Comparison of 10CFR.50, Appendix B & ASME NQA-1-1994 ...

[Pages:211]108US-01910-ASD-001 2003/01/31

Assessment Document

Comparison of 10CFR50 Appendix B and ASME NQA1-1994 Requirements Versus CSA N286 Series of Standards

ACR USA

108US-01910-ASD-001 Revision 0

2003 February Fevrier 2003

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Assessment Document

Comparison of lOCFR50 Appendix B and ASME NQA1- 1994 Requirements Versus CSA N286 Series of Standards

ACR USA

1OSUS-0191 O-ASD-001

Revision 0

Rfw!aWeu by V&lfi~ per

e

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T. V. Banna

Nuclear CM Manager, Bechtel Power Corporation

Reviewed by VBrifi6 par

Approved by Approuv6 par

R. K.Ghei

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QA Manap Corporate Design QA

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

2003 February

Fevrier 2003

0 Atomic Energy of Canada Limited

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Revision History

0939B Rev. 13

Liste des documents et des r?visions

Document Details / D?tails sur le document

Title Titre

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 r?visions

Release Document

No./No

Date

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Date

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1

D1 2003/01/24 Issued internally for comments

Prepared by R?dig? par

R. Abel

2003/02/04 Draft finalized to incorporate comments received

R. Abel

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

2

2003/02/26 0 2003/02/26 Approved document released for use.

R. K. Ghai

Total no. of pages Nbre total de pages

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Approved by Approuv? par

R.K. Ghai V. Snell S. S. Dua

T.V. Sarma- Bechtel

See above

T.V. Sarma- Bechtel

S. S. Dua V. Snell V. Langman

See above

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

SECTION

108US-01910-ASD-001 Page i Rev. 0 TABLE OF CONTENTS

PAGE

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

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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.

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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.

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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-11994 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, scientific, and design computer programs. It is designed to complement the QA program requirements in any of the other CSA N286 sub-tier standards. It is required to be used in combination with the appropriate sub-tier standard in order to define the complete QA program requirements for a particular nuclear power plant life cycle phase.

The ASME NQA-1-1994 standard contains 18 main clauses that are modelled after the 18 criteria of 10CFR50, Appendix B. Each of these main clauses contains Basic Requirements. Additional detailed requirements are included as mandatory Supplements for each of these clauses. The CSA N286 series of standards is designed so that each sub-tier standard can be used as a stand-alone document without having to refer to CSA N286.0 or any other sub-tier standard.

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3.3

Difference in Scope

ASME NQA-1-1994 includes in its scope the activities related to siting of a nuclear facility. The CSA N286 standards do not specify any requirements in this area. In Canada, the site selection process is considered part of the nuclear licensing process. Specific requirements regarding activities to select a site are specified by the Canadian Nuclear Safety Commission.

3.4

Difference in Requirements

The Comparison Table (Section 4) provides:

(a) A description of the requirements as identified in 10CFR50 Appendix B, ASME NQA1-1994, and the CSA N286 series of standards.

(b) An evaluation of differences between the two sets of standards, and

(c) An assessment of differences with respect to the ACR QA program and the required actions, as applicable.

Overall, both ASME NQA-1 and the CSA N286 series of standards require that quality assurance programs applicable to nuclear facilities address the same quality assurance program elements. This comparison shows there are no fundamental differences between ASME NQA-1-1994 and the CSA N286 series of standards, and that the differences are only in details with respect to implementation of the requirements. As noted in the Comparison Table, in some areas, where there are significant differences in the two sets of standards, the existing ACR QA program covers the differences adequately. There are, however, a few areas where the ACR QA program needs some minor modifications. The table below identifies areas of significant differences and the required actions to modify the ACR QA program applicable to ACR Design Certification phase. The Comparison Table (last column) provides detailed assessment on the ACR QA program for each of the NQA-1-1994 requirements.

NQA-1 Clause

Area of Significant Differences

Required Action

Clause 2 QA Program

a) Qualification of Inspection and Test Personnel and Non- destructive Examination Personnel

ACR to ensure that the organizations performing inspections and tests and non-destructive examination activities for ACR Design Certification meet the additional requirements of Supplements 2S-1 and 2S-2 of NQA1-1994. ACR to review its QA program and modify the QA Manual and/or procedures as appropriate.

b) Qualification of lead auditors

ACR to ensure that the additional requirements on lead auditor qualification (Supplement 2S-3 of NQA1-1994) are reviewed and

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

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