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IAEA Safety Standards in EPR with
overview of GSR Part 7
Joint IAEA-KINS Regional Network Meeting on Radiation
Safety and Emergency Preparedness and Response
25 – 29 June 2018, Daejeon, Republic of Korea
Incident and Emergency Centre , IAEA
Contents
• Safety Standards in EPR
– Overview
– Future standards
• EPR series
• Overview of GSR Part 7
IAEA Statute (1956)
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 (including such standards for labour conditions), and to provide for the application of these standards...”
Assistance Convention (1986)
Under Article 5, the IAEA is given the function:
“To collect and disseminate to States Parties and Member States information concerning … (ii) methodologies, techniques and available results of research relating to response to nuclear accidents or radiological emergencies; …”
Evolution (cont.)
2011
2007
2002
2015
Valid Safety Standards in EPR(Follow the long-term structure of IAEA Safety
Standards adopted in 2008)
2006
Image courtesy IAEA
2018
Safety Standards - Structure
SF
GSRs
GSGs
SSRs
SSGs
Safety Fundamentals
General Safety Requirements
Specific Safety Requirements
General Safety Guides
Specific Safety Guides
Safety Standards in EPR
• FundamentalsSF-1
• RequirementsGSR Part 7
GS-G-2.1
GSG-2
GSG-11Recommendations
Safety Standards in EPR
An international consensus on what constitutes a high level
of safety for protecting people and the environment from
harmful effects of ionizing radiation…
Safety Standards – Levels
Safety Fundamentals
Fundamental safety
objectives and principles
for protecting people and
environment
Safety Requirements
Requirements that
must be met to ensure
protection of people
and environment
Safety Guides
Recommended
ways of meeting
the requirements
Safety Fundamentals
No. SF-1
• Establishes the fundamental
safety objective, safety principles
and concepts that provide the
bases for the IAEA’s safety
standards and its safety related
programme
• Published in 2006
• Cosponsored by Euratom, FAO,
IAEA, ILO, IMO, OECD/NEA,
PAHO, UNEP and WHO
Safety Fundamentals
No. SF-1
Principle 9: EPR
“Arrangements must be
made for emergency
preparedness and
response for nuclear or
radiation incidents.”
General Safety Requirements
No. GSR Part 3
Relevant requirements in
Section 4 on Emergency
exposure situations
• Requirements level: ‘Shall’ or ‘What’ to be done
• Approved on September 2011 by IAEA Board of Governors
• Published 2014
• Co-sponsored by EC, FAO, IAEA, ILO, OECD\NEA, PAHO, UNEP, WHO
General Safety Requirements
No. GSR Part 7
Establishes requirements for an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause
• Requirements level: ‘Shall’ or ‘What’ to be done
• Approved in 2015
• Co-sponsored by FAO, IAEA, ICAO, ILO, IMO, Interpol, OECD/NEA, PAHO, UNEP, UNOCHA, WHO, WMO, CTBTO
• Supersedes No. GS-R-2 issued in 2002
Details in the second part of the presentation
Safety Guides
No. GS-G-2.1
Provides recommendations on
implementation of specific safety
requirements established in GS-R-2
– Recommendations level: ‘Should’ or ‘How’ to be done
– Published in 2007
– Co-sponsored by FAO, IAEA, ILO, OCHA, WHO, PAHO
GS-G-2.1
Contents
• Basic concepts in EPR• Types of potential nuclear or radiological emergencies
• Overview of:• Radiation induced health effects
• Exposure pathways
• Protective actions and other response actions
• Hazard (threat) assessment and categories• Criteria for determining categories
• Defines concept of dangerous source and provides D-
values
• Lists typical facilities and activities per category
• Defines area and zone sizes and discusses the basis
GS-G-2.1
Contents /2
• Roles and responsibilities
• Defined at operator, off-site
and international levels
• All categories covered
• Guidance for a coordinating
mechanism
• National Coordinating Authority
• Guidance on integrated
planning
• All hazards approach
GS-G-2.1
Contents /3
• Further guidance provided on
infrastructural requirements • Including detailed description of recommended
emergency response facilities and locations, their
functions and characteristics
