ISO 20043-2:2023
(Main)Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation
These international guidelines are based on the assumption that monitoring of environmental components (atmosphere, water, soil and biota) as well as food quality is performed to ensure the protection of human health[5][7][8][9][10][11][12]. The guidelines constitute a basis for the setting of national regulations, standards, and inter alia, for monitoring air, water and food in support of public health, specifically to protect the public from ionizing radiation. This document provides: — guidance to collect data needed for the assessment of human exposure to radionuclides naturally present or discharged by anthropogenic activities in the different environmental compartments (atmosphere, waters, soils, biota) and food; — guidance on the environmental characterization needed for the prospective and/or retrospective dose assessment methods of public exposure; — guidance that addresses actions appropriate for an event involving uncontrolled releases of gamma-emitters (e.g. nuclear power reactor emergencies) and also events that would involve beta- or alpha-emitters would require additional consideration of the pathways, instrumentation, laboratory analysis, operational intervention levels, protective actions, etc., appropriate to their release; — guidance for staff in nuclear installations responsible for the preparation of radiological assessments in support of permit or authorization applications and National Authorities’ officers in charge of the assessment of doses to the public for the purposes of determining gaseous or liquid effluent radioactive discharge authorizations; — information to the public on the parameters used to conduct a dose assessment for any exposure situations to a representative person/population. It is important that the dose assessment process be transparent, and that assumptions are clearly understood by stakeholders who can participate in, for example, the selection of habits of the representative person to be considered. This document refers to various published ISO documents. When appropriate, this document also refers to national standards or other publicly available documents.
Mesurage de la radioactivité dans l'environnement — Lignes directrices pour l’évaluation de la dose efficace à l’aide de données de surveillance environnementale — Partie 2: Situations d'exposition d’urgence nucléaire
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INTERNATIONAL ISO
STANDARD 20043-2
First edition
2023-07
Measurement of radioactivity in
the environment — Guidelines for
effective dose assessment using
environmental monitoring data —
Part 2:
Emergency exposure situation
Mesurage de la radioactivité dans l'environnement — Lignes
directrices pour l’évaluation de la dose efficace à l’aide de données de
surveillance environnementale —
Partie 2: Situations d'exposition d’urgence nucléaire
Reference number
ISO 20043-2:2023(E)
© ISO 2023
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ISO 20043-2:2023(E)
COPYRIGHT PROTECTED DOCUMENT
© ISO 2023
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication may
be reproduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying, or posting on
the internet or an intranet, without prior written permission. Permission can be requested from either ISO at the address below
or ISO’s member body in the country of the requester.
ISO copyright office
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Phone: +41 22 749 01 11
Email: copyright@iso.org
Website: www.iso.org
Published in Switzerland
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ISO 20043-2:2023(E)
Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 2
4 Symbols . 4
5 Principle . 6
6 Implementation system of monitoring and emergency response plan .9
6.1 General . 9
6.2 Plan and implementation system . 9
6.3 Urgent response phase monitoring . 10
6.4 Early response phase monitoring . 11
6.5 Transition phase monitoring . 12
7 Guidance on emergency measurement .12
7.1 General .12
7.2 Ambient dose equivalent . 13
7.3 Measurement by survey meter and monitoring vehicle . 13
7.4 Aerial monitoring . 13
7.5 Radiation monitoring on surface water . 13
7.6 Environmental media and food monitoring . 14
7.6.1 General . 14
7.6.2 Measurement of radioactive materials in environmental media. 14
7.6.3 Measurement of radioactive materials in food and drink . 14
8 Discussion of Default OILs .14
8.1 Radiation monitoring for OIL 1 . 14
8.2 Radiation monitoring for OIL 2 . 14
8.3 Radiation monitoring for OIL 6 . 15
9 Projected dose assessment based on monitoring results .15
9.1 General . 15
9.2 Projected dose assessment during a release . 16
9.3 Projected dose assessment after a plume passage . 18
10 Laboratory management .19
10.1 Laboratory staff management . 19
10.2 Sample management . 20
10.3 Quality management . 20
10.4 Publication of results . 20
Annex A (informative) OILs for assessing the results of field monitoring and screening of
foodstuff concentrations from laboratory analysis .21
Annex B (informative) Example of operational intervention levels determination related
to living area during plume passage .23
Annex C (informative) Example of operational intervention levels determination related
to living area after a plume passage .27
Bibliography .32
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ISO 20043-2:2023(E)
Foreword
ISO (the International Organization for Standardization) is a worldwide federation of national standards
bodies (ISO member bodies). The work of preparing International Standards is normally carried out
through ISO technical committees. Each member body interested in a subject for which a technical
committee has been established has the right to be represented on that committee. International
organizations, governmental and non-governmental, in liaison with ISO, also take part in the work.
ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of
electrotechnical standardization.
