for how nuclear system CFD calculations are performed, verified, and validated.

    Suggestions to ASME V&V 30 Committee(4/7)

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    Suggestions to ASME V&V 30 Committee(5/7)

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    Suggestions to ASME V&V 30 Committee(6/7)

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    Suggestions to ASME V&V 30 Committee(7/7)

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    Thank you for your attention !!