• Elaborated concept of operations for a
range of postulated nuclear or radiological
emergency• For categories I-V
GS-G-2.1
Contents /4
• Further guidance on how to implement
following functional requirements:
• Identifying, notifying and activating
• Taking urgent protective actions
• Keeping the public informed
• Managing the medical response
• Taking early protective and other actions
• Mitigating the non-radiological consequences
Safety Guides
No. GSG-2
GSG-2 provides guidance on criteria for taking protective actions and other response actions in a nuclear or radiological emergency
• Recommendations level:
‘Should’ or ‘How’ to be done
• Published in 2011
• Co-sponsored by FAO, IAEA,
WHO, PAHO, ILO
• Supersedes intervention
levels and generic action
levels from GS-R-2
GSG-2
Contents
• Elaborates framework for
emergency response
criteria at which specific
emergency response actions
need to be taken
• Defines system of:
• Generic criteria
• Operational criteria
• OILs, EALs, Observables
• Guidance values applicable for
emergency workers
ACTIONS
GENERIC CRITERIA
Operational
Intervention
Levels
(OIL)
Emergency
Action Levels
(EAL)
Observables/
Indicators
Abnormal facility
conditions
Conditions
on-scene
Field and laboratory
measurements
Intake,
I [Bq]
Equivalent dose
in tissue or
organ T,
HT [Sv]
Absorbed
dose in
tissue or
organ T,
DT [Gy]
RBE weighted
dose in tissue or
organ T,
ADT [Gy]
Radiation
fluence
F,
[cm-2
]
WR
RBER,T
Effective dose,
E [Sv]
Evaluation
of deterministic
effects
Evaluation
of stochastic
effects
Evaluation
radiation
detriment
WT
GSG-2
Contents /2
• Example of default OILs for:• Deposition
• Individual contamination
• Contamination of food, milk and drinking water
• Plain language explanations in support of the
criteria
Dose rate from skin
contamination
Dose rate above
ground
Food, milk and water
concentrations
GSG-2
Contents /3
• Guidance on EALs development including
example EALs for LWRs
• Suggested radii for inner cordoned area for
radiological emergency
Safety Guides
No. GSG-11
GSG-11 provides guidance on arrangements for termination of a nuclear or radiological emergency and subsequent transition to new exposure situation (either planned or existing)
• Recommendations level:
‘Should’ or ‘How’ to be done
• Published in 2018
• Co-sponsored by FAO, IAEA,
ICAO, ILO, IMO, INTERPOL,
OECD/NEA, OCHA, WHO,
WMO
GSG-11
Contents
• Defines phases of nuclear or radiological emergency
• Sets objective and prerequisites for terminating emergency
• Gives details on arrangements for transition phase
• Provides case studies, etc.
Safety Guides
What to expect in future
• Arrangements for Communications with the
Public in Preparedness and Response for a
Nuclear or Radiological Emergency (DS475)
– Recommendations and guidance on communicating
with the public in emergency preparedness and
response taking into account some particular
circumstances (e.g. coincident emergencies,
emergencies triggered by a nuclear security event,
transition phase)
– Expected completion: 2018, to be published 2019
Safety Guides
What to expect in future /2
• Preparedness and Response for an
Emergency during the Transport of
Radioactive Material (DS469)
– Revision of TS-G-1.2 issued in 2002
– Guidance and recommendations on
the implementation of the requirements
established primarily in GSR Part 7
and SSR 6 in order to prepare for and
respond to emergencies during the
transport of radioactive material
– Expected completion: 2019/2020, to be published 2020
• DS504 (Safety Guide on EPR, revision of
GS-G-2.1):
– Drafting stage
– Expected completion: 2021/2022
• DS505 (Safety Guide on Source,
environmental and individual monitoring,
revision on RS-G-1.8):
– Drafting stage
– Expected completion: 2021/2022
Safety Guides
What to expect in future /3
Contents
• Safety Standards in EPR
– Overview
– Future standards
• EPR series
• Overview of GSR Part 7
What is not a Safety Standard?
• Other Agency’s publications than Safety Fundamentals,
Safety Requirements and Safety Guides, for example:
– Safety Reports
– Accident Reports
– EPR Series
– TECDOC Series etc.