The procedures used to develop this document and those intended for its further maintenance are
described in the ISO/IEC Directives, Part 1. In particular the different approval criteria needed for the
different types of ISO documents should be noted. This document was drafted in accordance with the
editorial rules of the ISO/IEC Directives, Part 2 (see www.iso.org/directives).
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. ISO shall not be held responsible for identifying any or all such patent rights. Details of
any patent rights identified during the development of the document will be in the Introduction and/or
on the ISO list of patent declarations received (see www.iso.org/patents).
Any trade name used in this document is information given for the convenience of users and does not
constitute an endorsement.
For an explanation on the voluntary nature of standards, the meaning of ISO specific terms and
expressions related to conformity assessment, as well as information about ISO's adherence to the
World Trade Organization (WTO) principles in the Technical Barriers to Trade (TBT) see the following
URL: www.iso.org/iso/foreword.html.
This document was prepared by Technical ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection.
A list of all parts in the ISO 20043 series can be found on the ISO website.
Any feedback or questions on this document should be directed to the user’s national standards body. A
complete listing of these bodies can be found at www.iso.org/members.html.
iv
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ISO 20043-2:2023(E)
Introduction
Everyone is exposed to natural radiation. The natural sources of radiation are cosmic rays and
naturally occurring radioactive substances existing in the Earth itself and inside the human body.
Human activities involving the use of radiation and radioactive substances cause radiation exposure in
addition to the natural exposure. Some of those activities, such as the mining and use of ores containing
naturally-occurring radioactive material (NORM) and the production of energy by burning coal that
contains such substances, simply enhance the exposure from natural radiation sources. Nuclear
installations use radioactive materials and produce radioactive effluent and waste during operation
and on their decommissioning. The use of radioactive materials in industry, agriculture and research is
expanding around the globe.
All these human activities generally also give rise to radiation exposures that are only a small fraction
of the global average level of natural exposure. The medical use of radiation is the largest and a growing
man-made source of radiation exposure. It includes diagnostic radiology, radiotherapy, nuclear medicine
and interventional radiology.
Radiation exposure also occurs as a result of occupational activities. It is incurred by workers in
industry, medicine and research using radiation or radioactive substances, as well as by crew during
air travel and by astronauts. The average level of occupational exposures is generally similar to the
[4]
global average level of natural radiation exposure .
As the uses of radiation increase, so do the potential health risk and the public’s concerns increase.
Thus, all these exposures are regularly assessed in order to
a) improve the understanding of global levels and temporal trends of public and worker exposure,
b) evaluate the components of exposure so as to provide a measure of their relative importance, and
c) identify emerging issues that may warrant more attention and scrutiny. While doses to workers
are usually directly measured, doses to the public are usually assessed by indirect methods
using radioactivity measurements results performed on various sources: waste, effluent and/or
environmental samples.
To ensure that the data obtained from radioactivity monitoring programs support their intended use,
it is essential in the dose assessment process that stakeholders (the operators, the regulatory bodies,
the local information committee and associations, etc.) agree on appropriate data quality objectives,
methods and procedures for: the sampling, handling, transport, storage and preparation of test
samples; the test method; and for calculating measurement uncertainty. An assessment of the overall
measurement uncertainty also needs to be carried out systematically. As reliable, comparable and ‘fit
for purpose’ data are an essential requirement for any public health decision based on radioactivity
measurements, international standards of tested and validated radionuclide test methods are an
important tool for the production of such measurement results. The application of standards serves
also to guarantee comparability over time of the test results and between different testing laboratories.
Laboratories apply them to demonstrate their technical competences and to complete proficiency tests
successfully during interlaboratory comparisons, two prerequisites to obtain national accreditation.
Today, over a hundred International Standards, prepared by ISO Technical Committees, including
those produced by this Technical Committee, and the International Electrotechnical Commission, are
available for measuring radionuclides in different matrices by testing laboratories.
Generic standards help laboratories to manage the measurement process, and specific standards
describing test methods are used specifically by those in charge of radioactivity measurement. The
latter cover test methods for:
40 14
— natural radionuclides, including K, tritium, C and those originating from the thorium and
226 228 234 238 220 222 210
uranium decay series, in particular Ra, Ra, U, U, Rn, Rn, and Pb, which can
be found in every material from natural sources or can be released from technological processes
involving naturally occurring radioactive materials (e.g. the mining and processing of mineral sands
or phosphate fertilizer production and use), and
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ISO 20043-2:2023(E)
— man-made radionuclides, such as transuranium elements (americium, plutonium, neptunium, and
14 90
curium), tritium, C, Sr and gamma emitting radionuclides found in waste, liquid and gases
effluent and in environmental matrices (air, soil, water, biota) as a result of authorized releases into
the environment and of fallout resulting from the explosion in the atmosphere of nuclear devices
and accidents, such as those that occurred in Chernobyl and Fukushima. Radionuclides, such as
14
tritium and C, occur both naturally and as by-products of the operation of nuclear reactors.
