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

craner@asme.org

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

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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

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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

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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

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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

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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

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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

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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

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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

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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

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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)

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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

craner@asme.org