EPR Series and training materials
• To support the application of the IAEA Safety Standards in EPR:
– EPR Series give further technical guidance and tools to support the establishment of effective and efficient emergency arrangements by Member States
– EPR Training Materials provide material to be used for training purposes at the international and regional levels or as a basis for development of training materials at national level in various areas of EPR
Relevant operational arrangements
• Based on Early Notification and Assistance Conventions and IAEA Safety Standards
• Support the establishment of operational arrangements for notification, information exchange and assistance in EPR
EPR Series
What to expect in future
• EPR Protection Strategy
– Practical guidance for the development, justification and
optimization of a protection strategy and
– Implementation of reference levels and generic criteria
– Expected completion: end of 2018, to be published 2019
• EPR-Combined emergencies– Guidance for emergency occurring in combination with a
disaster caused by an extreme natural event
– Expected completion: 2018, to be published 2018
EPR Series
What to expect in future /2
• EPR-NPP On-site– Arrangements for Operating Organization
– Expected completion: 2018, to be published 2019
• EPR-RAD OILs
– Operational Intervention Levels for Radiological
Emergencies and methodology for their derivation
– Expected completion: end of 2018, to be published 2019
Contents
• Safety Standards in EPR
– Overview
– Future standards
• EPR series
• Overview of GSR Part 7
Structure
• Follows old GS-R-2 to the extent possible
– In line with guiding principles for revision
– Division among general, functional and infrastructural requirements kept
• Does not distinguish Response and Preparedness functional requirements
• Has no extensive cross-references
• Has improved consistency in terminology
Structure /2
• Follows the new format for IAEA
Safety Standards Series:
– Introduces additional Section on:
Interpretation, Resolution of conflicts
and Entry into force
– Introduces overarching requirements vs
associated requirements
Overarching vs Associated
requirements /2
• Overarching requirements
– Emphasis on topic
– Assigned to the Government
• Associated requirements
– Detailed requirements associated with the
overarching requirement topic
– Wherever possible, assigned to relevant
organization unless responsibilities are on
several organizations simultaneously
• There is NO hierarchy among requirements!
GSR Part 7 Contents
• INTRODUCTION
• INTERPRETATION, RESOLUTION OF CONFLICTS AND ENTRY INTO FORCE
• GOALS OF EMERGENCY PREPAREDNESS AND EMERGENCY RESPONSE
• GENERAL REQUIREMENTS
• FUNCTIONAL REQUIREMENTS
• REQUIREMENTS FOR INFRASTRUCTURE
• Appendices:– Guidance values for emergency workers
– Generic criteria for use in EPR
• Annex: Applicability of paragraphs by category
GS-R-2 (2002) GSR Part 7 (2015)
General Requirements
Basic ResponsibilitiesEmergency management system
Roles and responsibilities
Threat assessment Hazard assessment
Protection strategy
Requirements for Infrastructure
Authority Authorities for emergency preparedness and
response (EPR)
Organization Organizations and staffing for EPR
Coordination of EP Coordination of EPR
Plans and procedures Plans and procedures for ER
Logistical support and facilities Logistical support and facilities for ER
Training, drills and exercises Training, drills and exercises for EPR
QA programme QM Programme for EPR
GS-R-2 (2002) GSR Part 7 (2015)
Functional Requirements
Establishing emergency
management and operationsManaging emergency response operations
Identifying, notifying and
activatingIdentifying and notifying a nuclear or radiological
emergency and activating an emergency response
Performing mitigatory actions Taking mitigatory actions
Carrying out urgent protective
actions
Assessing the initial phase
Taking urgent protective actions and other response
actions
Providing information and
issuing instructions and
warnings to the public
Providing instructions, warnings and relevant
information to the public
Protecting emergency
workers
Protecting emergency workers and helpers in an
emergency
Managing the medical
response
Managing the medical response in a nuclear or
radiological emergency
GS-R-2 (2002) GSR Part 7 (2015)
Functional Requirements (cont.)
Keeping the public informed Communicating with the public throughout a
nuclear or radiological emergency
Carrying out agricultural
countermeasures,
countermeasures against
ingestion and longer term
protective actions
Taking early protective actions and other
response actions
Managing radioactive waste in a nuclear or
radiological emergency
Mitigating the non-radiological
consequences of an emergency
response
Mitigating non-radiological consequences of a
nuclear or radiological emergency and
emergency response
Conducting recovery operations Terminating a nuclear or radiological emergency
-Requesting, providing and receiving international
assistance for emergency preparedness and
response
-Analysing the emergency and the emergency
response
Revised terminology
GS-R-2 (2002) GSR Part 7 (2015)Threat assessment Hazard assessment
Threat categories Emergency preparedness categories
Quality assurance programme Quality managementprogramme
Iodine prophylaxis Iodine thyroid blocking
Revised concepts
GS-R-2 (2002) GSR Part 7 (2015)
National coordinating authority National coordination mechanism
Threat category V Emergency preparedness category V
Intervention Protective actions and other response
actions
Protection strategy
Agricultural countermeasures,
countermeasures against
ingestion and longer term
protective actions
Urgent and early protective actions:
Protection of food-chain and water
supply systems
Prevention of ingestion of food, milk
and drinking water
Prevention of inadvertent ingestion
Protection strategy
GS-R-2 (2002)
Implementation of an
intervention (i.e.