The International Commission on Radiological Protection (ICRP) recognises three types of exposure
[2]
situations that are intended to cover the entire range of exposure situations: planned, emergency
and existing exposure situations. Planned exposure situations involve the planned introduction and
operation of sources (previously categorised as practices). Emergency exposure situations require
prompt action in order to avoid or to reduce adverse consequences. Existing exposure situations are
exposure situations that already exist when a decision on control is taken, such as those caused by
enhanced natural background radiation (e.g. on remediated land).
The fraction of the background dose rate to man from environmental radiation, mainly gamma
radiation, varies considerably, and depends on factors such as the radioactivity of the local rock and
soil, the nature of building materials and the construction of buildings in which people live and work.
This document sets out principles and guidance for the radiological characterisation of the environment
needed for checking the results of
— prospective assessment of dose to the public arising from exposure to ionizing radiation which
may arise from planned discharges to the atmosphere and to the aquatic environment or following
remediation action, and
— retrospective assessment for dose that may be made for discharges or disposals that were not
initially covered by or authorized by a national regulatory body (e.g. contaminated land or dose
associated with accidental releases of radionuclides into the environment).
This document is one of a set of generic ISO Standards on measurement of radioactivity. Example of
dose assessment in different exposure situations are shown in the table below.
Example of dose assessment in different exposure situations, modified from Reference [6]
Type of assessment
Situation
Prospective Retrospective
Determining compliance with the relevant dose
constraint (dose limit or regulatory require-
Estimating dose to the public from past
Planned ments). A prospective assessment includes the
operations
exposures expected to occur in normal opera-
tion.
Future prolonged exposures (e.g. after remedi- Past exposures (e.g. occupancy of contami-
Existing
ation) nated lands)
Emergency planning (operational intervention
Emergency Actual impacts after emergency
level)
Generic mathematical models used for the assessment of radiological human exposure are presented
to identify the parameters that should be monitored in order to select, from the set of measurement
results, the "best estimates" of these parameter values. More complex models are often used that
require the knowledge of supplementary parameters.
Since the Fukushima Daichi nuclear power plant accident in March 2011, an effective emergency
response after a nuclear facility accident is re-emphasized and is summarized as follows. In the initial
stages of an accident, decision makers collect and report monitoring data promptly and determine
appropriate protective measures for the population, such as sheltering, evacuation, and the distribution
of iodine prophylaxis. Teams need to collect reliable information and make adequate decisions for
protective measure determinations. Appropriate prearranged procedures aid in the response to
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ISO 20043-2:2023(E)
emergency exposure situations. Also, decision makers should consider the possibility of coincident
events, such as natural disasters and infectious diseases occurring at the same time.
For emergency exposure situations, operational intervention levels are derived from IAEA Safety
[19]
Standards [IAEA GSG-2] .
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INTERNATIONAL STANDARD ISO 20043-2:2023(E)
Measurement of radioactivity in the environment —
Guidelines for effective dose assessment using
environmental monitoring data —
Part 2:
Emergency exposure situation
1 Scope
These international guidelines are based on the assumption that monitoring of environmental
components (atmosphere, water, soil and biota) as well as food quality is performed to ensure the
[5][7][8][9][10][11][12]
protection of human health . The guidelines constitute a basis for the setting of
national regulations, standards, and inter alia, for monitoring air, water and food in support of public
health, specifically to protect the public from ionizing radiation.
This document provides:
— guidance to collect data needed for the assessment of human exposure to radionuclides naturally
present or discharged by anthropogenic activities in the different environmental compartments
(atmosphere, waters, soils, biota) and food;
— guidance on the environmental characterization needed for the prospective and/or retrospective
dose assessment methods of public exposure;
— guidance that addresses actions appropriate for an event involving uncontrolled releases of gamma-
emitters (e.g. nuclear power reactor emergencies) and also events that would involve beta- or alpha-
emitters would require additional consideration of the pathways, instrumentation, laboratory
analysis, operational intervention levels, protective actions, etc., appropriate to their release;
— guidance for staff in nuclear installations responsible for the preparation of radiological assessments
in support of permit or authorization applications and National Authorities’ officers in charge of
the assessment of doses to the public for the purposes of determining gaseous or liquid effluent
radioactive discharge authorizations;
— information to the public on the parameters used to conduct a dose assessment for any exposure
situations to a representative person/population. It is important that the dose assessment process
be transparent, and that assumptions are clearly understood by stakeholders who can participate
in, for example, the selection of habits of the representative person to be considered.
This document refers to various published ISO documents. When appropriate, this document also refers
to national standards or other publicly available documents.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements of this document. For dated references, only the edition cited applies. For
undated references, the latest edition of the referenced document (including any amendments) applies.
