Comparison of 10CFR.50, Appendix B & ASME NQA-1-1994 ... For this comparison, ASME NQA-1-1994 is used

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  • 108US-01910-ASD-001 2003/01/31

    Assessment Document

    Comparison of 10CFR50 Appendix B and ASME NQA- 1-1994 Requirements Versus CSA N286 Series of Standards

    ACR USA

    108US-01910-ASD-001 Revision 0

    2003 February All rights reserved by Atomic Energy of Canada Limited. No part of this document may be reproduced or transmitted in any form or by any means, including photocopying and recording, without the written permission of the copyright holder, application for which should be addressed to Atomic Energy of Canada Limited. Such written permission must also be obtained before any part of this document is stored in a retrieval system of any nature.

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  • A f AECL EACL Assessment Document Comparison of lOCFR50 Appendix B and ASME NQA- 1- 1994 Requirements Versus CSA N286 Series of Standards

    ACR USA

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    S. S. Dua - Dlrector. Corporate Standards & CANDU Products and Servlces CIA

    2003 February Fevrier 2003

    0 Atomic Energy of Canada Limited 2251 Speakman Drive Mississauga, Ontario Canada L5K 182

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  • Release and Liste des documents Revision History et des révisions 0939B Rev. 13

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    Comparison of 10CFR50 Appendix B and ASME NQA-1-1994 Requirements Versus CSA N286 Series of Standards

    Release and Revision History / Liste des documents et des révisions

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    108US 01910 ASD 001 1 1 108US-01910-ASD-001 2003/01/31

    1 D1 2003/01/24 Issued internally for comments

    R. Abel R.K. Ghai V. Snell S. S. Dua T.V. Sarma- Bechtel

    2003/02/04 Draft finalized to incorporate comments received

    R. Abel See above

    2003/02/24 Revised to include impact of differences between the two sets of standards on the ACR QA program and the required actions. Issued to named reviewers. Comments received incorporated.

    R. K. Ghai T.V. Sarma- Bechtel S. S. Dua V. Snell V. Langman

    2 2003/02/26 0 2003/02/26 Approved document released for use. R. K. Ghai See above S. S. Dua

  • 108US-01910-ASD-001 Page i Rev. 0

    TABLE OF CONTENTS

    SECTION PAGE

    108US-01910-ASD-001 2003/01/31

    1. STATEMENT OF PURPOSE .............................................................................1-1

    2. METHOD OF COMPARISON ...........................................................................2-1

    3. SUMMARY OF MAJOR DIFFERENCES .........................................................3-1

    3.1 Difference in Standards Writing Approach..........................................................3-1 3.2 Difference in Structure .........................................................................................3-1 3.3 Difference in Scope..............................................................................................3-2 3.4 Difference in Requirements .................................................................................3-2

    4. COMPARISON TABLE......................................................................................4-1

    FIGURES

    Figure 1 ..............................................................................................................................3-4

  • 108US-01910-ASD-001 Page 1-1 Rev. 0

    108US-01910-ASD-001 2003/01/31

    1. STATEMENT OF PURPOSE

    The purpose of this document is to provide a comparison of the Canadian CSA N286 series of standards versus US NRC 10CFR50, Appendix B and ASME NQA-1-1994 standard and an assessment of the impact of differences, if any, on the ACR QA program and their proposed disposition. The selection of ASME NQA-1-1994 instead of the latest NQA-1-2000 is made based on discussions with US NRC.

    Section 2 of this document provides method of comparison. Section 3 provides a summary of major differences with respect to standards writing approach, structure, scope, requirements and assessment of differences on the Advanced CANDU Reactor (ACR) QA program and the required actions. Section 4 provides a detailed Comparison Table.

  • 108US-01910-ASD-001 Page 2-1 Rev. 0

    108US-01910-ASD-001 2003/01/31

    2. METHOD OF COMPARISON

    The Comparison Table (Section 4) provides a comparison of the requirements of the 10CFR50 Appendix B and ASME NQA-1-1994 versus the requirements of CSA N286 series of standards. Since the CSA N286 series of standards, and particularly CSA N286.1, Procurement Quality Assurance for Nuclear Power Plants, refers to the Canadian CSA Z299 series of standards for manufacturing and testing, this comparison also makes use of the CSA Z299 series of standards, as appropriate. The scope of the comparison in the Comparison Table is limited to the elements of the QA program requirements as defined in 10CFR50, Appendix B and as applicable to ACR Design Certification. The following parts of ASME NQA-1-1994 with corresponding requirements in the CSA N286 series of standards are not included: - Part II: Quality Assurance Requirements for Nuclear Facility Applications; - Part III: Non-mandatory Appendices.

    For this comparison, ASME NQA-1-1994 is used as the reference document. Therefore, the clauses and paragraphs of other documents are aligned with the requirements stated in ASME NQA-1-1994. For example, the text of 10CFR50 Appendix B in the Comparison Table is not in the same order as it appears in the original document.

  • 108US-01910-ASD-001 Page 3-1 Rev. 0

    108US-01910-ASD-001 2003/01/31

    3. SUMMARY OF MAJOR DIFFERENCES

    3.1 Difference in Standards Writing Approach

    One fundamental difference between the CSA N286 series of standards and ASME NQA-1- 1994 is in the approach as follows:

    The CSA N286 series is a set of industry consensus standards reflecting currently recommended Canadian best practices. The CSA N286 series of standards is based on a set of 16 Management Principles to Achieve Quality. The Canadian Nuclear Safety Commission participates as an equal member in this consensus process. It prescribes compliance with these standards as a condition of granting construction, commissioning, or operating licences.

    Whereas, ASME NQA-1-1994, an industry consensus standard, contains 18 criteria aligned with those addressed in 10CFR50 Appendix B. It reflects industry practices and processes for meeting the requirements. One of this standard’s objectives is to obtain endorsement by regulatory bodies as meeting the respective QA Regulations.

    3.2 Difference in Structure

    The ASME NQA-1-1994 standard applies to all phases of a nuclear facility's life cycle and to both the owner of the facility and any participants in the project. The CSA N286 standards represent a series of documents where CSA N286.0 is the standard addressed to the owner of the nuclear power plant defining the overall quality assurance program requirements. The CSA N286 sub-tier standards provide detailed quality assurance requirements for each of the major phases of a nuclear power plant life cycle, including procurement, design, construction, commissioning, and operation. Figure 1 illustrates the hierarchy and relationship among the CSA N286 series of standards. In addition to the sub-tier standards addressing QA requirements for the major life cycle phases illustrated in Figure 1, the CSA N286 series of standards also includes CSA N286.7, Quality Assurance of Analytical, Scientific, and Design Computer Programs for Nuclear Power Plants. CSA N286.7 standard specifies requirements for the design, development, and use of analytical,

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