Quality

"The Amidyne Group is essentially a Quality Assurance company that just happens to make things"

Our Quality Assurance System is at the heart of everything that we do. From contract review to quality planning, vendor audit to incoming inspection, measurement and test equipment to final inspection, from document control to design reviews, not an activity takes place that is not planned, reviewed, and verified to ensure an auditable paper trail is left behind.

Our QA program meets the requirements of the following standards:

• CSA CAN3-Z299.2-85,
• CSA N285.0
• CSA N286.1-00 and CSA 286.2-00
• 10 CFR 50 Appendix B with 10 CFR Part 21 responsibility
• ASME NQA-1  
• ISO 9001:2000

Our QA program has been audited by CANPAC to the requirements of CSA CAN3-Z299.2-85 and CSA N286.1-00 and CSA 286.2-00. And by a NUPIC member company to the requirements of 10 CFR 50 Appendix B.

Versatile Measuring Instruments has implemented and maintains a Quality Assurance program that meets the requirements of:

• CSA Z299.2
• CSA N286.1
• CSA N286.2
• 10CFR50 Appendix B – 10CFR Part 21
• ASME NQA-1

CANPAC, QMI SAI-Global, AECL and SNC Lavalin Nuclear have audited specific programs for the Canadian market. Duke Energy, (with participation from Progress Energy and South Carolina Gas & Electric), and Westinghouse Electric Company have performed audits for the United States.  A Member Assessment has been performed by a member of the Nuclear Industry Assessment Committee (NIAC) covering the 10CFR50 Appendix B/NQA-1 quality program.

 

Lisle-Metrix which mainly serves Canadian market, has Quality Assurance program meeting:

• CSA Z299.2
• CSA N286.1
• CSA N286.2
• CSA N285.0

Lisle-Metrix holds “Certificates of Authorization” from TSSA for both Nuclear and Non-Nuclear category A, F & H fittings. (N285.0 & CSA B51)

Lisle-Metrix, has been audited by CANPAC, QMI SAI-Global, AECL and SNC Lavalin Nuclear

 

Summary of Qualifications:

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Definitions:

 

Safety Related
Safety-related applications are systems, structures, components, procedures, and controls (of a facility or process) that are relied upon to safely shut down a plant and maintain the plant in a shutdown state while the residual heat is safely removed without the release of radioactive substances into the environment.

 

10CFR50 Appendix B (Title 10 Code of Federal Regulations, Part 50)
Appendix B to Part 50--Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants issued by the Nuclear Regulatory Commission.

 

10CFR Part 21 – Reporting of Defects and Noncompliance
The Nuclear Regulatory Commission regulation, detailing the requirements for the reporting of Defects and Noncompliance.

 

ASME NQA-1
A Standard, that provides requirements and guidelines for the establishment and execution of quality assurance programs during siting, design, construction, operation and decommissioning of nuclear facilities. The Standard reflects industry experience and current understanding of the quality assurance requirements necessary to achieve safe, reliable, and efficient utilization of nuclear energy, and management and processing of radioactive materials. The Standard focuses on the achievement of results, emphasizes the role of the individual and line management in the achievement of quality, and fosters the application of these requirements in a manner consistent with the relative importance of the item or activity.

 

ANSI-45.2
Quality Assurance Program Requirements for Nuclear Facilities – predecessor to ASME NQA-1 

 

CSA CAN3-Z299
A series of quality assurance standards developed by the Canadian Standards Association in the 1970s. These standards are still in use by the Nuclear Industry in Canada.

 

CSA-N285.0
“General requirements for pressure-retaining systems and components in CANDU nuclear power plants”. The CSA standard utilized for the design, manufacture and registration of pressure retaining components and systems.