ISO/IEC Guide 98-3, Uncertainty of measurement — Part 3: Guide to the expression of uncertainty in
me a s ur ement (GUM: 1995)
ISO/IEC Guide 99, International vocabulary of metrology — Basic and general concepts and associated
terms (VIM)
1
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ISO 20043-2:2023(E)
ISO 80000-10, Quantities and units — Part 10: Atomic and nuclear physics
3 Terms and definitions
For the purposes of this document, the terms and definitions given in ISO 80000-10, ISO/IEC Guide 98-3,
ISO/IEC Guide 99 and the following apply.
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
— ISO Online browsing platform: available at https:// www .iso .org/ obp
— IEC Electropedia: available at https:// www .electropedia .org/
3.1
atmospheric transfer coefficient
coefficient which characterizes the radioactivity dispersion in the atmosphere at a given location
Note 1 to entry: In the case of a continuous release, it is the ratio between the activity concentration in the air (C )
a
at a given location and the released activity rate ( A ). In the case of a puff release of a duration T it is the ratio
f
T T
f f
between Ctd at a given location and the total released activity Atd .
a
∫ ∫
0 0
Note 2 to entry: The atmospheric transfer coefficient at a given location depends on the distance between the
released position and the given location, the release height, the wind speed and the atmospheric stability, which
is characterized by either normal or weak diffusion according to the temperature difference between 100 m
altitude and the ground level. A diffusion is weak when this temperature difference is positive.
Note 3 to entry: The atmospheric transfer coefficient is usually calculated by valid computer code on the basis of
a mathematical model of atmospheric dispersion.
3.2
background (dose)
dose or dose rate (or an observed measure related to the dose or dose rate) attributable to all sources
other than the one(s) specified
Note 1 to entry: Strictly, this applies to measurements of dose rate or count rate from a sample, where the
background dose rate or count rate must be subtracted from all measurements. However, background is used
more generally, in any situation in which a particular source (or group of sources) is under consideration, to
refer to the effects of other sources. It is also applied to quantities other than doses or dose rates, such as activity
concentrations in environmental media
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
3.3
detection alarm level
real time measurement value corresponding to an acceptable false alarm rate
Note 1 to entry: When the detection alarm level increases false alarm rate decreases.
Note 2 to entry: The detection alarm level usually far more exceeds the decision threshold.
3.4
emergency action level
EAL
specific, predetermined, observable criterion used to detect, recognize and determine the emergency
class
Note 1 to entry: An emergency action level could represent an instrument reading, the status of a piece of
equipment or any observable event, such as a fire.
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
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ISO 20043-2:2023(E)
3.5
emergency exposure situation
exposure situation that arises as a result of an accident, a malicious act or other unexpected event, and
requires prompt action in order to avoid or to reduce adverse consequences
Note 1 to entry: This may include unplanned exposures resulting directly from the emergency and planned
exposures to persons undertaking actions to mitigate the consequences of the emergency. Emergency exposure
may be occupational exposure or public exposure.
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
3.6
monitoring
radiation monitoring
measurement of dose, dose rate or activity for reasons relating to the assessment or control of exposure
to radiation or exposure due to radioactive substances, and the interpretation of the results
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
3.7
environmental monitoring
measurement of external dose rates due to sources in the environment or of radionuclide concentrations
in environmental media
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
3.8
existing exposure situation
exposure situation which already exists when a decision on the need for control needs to be taken
Note 1 to entry: Existing exposure situation includes exposure to background radiation and exposure to residual
radioactive material from a nuclear or radiological emergency after the emergency exposure situation has been
declared ended.
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
3.9
operational intervention level
OIL
set level of a measurable quantity that corresponds to a generic criterion
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
Note 1 to entry: Operational intervention levels are typically expressed in terms of dose rates or of activity of
radioactive material released, time integrated air activity concentrations, ground or surface concentrations, or
activity concentrations of radionuclides in environmental, food or water samples.
Note 2 to entry: An operational intervention level is used immediately and directly (without further assessment)
to determine the appropriate protective actions on the basis of an environmental measurement.
3.10
precautionary action zone
PAZ
area around a facility for which arrangements have been made to take urgent protective actions in the
event of a nuclear or radiological emergency to avoid or to minimize severe deterministic effects off the
site
Note 1 to entry: Protective actions within this area are to be taken before or shortly after a release of radioactive
material or an exposure, on the basis of the prevailing conditions at the facility.
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
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ISO 20043-2:2023(E)
3.11
planned exposure situation
situation of exposure that arises from the planned operation of a source or from a planned activity that
results in an exposure due to a source
[SOURCE: IAEA. Vienna: IAEA, 2022. 246 p.]
3.12
risk
combination of the probability of occurrence of harm and the severity of that harm
Note 1 to entry: The probability of occurrence includes the exposure to a hazardous situation, the occurrence of a
hazardous event and avoid or limit the harm.
[SOURCE: ISO/IEC Guide 51:2014, 3.9]
3.13
screening
type of analysis aimed at eliminating the further consideration of factors that are less significant for
protection or safety, in order to concentrate on the more significant
...
