INTERNATIONAL ATOMIC ENERGY AGENCY
Technical Meeting to Share Experiences and Lessons Learned
from the Application of Different Management System
Standards in the Nuclear Industry
ASME Nuclear Codes and Standards Development Activities
15-19 December 2015
Vienna, Austria
Ryan Crane, P.E.
ASME Nuclear Codes and Standards Europe Liaison
Origins of The Society
• Technical professional society; founded in
1880 as the American Society of Mechanical
Engineers; not-for-profit
• Engineers convened to foster engineering
innovation, education and research
• First standard issued in 1884 – boiler efficiency
test
• Headquarters in New York City
• Offices in Atlanta, Houston, New Jersey,
Beijing (China), Brussels (Belgium), Mumbai
(India)
Origins of The Society
ASME’s Mission:
• To serve our diverse global communities by
advancing, disseminating and applying
engineering knowledge for improving the
quality of life; and communicating the
excitement of engineering
ASME Standards and Certification
• 70 Consensus Committees
• 700 Total Committees
• 5 Supervisory Boards
• 5,100 Volunteers (800 International and growing)
• 500 Standards
• ASME Standards Accepted for Use in Over 100 Nations
• Administer Over 40 U.S. TAG’s to ISO
• 12 Conformity Assessment Programs
• More than 200 training programs worldwide
ASME Codes and Standards
Consensus Process
• Decisions are reached through consensus among those
affected.
• Participation is open to all affected interests: no
membership fees or requirement to be ASME society
member
• Balance is maintained among competing interests
– Designers, Manufacturers, Users, Regulators, General Interests,
etc.
• The process is transparent - information on the process
and progress is directly available.
ASME Codes and Standards
Consensus Process • Due process assures that all views will be considered and
that appeals are possible.
• The process is flexible, allowing the use of different methodologies to meet the needs of different technology and product sectors.
• The process is timely; purely administrative matters do not slow down the work.
• Standards activities are coherent, avoiding overlap or conflict.
What does "Consensus" mean?
• ASME standards are consensus standards
• Consensus means – Substantial agreement by affected interest categories
– Consideration of views, attempted resolution is part of the process
– Unanimity not required
• The Standards Committee is responsible for establishing consensus on proposed standards actions.
The Consensus Development
Process
• Development of standards action
• Recorded vote
• Public review
• Supervisory Board approval
• Appeals
• ANSI approval
The Committees
• Administrative
– Consensus Procedures – Evolved over the years
to become the model for standards development
• ANSI accredited
• Consistent with principles of WTO Technical Barriers to
Trade Agreement
– Technical staff to administer committees and
interact with standards users
– Development of C&S Connect – in-house web-
based program to manage committee
communications, records, and ballots
Participation
Volunteer Participation
• Individual “voluntary” participation
• ASME Codes & Standards relies on industry supporting
participation by knowledgeable experts
– Involve the best and the brightest people from all around the world to
develop, maintain, and promote the use of these ASME products and
services
• Technical and administrative support to the committees
ASME Codes and Standards
Development
• No funding by government
• No fees to participate
• Supported by revenue from S&C sales and related programs
• Volunteer members not compensated by ASME
12
U.S. Public Policy
• OMB Circular A119
– Instructs Federal Agencies to use voluntary standards and
participate in their development, unless impractical
• National Technology Transfer and Advancement Act of 1995
– Mandates government agency use of private sector voluntary
consensus standards
– Obliges federal government participation in voluntary
standards development
13
Fulfills Regulators’ Expectations
• Meets public safety, health and environmental
objectives
• Provides confidence in the technical integrity of the
product or service
• Supports mutual recognition essential to international
trade
• Regulatory Agencies support members to the
committees
Interpretations
• Interpretations are used to clarify the meaning of a
requirement
• Clarifies ambiguous or incorrect wording, which may result
in a revision
• Formal approval and response to a inquiry request
• Official ASME interpretation letterhead
• A request may come from individuals, committees,
professional organizations, government agencies, industry
groups, public interest groups, etc.
