The Use of ASME Codes and Standards in the Nuclear Industry

Neil Broom30 May 2012

Contents• Development of ASME Codes and Standards• Background to ASME Nuclear Code• NQA-1 Quality Assurance Requirements for Nuclear Facility

Applications• Section III Rules for Construction of Nuclear Facility

Components• Section XI Rules For Inservice Inspection Of Nuclear Power

Plant Components• South African Application

Development of ASME Codes and Standards

• In the USA during 19th and early 20th century boiler explosions were happening at a rate of more than one per week, causing thousands of deaths.

• In April 1865 the boiler explosion on the steamboat Sultana killed over 1500.

Development of ASME Codes and Standards

• In March 1905 the boiler explosion at in Brockton, Massachusetts caused 58 deaths and 117 injuries and completely levelled the factory.

History of ASME Codes and Standards

• At the time most dismissed these incidences as “acts of god.” People who ran industrial concerns simply assumed that their boilers would explode and they would lose one or two other workers.

• Legislative bodies and insurance companies identified the need for rules for construction and testing of boilers to protect the public against such accidents with pressure-retaining equipment.

• This led to ASME issuing:-

History of ASME Codes and Standards

• In 1924 Code for Unfired Pressure Vessels Published• In 1956 a Committee for ASME Pressure Vessel Code for the Nuclear

Age• In 1963 Section III(Nuclear Power) published• Now (2011 addenda) comprises 30 books that are either Standards

that provide the rules for fabricating a component or they are supporting documents such as Materials (Section II, Parts A through D), Non-Destructive Examination (Section V) and Welding (Section IX).

Development of ASME Codes and Standards

• Written– By volunteer Committees based on their expertise and

their potential for making sound contributions to the writing, revising, interpreting and administering of the document.

– By users for users• Regularly up-dated – now on a 2 year cycle• Provision for Code Cases and Interpretations

ASME Codes and Standards

• The ASME Code is:– Recognized and accepted in over 100 nations– Leading standards across an array of industries throughout the world

– Current translations by others in Japanese, Korean, French and Chinese

– ASME Spanish version of BPV Section I, Power Boilers

– Recent references in national regulations of: • India - Nigeria - South Africa - Colombia

– Developed by volunteers from over 40 nations

Background - ASME Nuclear Code

• In 1946 the US Atomic Energy Commission was created to regulate Nuclear activities, regulatory programs sought to ensure public health and safety from the hazards of nuclear power without imposing excessive requirements that would inhibit the growth of the industry.

• Committee for ASME Pressure Vessel Code for the Nuclear Age, rules to meet the AEC’s requirements.

• Section III first published in 1963 as a single volume, now in 12 volumes.• Section III provides rules for construction,(an all-inclusive term comprising materials, design,

fabrication, examination, testing, inspection, and certification required in the manufacture and installation of an item.) of vessels, pumps, valves, piping, and storage tanks.

• In the USA the use of ASME Section III is mandated through reference in the Code of Federal Regulations 10 CFR 50, 55a.

• 10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

• NQA-1 was created by ASME in 1979 as a means of implementing federal regulations at nuclear power plants and fuel processing plants.

• There are three key elements to the ASME code for Nuclear Applications:– NQA-1– ASME BPVC III– ASME BPVC XI

NQA-1 Quality Assurance Requirements for Nuclear Facility Applications

• Difference between NQA-1 and ISO 9001– NQA-1

• Nuclear specific• Prescriptive

– ISO 9001• Universally applicable• Aimed at continually improving processes and monitoring

customer satisfaction.

NQA-1• Based on requirements of 10

CFR 50 Appendix B• Provides a means of

meeting the 18 requirements.

• A Quality Management System based only on ISO 9001 will not meet the requirements of NQA-1.

• NQA-1 provides the basis for most Nuclear QMS

Section III Rules for Construction of Nuclear Facility Components

• Provides a consistent set of rules backed on structural analysis and an improved knowledge of material behaviour. – it incorporates:

• Design by stress analysis• Design By Rule• Stress categorization• Thermal stress• Fatigue• Non ductile failure• Dynamic loadings (including earthquake)

Section III• Section III for the Boiler and Pressure Vessel code

covers:– Division 1

• 3 Classes of Construction• Supports (NF)• Reactor Core Support Structures(NG)• Steel Containment Vessels (NE)• Class 1 Components at Elevated Temperature (NH)