DRAFT INTERNATIONAL STANDARD
ISO/DIS 20043-2
ISO/TC 85/SC 2 Secretariat: AFNOR
Voting begins on: Voting terminates on:
2022-06-10 2022-09-02
Measurement of radioactivity in the environment —
Guidelines for effective dose assessment using
environmental monitoring data —
Part 2:
Nuclear emergency exposure situation
Partie 2: Situations d'exposition d’urgence nucléaire
ICS: 17.240; 13.280
THIS DOCUMENT IS A DRAFT CIRCULATED
FOR COMMENT AND APPROVAL. IT IS
THEREFORE SUBJECT TO CHANGE AND MAY
This document is circulated as received from the committee secretariat.
NOT BE REFERRED TO AS AN INTERNATIONAL
STANDARD UNTIL PUBLISHED AS SUCH.
IN ADDITION TO THEIR EVALUATION AS
BEING ACCEPTABLE FOR INDUSTRIAL,
TECHNOLOGICAL, COMMERCIAL AND
USER PURPOSES, DRAFT INTERNATIONAL
STANDARDS MAY ON OCCASION HAVE TO
BE CONSIDERED IN THE LIGHT OF THEIR
POTENTIAL TO BECOME STANDARDS TO
WHICH REFERENCE MAY BE MADE IN
Reference number
NATIONAL REGULATIONS.
ISO/DIS 20043-2:2022(E)
RECIPIENTS OF THIS DRAFT ARE INVITED
TO SUBMIT, WITH THEIR COMMENTS,
NOTIFICATION OF ANY RELEVANT PATENT
RIGHTS OF WHICH THEY ARE AWARE AND TO
PROVIDE SUPPORTING DOCUMENTATION. © ISO 2022
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ISO/DIS 20043-2:2022(E)
COPYRIGHT PROTECTED DOCUMENT
© ISO 2022
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication may
be reproduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying, or posting on
the internet or an intranet, without prior written permission. Permission can be requested from either ISO at the address below
or ISO’s member body in the country of the requester.
ISO copyright office
CP 401 • Ch. de Blandonnet 8
CH-1214 Vernier, Geneva
Phone: +41 22 749 01 11
Email: copyright@iso.org
Website: www.iso.org
Published in Switzerland
ii
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ISO/DIS 20043-2:2022(E)
Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Normative references . 2
3 Terms and definitions . 2
4 Symbols . 5
5 Principle . 6
6 Implementation system of monitoring and action plan .10
6.1 Plan and implementation system . 10
6.2 Urgent response phase monitoring . 11
6.3 Early response phase monitoring .12
6.4 Transition phase monitoring .13
7 Guidance on emergency measurement .13
7.1 Ambient dose equivalent .13
7.2 Measurement by survey meter and monitoring vehicle . 14
7.3 Aerial monitoring . 14
7.4 Radiation monitoring on surface water . 14
7.5 Environmental media and food monitoring . 14
7.5.1 Measurement of radioactive materials in environmental media. 14
7.5.2 Measurement of radioactive materials in food and drink .15
7.5.3 Internal exposure management . 15
8 Discussion of Default OILs .15
8.1 Radiation monitoring for OIL 1 .15
8.2 Radiation monitoring for OIL 2 .15
8.3 Radiation monitoring for OIL 6 . 15
9 Projected dose assessment based on monitoring results .16
9.1 Projected dose assessment during a release . 17
9.2 Projected dose assessment after a plume passage . 18
10 Laboratory management .20
10.1 Laboratory staff management . 20
10.2 Sample management . 20
10.3 Quality management . 20
10.4 Publication of results . 20
Annex A (informative) Example of monitoring system for emergency exposure situation .21
Annex B (informative) Example of schematic diagram of action plan for radiation
protection in emergency exposure situation .22
Annex C (informative) OILs for assessing the results of field monitoring and screening of
foodstuff concentrations from laboratory analysis .23
Annex D (informative) Example of operational intervention levels determination related
to living area during plume passage .25
Annex E (informative) Example of operational intervention levels determination related to
living area after a plume passage .29
Bibliography .34
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ISO/DIS 20043-2:2022(E)
Foreword
ISO (the International Organization for Standardization) is a worldwide federation of national standards
bodies (ISO member bodies). The work of preparing International Standards is normally carried out
through ISO technical committees. Each member body interested in a subject for which a technical
committee has been established has the right to be represented on that committee. International
organizations, governmental and non-governmental, in liaison with ISO, also take part in the work.
ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of
electrotechnical standardization.
The procedures used to develop this document and those intended for its further maintenance are
described in the ISO/IEC Directives, Part 1. In particular the different approval criteria needed for the
different types of ISO documents should be noted. This document was drafted in accordance with the
editorial rules of the ISO/IEC Directives, Part 2 (see www.iso.org/directives).
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. ISO shall not be held responsible for identifying any or all such patent rights. Details of
any patent rights identified during the development of the document will be in the Introduction and/or
on the ISO list of patent declarations received (see www.iso.org/patents).