ASME Codes and Standards
Consensus Process
Proprietary Issues
• ASME does not ‘approve’, ‘rate’ or ‘endorse’ any
item, construction, proprietary device, or activity
• Proprietary devices may only be incorporated in a
generic manner
International Participation
• Incorporation of market and governmental needs into ASME codes and standards
• ASME encourages international participation in its standards development committees – Individual Experts
– Delegate Program
– International Interest Review Group (BPV)
– International Review Groups
– International Working Groups
– Contributing Members
• International participation facilitated by use of electronic tools (C&S Connect) in standards development activity
International Working Group • An International Working Group (IWG) accommodates participation by
members in a common geographic location who would otherwise be unable
to meet the attendance expectations of committees that meet principally in
the U.S. and Canada
• An IWG is a “sub-tier” ASME code committee, and integrated into a
Standards Committee’s hierarchy much like other “sub-tier” groups and are
identical to “traditional” subcommittees, subgroups, and working groups
• IWGs address the challenges presented by time zones, travel constraints,
and language barriers that prevent experts based overseas from
participating in the ASME standards activities
• IWGs provide additional expertise and resources to Code committees to
understand identify, clarify and address Stakeholder issues arising in
regions outside of N. America
• IWGs typically conduct all of their meetings outside of the U.S. and Canada
and in a language other than English
18
IWG Members
• Enjoy all typical privileges and benefits of participation
• Have CS-Connect accounts and “full” member access
• Vote on IWG proposals and administrative matters
• Are required to vote when the IWG is included on a ballot distribution
• Are permitted to comment when the IWG is included in Review &
Comment distributions
• IWGs have been established for
– China, European Union, Germany, India, and Korea
• IWG also discuss inquiries and technical clarification prior to
submitting
19
NQA IWG Efforts
• NQA Task Group on International Working Groups Have CS-Connect
accounts and “full” member access
– The NQA Task Group (TG) on International Working Groups (IWG) will engage
international stakeholders (outside the United States and Canada) and perform
outreach activities on the concept of IWGs abroad. The TG will coordinate these
efforts with the goal of forming IWGs on a regional basis. The TG will provide
updates and recommendations to the NQA Standards Committee.
– Bud Danielson, Chair
• NQA International Working Group Europe (IWG-EU)
– The NQA International Working Group Europe (IWG-EU) serves as a forum to
provide for the participation of NQA technical experts based in Europe and to create
a means of communication and collaboration between ASME NQA and other
stakeholders in Europe. The NQA International Working Group Europe will: Review
and comment on proposed changes or additions to NQA-1; initiate and process
proposed standards actions for NQA-1; conduct activities in Europe related to codes
and standards, administrative and personnel matters in accordance with approved
ASME procedures, policies, and established guidelines; coordinate NQA International
Working Group Europe activities with the parent NQA Executive Committee and
ASME Staff.
– Christian Spletter, Areva, Chair
IWGs and NCS long-term outlook
In order to ensure the continued excellence of its standards, ASME
must embrace the challenge to enlist experts from around the globe
to participate in the its standards development process
• Regions outside of North America are significant markets of
nuclear components and have significant sources for heavy
equipment
• Such markets have the requisite knowledge and experience
to fully participate in standards writing
22
Board of Governors
Engineering Workforce Development, Energy, Global Impact
Council on Standards & Certification
Board on Nuclear Codes & Standards
Committee on BNCS Operations
Committee on BNCS Strategic Initiatives
BNCS Task Group on Regulatory Endorsement
24
Standards & Certification Organization
Energy and Environmental Standards Advisory Board
Board on Nuclear Codes and Standards
Board on Standardization
and Testing
Council on Standards and Certification
Board on Pressure Technology Codes and Standards
Board on Safety Codes and Standards
Board on Conformity Assessment
Board on Codes and Standards
Operations
Board on Strategic Initiatives
Board on Hearings and Appeals
BNCS Provides procedural oversight for all NCS
Standards
Committees
Establishes consensus on all technical matters in a
given subject area – Nuclear Quality Assurance
Subcommittees Provides recommendations to the standards on technical
matters in a given specialty –
Assessment and Verification, Applications, Engineering and
Procurement, Interfaces and Administration, Program
Management Process, Software Quality Assurance, Waste
Management
ASME Structure / Process Overview
WGs, TGs, PTs Develops detailed proposals in a specific field
26
ASME Nuclear Codes and Standards • Standards Committee on Nuclear
Air and Gas Treatment
• Joint Committee on Nuclear Risk Management (JCNRM)
• Standards Committee on Nuclear Quality Assurance
• Standards Committee on Operation and Maintenance of Nuclear Power Plants
• Standards Committee on Qualification of Mechanical Equipment Used in Nuclear Facilities
• Committee on Nuclear Certification (CNC)
• Board on Nuclear Codes and Standards
• BNCS Task Group on Regulatory Endorsement
• Committee on Board (NCS) Strategic Initiatives
• BPV Committee on Construction of Nuclear Facility Components (III)
• BPV Committee on Nuclear Inservice Inspection (XI)
• Standards Committee on Cranes for Nuclear Facilities
• Standards Committee on Nuclear Risk Management (CNRM)
• Verification and Validation in Computational Simulation of Nuclear System Thermal Fluids Behavior
NQA-1-2014 - Quality Assurance Requirements for Nuclear Facility
Applications (QA)
ASME Nuclear Codes & Standards
ASME NQA-1
• New editions do not automatically supersede or negate previous issued versions.
