iaea international atomic energy agency iaea safety standards history, status, structure, contents...

IAEAInternational Atomic Energy Agency

IAEA SAFETY STANDARDS

History, Status, Structure, Contentsby Stephen Evans, IAEA NSRW RIT

School of Drafting Regulations

Vienna, November 2012

IAEA Reg'l WS on IAEA SSs and WENRA RLs 2

Outline

• History and status of the IAEA Safety Standards• Hierarchy and Structure of the SS’s• General Safety Regulations• Specific Safety Standards• Safety Regulations and Guides • Fundamental Safety Principles

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History – IAEA statute

Under Article III.A.6 of its Statute, the IAEA is authorized:

“to establish or adopt, in consultation and, where appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned, standards of safety for protection of health and minimization of danger to life and property.”

In 1958, the IAEA published its first Safety Standard, Safety Series No. 1, Safe Handling of Radioisotopes. Over

the years, some 200 publications have been issued in the Safety Series.

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Historical milestones

1958 1961 1962 1965

SS No. 15

Radioactive WasteDisposal into the

Ground

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Historical milestones (cont.)

1974

SS No. 15

1988 1996 2006

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Development

• From 1958 to 2006: “Bottom-up approach”• 1996: Commission on Safety Standards (CSS) –

standing body of senior governmental officials• Committees: NUSSC, RASSC, WASSC,

TRANSSC – standing bodies of senior experts• From 2006: “Top down-approach”

• Safety Fundamentals (2006)• Roadmap for the long term development of the Safety

Requirements (2008)

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IAEA 7

The role and functions of CSS

• To provide guidance on the approach and strategy for establishing the Agency’s SSs

• To resolve issues raised by the committees• To endorse the texts of the SF, SRs and SGs• To provide general advice and guidance on SSs

issues

01-04 October 2012Reg'l WS on IAEA SSs and WENRA RLs


Role and functions of the Committees

• To advise on the nuclear installation/radiation/ transport/waste safety programme for the development of the safety standards

• To recommend activities and areas for improvement to enhance the overall program

• To review reports on feedback from the Secretariat and NUSSC/RASSC/TRANSSC/ WASSC members on the application and use of the safety standards

• To review proposals for the development of relevant new standards and review and accept draft standards

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Hierarchy

Safety Fundamentals

Safety Requirements

Safety Guides

Technical documents

Principles for protecting people and environment

Requirements to be applied to meet the principles

Recommended ways of meeting the requirements

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Relationship with National Legislation

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Summary of Safety Standards

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Other publications

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Other publications (cont.)

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Final Structure of Safety Standards

Under development01-04 October 2012

IAEA 15

Development of Safety Standards

• Developed and reviewed by IAEA staff and international experts

• In close consultation with Member States• SF and SRs approved by the Board of Governors• SGs are approved by IAEA DG• Review periodicity is about 10 years• Since 1996 more than 100 volumes published


IAEA 16

General SRs

http://ww

w-ns.ia

ea.org/standards

/ docum

ents/general.asp


http://www-ns.iaea.org/standards/







Facility/Activity Specific SSs

Status of the SSs is available at

http://www-ns.iaea.org/committees/ files/CSS/205/status.pdf

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http://www-ns.iaea.org/committees/





Nuclear Power Plants

• Specific Safety Requirements:

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Nuclear Power Plants (cont.)

• Specific Safety Guides to be discussed:• Design of Emergency Power Systems for Nuclear Power

Plants Safety Guide, NS-G-1.8 (2004)• Design of the Reactor Coolant System and Associated

Systems in Nuclear Power Plants Safety Guide, NS-G-1.9 (2004)

• Design of Reactor Containment Systems for Nuclear Power Plants Safety Guide, NS-G-1.10 (2004)

• Design of the Reactor Core for Nuclear Power Plants Safety Guide, NS-G-1.12 (2005)

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Nuclear Power Plants (cont.)

• Modifications to Nuclear Power Plants Safety Guide,NS-G-2.3 (2001)

• Maintenance, Surveillance and In-service Inspection in Nuclear Power Plants Safety Guide, NS-G-2.6 (2002)

• Commissioning for Nuclear Power Plants Safety Guide,NS-G-2.9 (2003)

• Licensing Process for Nuclear Installations Specific Safety Guide, SSG-12 (2010)

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Current status of SSs

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Recently published

http://www-pub.iaea.org/MTCD/Publications/PDF/Pub1573_web.pdf

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Safety Guide Review Plan (priorities)• NS-G-1.3 Instrumentation and Control Systems Important to Safety in Nuclear Power Plants (2002)• NS-G-1.8 Design of Emergency Power Systems for Nuclear Power Plants (2004)• NS-G-1.9 Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants (2004)• NS-G-1.4 Design of Fuel Handling and Storage Systems for Nuclear Power Plants (2003)• NS-G-1.10 Design of Reactor Containment Systems for Nuclear Power Plants (2004)• NS-G-1.7 Protection against Internal Fires and Explosions in the Design of Nuclear Power Plants (2004) • NS-G-1.11 Protection against Internal Hazards other than Fires and Explosions in the Design of Nuclear

