Guide for Establishing and Maintaining a Quality Assurance Program for Analytical Laboratories Within the Nuclear Industry

2021 ◽  
Author(s):  
2014 ◽  
Vol 136 (02) ◽  
pp. 40-43
Author(s):  
Joseph Pang ◽  
Chris Mähler

This article discusses various aspects of a new ASME program that seeks to support a robust global supply chain for the nuclear industry. Under the program, an ASME audit team will assess a company’s quality assurance program. It will make an accurate assessment of a supplier’s capability in implementing its QA program in compliance with the NQA-1 standard and will issue a certificate affirming that the company has been found in compliance. Safeguards are in place for companies to receive a fair and unbiased evaluation. Conflicts of interest are removed by having the ASME Conformity Assessment Department develop and administer the program. The ASME audit team will visit all locations where the nuclear quality assurance program is being implemented and will require a company to implement or demonstrate all aspects of its program. The review of the supplier’s QA manual and the on-site audit will be the basis of the team’s report in conveying to ASME the company’s capabilities, knowledge, and understanding of its program and of the ASME NQA-1 standard.


Author(s):  
John G. Adkins

In 2009 the United States Nuclear Regulatory Commission (NRC) will issue Regulatory Guide 1.28 [1] endorsing the Nuclear Quality Assurance (NQA) Standard, NQA-1-2008 Edition with NQA-1a-2009 Addenda [2] as the appropriate quality assurance (QA) requirements for the design, construction and operation of new and existing U.S. nuclear generating facilities. This endorsement will change the U.S. regulatory QA position from NQA-1-1994 and incorporate 15 years of quality experience, lessons learned, technology enhancements and regulatory changes. This regulatory position change will subsequently be included in a revision to the NRC’s NUREG-0800, Standard Review Plan (SRP) 17.5, Quality Assurance Program Description – Design Certification, Early Site Permit and New License Applicants [3]. The Nuclear Energy Institute’s NEI 06-14A, Quality Assurance Program Description (QAPD) [4], which provides a generic QA template for use by new generation early site permit and combined license applicants for implementing QA regulatory requirements of SRP 17.5 will subsequently be revised to document the new regulatory position for the use of NQA-1a-2009. These new quality requirements will be passed on by the utilities constructing new generating facilities to the both U.S. and international suppliers, thus changing the basis of QA requirements for the nuclear industry. The NQA-1 Standard is a four-part criteria standard that provides quality requirements and acceptance criteria for the implementation of a nuclear facility quality assurance program. Part I describes the basic QA program elements and Part II provides requirements for specialized support and application activities for design, construction and operations. Part III contains guidance that support Parts I and II, and Part IV provides guidance for comparison of NQA-1 with other quality standards. This paper will focus on the background of the quality changes included in the endorsement on NQA-1-2008 with the NQA-1a-2009 Addenda and provide a detailed discussion of the following major changes: • Facility configuration control – measures to ensure changes that may affect the approved facility configuration are recognized and processed. • Engineering interface controls – controls to ensure interfaces for design changes are established among design organizations. • Software design controls – alternate design measures specifically for software design to ensure design input, design processes, verification and change control are appropriately performed. • Software application requirements – controls for the software engineering requirements for the acquisition, development, operation, maintenance, and retirement of software. • Electronic records – controls that address use of electronic media for QA record activities. • Commercial grade items – a composite document of criteria for the identification and dedication of commercial grade items and services. • Clarifications for consistency of basic QA requirements – areas in the Standard where the QA text needed to be return to basic principles and to add clarification to ensure national and international consistent application.


2021 ◽  
Vol 8 (3A) ◽  
Author(s):  
ANA ROSA BALIZA MAIA ◽  
Youssef Morghi ◽  
AMIR ZACARIAS MESQUITA

According to NRC, the commercial-grade dedication is a process by which a commercial-grade item (CGI) is designated for use as a basic component. This acceptance process is undertaken to provide reasonable assurance that a CGI to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. In Brazil there are two Nuclear Power Plants in operation, one is American design (Angra 1), other is German design (Angra 2) and one is under construction that is German design (Angra 3). The nuclear safety items are imported and many of them are obsolete and besides the process of purchasing imported items is very complicated. If the nuclear industry in Brazil adopt the Commercial-grade dedication it will improve the internal market and facilitate the process of purchasing items. The Brazilian Quality Assurance Standard (Cnen NN 1.16) shows the 18 Basic requirements of 10 CFR 50 App B, so the Brazilian Industry can be qualified according to this Brazilian standard. The critical characteristics identification and the testing process is an engineering responsibility that Brazilian engineer can perform. This work shows the challenge of commercial-grade dedication in Brazil and discuss the importance of this process to the operation of the nuclear power plants in Brazil, including the long-term operation and others Brazilian nuclear projects..


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