Any trade name used in this document is information given for the convenience of users and does not
constitute an endorsement.
For an explanation on the voluntary nature of standards, the meaning of ISO specific terms and
expressions related to conformity assessment, as well as information about ISO's adherence to the
World Trade Organization (WTO) principles in the Technical Barriers to Trade (TBT) see the following
URL: www.iso.org/iso/foreword.html.
This document was prepared by Technical ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection.
A list of all parts in the ISO 20043 series can be found on the ISO website.
Any feedback or questions on this document should be directed to the user’s national standards body. A
complete listing of these bodies can be found at www.iso.org/members.html.
iv
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ISO/DIS 20043-2:2022(E)
Introduction
Everyone is exposed to natural radiation. The natural sources of radiation are cosmic rays and
naturally occurring radioactive substances existing in the Earth itself and inside the human body.
Human activities involving the use of radiation and radioactive substances cause radiation exposure in
addition to the natural exposure. Some of those activities, such as the mining and use of ores containing
naturally-occurring radioactive material (NORM) and the production of energy by burning coal that
contains such substances, simply enhance the exposure from natural radiation sources. Nuclear
installations use radioactive materials and produce radioactive effluent and waste during operation
and on their decommissioning. The use of radioactive materials in industry, agriculture and research is
expanding around the globe.
All these human activities generally also give rise to radiation exposures that are only a small fraction
of the global average level of natural exposure. The medical use of radiation is the largest and a growing
man-made source of radiation exposure in developed countries. It includes diagnostic radiology,
radiotherapy, nuclear medicine and interventional radiology.
Radiation exposure also occurs as a result of occupational activities. It is incurred by workers in
industry, medicine and research using radiation or radioactive substances, as well as by passengers
and crew during air travel and for astronauts. The average level of occupational exposures is generally
[1]
similar to the global average level of natural radiation exposure .
As the uses of radiation increase, so do the potential health risk and the public’s concerns increase.
Thus, all these exposures are regularly assessed in order to
a) improve the understanding of global levels and temporal trends of public and worker exposure;
b) to evaluate the components of exposure so as to provide a measure of their relative importance,
and
c) to identify emerging issues that may warrant more attention and scrutiny. While doses to workers
are usually directly measured, doses to the public are usually assessed by indirect methods
using radioactivity measurements results performed on various sources: waste, effluent and/or
environmental samples.
To ensure that the data obtained from radioactivity monitoring programs support their intended use,
it is essential in the dose assessment process that stakeholders (the operators, the regulatory bodies,
the local information committee and associations, etc.) agree on appropriate data quality objectives,
methods and procedures for: the sampling, handling, transport, storage and preparation of test
samples; the test method; and for calculating measurement uncertainty. An assessment of the overall
measurement uncertainty also needs to be carried out systematically. As reliable, comparable and ‘fit
for purpose’ data are an essential requirement for any public health decision based on radioactivity
measurements, international standards of tested and validated radionuclide test methods are an
important tool for the production of such measurement results. The application of standards serves
also to guaranty comparability over time of the test results and between different testing laboratories.
Laboratories apply them to demonstrate their technical competences and to complete proficiency tests
successfully during interlaboratory comparisons, two prerequisites to obtain national accreditation.
Today, over a hundred international standards, prepared by Technical Committees of the International
Standardization Organization for Standardizations, including those produced by ISO/TC 85 working
groups, and the International Electrotechnical Commission, are available for measuring radionuclides
in different matrices by testing laboratories.
Generic standards help laboratories to manage the measurement process and specific standards
describing test methods are used specifically by those in charge of radioactivity measurement. The
later cover test methods for:
40 14
— Natural radionuclides, including K, tritium, C and those originating from the thorium and
226 228 234 238 220 222 210
uranium decay series, in particular Ra, Ra, U, U, Rn, Rn, and Pb, which can
be found in every material from natural sources or can be released from technological processes
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ISO/DIS 20043-2:2022(E)
involving naturally occurring radioactive materials (e.g. the mining and processing of mineral sands
or phosphate fertilizer production and use), and
— Man-made radionuclides, such as transuranium elements (americium, plutonium, neptunium, and
14 90
curium), tritium, C, Sr and gamma emitting radionuclides found in waste, liquid and gases
effluent and in environmental matrices (air, soil, water, biota) as a result of authorized releases into
the environment and of fallout resulting from the explosion in the atmosphere of nuclear devices
and accidents, such as those that occurred in Chernobyl and Fukushima. Radionuclides, such as
14
tritium and C occur both naturally and as by-products of the operation of nuclear reactors.
[2]
The ICRP recognises three types of exposure situations that are intended to cover the entire range
of exposure situations: planned, emergency and existing exposure situations. Planned exposure
situations involve the planned introduction and operation of sources (previously categorised as
practices). Emergency exposure situations require prompt action in order to avoid or to reduce adverse
consequences. Existing exposure situations are exposure situations that already exist when a decision
on control is taken, such as those caused by enhanced natural background radiation (e.g. on remediated
land).