• A Quality Program based on an earlier Edition will still be in compliance with future Editions
• A fundamental part of the process in developing new requirements or revisions is ensuring there is consistency and no conflicts with existing requirements
ASME NQA-1
• There is no requirement to upgrade a Program just because a new version is issued
• Changes in the standard occur in order to incorporate advances in technology and lessons learned – computer software used in design development
– suspect and counterfeit item detection
– need for better controls over design changes
Boiler and Pressure Vessel Code Sections
Section I - Power Boilers
Section II - Materials
Section III - Rules for Construction of Nuclear Facility
Components
Section IV - Heating Boilers
Section V - Nondestructive Examination
Section VI - Recommended Rules for the Care and Operation of
Heating Boilers
Boiler and Pressure Vessel Code Sections
Section VII - Recommended Guidelines for the Care of Power Boilers
Section VIII Pressure Vessels
Section IX - Welding and Brazing Qualifications
Section X - Fiber-Reinforced Plastic Pressure Vessels
Section XI - Rules for Inservice Inspection of Nuclear Power Plant
Components
Section XII - Rules for the Construction and Continued Service of
Transport Tanks
ASME Section III
• Division 1
– Rules for Construction of Nuclear Facility Components
• Division 2
– Code for Concrete Reactor Vessels and Containments
• Division 3
– Containment Systems and Transport Packaging for Spent Nuclear Fuel and High-Level Radioactive Waste
• Division 4
– Magnetic Confinement Fusion Energy Devices
• Division 5
– High Temperature Reactors
ASME Section XI
• Division 1
– Rules for Inspection and Testing of
Components of Light-Water-Cooled
Plants
• Division 2
– Rules for Inspection and Testing of
Components of Gas-Cooled Plants
– Being revised to implement a Reliability
Integrity Management (RIM) system for
all reactor type
• Division 3
– Rules for Inspection and Testing of
Components of Liquid-Metal-Cooled
Plants
• OM - Code for Operation and Maintenance of Nuclear Power Plants
• RA-S - Probabilistic Risk Assessment for Nuclear Power Plant
Applications (PRA)
• QME-1 - Qualification of Active Mechanical Equipment used in Nuclear
Power Plants
• AG-1 - Code on Nuclear Air and Gas Treatment
• N509 - Nuclear Power Plant Air-Cleaning Units and Components
• N510 - Testing of Nuclear Air-Treatment Systems
• N511 - In-Service Testing of Nuclear Air Treatment, Heating, Ventilating,
and Air-Conditioning Systems
ASME Nuclear Codes & Standards
ASME Nuclear Codes & Standards
• NOG-1 - Rules for Construction of Overhead and Gantry Cranes
(Top Running Bridge, Multiple Girder)
• NUM-1 - Rules for Construction of Cranes, Monorails, and Hoists
(with Bridge or Trolley or Hoist of the Underhung Type)
• QME-1 - Qualification of Active Mechanical Equipment used in
Nuclear Power Plants
• PTC 32.1 - Nuclear Steam Supply Systems
ASME V&V Standards Committee
Coordinate, promote, and foster the development of standards that
provide procedures for assessing and quantifying the accuracy and
credibility of computational models and simulations.