single protective
action) on the base of
generic intervention
level of dose actually
avertable by taking
that action
GSR Part 7 (2015)
Implementation of
protection strategy (i.e. set of protective actions and
other response actions)
on the basis of
generic criteria for dose
projected and dose
received with account taken
of the reference level for
residual dose
Set reference level
of residual dose between
20 mSv - 100 mSv
Establish Generic Criteria of projected or
received dose warranting specific protective
actions and other response actions
Develop default operational criteria:
measurable parameters or observables
(e.g. OILs, EALs)
Protection Strategy /2
100 mSvEmergency
exposure situation
20 mSv
1 mSv
Existing exposure situation
Planned exposure situation
Reference level
of residual dose
Revised concepts (cont.)
GS-R-2 (2002) GSR Part 7 (2015)
Generic intervention levels in
terms of avertable dose
Generic criteria in terms of projected dose and
received dose
Generic action levels for
foodstuffs (for activity
concentrations)
Generic criteria for food, milk and drinking
water (in terms of projected dose and
received dose)
Operational intervention levels (for activity
concentrations) (contained in GSG-2)
Management system Emergency management system
Conducting recovery
operations
Transition from emergency
response to long term
recovery operations
Terminating a nuclear or radiological
emergency
Transition from an emergency exposure
situation to an existing exposure situation
or to a planned exposure situation
New or strengthened concepts
GSR Part 7 (2015)
Emergency planning distances
System for placing health hazards in perspective
Interface with nuclear security in EPR
Responsibilities of international organizations
Leadership in EPR
Fitness for duty of emergency workers
Helpers in an emergency
Reference levels for emergency exposure situation
Keeping international community and IAEA informed in an emergency
Analysis of the emergency and emergency response
International assistance in EPR
Periodic and independent appraisals
Compensation of victims for damage
Extended planning distance
(EPD)
Area around a facility in category I and
II in which monitoring would need to
be carried out following declaration of
a general emergency in order to
identify timely areas warranting
emergency response actions (such as
relocation) off-site
Ingestion and commodities planning
distance (ICPD)
Area around a facility in category I
and II in which effective emergency
response actions in relation to
restrictions on food, milk and drinking
water and non-food commodities are
warranted following declaration of a
general emergency
Interface with nuclear security in EPR (cont.)
GSR Part 7 (2015)
Applies for nuclear or radiological emergency irrespective of the cause
explicitly (which may be a nuclear security event)
Establishes requirements for coordination and integration of emergency
arrangements and response measures to circumstances surrounding a
nuclear security event at all levels to a greater extent
Addresses interfaces where emergency arrangements or the emergency
response may affect nuclear security systems and the nuclear security
systems may affect the emergency arrangements
Protecting sensitive/confidential information and data in EPR
Provides references to existing Nuclear Security Recommendations
publications where necessary
Requirements for
infrastructure
AuthorityOrganization and staffing
CoordinationPlans and
procedures
Logistical support
and facilities
Training, drills and exercises
QM programme
Requirements for infrastructure
• Broadened to cover EPR overall
• Details appropriate for guidance removed
• Strengthened:
– Giving authorities and discharging them
• Directing response actions
• Decision making
– Staffing and fitness for duty
– Recognition of limitations of analytical tools
– Emergency response facilities and locations
– Periodic and independent appraisals
Appendix I
• Guidance values for restricting exposure of
emergency workers in an emergency
response
– To provide a basis for operational guidance
Appendix II
• Generic criteria for doses:
– For which protective actions and other response actions are expected to be taken:
• Under any circumstances to avoid or to minimize severe deterministic effects
• If they can be taken safely, to reasonably reduce the risk of stochastic effects
– For which restriction of international trade is warranted with due consideration of non-radiological consequences
– For use as a target dose for the transition to an existing exposure situation
Where to Get More
Information?
• IAEA Safety Standards and
EPR publications are available on-line in pdf
• Just search for the title!
Summary
• IAEA Safety Standards represent
international consensus
• EPR Series publication give practical
guidance
• GSR Part 7 replaces GS-R-2 and brings
much improved EPR