The fraction of the background dose rate to man from environmental radiation, mainly gamma
radiation, varies considerably, and depends on factors such as the radioactivity of the local rock and
soil, the nature of building materials and the construction of buildings in which people live and work.
This document sets out principles and guidance for the radiological characterisation of the environment
needed for checking the results of
— prospective assessment of dose to the public arising from exposure to ionizing radiation which
may arise from planned discharges to the atmosphere and to the aquatic environment or following
remediation action;
— retrospective assessment for dose that may be made for discharges or disposals that were not
initially covered by or authorized by a national regulatory body (e.g. contaminated land or dose
associated with accidental releases of radionuclides into the environment).
This document is one of a set of generic ISO Standards on measurement of radioactivity. Example of
dose assessment in different exposure situations are shown in the Table 1 below.
Table 1 — Example of dose assessment in different exposure situations, modified from
reference [3]
Type of assessment
Situation
Prospective Retrospective
Determining compliance with the relevant dose
constraint (dose limit or regulatory require-
Estimating dose to the public from past
Planned ments). A prospective assessment includes the
operations
exposures expected to occur in normal opera-
tion.
Future prolonged exposures (e.g. after remedi- Past exposures (e.g. occupancy of contami-
Existing
ation) nated lands)
Emergency planning (operational intervention
Emergency Actual impacts after emergency
level)
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DRAFT INTERNATIONAL STANDARD ISO/DIS 20043-2:2022(E)
Measurement of radioactivity in the environment —
Guidelines for effective dose assessment using
environmental monitoring data —
Part 2:
Nuclear emergency exposure situation
1 Scope
These international guidelines are based on the assumption that monitoring of environmental
components (atmosphere, water, soil and biota) as well as food quality must be performed to ensure the
[2][4][5][6][7][8]
protection of human health . The guidelines constitute a basis for the setting of national
regulations and standards, inter alia, for monitoring air, water and food in support of public health,
specifically to protect the public from ionizing radiation.
This document provides
— guidance to collect data needed for the assessment of human exposure to radionuclides naturally
present or discharged by anthropogenic activities in the different environmental compartments
(atmosphere, waters, soils, biota) and food;
— guidance on the environmental characterization needed for the prospective and/or retrospective
dose assessment methods of public exposure;
— guidance that addresses actions appropriate for an event predominantly involving uncontrolled
releases of gamma-emitters (e.g., nuclear power reactor emergencies). Events that would involve
predominantly beta- or alpha-emitters would require additional consideration of the pathways,
instrumentation, laboratory analysis, operational intervention levels, protective actions, etc.,
appropriate to their release. These additional considerations are not reviewed in detail in this
standard;
— guidance for staff in nuclear installations responsible for the preparation of radiological assessments
in support of permit or authorization applications and National Authorities’ officers in charge of
the assessment of doses to the public for the purposes of determining gaseous or liquid effluent
radioactive discharge authorizations;
— information to the public on the parameters used to conduct a dose assessment for any exposure
situations to a representative person/population. It is important that the dose assessment process
be transparent, and that assumptions are clearly understood by stakeholders who can participate
in, for example, the selection of habits of the representative person to be considered.
Generic mathematical models used for the assessment of radiological human exposure are presented to
identify the parameters that shall be monitored in order to select, from the set of measurement results,
the "best estimates" of these parameter values. More complex models are often used that require the
knowledge of supplementary parameters.
Since the Fukushima Daichi nuclear power plant accident in March 2011, an effective emergency
response after a nuclear facility accident is re-emphasized and is summarized as follows. In the
initial stages of an accident, decision makers have to collect and report monitoring data promptly and
determine appropriate protective measures for the population, such as sheltering, evacuation, and
the distribution of iodine prophylaxis. Teams need to collect reliable information and make adequate
decisions for protective measure determinations. Appropriate prearranged procedures aid in the
response to radiological emergency exposure situations. Also, decision makers should consider the
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ISO/DIS 20043-2:2022(E)
possibility of coincident events, such as natural disasters and infectious diseases occurring at the same
time.
For emergency exposure situations, operational intervention levels are derived from IAEA Safety
Standards [IAEA GSG-2] or national authorities [FAO-WHO Codex Alimentarius (2015)].
This document refers to various published ISO documents. When appropriate, this document also refers
to national standards or other publicly available documents.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements of this document. For dated references, only the edition cited applies. For
undated references, the latest edition of the referenced document (including any amendments) applies.
ISO/IEC Guide 98-3, Uncertainty of measurement — Part 3: Guide to the expression of uncertainty in
me a s ur ement (GUM: 1995)
ISO/IEC Guide 99, International vocabulary of metrology — Basic and general concepts and associated
terms (VIM)
ISO 80000-10, Quantities and units — Part 10: Atomic and nuclear physics
3 Terms and definitions
For the purposes of this document, the terms and definitions given in ISO 80000-10, ISO/IEC Guide 98-3,
ISO/IEC Guide 99 and the following apply.