• V&V 10 Verification and Validation in Computational Solid
Mechanics
• V&V 20 Verification and Validation in Computational Fluid
Dynamics and Heat Transfer
• V&V 30 Verification and Validation in Computational Simulation
of Nuclear System Thermal Fluids Behavior – Provides the practices and procedures for verification and validation of
software used to calculate nuclear system thermal fluids behavior. The software includes system analysis and computational fluid dynamics, including the coupling of this software.
• V&V 40 Verification and Validation in Computational Modeling of
Medical Devices
Published documents
V&V for New Nuclear Reactor Design
• V&V of software used to calculate nuclear system thermal fluids behavior
– Initial focus -- high temperature gas-cooled reactors in response to Department of Energy activities
• Responsive to changes in industry to promote best V&V practices within the community
Conformity Assessment Program History
• 1916 First ‘S’ Certificate and Stamp issued
• 1919 National Board of Boiler and Pressure Vessel Inspectors
founded – uniform qualification of third party Inspectors
• 1972 ASME Certification offered outside the US and Canada
• 1990’s ASME accredits Authorized Inspection Agencies
• Today Over 7000 certified companies in 75 countries
ASME Global Growth Certified Boiler & Pressure Vessel Manufacturers
0
1000
2000
3000
4000
5000
6000
7000
90 92 94 96 98 00 02 04 06 08 10 12
Cert
ifie
d M
an
ufa
ctu
rers
US International Total
Data as of 2013-12-31
Nuclear Component Certification
• Certification of an organization's quality assurance program
in accordance with Section III of the ASME Boiler and
Pressure Vessel Code (BPVC) for components installed in
nuclear facilities.
– N - Vessels, pumps, valves, piping systems, storage tanks, core
support structures, concrete containments, and transport packaging
– NA - Field installation and shop assembly of all items
– NPT - Parts, appurtenances, welded tubular products, and piping
subassemblies
– NS - Supports
– NV - Pressure relief valves
– N3 - Transportation containments and storage containments
– OWN - Nuclear power plant owner
41
NQA-1 Certification
The ASME NQA-1 Certification program provides a means for an
organization supplying items or services which provide a safety
function for nuclear facilities to have its Quality Assurance Program
recognized by ASME as having had its Quality Assurance Program
audited and verified to be in conformance with the requirements of the
ASME NQA-1 Standard.
http://www.asme.org/kb/standards/certification---
accreditation/product-certification/nqa-1-certification-program
42
NQA-1 Certification
• The NQA-1 Quality Program Certificate is available to organizations
implementing the ASME NQA-1 Standard, Part I and Part II, or
portions thereof
• Starting with the 2008 edition, organizations have the option to
either update their QA Program to meet the latest published
edition/addenda of the ASME NQA-1 Standard, or, freeze its
program to a specific edition/addenda
• An NQA-1 Quality Program Certificate does not apply to or replace
the certification requirements to supply, manufacture, construction
and fabrication of items falling under the scope of Section III
• An NQA-1 Quality Program Certificate does not prequalify or
exempt an organization from a qualification audit being performed
by the Purchaser of the items or services provided by the
organization
43
NQA-1 Quality Program Certificate
Joint Efforts
• API 579-1/ASME FFS-1- Fitness-for Service
• Joint ACI-ASME Committee on Concrete Components for
Nuclear Service
• ISO/ASME 14414 - Pump system energy assessment
• ASTM material specifications for ASME Section II
• SDO Convergence Board
• Input to MDEP CSWG and Code Comparison Project
• Nuclear Energy Standards Coordination Collaborative
(NESCC)
• WNA Cooperation in Reactor Design Evaluation and
Licensing (CORDEL)
45
The Future
• ASME will continue to pursue its mission of
advancing, and applying engineering
knowledge for improving the quality of life
• Engineers and experts from all over the world
will continue to share their knowledge in pursuit
of the highest quality technical standards for
the benefit of a global society
Questions?
Ryan Crane, P.E.
ASME Nuclear Codes and Standards Europe Liaison
2 Park Avenue
New York, NY 10016 USA
+1-212-591-7004