This document discusses quality assurance and quality control programs for industrial radiation practices. It provides definitions of QA and QC, including that QA is a set of processes to ensure desirable outcomes by reducing defects. It outlines the key elements of a comprehensive QA program, including a quality assurance committee, policies and procedures manual, and quality audits. The document also discusses international standards and guidelines for QA programs from organizations like the IAEA and ISO.

1. 5th BAERA Training Course on Radiation Protection
for Radiation Control Officers (RCO) of Industrial
Practices
06-9 November 2017
L17: QA for Industrial Practices
Md Mustafijur Rahman
Principal Engineer
Bangladesh Atomic Energy Regulatory Authority

2. What is a QA/QC program?
• A Quality Assurance program is a set of processes that
help to ensure a desirable outcome by reducing defects
and non-conformance. The program starts at the design
phase and includes the specification, procurement,
manufacturing, fabrication, installation, and
commissioning of materials and/or equipment.
• Quality Control is a component of the Quality Assurance
program, and involves inspections and testing to identify
defects and non-conforming items. Quality Control also
provides a valuable feedback loop to improve the Quality
Assurance process
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3. What is a QA/QC program?
• “All those planned and systematic actions necessary to
provide confidence that a product or service will satisfy
given requirements for quality.” (ISO 9000)
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4. Legal basis for QA
• Rule-19.1 of NSRC Rules-1997
• “ A Licensee shall establish an appropriate
Quality assurance (QA) programme following
standard, code and guide in order to ensure
the implementation of all nuclear safety and
radiation protection requirement.
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5. Purpose of QA
To provide:
• A quality product or quality services for
customer satisfaction
• Reduce radiation exposure to workers to a
level As Low As Reasonably Achievable
(ALARA).
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6. Principles and Criteria for good practice
• Mission and vision of the radiation facility
• Quality management system
• Structure of the facility
• Equipment
• Documentation control
• Consumer feedback and complaints
• Communication
• The audit programme
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7. A Comprehensive QA Program typically
comprises of
• Quality Assurance Committee
• Policies and Procedures Manual
• Quality Assurance team
• Quality audit
• Resources
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8. Benefits of an Effective QA/QC Program
• Reduced defects & rework
• Assurance payments are in lock-step with work
• Quicker holdback release (bill more confidently; pay
more confidently)
• Better insurance and performance security terms
• Lower asset lifecycle costs
• Enhanced reputation and improved client and
subcontractor relations
• Greater certainty of project success
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9. Designing a Best-in-Class QA/QC Program
• Identifying and documenting best practices
• Implementation and Operation
• Continuous improvement (feedback loops)
• Evidence of compliance (audits)
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10. Elements of Quality Management system
• Control of documents and records
• Purchasing
• Traceability
• Calibration
• Maintenance
• Non-conforming product
• Internal audit
• Personnel
• Responsibilities and the irradiation contract
(IAEA Radiation Technology series-4, 2013)
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11. Standards, Code and Guides
• IAEA Safety Series No. 50-C/SG-Q
• The International Atomic Energy Agency (IAEA) Code
and Safety Guides contained in the Safety Series No.
50-C/SG-Q define basic quality assurance requirements,
which must be considered to ensure safety, and provides
recommendations on how to fulfill these basic
requirements.
• The IAEA 50-C/SG-Q standard reflects the performance
based approach to quality assurance covering all
aspects of plant safety, economics and efficiency
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12. • The International Organization for Standardization (ISO)
International Standard ISO 9001:1994 specifies quality
system requirements for use where any supplier’s
capability to design and supply a conforming product
needs to be demonstrated.
• The requirements specified are aimed primarily at
achieving customer satisfaction by preventing
nonconformity at all stages from design through to
servicing
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13. The comparison of the following publications
• IAEA Safety Series No. 50-C/SG-Q (1996), Quality
Assurance for Safety in Nuclear Power Plants and other
Nuclear Installations, Code and Safety Guides Q1–Q14
• ISO 9001:1994, Quality Systems — Model for Quality
Assurance in Design, Development, Production,
Installation and Servicing
• ISO 9002:1994, Quality Systems — Model for Quality
Assurance in Production, Installation and Servicing
• ISO 9003:1994, Quality Systems — Model for Quality
Assurance in Final Inspection and Test
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14. IAEA The quality assurance Code 50-C-Q consists of 10
basic requirements (BR);
1. Management
• BR 1: Quality Assurance Programme
• BR 2: Training and Qualification
• BR 3: Non-Conformance Control and Corrective Actions
• BR 4: Document Control and Records
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15. 2. Performance
• BR 5: Work
• BR 6: Design
• BR 7: Procurement
• BR 8: Inspection and Testing for Acceptance
3. Assessment
• BR 9: Management Self-Assessment
• BR 10: Independent Assessment
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16. Quality System Standard ISO 9001:1994
The clauses of ISO 9001:1994 are:
• 4.1 Management Responsibility
• 4.2 Quality System
• 4.3 Contract Review
• 4.4 Design Control
• 4.5 Document and Data Control
• 4.6 Purchasing
• 4.7 Control of Customer-Supplied Product
• 4.8 Product Identification and Traceability
• 4.9 Process Control
• 4.10 Inspection and Testing
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17. • 4.11 Control of Inspection, Measuring and Test Equipment
• 4.12 Inspection and Test Status
• 4.13 Control of Nonconforming Product
• 4.14 Corrective and Preventive Action
• 4.15 Handling, Storage, Packaging, Preservation and
Delivery
• 4.16 Control of Quality Records
• 4.17 Internal Quality Audits
• 4.18 Training
• 4.19 Servicing
• 4.20 Statistical Techniques
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