– Division 2 Concrete Containment– Division 3 Containments for Transportation and Storage– Division 5 High Temperature Reactors

Section III• Relies on other sections of the code for:

– Material Specifications and Mechanical Properties (Section II)

– Nondestructive Examination (Section V)– Welding and Brazing Qualifications (Section IX)

Section III• Nuclear Component Certification Program (N-Type Stamps)• QSC-Quality System Certificate for Nuclear Material Organizations• The ASME certification mark, which is regarded as the hallmark of

acceptance and certification, is used to indicate that the stamped item(s) conform to the latest edition of the ASME Boiler and Pressure Vessel Codes

Section III• The Certification Program confirms:

– An operating Quality Assurance Program meeting the requirements of NCA-4000 and NQA-1.

– Ability to perform manufacturing the activities shown on the certificate in accordance with Section III requirements.

– Ability to Test, Inspect, Examine and Certify these activities in accordance with Section III requirements.

– The existence of a contract with an Authorized Inspection Agency• who will carryout inspections and witness or verify any other examinations

and additional investigations that, in his judgment, are necessary to ascertain whether the item being inspected has been constructed in compliance with the rules of Section III.

Section XI Rules for Inservice Inspection of Nuclear Power Plant Components

• DIVISION 1- Rules for Inspection and Testing of Components of Light-water Cooled Plants.– program of examinations, testing, and inspections to

evidence adequate safety and to manage deterioration and aging effects.

– covers individual components and complete plants that have met all the requirements of the Construction Code

Section XI Rules for Inservice Inspection of Nuclear Power Plant Components

• The object of inservice inspection of components in nuclear power plants is to provide a continuing assurance that they are safe.

• to provide appropriate levels of assurance according to the importance of the component in its relationship to plant safety

South African Context• National Nuclear Regulator

– RD 0034 - Quality and Safety Management for Nuclear Installations– References

• IAEA GS-R-3, ISO 9001, ASME NQA-1 • Occupational Health and Safety Act

– Pressure Equipment Regulations• ASME Section III included in SANS 347 Annex A

ASME NQA-1a-2009 SUBPART 4.3

• Use of the ISO 9001:2008 Quality Management Systems Standard for Compliance with ASME NQA-1– This application appendix provides guidance to the ISO 9001:2008 Standard users and

interested organizations who may elect to use the ISO 9001:2008 Quality Management System Standard as the basis for establishing a Quality Assurance Program that meets the requirements of ASME NQA-1 Standard

– The purposes of this guidance is to:• Compare requirements of ISO 9001:2008 and ASME NQA-1-2008 Part I with the

NQA-1a-2009 addenda (NQA-1); • Identify the similarities and differences; and, • Identify where actions may be needed to address the differences. The guidance is

intended for all parties involved in the nuclear industry that are currently applying/implementing either NQA-1 or ISO 9001:2008 requirements and are required to comply with both standards.

ASME NQA-1a-2009 SUBPART 4.7

• Compares NQA-1and IAEA Safety Standard GS-R-3,• The purposes of this Application Guide are to:

– Identify the similarities and differences; and, – Identify where actions may be needed to address the differences.– The comparisons are illustrated from two perspectives: – How IAEA GS-R-3 requirements address NQA-1 requirements; and – How NQA-1- requirements address IAEA GS-R-3 requirements. – Two tables are included providing a detailed line-by-line comparison from each

perspective.• Provides guidance on how a NQA-1 based management system can be integrated

with a GS-R-3 system to allow a user to comply with both systems.

ASME Training Courses

• Where can you get more information: ASME Training courses:– QA Considerations for New Nuclear Facility Construction 

• Course No. PD635 (3 days) or online (ZI370)– Comparison of Global Quality Assurance & Management System Standards used for Nuclear Applications

• Course No. PD634 (3 days) or online (ZI360)– BPV Code Section III, Division 1 - Rules for Construction of Nuclear Facility Components

• Course No. PD184 – Manufacturing, Fabrication and Examination Responsibilities in Codes, Standards and Regulations for

Nuclear Power Plant Construction • Course No. PD631 (3 days)

– Design in Codes and Standards for Nuclear Power Plant Construction• Course No. PD 632

– Advanced Design and Construction of Nuclear Facility Components per ASME Section III– Course No. PD 644

Thank You

• Contact: Neil Broom : Bufo Technology CC

– E-mail : neil.broom@bufo.co.za– Phone : 012 667 1212 Cell : 082 374 1877