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

211 Pages·2003·0.99 MB·English

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 Fevrier 2003

All rights reserved by Atomic Tous droits réservés pour
Energy of Canada Limited. Énergie atomique du Canada
No part of this document may limitée. Il est interdit de
be reproduced or transmitted reproduire ou de transmettre,
in any form or by any means, par quelque procédé que ce
including photocopying and soit, y compris de photocopier
recording, without the written ou d’enregistrer, toute partie du
permission of the copyright présent document, sans une
holder, application for which autorisation écrite du
should be addressed to propriétaire du copyright
Atomic Energy of Canada obtenue auprès d’Énergie
Limited. Such written atomique du Canada limitée. De
permission must also be plus, on doit obtenir une telle
obtained before any part of autorisation avant qu’une partie
this document is stored in a du présent document ne soit
retrieval system of any intégrée dans un système de

nature. recherche documentaire de

n’importe quelle nature.
(cid:1) Atomic Energy of © Énergie atomique du
Canada Limited Canada limitée
2251 Speakman Drive 2251, rue Speakman
Mississauga, Ontario Mississauga (Ontario)
Canada L5K 1B2 Canada L5K 1B2
108US-01910-ASD-001 2003/01/31
f
A AECL EACL
Assessment Document
Comparison of lOCFR50
Appendix B and ASME NQA-
1- 1994 Requirements Versus
CSA N286 Series of Standards
ACR USA
1 OSUS-0191 O-ASD-001
Revision 0
Rfw!aWeu by Reviewed by
V&lfi~ per e *_ VBrifi6 par
T. V. Banna R. K.Ghei ’
Nuclear CM Manager, Bechtel Power Corporation QA Manap Corporate Design QA
Approved by
Approuv6 par
S. S. Dua -
Dlrector. Corporate Standards & CANDU
Products and Servlces CIA
2003 February Fevrier 2003
0 Atomic Energy of Q hergie atomique du
Canada Limited Canada limitke
2251 Speakman Drive 2251, rue Speakman
Mississauga, Ontario Misslssauga (Ontario)
Canada L5K 182 Canada L5K 182
-
I
!
Release and Liste des documents
Revision History et des révisions
0939B Rev. 13
Document Details / Détails sur le document
Title Total no. of pages
Titre Nbre total de pages
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
Release Revision Purpose of Release; Details of Rev./Amendement Prepared by Reviewed by Approved by
Document Révision Objet du document; détails des rév. ou des modif. Rédigé par Examiné par Approuvé par
No./No Date No./No Date

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 R. K. Ghai T.V. Sarma- Bechtel
of standards on the ACR QA program and the required actions. S. S. Dua
Issued to named reviewers. Comments received incorporated. 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

DCS/RMS Input / Données SCD ou SGD
Sheet
Feuille
Rel. Proj. Project Serial No. Of Unit No.(s)
Proj. conn. Projet SI Section Série No De Tranche no
108US 01910 ASD 001 1 1

108US-01910-ASD-001 2003/01/31
108US-01910-ASD-001 Page i
Rev. 0
TABLE OF CONTENTS
SECTION 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

108US-01910-ASD-001 2003/01/31
108US-01910-ASD-001 Page 1-1
Rev. 0

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 2003/01/31
108US-01910-ASD-001 Page 2-1
Rev. 0

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 2003/01/31
108US-01910-ASD-001 Page 3-1
Rev. 0

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, 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.

108US-01910-ASD-001 2003/01/31
108US-01910-ASD-001 Page 3-2
Rev. 0

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 NQA-
1-1994, 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 Area of Significant Required Action
Clause Differences

Clause 2 a) Qualification of Inspection ACR to ensure that the organizations
QA Program and Test Personnel and performing inspections and tests and
Non- destructive non-destructive examination activities
Examination Personnel 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 ACR to ensure that the additional
auditors requirements on lead auditor
qualification (Supplement 2S-3 of
NQA1-1994) are reviewed and
108US-01910-ASD-001 2003/01/31
108US-01910-ASD-001 Page 3-3
Rev. 0

NQA-1 Area of Significant Required Action
Clause Differences
incorporated into the audit procedure,
as appropriate.

c) Personnel Indoctrination ACR to produce and implement
and Training procedure/operating instructions to
meet the requirements of personnel
indoctrination and training
(Supplement 2S-4 of NQA1-1994).

Clause 3 a) Design Reviews ACR to review the Design Review
Design procedure and modify it as appropriate
Control to ensure that the requirements of
Clause 4.2.1 of Supplement 3S-1 are
met.

b) Qualification Tests ACR to ensure that qualification testing
demonstrates adequacy of performance
under the most adverse design
conditions; establishes and verifies
scaling laws; and applies error analysis,
where applicable, to the results of
model test work, prior to use in final
design work; ACR to review the
qualification test specification
procedure and revise it as appropriate.

Clause 7 a) Commercial Grade Items ACR to review its method of
Control of acceptance of commercial grade items,
Purchased when it utilizes such items, and produce
Items and a procedure or operating instructions to
Services ensure that the requirements of Clause
10 of Supplement 7S1 are followed.

108US-01910-ASD-001 2003/01/31
108US-01910-ASD-001 Page 3-4
Rev. 0

The CSA N286 Series of Standard
Quality Princ iples

Overall
Program
N286.0.1
N286.0
Commentary
on principles
N286.1 N286.2 N286.3 N286.4 N286.5 N286.6

n n g
nt g o g s n
n
e i i n i
s t o n
em De ruc oni ati sio
ur st si er s
c n s p mi
o o mi O
r C m
P m
o
o c
C e
D

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