Power Plants (2004)• SSG-2 Deterministic Safety Analysis for Nuclear Power Plants (2009)• NS-G-2.15 Severe Accident Management Programmes for Nuclear Power Plants (2009)• SSG-15 Storage of Spent Fuel (in publication)• GS-G-2.1 Arrangements for Preparedness for a Nuclear or Radiological Emergency (2007)• GSG-2 Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency (2011)• WS-G-3.1 Remediation Process for Areas Affected by past activities and accidents (2007)• GS-G-1.1 Organization and staffing of the regulatory body for nuclear facility (2002)• GS-G-1.2 Review and assessment of nuclear facilities by the regulatory body (2002)• GS-G-1.3 Regulatory inspection of nuclear facilities and enforcement by the regulatory body (2002)• GS-G-1.4 Documentation for use in regulating nuclear facilities (2002)• SSG-12 Licensing Process for Nuclear Installations (2010) • SSG-16 Establishing the Safety Infrastructure for a Nuclear Power Programme (2011)

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Fundamental Safety Principles

Principle 1: Responsibility for safetyThe prime responsibility for safety must rest with the person or organization responsible for facilities and activities that give rise to radiation risks.

• Authorization may be granted• Prime responsibility is retained• Responsibility for given activities in

accordance with applicable safety objectives• Responsibility for long term operation and

wastes

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Fundamental Safety Principles (cont.)

Principle 2: Role of government

An effective legal and governmental framework for safety, including an independent regulatory body, must be established and sustained.

• Framework to fulfil national responsibilities• Arrangements to reduce radiation risks• The RB has competence, resources; is effectively

independent; informs and consults with interested parties;

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Principle 3: Leadership and management for safety

Effective leadership and management for safety must be established and sustained in organizations concerned with, and facilities and activities that give rise to, radiation risks.

• Leadership in safety matters at the highest level• Safety culture integrated into the management system• Accounting for human factor• Graded approach to safety assessment• Precursors to accident identified and analysed,

feedback of OE

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Principle 4: Justification of facilities and activities

Facilities and activities that give rise to radiation risks

must yield an overall benefit.• Benefits must outweigh the radiation

risk• Risk/benefit decisions taken on state

or regulatory body levels• Justification of medical radiation

exposure in the benefit of the patient

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Principle 5: Optimization of protection

Protection must be optimized to provide the highest level of safety that can reasonably be achieved

• To provide the highest level of safety that can reasonably be achieved (ALARA)

• For this all normal, abnormal and accident conditions must be assessed (in graded approach)

• Judgement of the relative significance of various factors• Resources devoted and measures commensurate with

the magnitude of the radiation risk

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Principle 6: Limitation of risks to individuals

Measures for controlling radiation risks must ensure that no individual bears an unacceptable risk of harm

• Doses and radiation risks controlled within specified limits

• Optimization of protection and limitation of doses go together

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Principle 7: Protection of present and future generations

People and the environment, present and future, must be protected against radiation risks

• Radiation risk across borders and for long time

• To protect the entire ecosystem• Waste management without undue

burden on the future generations

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Principle 8: Prevention of accidents

All practical efforts must be made to prevent and mitigate nuclear or radiation accidents

• Ensure that the likelihood of accident with harmful consequences be extremely low

• Defence in depth concept to prevent and mitigate

• Developing accident management procedures

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Principle 9: Emergency preparedness and response

Arrangements must be made for emergency preparedness and response for nuclear or radiation incidents

• Effective response at all levels• Ensure that the risk is minor• Mitigate consequences• Proper arrangements in advance• Consider all reasonably foreseeable

events

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Principle 10: Protective actions to reduce existing or unregulated radiation risks

Protective actions to reduce existing or unregulated radiation risks must be justified and optimized

• Radiation risks in situations other than in regulated facilities and activities

• Protective actions are justified if they yield sufficient benefit to outweigh radiation risks

• Optimized to result the greatest reasonably achievable benefit

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Review of compliance with SSs

• Integrated Regulatory Review Service (IRRS)• to peer review the host country’s nuclear and

radiation safety regulatory regime against the IAEA Safety Standards

• Modular review by international experts (15-20)• Core regulatory activities Modules• Mission report with Recommendations,

Suggestions, Good Practices (findings)

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What is an IRRS mission for?

IRRS is meant to provide• an opportunity for continuous improvement for the

host RB through self-assessment and through peer review by an international expert team

• a review of the technical and policy issues relevant for the host country

• an opportunity to share and exchange experience and discuss issues with international experts

• a contribution to the harmonization of regulatory approaches among Member States

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What is not an IRRS mission for?

The IRRS missions are NOT meant to• inspect regulatory or operator activity in the host

country• form any judgment on the host country

regulatory regime or practice• to provide comparison among Member States

Therefore the number of findings is in no way a measure of the status of the regulatory body. Comparisons of such numbers between IRRS reports from different countries should not be attempted.

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IRRS Missions to date

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IRRS Modules


IRRS mission sites (2006 – 2012)

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Inviting a mission

• Regulatory bodies in the region are highly encouraged to invite IRRS missions

• Invitation is to be addressed to the DDG for Nuclear Safety and Security of IAEA

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THANK YOU FOR YOUR ATTENTION

Ivan Lux, IAEA NSNI RAS, [email protected]

01-04 October 2012

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