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
— ISO Online browsing platform: available at https:// www .iso .org/ obp
— IEC Electropedia: available at https:// www .electropedia .org/
3.1
atmospheric transfer coefficient
coefficient which characterizes the radioactivity dispersion in the atmosphere at a given location
Note 1 to entry: In the case of a continuous release, it is the ratio between the activity concentration in the air (C )
a
at a given location and the released activity rate ( A ). In the case of a puff release of a duration T it is the ratio
f
T T
f f
between Cdt at a given location and the total released activity Adt .
a
∫ ∫
0 0
Note 2 to entry: The atmospheric transfer coefficient at a given location depends on the distance between the
released position and the given location, the release height, the wind speed and the atmospheric stability, which
is characterized by either normal or weak diffusion according to the temperature difference between 100 m
altitude and the ground level. A diffusion is weak when this temperature difference is positive.
Note 3 to entry: The atmospheric transfer coefficient is usually calculated by valid computer code on the basis of
a mathematical model of atmospheric dispersion.
3.2
background (dose)
doses, dose rates or activity concentrations associated with natural sources, or any other sources in the
environment that are not amenable to control
Note 1 to entry: Dose from sources that are not under the permit of the site with the radioactive discharge are
background sources from the perspective of the discharging site.
2
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ISO/DIS 20043-2:2022(E)
3.3
detection alarm level
real time measurement value corresponding to an acceptable false alarm rate
Note 1 to entry: When the detection alarm level increases false alarm rate decreases.
Note 2 to entry: The detection alarm level usually far more exceeds the decision threshold.
3.4
emergency action level
EAL
a specific, predetermined, observable criterion used to detect, recognize and determine the emergency
class
Note 1 to entry: An emergency action level could represent an instrument reading, the status of a piece of
equipment or any observable event, such as a fire.
[SOURCE: IAEA safety glossary 2018]
3.5
emergency exposure situation
exposure situation that arises as a result of an accident, a malicious act or other unexpected event, and
requires prompt action in order to avoid or to reduce adverse consequences
Note 1 to entry: This may include unplanned exposures resulting directly from the emergency and planned
exposures to persons undertaking actions to mitigate the consequences of the emergency. Emergency exposure
may be occupational exposure or public exposure.
[SOURCE: IAEA. IAEA Safety Glossary: 2018 edition. Vienna: IAEA, 2019. 278 p.]
3.6
monitoring
radiation monitoring
measurement of dose, dose rate or activity for reasons relating to the assessment or control of exposure
to radiation or exposure due to radioactive substances, and the interpretation of the results
[SOURCE: IAEA Safety Glossary 2018]
3.7
environmental monitoring
measurement of external dose rates due to sources in the environment or of radionuclide concentrations
in environmental media
[SOURCE: IAEA Safety Glossary 2018]
3.8
existing exposure situation
exposure situation which already exists when a decision on the need for control needs to be taken
Note 1 to entry: Existing exposure situation includes exposure to background radiation and exposure to residual
radioactive material from a nuclear or radiological emergency after the emergency exposure situation has been
declared ended.
[SOURCE: IAEA Safety Glossary: 2018 edition. Vienna: IAEA, 2019. 278 p.]
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ISO/DIS 20043-2:2022(E)
3.9
operational intervention level
OIL
set level of a measurable quantity that corresponds to a generic criterion
[SOURCE: IAEA. IAEA Safety Glossary: 2018 edition. Vienna: IAEA, 2019. 278 p.]
Note 1 to entry: OILs are calculated levels, measured by instruments or determined by laboratory analysis, that
correspond to an intervention level or action level.
3.10
precautionary action zone
PAZ
area around a facility for which arrangements have been made to take urgent protective actions in the
event of a nuclear or radiological emergency to avoid or to minimize deterministic effects off the site.
Note 1 to entry: Protective actions within this area are to be taken before or shortly after a release of radioactive
material or an exposure, on the basis of the prevailing conditions at the facility.
[SOURCE: IAEA Safety Glossary 2018]
3.11
planned exposure situations
situation of exposure that arises from the planned operation of a source or from a planned activity that
results in an exposure due to a source
[SOURCE: IAEA Safety Glossary 2018]
3.12
radioactive discharges
radioactive substances arising from a source within facilities and activities which are discharged
as gases, aerosols, liquids or solids to the environment, generally with the purpose of dilution and
dispersion
[SOURCE: IAEA Safety Glossary 2018]
3.13
risk
combination of the probability of occurrence of harm and the severity of that harm
[SOURCE: ISO/IEC Guide 51:1999, Safety aspects – Guidelines for their inclusion in standards, 3.2]
3.14
risk analysis
systematic use of available information to identify hazards and to estimate the risk
[
...
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